OCCUPATIONAL ADIATION ^EXPOSURE

Transcription

1 DOEIEH064 OCCUPATIONAL ADIATION ^EXPOSURE g p6 Reprt V ^M^TRON»AEDE.E L c^0/v T^A 4. MASTER The U.S. Department f Energy Assistant SBcretaryjrJEnvirnment, Safety and Health Office fwrker Health and Safety % OKTRtBUTTON OF TH» OOCUMIMT 8 UNUMITID

2 DISCLAIMER Prtins f this dcument may be illegible electrnic image prducts. Images are prduced frm the best available riginal dcument.

3 Frewrd: The gal f the U.S. Department f Energy (DOE) is t cnduct its radilgical peratins t ensure the health and safety f all DOE emplyees including cntractrs and subcntractrs. The DOE strives t maintain radiatin expsures t its wrkers belw administrative cntrl levels and DOE limits and t further reduce these expsures and releases t levels that are "As Lw As Reasnably Achievable" (ALARA). The DOE Occupatinal Radiatin Expsure Reprt, 996 prvides summary and analysis f the ccupatinal radiatin expsure received by individuals assciated with DOE activities. The DOE missin includes stewardship f the nuclear weapns stckpile and the assciated facilities, envirnmental restratin f DOE and precursr agency sites, and energy research. Cllective expsure at DOE has declined by 8 ver the past decade due t a cessatin in pprtunities fr expsure during the transitin in DOE missin frm weapns prductin t cleanup, deactivatin and decmmissining, and changes in reprting requirements and dse calculatin methdlgy. In 996, the cllective dse decreased by frm the 99 value due t decreased dses at five f the seven highestdse DOE sites. Fr 996, these sites attributed the reductin in cllective dse t the cmpletin f several decntaminatin and decmmissining prjects, reduced spent fuel strage activities, and effective ALARA practices. This reprt is intended t be a valuable tl fr managers in their management f radilgical safety prgrams and cmmitment f resurces. The prcess f data cllectin, analysis, and reprt generatin is streamlined t give managers a current assessment f the perfrmance f the Department with respect t radilgical peratins. The cperatin f the sites in prmptly and crrectly reprting emplyee radiatin expsure infrmatin is key t the timeliness f this reprt. Yur feedback and cmments are imprtant t us t make this reprt meet yur needs. A user survey frm is included in Appendix F t cllect yur suggestins t imprve this reprt. Peter Brush Acting Assistant Secretary Envirnment, Safety and Health Jseph Fitzgerald. Jr. Deputy Assistant Secretary Office f Wrker Health and Safety 996 Reprt Frewrd

4 \jv This page intentinally left blank. D0E Occupatinal Radiatin Expsure

5 Tablet! Cntents!^ FOREWORD EXECUTIVE SUMMARY Hi ix SECTION INTRODUCTION. Reprt Organizatin. Reprt Availability SECTION STANDARDS AND REQUIREMENTS. Radiatin Prtectin Requirements.. Mnitring Requirements... External Mnitring... Internal Mnitring. Radiatin Dse Limits.. Administrative Cntrl Levels 4.. ALARA Principle 4. Reprting Requirements.4 Change in Internal Dse Methdlgy.4. Annual Effective Dse Equivalent.4. Cmmitted Effective Dse Equivalent 6.4. Impact n the Dse Data External Dse 7 SECTION OCCUPATIONAL RADIATION DOSE AT DOE. Analysis f the Data. Analysis f Cllective Data.. Number f Mnitred Individuals.. Number f Individuals with Measurable Dse.. Cllective Dse..4 Average Measurable Dse 4.. Dse Distributin. Dse t Individuals 8.. Dses in Excess f DOE Limits 8.. Dses in Excess f Administrative Cntrl Level 9.. Internal Depsitins f Radiactive Material.4 Site Analysis.4. Cllective by Operatins/Field Offices.4. Dse by Labr Categry.4. Dse by Facility Type Radiatin Prtectin Occurrence Reprts 7. Activities Cntributing t Cllective Dse in Reprt Table f Cntents

6 SECTION 4 ALARA ACTIVITIES AT DOE 4. Successful ALARA Prjects 4 4. W79 Cntaminatin Cntrl System at Pantex 4 4. FB Line Vault at Savannah River KBasin Superstructure Remval at Savannah River 4 4. Antiprtn Target Assembly Replacement at Fermilab Sample Preparatry Labratry Dustbag Replacement at Grand Junctin Submitting ALARA Success Stries fr Future Annual Reprts Lessns Learned Prcess Imprvement Team 47 SECTION CONCLUSIONS AND RECOMMENDATIONS. Cnclusins. Recmmendatins REFERENCES Rl GLOSSARY APPENDICES A DOE Reprting Sites and Reprting Cdes Al B Additinal Data Bl C Facility Type Cde Descriptins Cl D Limitatins f Data Dl E Access t Radiatin Expsure Infrmatin El F User Survey Fl Gl vi DOE Occupatinal Radiatin Expsure

7 LIST OF EXHIBITS Exhibit : DOE Dse Limits frm 0 CFR 8 Exhibit : Mnitring f the DOE Wrkfrce Exhibit : Cmpnents f, Exhibit : Average Measurable DDE Dse and Average Measurable Exhibit 4: Dse Distributins, Exhibit : Distributin f Cllective Dse vs Dse Values, Exhibit 6: Number f Individuals Exceeding rem (), Exhibit 7: Dses in Excess f DOE Limits, Exhibit 8: Number f Dses in Excess f the DOE rem ACL, Exhibit 9: Number f Intakes, Cllective Internal Dse, and Average Dse by Nuclides, Exhibit 0: Internal Dse Distributin frm Intakes, Exhibit : Cllective by Site/Facility Exhibit : Cllective and Number f Individuals with Measurable by Site/Facility Exhibit : Dses by Labr Categry, Exhibit 4: Graph f Dses by Labr Categry Exhibit : Graph f Dse by Facility Type, Exhibit 6: Dses by FacilityType, Exhibit 7: Criteria fr Radiatin Expsure and Persnnel Cntaminatin Occurrence Reprting 7 Exhibit 8: Radiatin Expsure Occurrence Reprts, Exhibit 9: Persnnel Cntaminatin Occurrence Reprts, Exhibit 0: Persnnel Cntaminatin Occurrences by Affected Area, Exhibit : Radiatin Expsure Occurrences by Site, Exhibit : Persnnel Cntaminatin Occurrences by Site, Exhibit : Radiatin Expsure Occurrences by Rt Cause, Exhibit 4: Persnnel Cntaminatin by Rt Cause, Exhibit : Activities Cntributing t Cllective in 996 fr Seven Sites Exhibit 4: Ventilatin Ductwrk fr Clse Capture System 4 Exhibit 4: Optima 000 Blwer Unit 4 Exhibit 4: W79 Clse Capture Cntaminatin Cntrl System 4 Exhibit 44: Technicians Remving Target Mdule While Mnitring Dse 44 Exhibit 4: Technician Observes Ht Target Frm Behind Lead Shielding Reprt Table f Cntents vii

8 77ZS page intentinally left blank. DOE Occupatinal Radiatin Expsure

9 Executive Summary The U.S. Department f Energy (DOE) Office f Envirnment, Safety and Health publishes the DOE Occupatinal Radiatin Expsure Reprt. This reprt is intended t be a valuable tl fr DOE/DOE cntractr managers in their management f radilgical safety prgrams and t assist them in the priritizatin f resurces. We appreciate the effrts and cntributins frm the varius stakehlders within and utside the DOE and hpe we have succeeded in making the reprt mre useful. This reprt includes ccupatinal radiatin expsure infrmatin fr all DOE emplyees, cntractrs, subcntractrs, and visitrs. The expsure infrmatin is analyzed in terms f cllective data, dse t individuals, and dse by site. Fr the purpses f examining trends, data fr the past years are included in the analysis. As shwn in the figure belw, between 99 and 996, the DOE cllective ttal effective dse equivalent () decreased by due t decreased dses at five f the seven dse sites with the highest radiatin dse. In additin, the average dse t wrkers with measurable dse decreased by 6%, the number f individuals receiving measurable dse drpped by 4%, and there was ne expsure ver the DOE rem limit., I I Cllective Dse (persnrem) 0.8 =c= Average Meas. Dse (rem) g, E 0) D,00, u Q n en < > < Nearly 8% f the cllective fr the DOE cmplex was accrued at seven DOE sites in 996. These seven sites are (in descending rder f cllective dse) Rcky Flats, Hanfrd, Savannah River, Ls Alams, Idah, Brkhaven, and Oak Ridge. Weapns fabricatin and testing facilities accunt fr the highest cllective dse. It shuld be nted that Rcky Flats and Savannah River accunt fr the majrity f this dse. These sites are nw primarily invlved in nuclear materials stabilizatin and waste management but still reprt under this facility type. Fr the past 4 years, technicians received the highest cllective dse f any specified labr categry. Occupatinal radiatin expsure at DOE has been impacted ver the past years by changes in: reprting requirements, peratinal status and activities resulting in radiatin expsure at DOE facilities, and radiatin prtectin standards and practices. 996 Reprt Executive Summary

10 A change in the reprting requirements had a significant impact n the cllective dse at DOE between 99 and 99. The change in internal dse methdlgy frm annual effective dse equivalent (AEDE) t cmmitted effective dse equivalent (CEDE) between 99 and 99 resulted in an apparent reductin f the cllective dse by up t 8% because the dse t individuals frm intakes frm previus years is n lnger reprted in the current year. Als, the peratinal status f DOE facilities has had an impact n radiatin expsure due t the shift in missin frm prductin t cleanup activities and the shutdwn f certain facilities. Radiatin prtectin practices have changed during the past years because f the implementatin f the DOE Radilgical Cntrl (RadCn) Manual. The RadCn Manual established Administrative Cntrl Levels (ACL),standardized radiatin prtectin prgrams, and frmalized "As Lw As Reasnably Achievable" (ALARA) practices. D LEGEND Internal Dse (AEDE) Accrued during Mnitring Year Internal Dse (AEDE) Accrued frm Legacy Intakes 9 Internal Dse (CEDE) Accrued during Mnitring Year External Dse (DDE) Accrued during Mnitring Year UJ Q Ul E z DOE Occupatinal Radiatin Expsure

11 Occupatinal dses at DOE facilities in excess f rem ACL and rem regulatry limit have decreased ver the past years, as shwn in the figures n the previus page. There was ne individual in 996 wh received a dse in excess f the rem limit. This individual received an internal dse f. rem due t an unanticipated intake f plutnium at the Savannah Site. The intake ccurred in December f 996, but was discvered and reprted in 997 after a special fllwup biassay was perfrmed. This verexpsure led t an enfrcement actin and fine against the cntractr under the prvisins f the PriceAndersn Act fr vilatins f 0 CFR 8. As a result f the analysis presented in this reprt, several recmmendatins are made. The DOE missin has changed ver the years frm weapns prductin, peratin, and stabilizatin t envirnmental restratin and surveillance.this shift in DOE missin has made it necessary t track and analyze ccupatinal radiatin expsure data in relatin t the phase f peratin f the DOE facilities. It is recmmended that Sites and Operatins Offices begin reviewing their data cllectin prcess in anticipatin f cllecting the phase f peratin data (see Appendix A.) It is recmmended that sites review their recrdkeeping and reprting prcesses in rder t imprve the reprting f ccupatin cdes in accrdance with DOE Manual. and, as a result, imprve the analysis f radiatin expsure infrmatin by ccupatin. Analysis f ccurrence reprts indicates an increase in expsure ccurrences due t unknwn surces f radiatin in 996. While this became a new rt cause categry fr 99,the increasing trend requires cntinued mnitring. It is recmmended that sites reprting these ccurrences review and remediate situatins that result in these expsure ccurrences. T prvide a mre cmplete analysis f the radiatin expsure data reprted t DOE Headquarters.it is necessary t cllect additinal infrmatin frm the highest dse sites. It is recmmended that these highest dse sites prvide a brief annual summary f activities and descriptins f ALARA prjects in additin t their annual radiatin recrds submittals. The data in the REMS database are subject t crrectin and update n a cntinuus basis. Data fr prir years are subject t crrectin as well as the data fr the mst recent year included in this reprt. The mst cmmn reasn fr crrectin t a dse recrd is because f a final dse determinatin f an internal dse lng after the riginal dse recrd was submitted t REMS. This delay is due t the time needed t assess the biassay results and determine the dse frm lnglived radinuclides. It is recmmended that sites review their dse recrd update and reprting prcess, specifically fr internal dse determinatin, and cnsider the additin f a mechanism whereby they reprt dse updates t REMS in a timely fashin when updates ccur. DOE shuld investigate the feasibility, cst, and benefit f establishing a histrical repsitry f intake infrmatin t track and access radiatin dse frm intakes in prir years. 996 Reprt Executive Summary xi

12 xii_ This page intentinally left blank. DOE Occupatinal Radiatin Expsure

13 The DOE Occupatinal Radiatin Expsure Reprt, 996 reprts ccupatinal radiatin expsures incurred by individuals at US. Department f Energy (DOE) facilities during the calendar year 996. This reprt includes ccupatinal radiatin expsure infrmatin fr all DOE emplyees, cntractrs.subcntractrs,and visitrs. This infrmatin is analyzed and trended ver time t prvide a measure f the DOE's perfrmance in prtecting its wrkers frm radiatin. The analysis f trends is cmplicated by recent changes in internal dse reprting methdlgy and the shifting f the DOE missin frm weapns prductin t stabilizatin and cleanup activities acrss the DOE cmplex. The change in internal dse reprting and its impact n the ccupatinal expsure data are examined in Sectins and. In general, the ccupatinal radiatin expsure received by DOE wrkers is lw cmpared t DOE expsures in prir years, particularly during the Cld War era, and in cmparisn with ccupatinal expsure received in the cmmercial nuclear industry. Reprt Organizatin This reprt is rganized int the five sectins listed belw. Supprting technical infrmatin, tables f data, and additinal items that were identified by users as useful are prvided in the appendices.. Reprt Availability Requests fr additinal cpies f this reprt r access t the data files used t cmpile this reprt shuld be directed t Ms.Nirmala Ra, REMS Prject Manager, U.S. Department f Energy Office fwrker Prtectin Prgrams and Hazards Management (EH),Germantwn,MD 0874 r by calling the ES&H InfCenter at A discussin f the varius methds f accessing the DOE ccupatinal radiatin expsure infrmatin is presented in Appendix E. Visit the DOE Radiatin Expsure web site fr infrmatin cncerning ccupatinal radiatin expsure at the DOE at Sectin One Sectin Tw Sectin Three Sectin Fur Sectin Five Prvides a descriptin f the cntent and rganizatin f this reprt. Prvides a discussin f the radiatin prtectin and dse reprting requirements and their impacts n data interpretatin. Additinal infrmatin n dse calculatin methdlgies, persnnel mnitring methds and reprting threshlds, regulatry dse limits, and ALARA are included. Presents the ccupatinal radiatin dse data frm mnitred individuals at DOE facilities fr 996. The data are analyzed t shw trends ver the past years. Includes examples f successful ALARA prjects within the DOE cmplex. Cnclusins are presented based n the analysis cntained in this reprt. Where applicable, recmmendatins are included t address issues that require attentin. 996 Reprt Intrductin

14 This page intentinally left blank. DOE Occupatinal Radiatin Expsure

15 One f DOE's primary bjectives is t prvide a safe and healthy wrkplace fr all emplyees and cntractrs. T meet this bjective,doe's Office fwrker Prtectin Prgrams and Hazards Management establishes cmprehensive and integrated prgrams fr the prtectin f wrkers frm hazards in the wrkplace, including inizing radiatin. The basic DOE standards are radiatin dse limits, which establish maximum permissible dses t wrkers and visitrs. In additin t the requirement that radiatin dses nt exceed the limits, it is DOE's plicy that dses als be maintained as lw as reasnably achievable (ALARA). This sectin discusses the radiatin prtectin standards and requirements that were in effect fr the year 996. The requirements leading up t this time perid are als included t facilitate a better understanding f changes that have ccurred in the recrding and reprting f ccupatinal dse.. Radiatin Prtectin Requirements DOE radiatin prtectin standards are based n federal guidance fr prtectin against ccupatinal radiatin expsure prmulgated by the US. Envirnmental Prtectin Agency (EPA) in 987 []. These standards are prvided t ensure that wrkers at DOE are adequately prtected frm expsure t inizing radiatin. This guidance, initially implemented by DOE in 989, is based n the 976 recmmendatins f the Internatinal Cmmissin n Radilgical Prtectin [] and the Natinal Cuncil n Radiatin Prtectin and Measurements []. The new guidance required that internal rgan dse (resulting frm the intake f radinuclides) be added t the external whlebdy dse t determine the Ttal Effective Dse Equivalent (). Prir t this, the whlebdy dse and internal rgan dse were each limited separately The new DOE dse limits based n the were established frm this guidance. DOE became the first federal agency t implement the revised guidance when it prmulgated DOE Order 480.,"Radiatin Prtectin fr Occupatinal Wrkers," in December 988 [4]. DOE Order 480. was effective frm 989 thrugh 99. In June 99, the DOE Radilgical Cntrl (RadCn) Manual [] was issued and became effective in 99. The RadCn Manual was the result f a Secretarial initiative t imprve and standardize radilgical prtectin practices thrughut DOE and t achieve the gal f making DOE the pacesetter fr radilgical health and safety. The RadCn Manual is a cmprehensive guidance dcument written fr wrkers, line managers, and senir management. The RadCn Manual states DOE's views n the best practices currently available in the area f radilgical cntrl. The RadCn Manual was revised in 994 in respnse t cmments frm the field and t enhance cnsistency with the requirements inl0cfr8[6]. 0 CFR 8 became effective n January,994, and required full cmpliance by January,996. In general, 0 CFR 8 cdified existing radiatin prtectin requirements in DOE Order The rule prvides nuclear safety requirements that, if vilated, will prvide a basis fr the assessment f civil and criminal penalties under the PriceAndersn Amendments Act f 988, Public Law 00408,August 0, 988 [7] as implemented by 0 CFR 80 "Prcedural Rules fr DOE Nuclear Activities," August 7,99. [8] One and ne half years after the prmulgatin f 0 CFR 8, DOE Order 480. was canceled and the RadCn Manual was made nnmandatry guidance. D Ct 996 Reprt Standards and Requirements

16 DOE Ntice 44., "Radilgical Prtectin fr DOE Activities," [9] (applicable t defense nuclear facilities) was issued t establish radilgical prtectin prgram requirements that, cmbined with 0 CFR 8 and its assciated nnmandatry implementatin guidance, the RadCn Manual, frms the basis fr a cmprehensive radilgical prtectin prgram. During 994 and 99, DOE undertk an initiative t reduce the burden f unnecessary repetitive, r cnflicting requirements n DOE cntractrs. As a result, DOE Order 484. [0] requirements fr reprting radiatin dse recrds are nw lcated in the assciated manual, DOE M., "Envirnment, Safety and Health Reprting" [],which became effective September 0,99. The requirements f DOE M. are basically the same as Order 484.; hwever, the dse terminlgy was revised t reflect the changes made in radiatin prtectin standards and requirements. Fr 99, DOE Order 484. remained in effect. Mst sites reprted under the new DOE M. fr 996. Because each site implements the new requirements as perating cntracts are issued r renegtiated, cmplete implementatin will take several years... Mnitring Requirements 0 CFR 8.40 requires that, fr external mnitring, persnnel dsimetry be prvided t general emplyees expected t receive an effective dse equivalent t the whlebdy greater than 0. rem r an effective dse equivalent t the skin r extremities, lens f the eye, r any rgan r tissue greater than f the crrespnding annual limits. Mnitring fr internal radiatin expsure is required when the general emplyee is likely t receive 0. rem r mre Cmmitted Effective Dse Equivalent (CEDE),and/r rems r mre Cmmitted Dse Equivalent (CDE) t any rgan r tissue. Mnitring fr minrs and members f the public is required if the dse (internal r external) is likely t exceed f the annual limit f 0. rem. Mnitring f declared pregnant females is required if the dse (internal r external) t the embry/fetus is likely t exceed f the limit f 0. rem. Mnitring fr external expsures is required fr any individuals entering a high r very high radiatin area.... External Mnitring External r persnnel dsimeters are used t measure inizing radiatin frm surces external t the individual. The chice f dsimeter is based n thetypeand energy f radiatin that the individual is likely t encunter in the wrkplace. An algrithm is then used t cnvert the expsure readings int dse. External mnitring devices include phtgraphic film (film badges),thermluminescent dsimeters, pcket inizatin chambers, electrnic dsimeters, persnnel nuclear accident dsimeters, bubble dsimeters, plastic dsimeters, and cmbinatins f the abve. Beginning in 990, the DOE Labratry Accreditatin Prgram (DOELAP) frmalized accuracy and precisin perfrmance standards fr external dsimeters and quality assurance/quality cntrl requirements n the verall external dsimetry prgrams fr facilities within the DOE cmplex. All DOE facilities were DOELAPaccredited by the fall f 99. External dsimeters have a lwer limit f detectin f apprximately rem per mnitring perid. The differences are attributable t the particular type f dsimeter used and thetypesf radiatin mnitred. Mnitring perids are usually quarterly fr individuals receiving less than 0.00 rem/year and mnthly fr individuals wh rutinely receive higher dses r wh enter higher radiatin areas. DOE Occupatinal Radiatin Expsure

17 ... Internal Mnitring Biassay mnitring includes invitr (utside the bdy) and inviv (inside the bdy) sampling. Invitr assays include urine and fecal samples, nse swipes, saliva samples, and hair samples. Inviv assays include whlebdy cunting, thyrid cunting, lung cunting, and wund cunting. Mnitring intervals fr internal dsimetry are dependent n the radinuclides being mnitred and their cncentratins in the wrk envirnment. Rutine mnitring intervals may be mnthly, quarterly, r annually, whereas special mnitring intervals fllwing an incident may be daily r weekly. Detectin threshlds fr internal dsimetry are highly dependent n the mnitring methds, the radinuclides in questin, and their chemical frm. Fllwup measurements and analysis may take many mnths t cnfirm preliminary findings. With the advent f the publicatin f American Natinal Standards Institute (ANSI) N.0996, "Perfrmance Criteria fr Radibiassayf DOE has develped a Radibiassay Accreditatin Prgram with scheduled implementatin in Radiatin Dse Limits Radiatin dse limits are nw cdified in 0 CFR 8.0,04,06,07,08 and are summarized in Exhibit. Under 8.04, Planned Special Expsures (PSEs) may be authrized in certain cnditins allwing an individual t receive expsures in excess f the dse limits shwn in Exhibit. With the apprpriate prir authrizatin, the annual dse limit fr an individual may be increased t an additinal rems abve the rutine dse limit as lng as the individual des nt exceed a cumulative lifetime f rems frm ther PSEs and dses abve the limits. PSE dses are required t be recrded separately and are nly intended t be used in exceptinal situatins where dse reductin alternatives are unavailable r \ Exhibit : ' DOE Dse Limits frm 0 CFR 8 Persnnel Categry Sectin f 0 CFR 8 Type f Expsure Acrnym Annual Limit General Emplyees 8.0 Ttal Effective Dse Equivalent Deep Dse Equivalent + Cmmitted Dse Equivalent t any rgan r tissue (except lens f the eye). This is ften referred t as the Ttal Organ Dse Equivalent DDE+CDE ITODE) rems 0 rems Lens f the Eye Dse Equivalent LDE rems Declared Pregnant Wrker L_ Minrs I Members f [ the Public 8.06 Shallw Dse Equivalent t the skin f the Whlebdy r t any Extremity SDEWB and SDEME 0 rems Ttal Effective Dse Equivalent I 0. rem per gestatin perid 8.07 Ttal Effective Dse Equivalent 0. rem 8.08 i Ttal Effective Dse Equivalent 0. rem 996 Reprt Standards and Requirements

18 impractical. Restrictins n the use f PSEs are extensive and, fr this reasn, they are expected t be rarely used at DOE... Administrative Cntrl Levels Administrative Cntrl Levels (ACLs) were included in the RadCn Manual. ACLs are established belw the regulatry dse limits t administratively cntrl and help reduce individual and cllective radiatin dse. ACLs are multitiered, with increasing levels f authrity required t apprve a higher level f expsure. The RadCn Manual established a DOE ACL f rem per year per persn fr all DOE activities. Prir t allwing an individual t exceed this level, apprval frm the apprpriate Secretarial Officer r designee must be received. In additin, cntractrs were required t establish an annual facility ACL. This cntrl level is established by the cntractr senir site executive and is based upn an evaluatin f histrical and prjected radiatin expsures, wrklad, and missin. The RadCn Manual suggests an annual facility ACL f 0. rem r less; hwever, the Manual als states that a cntrl level greater than. rem is, in mst cases, nt sufficiently challenging. Apprval by the cntractr senir site executive must be received prir t an individual exceeding the facility ACL. ACLs are nt specified in 0 CFR 8. Hwever, they are specified under DOE Ntice 44.. Administrative cntrls are required t be implemented t keep dses belw the dse limits and t keep dses ALARA. DOE N 44. establishes the fllwing administrative cntrl limits: a rem annual, a rem cumulative per year f age, and requires that a facilityspecific ACL be established fr each site... ALARA Principle Up until the 970s, the fundamental radiatin prtectin principle was t limit ccupatinal radiatin dse t quantities less than the regulatry limits and t be cncerned mainly with high dse and high dse rate expsures. During the 970s, there was a fundamental shift within the radiatin prtectin cmmunity t be cncerned with lw dse and lw dse rate expsures because it can be inferred frm the linear nthreshld dse respnse hypthesis that there is an increased level f risk assciated with any radiatin expsure. The ALAP (As Lw As Practicable) cncept was initiated and became part f numerus guidance dcuments and radiatin prtectin gd practices. ALAP was eventually replaced by ALARA. DOE Order 480., the RadCn Manual, and 0 CFR 8 frmalized the guidance and required that each DOE facility have an ALARA Prgram as part f its verall Radiatin Prtectin Prgram. The ALARA methdlgy cnsiders bth individual and grup dses and generally invlves a cst/benefit analysis. The analysis cnsiders scial.technical, ecnmic, practical, and public plicy aspects t the verall gal f dse reductin. Because it is nt feasible t reduce all dses at DOE facilities t zer, ALARA cst/benefit analysis must be used t ptimize levels f radiatin dse reductin. Accrding t the ALARA principle, resurces spent t reduce dse needs t be balanced against the risks avided. Reducing dses belw this pint results in a misallcatin f resurces; the resurces culd be spent elsewhere and have a greater impact n health and safety. T ensure that dses are maintained ALARA at DOE facilities, the DOE mandated in DOE Order 480. and 4 DOE Occupatinal Radiatin Expsure

19 subsequently in the RadCn Manual that ALARA plans and prcedures be implemented and dcumented. T help facilities meet this requirement, the DOE develped a manual f gd practices fr reducing expsures t ALARA levels []. This dcument includes guidelines fr administratin f ALARA prgrams, techniques fr perfrming ALARA calculatins based n cst/benefit principles, guidelines fr setting and evaluating ALARA gals, and methds fr incrprating ALARA criteria int bth radilgical design and peratins. The establishment f ALARA as a required practice at DOE facilities demnstrates DOE's cmmitment t ensure minimum risk t wrkers frm the peratin f its facilities.. Reprting Requirements In 987, the DOE prmulgated revised reprting requirements in DOE Order 484. ^Envirnmental Prtectin, Safety, and Health Prtectin Infrmatin Reprting Requirements." Previusly, cntractrs were required t reprt nly the number f individuals wh received an ccupatinal whlebdy expsure in ne f 6 dse equivalent ranges. The revised Order requires the reprting f expsure recrds fr each emplyee and visitr. Required dse data reprting includes the, internal dse equivalent, shallw dse equivalent t the skin and extremities, and Deep Dse Equivalent (DDE). Other reprted data included the individual's age,sex, emplyment status, and ccupatin, as well as the relevant rganizatin and facility type. Occupatinal radiatin expsure reprting requirements are nw included in DOE M., which became effective September 0,99. The reprting requirements under DOE M. are very similar t thse under Order Change in internal Dse Methdlgy Prir t 989, intakes f radinuclides int the bdy were nt reprted as dse, but as bdy burden in units f activity (uci) f intake. The implementatin f DOE Order 480. in 989 specified that the intakes f radinuclides be cnverted t internal dse and reprted using the annual effective dse equivalent (AEDE) methdlgy. With the implementatin f the RadCn Manual in 99, the required methdlgy used t calculate and reprt internal dse was changed frm the AEDE t the 0year CEDE. The change was made t cnfrm with Federal Guidance Reprt # (987) which was based upn Internatinal Cmmissin n Radilgic Prtectin (ICRP) and Natinal Cuncil n Radiatin Prtectin and Measurements (NCRP) recmmendatins. These recmmendatins were als the driver behind the revised 0 CFR 0 [],which was implemented in 994 regulating cmmercial nuclear pwer plants and ther cmmercial uses f radiatin and radiactive materials. The CEDE methdlgy is nw cdified in 0 CFR 8. The fllwing is a descriptin f these methdlgies and a discussin f hw this change has impacted the DOE dse data..4. Annual Effective Dse Equivalent The AEDE methd f determining internal dse invlves calculating the annual dse t the wrker fr each year since the riginal intake event. Because many f the radinuclides used at DOE are lnglived, wrkers can receive a dse frm past intakes fr many years, even a lifetime. DOE adpted the AEDE methd fr calculating internal dse equivalent Readers shuld nte that the methd f calculating internal dse changed frm AEDE t CEDE between 99 and Reprt Standards and Requirements

20 because the annual dse resulting frm an intake was mre representative f the actual dse received by the wrker during each calendar year. The AEDE methd is prblematic frm a radilgical cntrl viewpint. It des nt accunt fr the dse that wuld be received by an individual when nt emplyed by DOE. Facilities must keep track f prir year intakes t determine the dse fr the current year. The AEDE methd des nt cnsider the future dse t the wrker resulting frm a current year intake. The AEDE methd may als adversely impact the individual's future jb ptential. The accumulatin f prir year AEDE dses (legacy dses) may result in a current year dse in excess f the facility's ACL and restrict the individual's current year radiatin wrk pprtunities..4. Cmmitted Effective Dse Equivalent The CEDE methd assigns all f the dse the individual will receive frm an intake fr the next 0 years t the year the intake ccurred. The sum f all AEDE dses ver 0 years frm a given intake f radinuclides is equal t the CEDE frm the same intake. By assigning all f the future dse t the year f intake, even small intakes f lnglived radiactive material can result in a relatively large dse being assigned t a single year in the year f intake. The CEDE increases the pressure n facilities t limit such expsures because the internal dse des nt have t be cnsidered in future years. DOE can limit internal dse during the year f ccurrence while nt unduly impacting the wrker's future emplyability..4. Impact n the Dse Data This change in internal dse accunting and reprting has tw main impacts n the DOE dse data. First and fremst is that "legacy dses" (internal AEDE dse resulting frm intakes in years prir t the dse reprt year) are included in the cllective shwn in this reprt fr 99 and 99. Legacy dses represent a significant amunt f dse t the DOE wrker ppulatin during these years. In 99, nearly,00 individuals were receiving 6% f their annual dse frm intakes that ccurred in prir years, many having ccurred 0 t 0 years befre. In the analysis f expsures in excess f the DOE limits and the rem ACL presented in Sectins.. and.., readers shuld nte that mst f the expsures fr 99 and 99 were because f the inclusin f the AEDE frm prir year intakes. Beginning in 99, internal dse was reprted using the CEDE methdlgy Legacy dses were n lnger included r reprted because the CEDE is calculated nly frm new intakes ccurring during the year f the reprt. The new reprting requirements did nt require the reprting f internal dse resulting frm intakes during prir mnitring years. Because these legacy dses are n lnger reprted, there is an apparent large drp frm 99 t 99 in the ttal cllective dse fr all wrkers, and in the number f wrkers wh received high dses. Where applicable, the cntributin frm legacy dse has been highlighted in this reprt. Readers shuld be alert t the significance f this change t crrectly interpret the data. 6 DOE Occupatinal Radiatin Expsure

21 The secnd majr impact f the change frm AEDE t CEDE is in the internal dse fr 99 thrugh 99. As nted previusly, the CEDE includes the dse t the individual fr the next 0 years. This greatly magnifies the impact f small intakes f lnglived radinuclides. Intakes that wuld have resulted in an AEDE belw ACLs prir t 99 nw may result in a CEDE abve the regulatry limits. Fr lnglived radinuclides, the difference in values between AEDE and CEDE may be up t 0 times. It is imprtant t nte that the change frm AEDE t CEDE impacted the calculatin f dse frm nly lnglived istpes.such as uranium and plutnium. Internal dse frm the intake f istpes with retentin perids f less than a year, such as tritium, were nt impacted. Fr shrtlived istpes r istpes with shrt retentin perids, AEDE is equal t the CEDE because the entire dse is accrued during the year f intake..4.4 External Dse The change frm the AEDE t CEDE fr internal dse des nt affect the reprting f external dse. The nly changes in the DDE data frm 987 thrugh 996 have been the cntinuing imprvements in dsimeter detectin levels and standardizatin thrugh accreditatin by DOELAR Interpreting the trends f DDE during this perid is, therefre, cnsistent. 996 Reprt Standards and Requirements 7

22 \S This page intentinally left blank. D0E Occupatinal Radiatin Expsure

23 A J IN* Y i Occupatinal Radiatin Dse at DOE. Analysis f the Data The purpse f analyzing ccupatinal radiatin dse data is t reveal pprtunities t imprve safety and t demnstrate perfrmance. This is accmplished thrugh analysis and explanatin f bserved trends. Several indicatrs were identified frm the data submitted t the central data repsitry that can be used t evaluate the ccupatinal radiatin expsures received at DOE facilities. Analysis f these indicatrs falls int three categries: cllective, individual, and site. In additin, the key indicatrs are analyzed t identify and crrelate parameters having an impact n radiatin dse at DOE. The key indicatrs fr the analysis f cllective data are: cllective dse, number f mnitred individuals and individuals with measurable dse, average measurable dse, and the distributin f dse. Analysis f individual dse data includes an examinatin f dses exceeding DOE regulatry limits, and dses exceeding the rem DOE ACL. Analysis f site data includes cmparisns by site, labr categry, and facility type. Additinal infrmatin is prvided cncerning activities at sites cntributing t the cllective dse.. Analysis f Cllective Data.. Number f Mnitred Individuals The number f mnitred individuals represents the size f the wrker ppulatin at DOE prvided with dsimetry. This number represents the sum f all mnitred individuals, including all DOE emplyees, cntractrs, and visitrs. The number f mnitred individuals is an indicatin f the size f a dsimetry prgram, but it is nt necessarily an indicatr f the size f the expsed wrkfrce. This is because f the cnservative practice at sme DOE facilities f prviding dsimetry t individuals fr reasns ther than the ptential fr expsure t radiatin and/r radiactive materials exceeding the mnitring threshlds. Many individuals are mnitred fr reasns such as security, administrative cnvenience, and legal liability. Sme sites ffer mnitring fr any individual wh requests mnitring, independent f the ptential fr expsure. Fr this reasn, wrkers receiving measurable dse better represent the expsed wrkfrce... Number f Individuals with Measurable Dse The DOE uses the number f individuals receiving measurable dse t represent the expsed wrkfrce size. The number f individuals with measurable dse includes any individuals with reprted greater than zer. Exhibit shws the ttal number f wrkers at DOE, the ttal number mnitred, and the number with measurable dse fr the past years. The percentage f the DOE wrkfrce mnitred fr radiatin expsure has increased by % frm 99 t 996. Hwever, mst f the mnitred individuals d nt receive any measurable radiatin dse. Only f mnitred individuals (4% f the DOE wrkfrce) received a measurable dse during the past years. The number f individuals receiving a measurable dse has decreased by % frm 99 t 996. The percentage f mnitred wrkers that received measurable dse has decreased by % frm 99 t 996. In summary, a larger percentage f the DOE wrkfrce was mnitred fr radiatin in 996, while a smaller percentage f the mnitred individuals received a measurable dse. «^ «==i, 996 Reprt Occupatinal Radiatin Dse at DOE

24 [Exhibit : \ Mnitring f the DOE Wrkfrce 00,000 80,000 I I Number f DOE Wrkers and Cntractrs I I Ttal Mnitred I I Number with Measurable Dse Twenty percent f mnitred wrkers received a measurable dse ver the past years. The number f wrkers with measurable dse has decreased by % ver the past years. The number f wrkers with a measurable dse decreased by 4% between 99 and 996. Abut half () f the 8 sites experienced decreases in the number f wrkers with measurable dse frm 99 t 996, with the largest decreases ccurring at the Prtsmuth Gaseus Plant (PORTS) and Ls Alams Natinal Labratry (LANL) sites. Overall, the number f individuals with a measurable dse decreased by 4% between 99 and 996. A discussin f activities at varius facilities is included in Sectin.... Cllective Dse The cllective dse is the sum f the dse received by all individuals with measurable dse (Exhibit ) and is measured in units f persnrem. The cllective dse is an indicatr f the verall radiatin expsure at DOE facilities and includes the dse t all DOE emplyees, cntractrs, and visitrs. DOE mnitrs the cllective dse as a measure f the verall perfrmance f radiatin prtectin prgrams t keep individual expsures and cllective expsures ALARA. As shwn in Exhibit, the cllective decreased at DOE by frm 99 t 996. Half f the DOE sites reprted decreases in the cllective frm the 99 values. Five ut f seven f the highest dse sites reprted decreases in the cllective. These seven sites are (in descending rder f cllective dse) Rcky Flats, Hanfrd, Savannah River, Ls Alams, Idah, Brkhaven, and Oak Ridge. A discussin f the activities leading t this decrease is included in Sectin.. DOE Occupatinal Radiatin Expsure

25 I Exhibit : Cmpnents f, 99996,00 u Legend Internal Dse (AEDE) frm New Intakes During the Mnitring Year Internal Dse (AEDE) frm Prir Intakes Internal Dse (CEDE) frm New Intakes During the Mnitring Year Phtn (Deep) Neutrn The cllective decreased by at DOE frm 99 t 996. Half f the DOE sites reprted decreases in the cllective frm the 99 values. Phtn dse the cmpnent f external dse frm gamma r xray electrmagnetic radiatin. Neutrn dse the cmpnent f external dse frm neutrns ejected frm the nucleus f an atm during nuclear reactins. Internal Dse radiatin dse resulting frm radiactive material taken int the bdy. 996 Reprt Occupatinal Radiatin Dse at DOE

26 It is imprtant t nte that the cllective includes the cmpnents f external dse and internal dse. Exhibit shws thetypesf radiatin and their cntributin t the cllective. The phtn, neutrn, and internal dse cmpnents are shwn. The large decrease in the internal dse frm 99 t 99 was due t the change in calculating and reprting f the internal dse frm AEDE t CEDE. It must be nted that the internal dse shwn in Exhibit fr 99 thrugh 996 is based n the CEDE and therefre shuld nt be cmpared with the AEDE internal dse frm 99. The internal dse cmpnent increased by 74% frm 99 t 996, primarily due t the single internal dse f. rem at SRS as well as increases in internal dse at Oak Ridge, Prtsmuth and LANL. Because the reprting f internal dse changed in 99 (see Sectin.4), it is necessary t analyze the cllective external dse during this time perid in rder t examine the cllective dse trend acrss the past years. External dse is cmprised f radiatin dse frm phtns (gamma r xray) and neutrns. The phtn dse remained fairly stable at abut,00 persnrem during the years 99994,but increased by 4% t,44 persnrem in 99 due t increased activities at several f the highest dse sites. Activities respnsible fr increased dse at these sites included wrk n pwer surces fr the Natinal Aernautics and Space Administratin (NASA), increased research at an acceleratr facility, nuclear materials stabilizatin activities, and decntaminatin and decmmissining wrk. In 996, the phtn dse decreased by % t a value f,78 persnrem. Sites attributed the reductin in dse t the cmpletin f several decntaminatin and decmmissining prjects, reduced spent fuel strage activities, and effective ALARA practices. A discussin f the activities leading t this decrease is included in Sectin.. The neutrn cmpnent f the decreased by % frm 99 t 996. This is primarily due t decreases in the neutrn dse at LANL and Brkhaven Natinal Labratry (BNL). LANL cntributed 4 f the neutrn dse at the DOE. This is because LANL is ne f the few remaining sites t actively handle plutnium. Wrking with plutnium in glvebxes results in neutrn dse frm the alpha;neutrn reactin and frm spntaneus fissin f the plutnium. Activities invlving plutnium at LANL decreased in 996, which resulted in decreased neutrn dse by frm 74. persnrem in 99 t.6 persnrem in 996. The cllective neutrn dse by site is shwn in Appendix B. Cllective dse infrmatin fr prir years can be fund in Appendix B4...4 Average Measurable Dse The average measurable dse t DOE wrkers is determined by dividing the cllective dse by the number f individuals with measurable dse. This is cnsidered a key indicatr f the verall level f radiatin dse received by DOE wrkers. The average measurable is shwn in Exhibit. The average measurable A DOE Occupatinal Radiatin Expsure

27 Exhibit : Average Measurable DDE Dse and Average Measurable n Average Measurable DDE (rem) Average Measurable (rem) Nte: 99 (=DDE + AEDE) ( = DDE + CEDE) decreased by 7% frm 99 t 994, increased by frm 994 t 99, and decreased by 6% frm 99 t 996.The decrease in the average measurable frm 99 t 996 is due t the decrease in the cllective cmbined with the 4% decrease in the number f individuals with measurable. The average measurable DDE als decreased by 9% frm 99 t 996. The average measurable DDE and values are prvided fr trending purpses, nt fr cmparisn between DDE and values. While the cllective dse and average measurable dse serve as measures f the magnitude f the dse accrued by wrkers at DOE, they d nt prvide any indicatin f hw each dse was distributed acrss the wrker ppulatin. An effective measure f ALARA is the reductin in dse t individuals, as well as t the verall wrkfrce... Dse Distributin Expsure data are cmmnly analyzed in terms f dse intervals t depict the manner in which the dse is distributed amng the wrker ppulatin. Exhibit 4 shws the number f individuals in each f 8 different dse ranges. The dse ranges are presented fr the and DDE t allw analysis f the dse independent f the change in internal dse reprting frm 99 t 99 (see Sectin.). The number f individuals The average measurable decreased by 6% frm 99 t Reprt Occupatinal Radiatin Dse at DOE

28 Exhibit 4: Dse Distributins, Ttal Mnitred Less than Measurable Measurable < > Number with Meas. Dse Number with Dse >0. rem j i,896 :,8 j:, 46 6 ' 9! 6 ' li 98,900l 0,947,09 j,0,8,487 i , ,7 I,7 i 7,04 9,44 4,8,09,8 I,79 \,,88 0,90 9,6, , j 9,4 i 0,66! 04,79 I 00,494, '' 0,469 I 9,7,47j!,89 ',4 8,9, 8,76, ,4 74 7,4 7, ,04 6, j 6,,7,90 4,66,78 I,879i!,797 I! i 7,76 7,76 j,9,79,6,48,7 4,40 I 4,9,966 0,44 7,90, ,9,89 % f Individuals with Meas. Dse 4% 8% % % 9% 8% 8% 8% Cllective Dse (persnrem) Average Measurable Dse (rem) i, II,04 ' 0.06 il,644 II 0.066,4 ' I, ,840 J 0.078, j,6 j I 0.07, ' Individuals with dses equal t the dse value separaang the dse ranges are included in the next higher dse range receiving dses abve 0. rem is als included t shw the number f individuals with dses abve the mnitring threshld specified in 0 CFR 8.40(a) and (c). Exhibit 4 shws that few individuals receive dses in the higher ranges and that the vast majrity f dses are at lw levels. This is ne indicatin that ALARA principles are being applied t keep dses at lw levels. A few examples f successful ALARA practices are included in Sectin 4. Anther way t examine the dse distributin is t analyze the percentage f the dse received abve a certain dse value cmpared t the ttal cllective dse. In 98, the United Natins Scientific Cmmittee n the Effects f Atmic Radiatin (UNSCEAR) [4] defined CRas the fractin f the cllective dse delivered abve. rem. UNSCEAR identified this parameter as an indicatr f the effrts t reduce high dses. The DOE has adapted this apprach t allw a quantificatin and analysis f the dse distributin at DOE. Ideally nly a small percentage f the cllective dse is delivered t individuals in the higher dse ranges. In additin, a 6 DOE Occupatinal Radiatin Expsure

29 Exhibit : Distributin f Cllective Dse vs Dse Values, T trend in the percentage abve a certain dse range decreasing ver time indicates the effectiveness f ALARA prgrams t reduce dses t individuals in the higher dse ranges. Exhibit shws the distributin rati given by percentage f cllective and DDE abve each f five dse values, frm 0. rem t rem. This graph shws the tw prperties described abve as the gal f effective ALARA prgrams at DOE: () a relatively small percentage f the cllective dse accrued in the high dse ranges, and () a decreasing trend ver time f the percentage f the cllective dse accrued in the higher dse ranges. Much f the bserved trend that ccurred frm 99 t 99 cincides with the change frm AEDE t CEDE. The data fr 996 indicate that the percentage f the cllective dse accrued abve 0. rem has decreased frm 99 in all dse ranges except fr the dse abve.0 rem, which experienced a small increase. The increase in the percentage abve.0 rem was due t three individuals receiving dses in excess f.0 rem (see Sectin..) and ne individual in excess f the rem limit (see Sectin..). The 99 distributin exhibited an increase in all f the dse ranges, which crrespnds with the % increase in the cllective dse in 99. In additin, the cllective dse increase in 99 tended t be accrued amng individuals in the dse ranges frm 0. rem t.0 rem. Mst f this increased dse was accrued by individuals in the peratins, scientists, and technicians labr categries. The distributin f the cllective dse in 996 reflects the decrease in the cllective dse frm 99 t 996 and is similar t the distributin in 994. Over the past 4 years, the general trend has been an increase in the percentage f dse abve each dse range frm 99 t 99 and then a decrease in 996. This cincides 996 Reprt Occupatinal Radiatin Dse at DOE 7

30 There was ne individual with a dse in excess f the rem limit in 996. All f the events resulting in dses in excess f DOE limits in 99 and 99 were frm internal dse. with the increase in the cllective dse reprted in 99 and the increase in activities resulting in radiatin expsures at the highest dse sites during 99. Mst f these sites reprted decreases in the cllective dse and radilgical activities in 996 (see Sectin.), which cincides with the bserved decreases in Exhibit.. Dse t Individuals The abve analyses are all based n cllective dse data fr DOE. Frm an individual wrker perspective as well as a regulatry perspective, it is imprtant t mre clsely examine the dses received by individuals in the high dse ranges t mre thrughly understand the circumstances leading t high dses in the wrkplace and hw these dses may be mitigated in the future. The fllwing analysis fcuses n dses received by individuals that were in excess f the DOE limit ( rem ) and the DOE ACL ( rem )... Dses in Excess f DOE Limits Exhibit 6 shws the number f dses in excess f the regulatry limit ( rem ) frm 99 thrugh 996. Further infrmatin cncerning the individual dses, radinuclides invlved, and site where the dses ccurred is shwn in Exhibit 7. Mst f the dses in excess f the limit shwn fr 99 were frm legacy intakes as nted in the exhibit. There was ne individual in 996 wh received a dse in excess f the rem limit (see Exhibit ). This individual received an internal CEDE dse f. rem due t an unanticipated intake f plutnium at the Savannah River Site. The intake ccurred in December f 996, but was discvered and reprted in 997 Exhibit 6: Number f Individuals Exceeding rem (), LEGEND UJ Q UJ E v in r c <u X III Internal Dse (AEDE) frm New Intakes I i Internal Dse (AEDE) frm Prir Intakes (0 q > E t One ptential dse was reprted t ORPS in 997. See Sectin... 8 DOE Occupatinal Radiatin Expsure

31 I Exhibit 7: Dses in Excess f DOE Limits, Year Year Uptake (rem) DDE (rem) Internal Dse* Intake Nuclides Facility Types Site <99 <99 < Pu8 Pu9, Pu40, Am4 Pu9, Pu40,Am4I Pu9,Pu40, Am4 Pu9,Pu40, Am4 Research, General Weapns Fabricatin Weapns Fabricatin Weapns Fabricatin Weapns Fabricatin Ls Alams Nat'l. Lab. Rcky Flats Rcky Flats Rcky Flats Rcky Flats Pu9, Pu40 Pu9, Pu40 Pu9, Pu40 Pu9,Pu40, Am4 Maint. & Supprt Research, General Research, General Weapns Fabricatin Ls Alams Nat'l. Lab. Ls Alams Nat'l. Lab. Ls Alams Nat'l. Lab. Rcky Flats Pu8, Pu9, Pu4 Fuel Prcessing Savannah River * AEDE fr 99, CEDE fr * * One ptential dse was reprted t ORPS in 997. See Sectin... < Year f uptake is unknwn, but is knwn t be prir t the year indicated. after a special fllwup biassay was perfrmed. After a thrugh review, it was cncluded that the individual received the intake during the remval f a radilgical cntainment hut. The peratr walked thrugh an area f elevated levels f airbrne cntaminatin withut the use f respiratry prtectin. Causes cited fr this event were persnnel errr, management prblems, and prcedural prblems. Crrective actins included briefings and persnnel training, a Jb Hazards Analysis review, and prcedural mdificatins. Fr mre infrmatin n this ccurrence, see the Occurrence Reprt SRWSRCFCAN There has been an ccurrence reprt submitted t ORPS by Rcky Flats as f December 997 that indicates that an individual received an intake in 99 that may result in a CEDE dse in excess f rem. The interim dse assessment resulted in an assigned CEDE f rem fr 99. The final dse assessment has nt yet been determined, nr has the cause f the intake. Fr further infrmatin, see Occurrence Reprt RFOKHLL70PS Due t the interim nature f this expsure infrmatin, this dse has nt been included in the tables presented in this reprt. Upn final dse determinatin, subsequent annual reprts will reflect this 99 dse... Dses in Excess f Administrative Cntrl Level The RadCn Manual recmmends a rem ACL fr, which is nt t be exceeded withut prir DOE apprval. Each DOE site is required t establish its wn, mre restrictive ACLs that require cntractr management apprval t be exceeded. The number f individuals receiving dses in excess f the rem ACL is a measure f the effectiveness f DOE's radiatin prtectin prgram. The number f individuals with expsures abve rem drpped cnsiderably frm 99 t 99, as shwn in Exhibit 8. Hwever, nearly all f this decrease ccurred between 99 and 99 because f the change in internal dse 996 Reprt Occupatinal Radiatin Dse at DOE 9

32 \ Exhibit 8: Number f Dses in Excess f the DOE rem ACL, LEGEND Internal Dse (AEDE) Accrued during Mnitring Year (0 UJ IS > E _ s CM O O) S? <" Z x UJ Internal Dse (AEDE) Accrued frm Legacy Intakes Internal Dse (CEDE) Accrued during Mnitring Year External Dse (DDE) Accrued during Mnitring Year reprting. Legacy internal dses cntributed t the vast majrity f the individuals abve rem prir t 99. If ne excludes the legacy dses frm prir years, it shuld be nted that the number f dses in excess f rem in 996 is the same as the number in 99. In 99 the number increased t six. This was als the first year f reprting the 0year CEDE, which results in the calculatin f higher internal dses frm lnglived nuclides. Fur f these six dses in 99 als exceeded the rem limit as described in Sectin... There were fur dses in excess f the rem ACL in 996. One f the dses was frm external dse, and the secnd and third were due t internal dse frm the intake f radiactive material. The furth dse abve the rem ACL was due t a cmbinatin f internal and external dse. One f the internal dses als exceeded the rem limit as described in Sectin... The ne external expsure abve rem was received by an individual wrking n DOE's Nrth Krea Prject. This individual received a dse f.0 rem.the prject is in supprt f the President f the United States nnprliferatin initiative. The Office f Nnprliferatin and Arms Cntrl (NN40), is securing the nuclear spent fuel lcated in the Demcratic Peples Republic f Krea (DPRK) and placing it under Internatinal Atmic Energy Agency safeguards. The wrk is being perfrmed under the US/DPRK Agreed Framewrk, which requires the DPRK t cease their nuclear weapns prgram in return fr tw Light Water Reactrs (LWR) and Heavy Fuel Oil during the cnstructin f the LWRs. The prject has the ptential fr higher than average dses due t the highly radiactive nature f the spent fuel. Tw f the internal dses in excess f rem ccurred at LANL and invlved intakes f plutnium9 at the TA Plutnium Prcessing Facility. One 0 DOE Occupatinal Radiatin Expsure

33 individual received a CEDE dse f. rem while the ther received a CEDE dse f. rem in additin t an external deep dse f rem. The tw intakes ccurred during separate events, but bth f them invlved glvebx failures. In ne event a glve failed during transfer f materials frm ne glvebx t anther. In the ther event, a large gasket arund a glvebx failed. In bth events the cntaminatin was detected and the expsed individuals were subjected t biassay prgrams, and the activities invlving the glvebxes were suspended until they culd be repaired r replaced. Because these expsures were unplanned, there was n advanced DOE apprval fr exceeding the DOE ACL. Fr mre infrmatin cncerning these events, see the Occurrence Reprts ALO LALANLTA and ALOLA LANLTA The ther internal dse in excess f the rem ACL was the. CEDE expsure at Savannah River; see sectin.. fr mre details... Internal Depsitins f Radiactive Material As discussed in Sectin.., in the past, sme f the mst significant dses t individuals have been the result f intakes f radiactive material. Fr this reasn, DOE emphasizes the need t avid intakes and tracks the number f intakes as a perfrmance measure. The number f internal depsitins f radiactive material (therwise knwn as wrker intakes) fr is shwn in Exhibit 9. The internal depsitins were categrized int ne f eight radinuclide grups. Intakes invlving multiple nuclides are listed as "mixed" nuclides. Nuclides where fewer than ten individuals had intakes ver the year perid were gruped tgether as "ther" nuclides. Only thse recrds with internal dse greater than zer are included in this analysis. It shuld be nted that the different nuclides have different radilgical prperties resulting in varying minimum levels f detectin and reprting. Exhibit 9 shws the intakes that ccurred during the past years that were reprted using the CEDE internal dse calculatin methdlgy Fr an analysis f legacy dses frm prir years, see the annual reprt fr the perid The internal dse recrds indicate that the majrity f the intakes reprted are at very lw dses. I Exhibit 9: Number f Intakes, Cllective Internal Dse, and Average Dse by Nuclides, Nuclide Number f Wrkers with New Intakes* Cllective CEDE (persnrem) Average CEDE (rem) Year Hydrgen (Tritium) Technetium Thrium Uranium < ' ! Plutnium Americium Other Mixed Ttals 4 6,8 4 4,8, , Nte: Arrwed values indicate the greatest value in each clumn. * Individuals may have received intakes f mre than ne nuclide and therefre may be cunted mre than nce. 996 Reprt Occupatinal Radiatin Dse at DOE

34 Mst intakes f radiactive material during the year perid were the result f expsure t tritium r uranium. The average CEDE dses frm these intakes are quite lw because f the radilgical and bilgical characteristics f these radinuclides and the large number f mnitred individuals with lw CEDE dse frm these radinuclides. The highest average and cllective CEDE dse fr 996 was frm plutnium. Plutnium yields particularly high values fr CEDE because f the lng radilgical halflife and the lngterm depsitin f the material in the bne. Americium intakes have a high average CEDE fr similar reasns, but the number f intakes and cllective dse are much smaller than fr plutnium. Bth the cllective and average dses fr plutnium increased in 996 primarily due t tw individuals wh received dses abve rem (see Sectin..) and ne individual wh received a dse f. rem CEDE (see Sectin..). The cllective CEDE frm thrium increased due t an increase in intakes at the Prtsmuth Gaseus Diffusin Plant. The internal dse recrds indicate that the majrity f the intakes reprted are at very lw dses. In 996,8% f the internal dse recrds were fr dses belw 0.00 rem.these recrds represent nly % f the cllective internal dse. The ther 7% f the internal dse recrds had dses abve 0.00 rem and accunted fr 88% f the cllective internal dse. Over the year perid, internal dses frm new intakes accunted fr nly 4% f the cllective. Only % f the individuals wh received internal dse were abve the mnitring threshld specified in 0 CFR 8.40 (c). Exhibit 0 shws the distributin f the internal dse frm 99 t 996. The ttal number f individuals with dses in each dse range is fr each recrd f intake. The internal dse des nt include dses frm prir intakes (legacy AEDE dse). Individuals with multiple intakes during the year may be cunted mre than nce in Exhibit 9 and, fr this reasn, the ttals in Exhibit 0 may nt crrespnd t thse in Exhibit 9. Dses belw 0.00 rem are shwn as a separate dse range t shw the large number f dses in this lwdse range. Even with the change in methdlgy frm AEDE t CEDE in 99, all but nine f the dses are belw the rem ACL and all but five are belw the rem DOE dse limit fr the years All but tw f the internal dses were belw rem in 996. The distributin f internal dse by site and nuclide fr 996 is presented in Appendix B. When examining trends invlving internal dse, several factrs shuld be cnsidered. Sme f the largest changes I Exhibit 0: Internal Dse Distributin frm Intakes, Number f Individuals* with internal dse in each dse range (rem) Year Meas >.0 Ttal N. f Indiv.* Ttal Cllective Internal Dse (persnrem) ,97],,7,64, , 70 ; , , ; 4 4 ' H r I 4 L i < Nte Individuals with dses equal t the dse value separating the dse ranges are included in the next higher dse range * Individuals may have multiple intakes in a year and, therefre, may be cunted mre than nce ** Cllective internal dse = AEDE fr 99, CEDE fr 99996,68i,979,99,8, DOE Occupatinal Radiatin Expsure

35 in the number f reprted intakes ver the years were the result f changes in internal dsimetry practices. Peridically, sites will change mnitring practices r prcedures, which may invlve increasing the sensitivity f the detectin equipment, thereby increasing the number f individuals with measurable internal dses. Cnversely, sites may determine that internal mnitring is n lnger required due t histrically lw levels f internal dse r a decreased ptential fr intake. There are relatively few intakes each year, and the CEDE methd f calculating internal dse can result in large internal dses frm the intake f lnglived nuclides. This can result in significant statistical variability f the internal dse data frm year t year..4 Site Analysis.4. Cllective by Operatins/Field Offices The cllective fr fr the majr DOE sites and Operatins/Field Offices is shwn in Exhibit. A list f the cllective and number f individuals with measurable fr the DOE Operatins/Field Offices and sites is shwn in Exhibit. The cllective decreased by between 99 and 996 with seven f the highest dse sites (LANL, BNL, Idah, Oak Ridge, Rcky Flats, Hanfrd, and Savannah River) cntributing 8% f the ttal DOE cllective. Exhibit : Relative Cllective by Site/Facility Nte: A cmplete list f the cllective dse, number f individuals with measurable dse, and average measurable dse fr each Operatins/Field Office can be fund in Appendix B. 996 Reprt Occupatinal Radiatin Dse at DOE

36 \ Exhibit : Cllective and Number f Individuals with Measurable by Site/Facility, Operatins/ Field Office A ~*~«% % %% Q <\ A Q \% ' % > Albuquerque Ops. and Other Facilities Ls Alams Natinal Lab. (LANL) Pantex Plant (PP) Sandia Natinal Lab. (SNL) Uranium Mill Tailings Remedial Actin (UMTRA) Prject , , , Chicag Ops. and Other Facilities Argnne Nat'l. Lab. East (ANLE) Argnne Nat'l. Lab. West (ANLW) Brkhaven Nat'l. Lab.(BNL) Fermi Natl Acceleratr Lab. (FERMI) ' ' 97, ,448 8 DOE HQ Idah Nevada Oakland DOE Headquarters DOE Nrth Krea Prject Idah Site Nevada Test Site (NTS) Ops. and Other Facilities Lawrence Berkeley Lab. (LBL) Lawrence Livermre Nat'l. Lab. (LLNL) Stanfrd Linear Acceleratr Center (SLAC) , , J , Oak Ridge Ops. and Other Facilities Oak Ridge Site Paducah Gaseus Diff. Plant (PGDP) Prtsmuth Gaseus Diff. Plant (PORTS) , , , , Ohi Ops. and Other Facilities Fernald Envirnmental Management Prject Mund Plant West Valley > ,,7 > Rcky Flats Rcky Flats Eng. Tech. Site (RFETS).9, , ,40 Richland Hanfrd Site 4.8, ,00 6.7,76 Savannah River Savannah River Site (SRS) 4.4 6,844. 4,846 <.8 4,76 i Ttals,64.,90,840.,6,6.9,7 Nte Arrwed values indicate the greatest value in each clumn 4 DOE Occupatinal Radiatin Expsure

37 \ Exhibit : Dses by Labr Categry, Labr Categry Agriculture Cnstructin Labrers Management Misc. Prductin Scientists Service Technicians Transprt Unknwn Ttals! Number with Meas. Dse Cllective * (persnrem) Average Meas. (rem) , 807,00,6,090,04 l,,0 4, ,7,90 r.,00 79;,69!,496,779 96,99,944,6 Nte. Arrwed values indicate the greatest value in each clumn * = CEDE * DDE.4. Dse by Labr Categry DOE ccupatinal expsures are tracked by labr categry at each site t facilitate identificatin f expsure trends, which assist management in priritizing ALARA activities. Wrker ccupatin cdes are reprted in accrdance with DOE Order 484. (r the new DOE M.) and are gruped int majr labr categries in this reprt. The cllective t each labr categry fr are shwn in Exhibits and 4. Technicians and prductin staff have the highest cllective fr 996 because they generally handle mre radiactive surces than individuals in the ther labr categries. Thirtysix percent f the technician dse is attributed t radiatin mnitring technicians. The cllective is als high fr the "unknwn"and"miscellaneus" categries. One f the reasns this ccupatin categry cntains a large number f individuals is because LANL reprts all f their wrkers in this categry Thirtynine percent f the dse in this 8,88 4,,04f,44,88 j 69,76 40, il, i <i.. ', , ,6.9 categry is attributed t LANL. The LANL cmputer system des nt currently maintain the data necessary t reprt ccupatin cdes in accrdance with DOE M.. LANL is addressing this \ Exhibit 4: Graph f Dses by Labr Categry, Reprt Occupatinal Radiatin Dse at DOE

38 Exhibit : Graph f Dse by Facility Type, I 0 0 issue Other sites als reprt large numbers f individuals with an ccupatin cde f "unknwn." Typically these wrkers are subcntractrs r temprary wrkers. Infrmatin cncerning these wrkers tends t be limited. T examine internal dse by labr categry, the dse frm intake is presented in Appendix B0. In additin, Appendix B shws the distributin f by labr categry and ccupatin fr 996. The dse distributin fr each ccupatin included under each labr categry is presented. Exhibit 6: Dses by Facility Type, Facility Type.4. Dse by Facility Type DOE ccupatinal expsures are tracked by facility type at each site t better understand the nature f expsure trends and assist management in priritizing ALARA activities. Cntributin f certain facilitytypest the DOE cllective is shwn in Exhibits and 6. The cllective dse fr each facility type at each Operatins/Field Office is shwn in Appendix B7. Facility Type Number with Meas. Dse Cllective (persnrem) Average Meas. (rem) Acceleratr,70 I,78 f,4 j , j 0.06 Fuel/Uranium Enrichment Fuel Fabricatin,,40 II,9 ii,0 j) J Fuel Prcessing,049,0, Maintenance and Supprt Other,89 l,889,80 L,0,886 j, j ' ! Reactr, !, ; 0.06 Research, General Research, Fusin Waste Prcessing/Mgmt.,4,6 i!,9,69,4';,48,09 6 ', Weapns Fab. and Testing,444,4, ji Ttals,90,6,7,64.,840., Nte Arrwed values indicate the greatest value in each clumn * = CEDE * DDE 6 DOE Occupatinal Radiatin Expsure

39 Exhibit 7: Criteria fr Radiatin Expsure and Persnnel Cntaminatin Occurrence Reprting Occurrence Categry DOE M.A Criteria Radiatin Expsure Persnnel Cntaminatin Unusual OffNrmal Unusual OffNrmal Individuals receiving a dse in excess f the ccupatinal expsure limits (See Exhibit ) fr nsite expsure r exceeding the limits in DOE 400. fr ffsite expsures t a member f the public. Any single ccupatinal expsure that exceeds an expected expsure by 00 mrem. Any single unplanned expsure nsite t a minr, student, r member f the public that exceeds 0 mrem. Any dse that exceeds the limits specified in DOE 400. fr ffsite expsures t a member f the public. Any single ccurrence resulting in the cntaminatin f five r mre persnnel r clthing at a level exceeding the RadCn Manual values fr ttal cntaminatin limits. Any ccurrence requiring ffsite medical assistance fr cntaminated persnnel. Any measurement f persnnel r clthing cntaminatin ffsite due t DOE peratins. ij Any measurement f persnnel r clthing cntaminatin at a level I exceeding the RadCn Manual ttal cntaminatin limits. The highest cllective fr were thse at weapns fabricatin and testing facilities. Sixtyfur percent f this dse was accrued at Rcky Flats, with % and 7% frm Savannah River and Pantex, respectively. It shuld be nted that, althugh weapns fabricatin and testing facilities accunt fr the highest cllective dse, Rcky Flats and Savannah River accunt fr the majrity f this dse and these sites are nw primarily invlved in nuclear materials stabilizatin and waste management. T examine internal dse by facility type, the internal dse frm intake is presented in Appendix B Radiatin Prtectin Occurrence Reprts In additin t the recrds f individual radiatin expsure mnitring required by DOE M. (previusly DOE Order 484.),sites are required t reprt certain unusual r ffnrmal ccurrences invlving radiatin under DOE Order. (previusly DOE Order 000.B). These reprts are submitted t the Occurrence Reprting and Prcessing Service (ORPS) in accrdance with the reprting criteria f DOE M. A. Tw f the categries f ccurrences are directly related t ccupatinal expsure and are required t be reprted under Sectin 9. as "Grup 4" ccurrences. Grup 4A reprts are radiatin expsure ccurrences, and Grup 4B are persnnel cntaminatin ccurrence reprts. The ccurrence reprting requirements fr DOE M.A are summarized in Exhibit 7. These requirements became effective in July f 997. In summary, radiatin expsure ccurrences are reprted in instances where individuals were expsed t radiatin abve anticipated levels. persnnel cntaminatin ccurrences are reprted when persnnel r clthing are 996 Reprt Occupatinal Radiatin Dse at DOE

40 Exhibit 8: Radiatin Expsure Occurrence Reprts, I Exhibit 9: I Persnnel Cntaminatin Occurrence Reprts, Number f Reprts Number f Occurrences Number f Reprts Number f Occurrences l l l Year Number f Reprts I Unusual Occurrence Number f Occurrences I Unusual Occurrence OffNrmal OffNrmal The number f Radiatin Expsure ccurrences has decreased by 7% frm 994 t 996. The number f Persnnel Cntaminatin ccurrences has decreased by 4%. cntaminated abve certain threshlds. The number f reprts submitted t ORPS is indicative f breaches r lapses in radiatin prtectin practices resulting in unanticipated radiatin expsure r cntaminatin f persnnel r clthing. Increases r decreases in the number f these ccurrences may reflect trends in activities that result in radiatin expsures and the effectiveness f radiatin prtectin prgrams at DOE. It is imprtant t nte that reprts are submitted t ORPS fr an ccurrence r event. In sme cases, ne event culd result in the cntaminatin r expsure f multiple individuals. In ORPS, this is cunted as ne ccurrence, even thugh multiple individuals were expsed. In additin, ne ccurrence reprt may invlve multiple similar ccurrences. Fr this reasn, the number f ccurrences and the number f ccurrence reprts are cnsidered here. The number f ccurrences and ccurrence reprts fr radiatin expsures and persnnel cntaminatins is presented in Exhibits 8 and 9. The number f ccurrence reprts fr bthtypesf events has decreased ver the past years. The number f radiatin expsure ccurrence reprts has decreased by 7% ver the past years, while the number f persnnel cntaminatin reprts has decreased by 8%. Fr radiatin expsure ccurrences, there is n difference in the number f reprts and the number f ccurrences, indicating that n reprts were submitted that included multiple ccurrences. Therefre the number f ccurrences and ccurrence reprts decreased by 7%. Fr persnnel cntaminatin ccurrences, there have been several reprts that cntain multiple ccurrences that have been submitted ver the past years, but nly fr "ffnrmal" ccurrences. All f 8 DOE Occupatinal Radiatin Expsure

41 the ccurrence reprts that were categrized as "unusual" dealt with a single ccurrence. The number f persnnel cntaminatin ccurrences has decreased by 4% frm 994 t 996. The decrease in the number f radiatin expsure ccurrences is primarily due t decreases in the number f ccurrences at the Rcky Flats, Hanfrd, and Savannah River sites between 99 and 996. A ptential factr in the change in the number f radiatin expsure ccurrences is the change in reprting requirements in 996. DOE. became effective at the end f 99 and was in effect fr 996. Under the previus requirements f DOE Order 000.B,any expsure in excess f the facility administrative limits r 0 percent f the annual limit (e.g.,00 millirem), whichever is lwer, must be reprted as an ffnrmal radiatin expsure ccurrence. The new reprting requirements f DOE.A specify any single expsure that exceeds the expected expsure by 00 millirem.the reprting threshld is generally lwer under the new requirements, but fr sites that have lw facility administrative cntrl levels, the reprting threshld may be higher. The significance f this change in reprting requirements is difficult t determine because sites vary in the implementatin date f the requirements and sites vary in facility ACLs. The decrease in the number f persnnel cntaminatin reprts is primarily due t decreases fr the Oak Ridge site (mainly they Plant) and Argnne Natinal Lab., West (ANLW). Three factrs cntributed t the decrease at the Oak Ridge site. In 994.Y began cmbining multiple ccurrences int ne reprt, called "rllup" reprts. TheY Plant als underwent an peratinal standdwn during 994 that reduced the pprtunities fr these types f ccurrences. In additin, the reprting requirements in effect fr Oak Ridge facilities changed frm DOE Order 000.A t Order 000.B during 99. The reprting threshld fr persnnel cntaminatin ccurrences under 000.A was much lwer than 000.B, and therefre, mre ccurrences were reprtable. At ANLW, the decrease in persnnel cntaminatin reprts is due t the cmpletin f decntaminatin activities at tw 0year ld facilities the Fuel Cycle Facility, cmpleted in 99, and the Analytical Labratry, cmpleted during 99. Fr 996, f the ccurrence reprts (9%) shwn in Exhibit 8 invlved "ffnrmal" ccurrences. Seven f the reprts (4%) invlved internal dse, while 6 f the reprts (46%) invlved external dse. Of the seven reprts invlving internal dse, ne reprt was categrized as an "unusual" ccurrence, althugh it des nt meet the criteria f an unusual ccurrence specified in DOE Order. A. The individual did exceed the rem ACL, but did nt exceed the DOE ccupatinal dse limit f rem. This ccurrence is described in Sectin... Five f the reprts were fr unanticipated internal dses greater than 00 millirem. One reprt was fr a cntaminatin event that did nt result in internal dse.the six reprts invlving external radiatin were fr unanticipated dses f greater than 00 millirem f the planned dse. N radiatin expsure ccurrence reprts submitted t ORPS frm 994 t 996 have invlved expsures t minrs r members f the public. Persnnel cntaminatin ccurrences can invlve cntaminatin f the skin, clthing, r shes. Exhibit 0 shws the breakdwn f ccurrences by affected area frm 994 t 996. The affected area is nt recrded as part f the ORPS reprt 996 Reprt Occupatinal Radiatin Dse at DOE 9

42 Exhibit 0: Persnnel Cntaminatin Occurrences by Affected Area, Skin Clthing She Affected Area and must be determined by reviewing the text f each reprt. Sme ccurrences may invlve mre than ne affected area and therefre may be cunted mre than nce. Between 99 and 996, cntaminatin ccurrences invlving the skin and shes have decreased by % and % respectively. Clthing cntaminatins increased by % frm 99 t 996, but the 996 value was % belw the 994 value. Exhibits and shw the breakdwn f ccurrence reprts fr radiatin expsure and persnnel cntaminatin by site fr the year perid 994 t 996. Frtyeight percent f the radiatin expsure ccurrences were reprted by tw sites, Rcky Flats and Hanfrd. Persnnel cntaminatin ccurrence reprts are distributed amng the sites, with Hanfrd and the Oak Ridge sites submitting 4% f the reprts. Almst all f the sites submitted fewer reprts fr bth types f expsure ccurrence fr 996 with the exceptin f Hanfrd and LANL, which submitted mre persnnel cntaminatin reprts in 996. I Exhibit : I Exhibit : Radiatin Expsure Occurrences by Site, \ Persnnel Cntaminatin Occurrences by Site, (4%) I 0 DOE Occupatinal Radiatin Expsure

43 Exhibits and 4 shw the breakdwn f ccurrence reprts by rt cause. Fr ORPS, the "rt cause" is defined as the cause that, if crrected, wuld prevent recurrence f this and similar ccurrences. Only the fur significant main rt cause categries are cnsidered here. Over the past years, management prblems were the identified rt cause fr 4% f the radiatin expsure and persnnel cntaminatin ccurrences. The mst ftencited management prblem is inadequate administrative cntrl. Other management prblems include inadequate plicy definitin and disseminatin, and planning deficiencies. While there were cnsiderable decreases in the number f ccurrences attributed t management prblems ver the past years, it was the largest cntributr ver the year perid and therefre deserves cntinued attentin. I Exhibit : Radiatin Expsure Occurrences by Rt Cause, Management Prblem Persnnel Errr Eqtfcpment'Maierial Rt Cause \ Exhibit 4: Persnnel Cntaminatin by Rt Cause, Unknwn Surce l Radiatin ADOthef The ther rt cause categries als experienced decreases with ne exceptin. The number f ccurrences attributed t unknwn surces f radiatin have increased fr bth radiatin expsure and persnnel cntaminatin ccurrences. This categry is assigned whenever the surce f expsure frm radilgical material cannt be reasnably determined. This rt cause represented the highest number f reprts fr bthtypesf ccurrences in 996. This categry f rt cause was added t the reprting requirements f DOE M.A and was nt a cause cde under the previus DOE Order 000.B,s the sites began reprting this cause cde in Management Prblem Persnnel Errr EqiKpmemVMaJenal Rt Cause Unknwn Surce l Radiatin Anther 996 Reprt Occupatinal Radiatin Dse at DOE

44 Fr this reasn, the increase in ccurrences attributed t this rt cause is a result f the change in requirements. In previus years this rt cause may have been categrized as a management prblem r ther rt cause. Hwever, due t the large number f ccurrences attributed t this rt cause in 996, attentin shuld be given t these ccurrences and actins taken in the field t ensure that previusly unidentified surces f expsure and cntaminatin are identified and remediated. The sites reprting the majrity f thesetypesf persnnel cntaminatin ccurrences in 996 were Hanfrd (),Savannah River (7), and LANL (4). The Mund Prject reprted f the radiatin expsure ccurrences attributed t unknwn surces in 996. Further infrmatin cncerning ORPS infrmatin can be btained by cntacting Eugenia Byle, f EH, r the ORPS web page at: Activities Cntributing t Cllective Dse in 996 In an effrt t identify the reasns fr changes in the cllective dse at DOE, several f the larger sites were cntacted t prvide infrmatin n activities that cntributed t the cllective dse fr 996. The sites were: BNL, Hanfrd, Idah, LANL, Oak Ridge, Rcky Flats, and Savannah River. These sites were the tp seven sites in their cntributin t the cllective fr 996 and cmprise 8% f the ttal DOE dse. Five f the seven sites reprted decreases in the cllective, which resulted in an decrease in the DOE cllective dse in 996. The seven sites are shwn in Exhibit including a descriptin f activities at the site that cntributed t the cllective fr 996. A histrical analysis f events and trends ver the past 0 years is included in Appendix B. DOE Occupatinal Radiatin Expsure

45 I Exhibit : Activities Cntributing t Cllective in 996 fr Seven Sites Cllective (persnrem) iir % Change frm 99 t 996 T Descriptin f Activities at the Site The site cllective decreased by frm 99 t 996. This fllws a 8% increase frm 994 t 99. Nearly 7% f the cllective dse at BNL was attributed t the Alternating Gradient Synchrtrn (AGS) in 996 and abut t the High Flux Beam Reactr and the Brkhaven Medical Research Reactr (HFBR/BMRR). AGS dse fr 996 remained abut the same as fr 99 even thugh the intensity and peratinal perids increased. This was accmplished by effrts t reduce prtn lsses in transprt lines, dsimetry imprvements, and ptimizing missin schedules t take advantage f radiactive decay factrs. HFBR/BMRR dse als remained abut the same frm 99 t 996. The remainder f the cllective dse at BNL decreased. 9%^ The site cllective decreased by 9% in 996. The K Basins accunt fr apprximately % f the ttal cllective fr the site, the Plutnium Finishing Plant (PFPJ accunts fr apprximately 4%, and the East Tank Farm, 4%. While activities at K Basins increased in 996, the cllective dse was significantly reduced due t the installatin f the perimeter shielding and cmpletin f the "clean and cat" prject. 4% ^ The site cllective decreased by 4% in 996. At the Idah site, the Idah Chemical Prcessing Plant [ICPPJ cntributes abut 8 f the site dse. The reductin in the i expsure frm 99 was due t the cmpletin f majr radilgical wrk perfrmed at the ICPP and the deactivatin f tw key facilities at the ICPP. % T The site cllective decreased by % fr 996. Fifty percent f the site cllective dse is attributed t TA. Principal peratins cnducted at TA include fabricatin f plutnium metal cmpnents, plutnium prcessing, and basic research n TRU materials. Dses at TA were reduced in 996 due t ALARA activities. In preparatin fr seismic upgrades t the vault at TA, mckup practice runs were carried ut that enabled the wrk t be dne at a cnsiderably reduced dse. % A The site cllective increased by % in 996 primarily due t activities in supprt f the restart f the Yl Plant invlving enriched uranium peratins. Yl has been shut dwn since 994. Envirnmental restratin activities increased at all three facilities Yl,ORNL,andKj. %i At Rcky Flats the cllective increased by % in 996 due t increased activities and decntaminatin and decmmissining cleanup at the site. These activities included tank drainings f enriched uranium and plutnium slutins, plutnium residue stabilizatin, and plutnium residue repackaging. These activities ccurred in the criticality research facility Building 886 and the plutnium peratins areas, mainly Buildings 7,77,707, 776/777, and J0S 9S SE ~ " j %T The site cllective decreased by % in 996. The majr cntributrs t the site i cllective cntinue t be in the nuclear materials stabilizatin and highlevel waste areas. Stabilizatin activities increased in 996 resulting in a increase in the cllective fr the FB Line, % increase fr the HB Line, and % decrease fr the H Tank Farm cmpared t 99 cllective dse. The largest decrease t the site cllective is fund in the strage f spent fuel. With the shutdwn f the reactrs, activities in spent fuel strage areas decreased dramatically, resulting in a 9% decrease in the cllective dse fr the M Area, a 9 decrease fr CReactr, and 46% decrease fr KReactr. SS 9 S4 S6 996 Reprt Occupatinal Radiatin Dse at DOE

46 I 4 This page intentinally left blank. D0E Occupatinal Radiatin Expsure

47 ALARA Activities at DOE This sectin recgnizes highly successful ALARA prjects and encurages the use f similar innvative ideas at ther lcatins in the DOE cmplex. In future years, ALARA success stries.such as thse described belw, will be included in the DOE Occupatinal Radiatin Expsure Reprt. Sites are encuraged t submit material n successful ALARA activities fr publicatin in future annual reprts. 4. Successful ALARA Prjects The fllwing are descriptins f several successful ALARA prjects submitted by Pantex, Savannah River, Fermilab, and Grand Junctin cncerning prjects that reduced radiatin expsure. 4. W79 Cntaminatin Cntrl System at Pantex The W79 is an artillery fired atmic prjectile (AFAP) scheduled t be dismantled at the Pantex plant in Amarill, Texas. The W79 is the first weapn with ptential fr plutnium cntaminatin t be dismantled at Pantex. Title 0 CFR 8.00 requires the use f design features t cntrl cntaminatin at its surce. The physical size f the W79, in cnjunctin with the size f the tls used n W79, make it impractical t use a glve bx. Therefre a team was assembled t design, develp, prcure, test, and implement the "clse capture" cntaminatin cntrl system. The cntaminatin cntrl system design specificatins were develped and tested fr cmpliance with applicable health physics and industrial hygiene requirements (including air flw, nise levels and average face velcity) while effectively cntrlling cntaminatin. The system was als required t be reused t decntaminate successive units while nt interfering with the wrk f technicians dismantling the weapn. The system cnsists f a dwndraft type fixture, (Exhibit 4) t draw air frm an f==^ Exhibit 4: Ventilatin Ductwrk fr Clse Capture System 996 Reprt ALARA Activities at DOE 4

48 I Exhibit 4: Optima 000 Blwer Unit Exhibit 4: W79 Clse Capture Cntaminatin Cntrl System Optima 000 blwer unit (Exhibit 4) thrugh tw sets f external high efficiency particulate air (HEPA) filters and ne HEPA filter internal t the blwer. Behind each HEPA filter and in general rm air, cntinuus air sampling was perfrmed. The exhaust f the blwer was mnitred using a passive air sampler. A metal screen was used t allw fr mre even distributin f air flw acrss the system face withut restricting the ttal air flw. The design f the cntaminatin cntrl system allws the entire weapn t be surrunded by air flw, while allwing fr 60 degree access t the wrk area. Smth aluminum surfaces were incrprated t prvide easy decntaminatin f the remvable prtin f the system, as shwn in Exhibit 4. The custm designed cntaminatin cntrl system prvides fr the efficient dismantling f cntaminated W79 units, while minimizing the risk f internal expsure t Pantex emplyees. 4. FB Line Vault at Savannah River The FB Line Vault dr lcking device needed repair t meet DOE and fire prtectin requirements. This task had been delayed numerus times based upn the predicted high radiatin expsures fr this jb. A team cnsisting f Westinghuse Savannah River Cmpany Operatins, Bechtel Savannah River Inc. (BSRl),and the Radilgical Cntrl Organizatin evaluated the task f installing the lcking device n the dr. The team invlved Engineering, Security Health Prtectin Technlgy, and Criticality Safety in reslving the varius issues that arse.the _acial.f_th_tam w»<^tardi ica.axnaci lre f the basin entry t ensure that all airbrne activity in excess f f the

49 Exhibit 4: Technician bserves ht target frm behind lead glass shielding. Pht Curtesy f Fermilab This target assembly is abut 4 inches in diameter and inches in height. It is attached t a large mdule that serves t psitin the target assembly in the beam and prvide electrical, mechanical, and cling cnnectins. Expsure rates frm these target assemblies can be several R/hr at ft after the beam is shut ff after a lng perid f peratins. The target assembly is engineered with these highexpsure rates in mind and as a result many cmpnents can be disassembled and manipulated remtely. It became necessary t replace this target assembly in September 996. In accrdance with well established prcedures at Fermilab, ALARA planning meetings were held befre cmmencing wrk. The planning meetings included detailed steps describing what was necessary t replace the target, alng with the estimated time t cmplete each step. Each step was thrughly discussed t ensure that wrkers culd cmplete the step in an efficient manner with the least expsure. The use f shielding in certain steps was als discussed t ensure that it was used apprpriately s as nt t adversely cmprmise efficiency. Estimates f the cllective dse equivalent and individual dse equivalents were made, alng with a cllective dse equivalent limit fr the entire jb. All individuals invlved in the wrk participated in drafting the ALARA plan. 996 Reprt ALARA Activities at DOE 4

50 Fermilab requires Radilgical Cntrl Technicians (RCTs) t prvide radilgical jb cverage fr highexpsure jbs. Their functin is t ensure that the jb prceeds accrding t the ALARA plan and t ensure that accumulated dse equivalents d nt exceed predetermined limits. The actual expsure rate frm the target assembly was 0 R/hr at ft. The estimated cllective dse equivalent t replace the target was 0.0 persnrem. The entire jb tk abut 6 hurs t cmplete. The times t cmplete each step were estimated cnservatively t allw fr minr prblems, but the jb prceeded extremely well s that the actual cllective dse equivalent was nly 0.07 rem fr eight wrkers and tw RCTs. The actual dse equivalent received was much lwer than the estimated dse because f the fllwing five factrs: Engineering and design f the facility and the target mdule t accmmdate the anticipated highexpsure rates. Detailed ALARA planning befre the jb cmmenced. Use f wrkers wh were experienced with target assembly replacement. Gd cmmunicatin and cperatin between wrkers and RCTs during the jb. Jb steps were cmpleted with less difficulty than cnservatively anticipated. Fr mre infrmatin n this prject, cntact Berlin Mre, (60) , at Fermilab. 4.6 Sample Preparatry Labratry Dustbag Replacement at Grand Junctin The prject invlved the replacement f the dustbags in the Sample Preparatry Labratry effluent filter baghuse. The primary radilgical expsure cncerns assciate with this prject included airbrne radiparticulate inhalatin and radilgical cntaminatin f persnnel, clthing, equipment, and materials. External radiatin expsure was nt a significant cncern. The area where the dustbags are lcated is a cnfined space due t restricted access. The adjacent walls needed t be wrapped t prevent majr decntaminatin prblems. This situatin presented an additinal and ptentially mre significant hazard f fire adjacent t a cnfined space frm the ptential ignitin f the wall wrapping material. Plastic sheeting is nrmally used fr temprary cntainment wrapping but because this increases fire and smke lading, wall cverings f sheet plastic with lw values fr "smkedevelped value" and "flame spread index" were sught. Ultimately, a material called Tyvek HmeWrap was selected fr the cntainment. Tyvek HmeWrap has been widely used fr the past years as a cmpnent in external walls f new huses. DuPnt specificatins shw n flame spread and a very lw amunt f develped smke frm this material. Ease f handling als resulted in time savings fr installatin and remval. Waste dispsal persnnel were cnfident that the HmeWrap wuld meet waste acceptance criteria. 4S DOE Occupatinal Radiatin Expsure

51 During disassembly the material released particles that had cllected n its surface. A fixatin spray such as the kind used in asbests abatement wuld likely have prevented that ccurrence. As an ALARA cnsideratin, DOE Operating Experience Weekly lessnslearned were used t avid the ptential permeatin f cntaminatin thrugh clth cveralls when saked with perspiratin. Because this prject required a duble set f prtective clthing and was t be perfrmed under cnditins that are cnducive t heat buildup, excessive perspiring was anticipated. As a result, alternative prtective cvering materials were analyzed where clth material nrmally wuld have been selected. Upn review f prtective clthing material ptins, a nnprus, filmcated, nnwven fabric material, which still exhibited gd heat remval characteristics, was selected fr the exterir set f cveralls. Althugh the wrkers' interir set f clth cveralls were cnsistently saturated with perspiratin, n persnnel r clthing cntaminatin prblems were experienced. In additin, the wrkers expressed satisfactin with the cmfrt f the prtective clthing ensemble. Althugh this utcme cannt be quantitatively and exclusively linked t the prtective material chice, the awareness f previus prblems and revised apprach in planning ensured maximum prbability f preventing radilgical cntaminatin f skin and clthing. Apprximately 0 persnhurs were saved. Fr mre infrmatin cntact Jeff Warga, RRPT.OHST, r jeffreywarga@degjp.cm 4.7 Submitting ALARA Success Stries fr Future Annual Reprts Individual success stries shuld be submitted in writing t the DOE Office f Wrker Prtectin Prgrams and Hazards Management. The submittal shuld describe the prcess in sufficient detail t prvide a basic understanding f the prject, the radilgical cncerns, and the activities initiated t reduce dse. The submittal shuld address the fllwing: missin statement, prject descriptin, radilgical cncerns, infrmatin n hw the prcess implemented ALARA techniques in an innvative r unique manner, estimated dse avided, prject staff invlved, apprximate cst f the ALARA effrt, impact n wrk prcesses, in persnhurs if pssible (may be negative r psitive), and pintfcntact fr fllwup by interested prfessinals. 4.8 Lessns Learned Prcess Imprvement Team In March 994, the Deputy Assciate Secretary fr Field Management established a DOE Lessns Learned Prcess Imprvement Team (LLPIT). The purpse f the LLPIT is t develp a cmplexwide prgram t standardize and facilitate identificatin, dcumentatin, sharing, and use f lessns learned frm actual perating experiences thrughut the DOE cmplex. This infrmatin sharing and utilizatin is cmmnly termed "Lessns 996 Reprt ALARA Activities at DOE

52 Learned within the DOE cmmunity The LLPIT has nw transitined int the DOE Sciety fr Effective Lessns Learned Sharing. The cllected infrmatin is currently lcated n an Internet Wrld Wide Web (Web) site as part f the Envirnmental Safety & Health (ES&H) Technical Infrmatin System (TIS). This system allws fr shared access t lessns learned acrss the DOE cmplex. The infrmatin available n the system cmplements existing reprting systems presently used within DOE. DOE is taking this apprach t enhance thse existing systems by prviding a methd t quickly share infrmatin amng the field elements. Als, this apprach ges beynd the typical ccurrence reprting t identify gd lessns learned. DOE uses the Web site t penly disseminate such infrmatin s that nt nly DOE but ther entities will have a surce f infrmatin t imprve the health and safety aspects f peratins at and within their facilities. Additinal benefits include enhancing the wrk place envirnment and reducing the number f accidents and injuries. The Web site cntains several items that are related t health physics. Items range frm ffnrmal ccurrences t prcedural and training issues. Dcumentatin f ccurrences includes the descriptin f events, rtcause analysis, and crrective measures. Several f the larger sites have systems that are cnnected thrugh this system. DOE rganizatins are encuraged t participate in this valuable effrt. The Web site address fr DOE Lessns Learned is: 80/thers/ll/ll.html The specific Web site address may be subject t change. This Web site can always be accessed thrugh the main ES&H TIS Web site at: DOE Occupatinal Radiatin Expsure

53 Cnclusins and Recmmendatins. Cnclusins The detailed nature f the data available has made it pssible t investigate distributin and trends in data and t identify and crrelate parameters having an effect n ccupatinal radiatin expsure at DOE sites. This als revealed the limitatins f available data, and identified additinal data needed t crrelate mre definitively trends in ccupatinal expsure t past and present activities at DOE sites. During the past years, the ccupatinal radiatin dse at DOE has been impacted by three factrs: changes in reprting requirements, changes in peratinal status, and changes in radiatin prtectin standards and practices. These factrs and their impact are discussed belw in rder f their significance. The change in methds t determine internal dse frm AEDE t CEDE between 99 and 99 resulted in an verall reductin f the reprted annual cllective f apprximately 700 persnrem (abut ) because f the exclusin in the annual reprting f the legacy internal dse. This represents a significant change in hw dse is accunted fr in the cllective dse reprted t DOE Headquarters. This change in methdlgy resulted in the largest impact n cllective in the past years. In 996, the cllective decreased by due t decreases in the cllective dse at five f the seven highest dse sites. These seven sites accunted fr mre than 8% f the cllective dse at DOE. Mst f the decrease in dse was attributed t a decrease in cleanup and material stabilizatin activities as well as dse reductin due t successful ALARA activities. The tw remaining sites that experienced increases in cllective dse attributed the increase t cleanup activities (see Sectin.). The cllective dse at DOE facilities has experienced a dramatic (8) decrease ver the past decade (see Appendix B and B). The main reasns fr this large decrease were the shutdwn f facilities within the weapns cmplex and the end f the Cld War era, which shifted the DOE missin frm weapns prductin t shutdwn, stabilizatin, and decmmissining and decntaminatin activities. The DOE weapns prductin sites have cntinued t cntribute the majrity f the cllective dse ver these years. As facilities are shut dwn and underg transitin frm peratin t stabilizatin r decmmissining and decntaminatin, there are significant changes in the pprtunities fr individuals t be expsed. Mre mdest reductins in cllective dse have ccurred during the past years at sme facilities that have cntinued t transitin t shutdwn and stabilizatin. The implementatin f the RadCn Manual and 0 CFR 8 has resulted in changes in radiatin prtectin practices. As described previusly, the RadCn Manual changed the methdlgy cncerning internal dse. While it is nt pssible t quantify the impact f the RadCn Manual n the cllective dse, it did establish ACLs, standardized radiatin prtectin prgrams, engineering cntrls, and frmalized ALARA practices.. Recmmendatins DOE will pursue the usefulness f cllecting data n the peratinal phase f facilities with endusers f this reprt. A "phase f peratin"status cde culd be added t the ccupatinal radiatin reprting requirements fr individual dse recrds (see Appendix A.4). In cmbinatin with the facility type cdes already reprted, this wuld prvide an indicatin f the peratinal mde and 996 Reprt Cnclusins and Recmmendatins

54 type f activities being cnducted at a given facility. This will becme increasingly imprtant as mre facilities transitin frm stabilizatin activities int decmmissining and decntaminatin. It is recmmended that Sites and Operatins Offices begin reviewing their data cllectin prcess in anticipatin f cllecting the phase f peratin data in the future. Many sites d nt reprt the ccupatin cdes fr mnitred individuals r reprt them as "miscellaneus" r"unknwn". This results in a large number f individuals gruped int the "unknwn" labr categry. Sites have indicated that it is ften difficult t btain the ccupatin cde fr subcntract wrkers. It is recmmended that Sites and Operatins Offices evaluate their recrdkeeping and reprting prcess and reprt the infrmatin t the Radiatin Expsure Mnitring System (REMS) system as specified in DOE. t imprve the analysis f radiatin expsure by ccupatin, and thus make this reprt mre useful t line manager and wrker prtectin decisin makers. Occurrence reprts invlving radiatin expsure and persnnel cntaminatin events are additinal indicatrs f the effectiveness f radiatin prtectin effrts at DOE. These events will cntinue t be analyzed and presented in this reprt. Particular attentin will be given t expsure events that were categrized as having resulted frm management prblems and unknwn surces f radiatin. This rt cause categry was added t the ccurrence reprting requirements in 99,s insufficient data exist t identify a trend at this time. Hwever, these events are f particular cncern due t the ptential fr expsure and the increase in the number f these ccurrences in 996. It is recmmended that sites reprting these ccurrences review and remediate situatins that result in these expsure ccurrences. T prvide analysis f the activities at DOE sites with respect t radiatin expsure (see Sectin.),it is necessary t augment the infrmatin reprted t the REMS database. In 99 and 996, DOE Headquarters requested additinal infrmatin frm the seven sites with the highest cllective dse. This infrmatin included a summary f activities, prject descriptins, and ALARA planning dcumentatin. DOE Headquarters will cntinue t request this infrmatin in subsequent years. It is recmmended that sites submit this infrmatin with their annual recrds. The data in the REMS database are subject t crrectin and update n a cntinuus basis. Data fr prir years are subject t crrectin as well as the data fr the mst recent year included in this reprt. The mst cmmn reasn fr crrectin t a dse recrd is because f a final dse determinatin f an internal dse lng after the riginal dse recrd was submitted t REMS. This delay is due t the time needed t assess the biassay results and determine the dse frm lnglived radinuclides. It is recmmended that sites review their dse recrd update and reprting prcess, specifically fr internal dse determinatin, and cnsider the additin f a mechanism whereby they reprt dse updates t REMS in a timely fashin when updates ccur. DOE shuld investigate the feasibility cst, and benefit f establishing a histrical repsitry f intake infrmatin t track and access radiatin dse frm intakes in prir years. DOE Occupatinal Radiatin Expsure

55 References. EPA (U.S. Envirnmental Prtectin Agency), 987. "Radiatin Prtectin Guidance t Federal Agencies fr Occupatinal Expsure," Federal Register, N. 7,8; with crrectins published in the Federal Registers f Friday, January 0, and Wednesday, February 4,987.. ICRP (Internatinal Cmmissin n Radilgical Prtectin), 977. "Recmmendatins f the Internatinal Cmmissin n Radilgical Prtectin," ICRP Publicatin 6,Annals f the ICRP Vl., N. (Pergamn Press, New Yrk).. NCRP (Natinal Cuncil n Radiatin Prtectin and Measurements), 987. "Recmmendatins n Limits fr Expsure t Inizing Radiatin," NCRP 9 superceded by NCRP Reprt N DOE (US. Department f Energy), Order 480., Radiatin Prtectin fr Occupatinal Wrkers, December,988, Change,June 7,99.. DOE 994. Radilgical Cntrl Manual. Revisin.DOE/EH06T, Assistant Secretary fr Envirnment, Safety and Health, April. 6. 0CFR Part 8. "Occupatinal Radiatin Prtectin." Final Rule; DOE Federal Register, December 4, The PriceAndersn Amendments Act f 988, Public Law 00408, August 0, CFR 80. "Prcedural Rules fr DOE Nuclear Activities." August 7, DOE Ntice 44.,"Radilgical Prtectin fr DOE Activities," September 9, DOE Order 484.."Envirnmental Prtectin, Safety, and Health Prtectin Infrmatin Reprting Requirements," February 4,98, Change 7, Octber 7,990.. DOE M.l,"Envirnment,Safety and Health Reprting," September 0,99.. Munsn.LH.et al., 988. Health Physics Manual f Gd Practices fr Reducing Radiatin Expsures t Levels that are As Lw As Reasnably Achievable (ALARA), PNL 677, Pacific Nrthwest Lab.. 0CFR Part 0. "Standards fr Prtectin Against Radiatin," Final Rule, Federal Register, May, UNSCEAR (United Natins Scientific Cmmittee n the Effects f Atmic Radiatin), 98. "Inizing Radiatin Surces and Bilgical Effects," reprt t the General Assembly.. Rich.B.L.et al., 988. Health Physics Manual f Gd Practices fr Uranium Facilities, EGG0, Idah Natinal Engineering Lab. 6. Faust,L.G.et al., 988. Health Physics Manual f Gd Practices fr Plutnium Facilities, EGG64, Pacific Nrthwest Lab, Reprt

56 \R This page intentinally left blank. D0E Occupatinal Radiatin Expsure

57 Glssary ALARA Acrnym fr "As Lw As Reasnably Achievable," which is the apprach t radiatin prtectin t manage and cntrl expsures (bth individual and cllective) t the wrkfrce and the general public t as lw as is reasnable, taking int accunt scial, technical, ecnmic, practical, and public plicy cnsideratins. ALARA is nt a dse limit but a prcess with the bjective f attaining dses as far belw the applicable limits as is reasnably achievable. Annual Effective Dse Equivalent (AEDE) The summatin fr all tissues and rgans f the prducts f the dse equivalent calculated t be received by each tissue r rgan during the specified year frm all internal depsitins multiplied by the apprpriate weighting factr. Annual effective dse equivalent is expressed in units f rem. Average Measurable Dse Dse btained by dividing the cllective dse by the number f individuals wh received a measurable dse. This is the average mst cmmnly used in this and ther reprts when examining trends and cmparing dses received by wrkers because it reflects the exclusin f thse individuals receiving a less than measurable dse. Cllective Dse The sum f the ttal annual effective dse equivalent r ttal effective dse equivalent values fr all individuals in a specified ppulatin. Cllective dse is expressed in units f persnrem. Cmmitted Dse Equivalent (CDE) (H T,0) The dse equivalent calculated t be received by a tissue r rgan ver a 0year perid after the intake f a radinuclide int the bdy. It des nt include cntributins frm radiatin surces external t the bdy. Cmmitted dse equivalent is expressed in units f rem. Cmmitted Effective Dse Equivalent (CEDE) (H E,0) The sum f the cmmitted dse equivalents t varius tissues in the bdy (^,0),each multiplied by the apprpriate weighting factr (w T ) i.e.,h E,0 = Ew^^O. Cmmitted effective dse equivalent is expressed in units f rem. CR CR is defined by the United Natins Scientific Cmmittee n the Effects f Atmic Radiatin as the rati f the annual cllective dse delivered at individual dses exceeding. rem t the cllective dse. Deep Dse Equivalent (DDE) The dse equivalent derived frm external radiatin at a depth f cm in tissue. 996 Reprt Glssary Gl

58 Effective Dse Equivalent (H E ) The summatin f the prducts f the dse equivalent received by specified tissues f the bdy (H T ) and the apprpriate weighting factr (w T ) i.e., H E = w T H r It includes the dse frm radiatin surces internal and/r external t the bdy The effective dse equivalent is expressed in units f rem. Lens f the Eye Dse Equivalent (LDE) The radiatin expsure fr the lens f the eye is taken as the external equivalent at a tissue depth f 0. cm. Lwer Limit f Detectin (LLD) The smallest quantity f radiactive material r level f radiatin that can be distinguished frm backgrund with a specified degree f cnfidence. Often used synnymusly with minimum detectin level (MDL) r minimum detectable activity (MDA). Number f individuals with measurable expsure The subset f all mnitred individuals wh receive a measurable expsure (greater than limit f detectin fr the mnitring system). Many persnnel are mnitred as a matter f prudence and may nt receive a measurable expsure. Fr this reasn, the number f individuals with measurable expsure is presented in this reprt as a mre accurate indicatr f the expsed wrkfrce. Occupatinal expsure An individual's expsure t inizing radiatin (external and internal) as a result f that individual's wrk assignment. Occupatinal expsure des nt include planned special expsures, expsure received as a medical patient, backgrund radiatin, r vluntary participatin in medical research prgrams. Shallw Dse Equivalent (SDE) The dse equivalent deriving frm external radiatin at a depth f cm in tissue. Ttal Effective Dse Equivalent () The sum f the effective dse equivalent fr external expsures and the effective dse equivalent fr internal expsures. Deep dse equivalent t the whle bdy is typically used as effective dse equivalent fr external expsures. The internal dse cmpnent f changed frm the Annual Effective Dse Equivalent (AEDE) t the Cmmitted Effective Dse Equivalent (CEDE) in 99. Ttal mnitred individuals All individuals wh are mnitred and reprted t the DOE Headquarters database system. This includes DOE emplyees, cntractrs, and visitrs. DOE Occupatinal Radiatin Expsure

59 DOE Reprting Sites and Reprting Cdes Al Labr Categries and Occupatin Cdes A A Organizatins Reprting t DOE REMS, A A Facility Type Cdes A7 A4 Phase f Operatin A8 C^ 996 Reprt DOE Reprting Sites and Reprting Cdes Al

60 A. Labr Categries and Occupatin Cdes The fllwing is a list f the Occupatin Cdes that are reprted with each individual's dse recrd t the DOE Radiatin Expsure Mnitring System (REMS) in accrdance with DOE Manual. []. Occupatin Cdes are gruped int Labr Categries fr the purpses f analysis and summary in this reprt. Exhibit A. Labr Categries and Occupatin Cdes. Labr Categry Agriculture Cnstructin Labrers Management Misc. Prductin Scientists Service Technicians Transprt Unknwn n Occupatin Cde (484.) " " Q90, _ " 000 Occupatin Name I Grundskeepers Frest Wrkers Misc. Agriculture Mechanics/Repairers Masns Carpenters Electricians Painters Pipe Fitter Miners/Drillers Misc^Repair/Cnstructin Handlers/Labrers/Helpers Manager Administratr Sales Admin. Supprt and Clerical Military Miscellaneus, Machinists Sheet Metal Wrkers Operatrs, Plant/ System/Utility Machine Setup/Operatrs Welders and Slderers Misc. Precisin/Prductin Engineer Scientist. Health Physicist, Misc. Prfessinal Dctrs and Nurses Firefighters Security Guards Fd Service Emplyees Janitrs Misc. Service Technicians Health Technicians Engineering Technicians ' Science Technicians Radiatin Mnitrs/Techs. ' Misc. Technicians Truck Drivers Bus Drivers Pilts Equipment Operatrs Misc. Transprt Unknwn A DOE Occupatinal Radiatin Expsure

61 A. Organizatins Reprting t DOE REMS, The fllwing is a listing f all rganizatins reprting t the DOE REMS frm 99 t 996. The Operatins Office and Site grupings used in this reprt are shwn in additin t the rganizatin reprting cde and name. I Exhibit A. Organizatins Reprting t DOE REMS, Operatins/ Field Office Site Ops and Other Facilities Ls Alams Natinal Lab (LANL) Pantex Plant (PPJ Sandia Natinal Lab (SNL) Uranium Mill Tailings Remedial Actin [UMTRA] Prject Ops and Other Facilities Fermi Nat'l. Acceleratr Lab (FERMI DOE Headquarters N. Krea Prject Organizatin Cde Organizatin Name 0000 I Albuquerque Field Office ] Albuquerque Office Subs. ; i 000 ' ' ' [ 80600, > 0000 Amanll Area Office > 04004, Battelle Pantex. 000 Masn & HangerAmanll [ 0006 I 0009 i { J 0800! j ] I0I r ! ' j ! Albuquerque Transprtatin Divisin Kansas City Area Office AlliedSignal, Inc. Martin Marietta Specialty Cmpnents Inc WIPP Prject Integratin Office Carlsbad Area Miscellaneus Cntractrs Natinal Renewable Energy Lab (NREL)GO Ls Alams Area Office Ls Alams Natinal Labratry Prtectin Technlgies Ls Alams Jhnsn Cntrls, Inc M&H Amanll Subcntractrs M&H Amanll Security Frces Kirtland Area Office Inhalatin Txiclgy Research Rss Aviatin, Inc. Sandia Natinal Labratry UMTRA Prject Office MKFergusn Subs UMTRA MKFergusn C UMTRA JacbsWestn Team Ames Labratry (Iwa State) Battelle Memrial InstituteClumbus (Old) Chicag Field Office Chicag Office Subs Envirnmental Meas Lab. New Brunswick Labratry Mass Inst f Tech Princetn Plasma Physics Labratry Natinal Renewable Energy Lab (NRELJCH Argnne Natinal Labratry East Argnne Natinal Labratry West Brkhaven Natinal Labratry Fermilab DOE Headquarters DOE Office Subs DOE Nrth Krea Prject CenTech Nrth Krea Nuclear Assurance Crp (NAC) Pacific Nrthwest Lab. Krea U S. Dept f State Nrth Krea Year Reprted '9 '9 '94 '9 '96 MIT i i,. i. < j.[. I! > <.,. '.,. [.. ',' H. L,. i!! * * «i i JL,JLJ. J_J,.» i i n, L*L»J!,_ _, 996 Reprt DOE Reprting Sites and Reprting Cdes A

62 Exhibit A. Organizatins Reprting t DOE REMS, (cntinued). Operatins/ Field Office Idah Site Nevada Test Site (NTS) Ops. and Other Facilities Oak Ridge Site Paducah Gas._Diff. Plant (PGDP) Prtsmuth Gaseus Diff. Plant (PORTS) I Organizatin Cde Organizatin Name Prtectin Technlgy INEL i ChemNuclear Getech 0000 EG&G Idah, Inc i Babcck & Wilcx Idah, Inc. 000 Westinghuse Idah Nuclear C Idah Field Office i _ldah Office Subs Lckheed Idah Tech. C. Services 0006 ' UTCO Subcntractrs Cnstructin 000 '' MKFergusn Cmpany ID 0006 JVIKFerguspn Subcntractrs ID 004 EG&G Kirtland 0804 EG&G Special Technlgies Labratries 0904 EG&G Washingtn D.C EG&G Las Vegas 004 EG&G Ls Alams 0404 EG&G Santa Barbara 0007 Fenix & Scissn, Inc Raythen Services Nevada 0604 Raythen Services Subcntractrs 070 Nevada Field Office 074 Nevada Miscellaneus Cntractrs 07 Defense Nuclear Agency Kirtland AFB 07 Envirnmental Prtectin Agency (NERC) 0804 Reynlds Elec. & Engr. C. Services 080 Reynlds Elec. & Engr. C. NTS 0870 Science Applicatins Internafl. Crp.NV Wackenhut Services, Inc. NV J0904 Westingh_cwse_EJectric Crp^ JW 4007 Jacbs Envirnmental Restratin Team Oak Ridge Inst, fr Science & Educ. (ORISE) Oak Ridge Field Office Bechtel Natinal, Inc. (FUSRAP) ' RMI Cmpany l[ MrrisnKnudsen (WSSRAP) ThmasJeffersn Natinal Accel. Facility 4000 Lckheed Martin/MKFergusn C Lckheed Martin Energy Systems (KJ Lckheed Martin Energy Systems (ORNL) Lckheed Martin Energy Systems (Yl ) ' Martin Marietta (Paducah) 4000 Martin Marietta (Prtsmuth) M.M. Prtsmuth Subcntractrs M.M. Prtsmuth Subcntractrs Year Reprted"** 9 '9 '94 '9 '96 i,! i A4 DOE Occupatinal Radiatin Expsure

63 Exhibit A. Organizatins Reprting t DOE REMS, (cntinued). Operatins/ Field Office Site Organizatin Cde Organizatin Name Year Reprted * '9 '9 I '94 I '9 I '96 Ops. and Other Facilities Rckwell Internatinal, Rcketdyne ETEC U. f Cal./Davis, Radibilgy Lab. LEHR U. f CaL/SF Lab f Radibilgy Oakland Field Office Lawrence Berkeley Lab. (LBL) Lawrence Berkeley Labratry Lawrence Livermre Nat'l. Lab Lawrence Livermre Natinal Labratry (LLNL) LLNL Subcntractrs LLNL Security LLNL Plant Services Lawrence Livermre Nat'l Lab. Nevada Stanfrd Linear Ace. Center (SLAC) Stanfrd Linear Acceleratr Center Ops. and Other Facilities " " Ohi Field Office 4000 Miamisburg Area Office Miamisburg Office Subs 4700 Jattelle Memrial Institute Clumbus Fernald Envirnmental* Westinghuse Envir. Mgmt. C. f Ohi (REM) 400 Fernald Area Office 4004 Fernald Office Service Subcntractrs 470 Fernald Envir. Rest. Mgmt. Crp (FERMCO) 4706 FERMCO Subcntractrs 070 Fernald Envir. Rest. Mgmt. Crp. Rcky Flats Mund Plant** West Valley Prject*** Rcky Flats Eng. Tech. Site (RFETS) Daytn Area Office EG&G Mund Applied Technlgies EG&G Mund Applied Technlgies EG&G Mund Subcntractrs EG&G Mund Security Frces West Valley Nuclear Services, Inc. West Valley Area Office West Valley Nuclear Services, Inc. Rcky Flats Office Rcky Flats Office Subs Rcky Flats Office Subs ' Rcky Flats Prime Cntractrs, Rcky Flats Subcntractrs J.A. Jnes Rcky Flats EG&G Rcky Flats Subcntractrs EG&G Rcky Flats Security Frces Wackenhut Services Rcky Flats _ KaiserHill RFETS Hanfrd Site 7000 Battelle Memrial Institute (PNL) Bechtel Pwer C Being Cmputer Services 7004 Hanfrd Envirnmental Health Fundatin 7000 Kaiser Engineers Hanfrd Cst Cnst Flur Daniel Hanfrd 7000 Flur Daniel Nrthwest Flur Daniel Nrthwest Services 996 Reprt DOE Reprting Sites and Reprting Cdes A

64 Exhibit A Organizatins Reprting t DOE REMS, (cntinued) Operatins/ Field Office Pittsburgh Naval Schenectady Naval Hanfrd Site Savannah River Site (SRS) Pittsburgh Naval Reactr Office Schenectady Naval Reactr Office Organizatin Cde Organizatin Name Babcck Wilcx Hanfrd Babcck Wilcx Prtectin, Inc Rust Services Hanfrd Rust Federal ServicesNrthwest Duke Engineering SeryicesJ^anfrd Dute Engineering^ Services Nrthwest, Inc NUMATEC Hanfrd LckheedjvlartinJlanfrd Lckheed Martin Services Inc Qyncrp Hanfrd SGN Eunsys Services Crp Richland Field Office US Crps f Engineers Westinghuse Hanfrd Services Westinqhuse Hanfrd Service Subs _ American Telephne & Telegraph Bechtel Cnstructin SR Westinghuse Savannah River C Service America Westinghuse S R Subcntractrs Diversc Industrial Phases SR S R Army Crps f Engineers S R Frest Statin Savannah River Field Office Miscellaneus DOE CntractrsSR Suthern Bell Tel & Tel Univ f Gergia Eclgy Labratries Wackenhut Services, Inc SR Nt included in this reprt (see Appendix D) Year Reprted**** '9 '9 '94 '9 ' Pittsburgh NR Office Westinghuse Plant Apparatus Divisin Westinghuse Electric (BAPL) I Westinqhuse Electric (NRF), ^ Newprt News Reactr Services LMKAPLKesselnng Gen Dynam Kesselnng Electric Bat UVKAPLKnlls LMKAPL Knlls Subs LM KAPL Windsr LM KAPL Windsr Electric Bat Schenectady N R Office * Fernald site reprted under the Oak Ridge Ops Office in 99 the Fernald Field Office in 99 and the Ohi Field Office in 994 * Mund Site reprted under Albuquerque Ops Office in 99 and 99 and nw reprts under the Ohi Field Office * West Valley Site reprted under Idah Ops Office in 99 and 99 and nw reprts under the Ohi Field Office * Thse rganizatins n lnger reprting radiatin expsure infrmatin have either ceased peratins requiring the mnitring and reprting f radiatin recrds are n lnger under cntract r subcntract at the DOE facility r have changed rganizatin cdes r the name f the rganizatin» e e A6 DOE Occupatinal Radiatin Expsure

65 A. Facility Type Cdes The fllwing is the list f facility type cdes reprted t REMS in accrdance with DOE IVIanual. []. A facility type cde is reprted with each individual's dse recrd indicating the facility type where the majrity f the individual's dse was accrued during the mnitring year. Exhibit A. Facility Type Cdes. Facility Type Cde ' Acceleratr Descriptin Fuel/Uranium Enrichment It Fuel Fabricatin Fuel Prcessing j! Maintenance and Supprt (Site Wide) Reactr i Research, General i Research, Fusin , n Waste Prcessing/Mgmt. Weapns Fab. and Testing Other See cmplete Facility Type descriptins shwn in Appendix C. 996 Reprt DOE Reprting Sites and Reprting Cdes A

66 A.4 Phase f Operatin In additin t the Facility Type listing that has been reprted in the past, the DOE Office f Envirnment Safety and Health is interested in btaining infrmatin n the peratinal status f these facilities. This infrmatin will be cdified in terms f a Phase f Operatin t describe the perating status f a facility. The listing that fllws cvers each f the phases f peratin frm cnstructin t the final stage f surveillance and maintenance nce a site has undergne envirnmental restratin. The phase f peratin will be recrded fr the calendar year fr which the phase f peratin is mst apprpriate. Fr facilities that transitin between phases during a year, the phase that is apprpriate fr the majrity f the calendar year shuld be recrded. The Phase f Operatin will be recrded and submitted alng with the Facility Type as part f the mnitred individual's dse recrd. Reprting frmat and specificatins will be included in subsequent revisins t DOEM. []. Each DOE facility falls int ne f the Phase f Operatins shwn in Exhibit A. In general, each phase fllws in sequential rder, althugh a facility may frg ne r mre phases r may nt fllw the rder listed here. This is the prpsed table fr the phases f peratin f DOE facilities. Please submit cmments, additins, r revisins t this table, t EH (see Appendix E fr address). If end users feel this additinal supprting infrmatin will be useful t them, then DOE M. will be s mdified. DOE Occupatinal Radiatin Expsure

67 Exhibit A4. I Phase f Operatin Lifecycle fr a DOE Facility. B C II Phase f Operatin Cnstructin (includes Majr Renvatin) Operatin/ Maintenance Stabilizatin Definitin New facilities that are brught n line t replace r augment existing facilities. This phase includes majr renvatins fr existing facilities but des nt include envirnmental restratin cnstructin. Includes the nrmal, missinrelated peratins and maintenance f the reprted Facility Type. Facilities that have been declared t be surplus (assigned t the envirnment restratin prgram). This includes facilities where all peratins have been suspended but envirnmental restratin activities have nt begun. This may include perids f surveillance and maintenance prir t envirnmental restratin activities. c Oi U V.C <J QE el LU Remediatin Decntaminatin \ and '[ Decmmissining Waste Management Perid during which crrective actins that are necessary t bring the facility int regulatry cmpliance are being perfrmed. Decntaminatin is the act f remving a chemical, bilgical, r radilgic cntaminant frm, r neutralizing its ptential effect n, a persn, bject r envirnment by washing, chemical actin, mechanical cleaning, r ther techniques. Decmmissining is the prcess f clsing and securing a facility. This phase includes the management f wastes generated during the envirnment restratin prcess. (D,E) Surveillance and Maintenance Other This phase includes thse activities that prvide fr the safety and prtectin f a facility after the envirnmental restratin phase. All DOE facilities shuld fit int ne f the abve categries. "Other" shuld be used nly in highly unusual circumstance. 996 Reprt DOE Reprting Sites and Reprting Cdes A9

68 \A0 This page intentinally left blank. D0E Occupatinal Radiatin Expsure

69 Additinal Data I Hfi Bla Operatins Office/Site Dse Data (994) B I Blb Operatins Office/Site Dse Data (99) B k Blc Operatins Office/Site Dse Data (996) B4 ^f * B Internal Dse by Operatins/Site, B M, B Neutrn Dse by Site, B6 Q^ B4 Distributin f Deep Dse Equivalent (DDE) and Ttal Effective Dse Equivalent ^^ (), B7 ^ B Cllective and Average Measurable Dse B8 O B6 Number with Measurable Dse and Average Measurable Dse B9 ^ B7a Distributin f by Facility Type 994 B0 ^ B7b Distributin f by Facility Type99 Bll ^==d B7c Distributin f by Facility Type996 B N=^, B8a Cllective by Facility Type, 994 B W> B8b Cllective by Facility Type, 99 B4 Q B8c Cllective by Facility Type, 996 B p* B9 Distributin f by Facility Type Listed in Descending Order f ^ Average Measurable fr Acceleratr Facilities, 996 B6 B0 Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Fuel Facilities, 996 B7 B Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Maintenance and Supprt, 996 B9 B Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Reactr Facilities, 996 B B Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Research, General, 996 B B4 Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Research, Fusin, 996 B4 B Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Waste Prcessing, 996 B B6 Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Weapns Fabricatin, 996 B7 B7 Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Other, 996 B8 B8 Internal Dse by Facility Type and Nuclide, B B9a Distributin f by Labr Categry 994 B B9b Distributin f by Labr Categry 99 B B9c Distributin f by Labr Categry, 996 B4 B0 Internal Dse by Labr Categry B B Dse Distributin by Labr Categry and Occupatin, 996 B6 B Internal Dse Distributin by Site and Nuclide, 996 B7 B Crrelatin f Occupatinal Radiatin Expsure with Nuclear Weapns Prductin B8 996 Reprt Additinal Data B

70 B a: Operatins Office/Site Dse Data (994) /0 Operatins/ Field Office Site <^> S<a.,%. <X%. %\ <& %% 9& \% A & A Albuquerque ps. and Other Facilities 0.4 T 6 7% T 0.06 % T Ls Alams Nat'l. Lab. (LANL) 90.0 % T,448 76% A % T 44% % Pantex Plant (PP) 9. 7% T 47 % T % T % 4% T Sandia Nat'l. Lab. (SNL).0 % A 0 T % A 4% 8% A Uranium Mill Tailings Remedial Actin (UMTRA) Prject.0 6% A 90 6% A % A Chicag 0ps. ana ther Facilities Argnne Naf I. Lab. East (ANLE) Argnne Nat'l. Lab. West (ANLW) Brkhaven Nat'l. Lab. (BNL) % T 9% A 7% T 4% A 7% T 80 % A 4 A 86 % A % A 7% A 9% T 7% A 6% 48% 0 A 7% A % 4% T 9% 4% A Fermi Nat'l. Acceleratr Lab. (FERMI) 4. % T 6 % A T DOEHQ DOE Headquarters (includes DNFSB).7 T 4 T % A ' 0 T Idah Idah Site 6.8 % A,69 4% A 0.4 9% T 4% 8% T Nevada Nevada Test Site (NTS).0 A A Oakland Ops. and Other Facilities 0.8 7% T 0 8% T % T 0 T Lawrence Berkeley Lab. (LBL).7 7% T 9 % T % A 9% T Lawrence Livermre Nat'l. Lab. (LLNL) 8.8 8% T 46 % T 0.9 7% T 47% 9% T Stanfrd Linear Acceleratr Center (SLACj 6. 6% T 9 64% T % A 8% T Oak Ridge Ops. and Other Facilities 6.8 T 49% A % T Oak Ridge Site Paducah Gaseus Diff. Plant(PGDP) Prtsmuth Gaseus Diff. Plant (PORTS) % T,6 7% T % A % T T 86 A % A % A 0.06 T 7% 8% T 4% % T Ohi ps. and Other Facilities Fernald Envirnmental Mgmt. Prject 4. 7% T 9 9% T 0.06 % A Mund Plant 9. 7% A 99 6% A % A 6% 0 A West Valley Prject 4. 9% A 9 7% A % A, 8% A Rcky Flats RCky Flats Eng. Tech. Site (RFETS).9 % T,660 % T % A % 7% T Richland Hanfrd Site 4.8 % A,66 % A % A % A Savannah River Savannah River Site (SRS) 4. % A 6,84 9% A 0.00 % T % 4% A Ttals,64. % A,90 6% A % % 4% A Nte: Bxed values indicate the greatest value in each clumn. \B DOE Occupatinal Radiatin Expsure

71 Bb: Operatins Office/Site Dse Data (99) 99 \ L s \\ yd Operatins/ Field Office Site \ Albuquerque 0ps, and ther Facilities Ls Alams Nat'l. Lab. (LANL) Pantex Plant (PP) Sandia Nat'l. Lab. (SNL) Uranium Mill Tailings Remedial Actin (UMTRA) Prject % A % A % 9% T 8 8% T 0.0 4% T 49% A 4% 6% A 0 T Chicag ps. and Other Facilities Argnne Nat'l. Lab. East (ANLE) Argnne Nat'l. Lab. West (ANLW) Brkhaven Nafl. Lab. (BNL) [ Fermi Nat'l. Acceleratr Lab. (FERMI) % T ' 8% T 4% A ' 8% A 6% T % T 6% A % T % A T i 0 08 % % 46% 4 % A T A A A 6% % 0 T 4% T % T % A DOEHQ DOE Headquarters (includes DNFSB) 0. 96% T Idah Idah Site 84.0 A,0 T ' p.89 % 6% 49% A Nevada Nevada Test Site (NTS) 0. 77% T 9 % T % Oakland I Ops. and Other Facilities Lawrence Berkeley Lab. (LBL) Lawrence Livermre Nat'l. Lab. (LLNL) Stanfrd Lnear Acceleratr Center (SLACJ % % 4% A T T A % 9% 8% T A A! % % 7% 6% A T, A 7% 4% 89% A 7% T % T Oak Ridge Ops. and Other Facilities Oak Ridge Site Paducah Gaseus Diff. Plant (PGDP) Prtsmuth Gaseus Diff. Plant (PORTS) % % % 9% T A A T ,6 % % 49% 94% T A A A % % % A T T 6% 4% % A 4% A Ohi ps. and Other Facilities I Fernald Envirnmental Mgmt Prject j Mund Plant West Valley Prject % % A " A 9 7 % 4% 7% A T A f % % 4% T A ' A A 9% 4% 4% A 8% T Rcky Flats Rcky F(ats Eng. Tecn_ Slte (RFETS) 60 8 % A.47 6% T % % i Richland Hanfrd Site i 90.7 % A.00 % T % 6% A Savannah River Savannah River Site (SRS). 9% T 4,846 [ % T 0.0 % % 4 T Ttals,840. % A,6 7%, A A ' Nte: Bxed values indicate the greatest value in each clumn. 996 Reprt Additinal Data B

72 Bc: Operatins Office/Site Dse Data (996) Operatins/ Field Office Site <6% ^ t % J* SO ^ \ s % \ 9 ' "9 s % so % \ > Albuquerque Ops. and Other Facilities Ls Alams Nat'l. Lab. (LANL) Pantex Plant (PP) Sandia Nat'l. Lab. (SNL) Uranium Mill Tailings Remedial Actin % A % T 4% T % A 67% T 7, % T % Y 4% A % T % A % A % T 7% A 7% T 8% 44% % % T 4% T (UMTRA) Prject Chicag Ops. and Other Facilities Argnne Nat'l. Lab. East [ANLEJ % Ai T 8 0 % A % Tls % A 7% Yi, 4% % 4% Y Argnne Nat'l. Lab. West (ANLW) 4.6 6% A! % Yl 0. 7% A, 8% 7 A Brkhaven Nat'l. Lab. (BNL) Fermi Nat'l. Acceleratr Lab. (FERMI) T % A (, % A 4% A i % Y 6% A.' 4 4% A DOEHQ DOE Headquarters (includes DNFSB) Nrth Krea Prject A 6 6 % Y % A 78% Idah Idah Site 64. 4% T,99 % Y 0.6 % Y % 7% Y Nevada Nevada Test Site [NTS).0 A % A Oakland Ops. and Other Facilities % Y 6 7 Y % Y Lawrence Berkeley Lab. (LBL) 4.6 % A 00 % A % Y < 0 Y Lawrence Livermre Nat'l. Lab. (LLNL) i 4.9 % A 87 8% A %Y' 4% 76% A Stanfrd Linear Acceleratr Center (SLAC) 9. 4% Y % A % Y % 66% Y Oak Ridge Ops. and Other Facilities.9 9% A 00 A % A % Oak Ridge Site 88.6 % A,8 % Y 0.06 % A % A Paducah Gaseus Diff. Plant (PGDP) % A 90 9% A A Prtsmuth Gaseus Diff. Plant (PORTS) % Y 0.09 % A % 9% A Ohi Ops. and Other Facilities Fernald Envirnmental Mgmt. Prject Mund Plant West Valley Prject 7.4 Y 0. 6% A. 9% Y % Y, 6% ' % A, 7% A 44% Y 6% 4% I 7% IA! 6% 6% Y Rcky Flats Rcky Flats Eng. Tech. Site (RFETS) 67.6 % A, % A 8% % Y Richland Hanfrd Site 6.7,76 A % Y 8% 46% Y I I Savannah Savannah River Site (SRS).8 % Y 4,76 % Y 0.0 % A % 6% A River Ttals,6.9 Y,7 4% Y % ' 4% Y Nte: Bxed values indicate the greatest value in each clumn. \B4 DOE Occupatinal Radiatin Expsure

73 t B: Internal Dse by Operatins/Site, Operatins/ Field Office Site N. f Individuals with New Intakes* Cllective CEDE Dse frm Uptake persnrem) Average CEDE (rem) Albuquerque Chicag Ops. and Facilities ' LANL ' Pantex i Sandia Ops. and Other Facilities 6 0 f, 7,4 48 " 0, ' i " [j 0.00 ' ANLE Idah Oakland ANLW BNL ' Idah Site LBL 0 '» l 4 6 n;.6 r 7 '7 ", ] '! Oak Ridge Ohi LLNL ""["ps. and Other Facilities Oak Ridge Site Paducah l Prtsmuth Fernald r i i i i ' ] [ ;«0.09 i 0.00 I ' a & Rcky Flats Richland Savannah River Ttals Mund Plant i Rcky Flats Hanfrd Site j Savannah River Site 70! 4 6<,949 78,6 f,8 i! i, Facilities with n new intakes: UMTRA, ANLW, Fermi Lab, DOEHQ, NTS, Oakland Ops., SLAC, Ohi Ops., West Valley Prject. Only includes intakes that ccurred during the mnitring year. Individuals may be cunted mre than nce. Nte: Arrwed values indicate the greatest value in each clumn j ][

74 B: Neutrn Dse by Site, \ O \ P s> <S. <s. <sj \ Operatins/ Field Office Albuquerque Site/Facility Ops. and Other Facilities Ls Alams Nat'l. Lab. (LANL) Pantex Plant (PP) Sandia Nafl. Lab. (SNL) Uranium Mill Tailings Remedial Actin (UMTRA) Prject H \ ^ A_*_ 9 % 8% < % Chicag Ops. and Other Facilities Argnne Nat'l. Lab. East (ANLE) Argnne Nat'l. Lab. West (ANLW) Brkhaven Nat'l. Lab. (BNL) i % 8% Fermi Nat'l. Acceleratr Lab. (FERMI) DOEHQ DOE Headquarters (includes DNFSB) Nrth Krea Prject Idah Idah Site.0..9 Nevada Nevada Test Site (NTS) Oakland Ops. and Other Facilities Lawrence Berkeley Lab. (LBL) Lawrence Livermre Nat'l. Lab. (LLNL) Stanfrd Linear Acceleratr Center (SLAC) Oak Ridge Ops. and Other Facilities Oak Ridge Site Paducah Gaseus Diff. Plant (PGDP) Prtsmuth Gaseus Diff. Plant (PORTS) % Ohi Ops. and Other Facilities Fernald Envirnmental Mgmt. Prject Mund Plant West Valley Prject % Richland Hanfrd Site % Rcky Flats Rcky Flats Eng. Tech. Site (RFETS) t % Savannah River Savannah River Site (SRS) % Ttals Nte Bxed values indicate the greatest value in each clumn B6 DOE Occupatinal Radiatin Expsure

75 s 8 B4: Distributin f Deep Dse Equivalent (DDE) and Ttal Effective Dse Equivalent (), Deep Dse Equivalent (DDE) Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) Year ~974~ Year Less than Meas. 7,060 4,90 8,408 4,7 4,7 48,9 4,66 4,77 47,40 48,40 ' 46,06 4,8,},86 4,4, 48,704 6,6 I 76,798 9,6 98,900 0,90 9,4 04,79 It 0,44 Less than Meas. 7,99 88,444 94,97 0,947 9, 0,66 00,494 Meas.I 9/7" 6,79 4, 44,70,444 48,,8, 0,988,84 8,8 4,7,67, 8,99 7,49 8,9,0! 7,49 4,769,00 4,89,0,70, Meas.I,780,086 9,40,00,0,4,64 7,,47,96,499,,8, ,,,6,79, ,, j 6 < { l ' jivale ' JI > t 0 > * =DDE+AEDE =DDE+CEDE Nte: Arrwed values indicate the greatest value in each clumn.!! ' Ttal Mnitred 69,7 80,4 8,489 88,47 96,7 98,8 80,64 78,90 79,79 8,78 86,44 90,677 88,9 7,76 76,7 8,77 08,06 9,770,7 7,04 6, 7,764,9 Ttal Mnitred 08,06 9,770,7 7,04, 6, 7,764,9 N. with Cll. DDE Avg. Meas. Meas. ODE (persnrem) DDE,7 7~ 8,94 4,08 46,900,84 0,96 6,90 4,,7 4,44 40,98 6,09,7 0,4 8,08 ' 9,74,67 7,44 4,8,7 4,66,48,79 0,04 ~ ,0 8,98 0,99 9,90 8,69 7,760 7, 7,8 7,70 8, 8,40 8,09 6,06,7,,0,76,04,4,600 ',809,98 J[ N. with Cll. Avg. Meas. Meas. (persnrem) 6,0744,6 9,44,09,90,6,7,04 ",74,9,644.64,840,

76 Average Measureable Dse* (persnrem) 0 OJ Q SJ </> (B OJ en s "* c «B g. u OQ III n n ii ni n Q ([\ > a> ^ O < i (Tl m r+ CO LU Q < + UJ Q Q II CD CO O Q CD > OJ O CM O) OJ O > CD LU Q LU + UJ Q Q II CD CO O a 0 > CD O CD 0) 0 CO m Oi E c a> Q. CD CO Q CD > CD O a F CD CD CO n CO CO CD CD CO CD > < n } C\f c" CD CM" Cllective Dse* (persnrem) \B8 DOE Occupatinal Radiatin Expsure

77 Average Measureable Dse* (persnrem) 0 > er» s4 *» OJ Q </> fxj.oj CD s C t QJ 8 Q S t CD QJ OJ s c > Q UJ Q LU UJ Q UJ < O + + LU UJ UJ Q Q Q Q II Q OJ II CO CD O Q CD CO Q OJ c OJ CD Q > > > tj b b J = = O O O O CM CD CD CD CD ffi O) O) 4 CO rc. Oi O ffl O) O) CD CO O Q CD.Q CO CO as CD sz CD O E Z z. E CD CD CO O Q CO as CD CD O) CO CD > < n r A* Number with Measureable Dse* 996 Reprt Additinal Data B9

78 C B7a: Distributin f by Facility Type 994 t r> O a Q i a. a I Ttal Effective Dse Equivalent () Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) Facility Type Acceleratr Fuel/Uran. Enrich. Fuel Fabricatin Fuel Prcessing Maint. and Supprt Other Reactr Research, General Research, Fusin Waste Prc./Mgmt. Weapns Fab. & Test Ttals Less than Meas. 6,48 0,07,79' i,44 6,74,96,9 6,776 98,974 4,0 9, Meas. 00,46,07,074,,64,796,46,09,776 ],8 4,8, , , ' Nte Arrwed values indicate the greatest value in each clumn J Ttal 4 4 > Mnitred, ' i i ' ' i ,08,9 \,9, D 6, 9,9 4,84,9 0, IK,4 8,897 9,477 Percent f Mnitred with Meas. % 9% 7% 6% 9% 4 < 7% 4% % 8% % N. with Meas.,70!,,40,049,89 j,889,80,4 60,9,444,90 Cllective (persnrem) <, Avg. Meas. (rem) j

79 S 8 B7b: Distributin f by Facility Type 99 ^ H Ttal Effective Dse Equivalent () Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) Facility Type i Acceleratr Fuel/Uran. Enrich. Fuel Fabricatin i Fuel Prcessing Maint. and Supprt Other j Reactr Research, General i Research, Fusin Waste Prc./Mgmt. J Weapns Fab. & Test Ttals Less than Meas I 0.0 I 0.7 Meas ,9},77 j 8J,669,8 7,67jj ,7, 7 j 6,76,4J 8 7,464,0 0 j l,74jj 70 j IIJ 8,80,79 66 I 909 nil! ll ' 6,80 ( l,09 7,60 4,89j 74IJ 0,66 9,7,4 6; 6 9 J 9 lj j' 98 9!,4 Nte: Arrwed values indicate the greatest value in each clumn. 8 4 ' 6 4 :, l! ll 4 79 f, * '!!» I; i' 6 l! ij 70 I I P P II ' 48 t i! 7 Ttal > Mnitred 8,69,84 il ;!,78 4,76 j 9,96 9,974 j!,60,49,04 9,08 ; ;;, 9 4 <! % 7,76 Percent f Mnitred with Meas. 4% 8% % j % % i 4% 4 % j % 7% 9% N. with Meas.,78 ',9,0,',0,80 J,0 896 j,69 4 j,48,4ij,6 Cllective (persnrem) ij 0.074,840.46! Avg. Meas. (rem) ! 0.07 : 0.08 J lb. B' a O 60

80 B7c: Distributin f by Facility Type 996 Ttal Effective Dse Equivalent () Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) M Facility Type Less than Meas I 0.0 I 0.7 Meas Ttal Mnitred Percent f Mnitred with Meas. N. with Meas. Cllective (persnrem) Avg. Meas. (rem) Acceleratr 8,948 i, ,9 %, Fuel/Uran. Enrich. 8, , Fuel Fabricatin,00 8 4,64 7% Fuel Prcessing,64, , 6%, Maint. and Supprt 4,6, , 7%, Other,66, ,794, Reactr, ,49 9% Research, General 7,866, ,96 %, Research, Fusin Waste Prc./Mgmt. 7,06, ,48 6%, Weapns Fab. & Test,46 4, ,464 %, t Ttals 00,494 8,79,44, ,9 8%,7, S Q ' a a. ' ' p Nte: Arrwed values indicate the greatest value in each clumn. Weapns Fabricatin and Testing remains the facility type with measurable dse. The highest average measurable was

81 B8a: Cllective by Facility Type, 994 DOE Operatins Albuquerque Site Ops. and Other Facilities Ls Alams Natinal Lab. (LANL) Pantex Plant (PP) Sandia Natinal Lab. (SNL) Uranium Mill Tailings Remedial Actin (UMTRA) Prject \W \\\f> J \>fe\ «> V \ X^ k\% > Chicag Ops. and Other Facilities Argnne Nat'l. Lab. East (ANLE) Argnne Nat'l. Lab. West (ANLW) Brkhaven Nat'l. Lab. (BNL) Fermi Nat'l. Acceleratr Lab. (FERMI) DOE HO DOE Headquarters.7.7 Idah Idah Site Nevada Nevada Test Site (NTS) ! Oakland Ops. and Other Facilities Lawrence Berkeley Lab.(LBL) Lawrence Uvermre Nat'l. Lab. (LLNL) Stanfrd Unear Acceleratr Center (SLAC) Oak Ridge Ops. and Other Facilities Oak Ridge Site Paducah Gaseus Diff. Plant (PGDP) Prtsmuth Gaseus Diff. Plant (PORTS) Ohi Ops. and Other Facilities Fernald Envirnmental Mgmt. Prject Mund Plant West Valley Rcky Flats Rcky Flats Eng. Tech. Site (RFETS).94.9 Richland Hanfrd Site Savannah River Savannah River Site (SRS) Ttals ,64. Nte: Arrwed values indicate the greatest value In each clumn.

82 CO B8b: Cllective by Facility Type, 99 DOE Operatins Albuquerque Chicag DOEHQ i i ^ Site \ Ops. and Other Facilities Ls Alams Natinal Lab. (LANL) Pantex Plant (PP) Sandia Natinal Lab. (SNL) UMTRA Ops. and Other Facilities Argnne Nat'l. Lab. East (ANLE) Argnne Nat'l. Lab. West (ANLW) Brkhaven Nat'l. Lab. (BNL) Fermi Nat'l. Acceleratr Lab. (FERMI) DOE Headquarters \.6! VA 0. \ * ^> \ r. \ O' \ % \ %* \ ll II 68 7 p., \ k\ \ %. \ W \ ^JTOSX \ \ V \^.( \ V^& \ \ >\A\V\\i\ \ * \ \%\ y \%\ * \ ,.0, ' ,. " Idah Idah Site Nevada Nevada Test Site (NTS) ' Oakland Ops. and Other Facilities Lawrence Berkeley Lab.(LBL) Lawrence Livermre Nat'l. Lab. (LLNL) Stanfrd Linear Acceleratr Center (SLAC) t R ' a Oak Ridge Ohi Rcky Flats Richland Ops. and Other Facilities Oak Ridge Site Paducah Gaseus Diff. Plant (PGDP) Prtsmuth Gaseus Diff. Plant (PORTS) Ops. and Other Facilities Fernald Envirnmental Mgmt. Prject Mund Plant West Valley Rcky Flats Eng. Tech. Site (RFETS) Hanfrd Site ' 4. ' 4.9 'l ' g. ' ' a t p Savannah River Savannah River Site (SRS) Ttals Nte: Arrwed values indicate the greatest value in each clumn ! , 840.

83 B8c: Cllective by Facility Type, 996 DOE Operatins Site \ " N \ \ N&\ \ ^ V\vA \ «& Albuquerque Ops. and Other Facilities Ls Alams Natinal Lab. (LANL) Pantex Plant (PP) Sandia Natinal Lab. (SNL) UMTRA Chicag Ops. and Other Facilities Argnne Nat'l. Lab. East (ANLE) Argnne Nat'l. Lab. West (ANLW) Brkhaven Nat'l. Lab. (BNL) Fermi Nat'l. Acceleratr Lab. (FERMI) DOE HQ Idah Nevada DOE Headquarters Nrth Krea Idah Site Nevada Test Site (NTS) I.0 i Oakland Oak Ridge Ohi Ops. and Other Facilities Lawrence Berkeley Lab.(LBL) Lawrence Uvermre Nat'l. Lab. (LLNL) Stanfrd Linear Acceleratr Center (SLAC) i ' Ops. and Other Facilities Oak Ridge Site I Paducah Gaseus Diff. Plant (PGDP) ' Prtsmuth Gaseus Diff. Plant (PORTS) Ops. and Other Facilities Fernald Envirnmental Mgmt. Prject Mund Plant West Valley I.I , ! O.O Rcky Flats Rcky Flats Eng. Tech. Site (RFETS) Z67.6< Richland Hanfrd Site Savannah River Savannah River Site (SRS) Ttals I I ,6.9 Nte: Arrwed values indicate the greatest value In each clumn. Cllective at Rcky Flats increased fr 996 and was the largest cntributr t the Weapns Fabricatin and Testing facility type, althugh it shuld be nted that Rcky Flats and SRS are n lnger active in the fabricatin and testing f weapns but is currently invlved in materials stabilizatin and cleanup activities. Fusin Research was the nly ther facility type that increased fr 996.

84 CO B9: Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Acceleratr Facilities, 996 t ' a a. ' ' I p ACCELERATORS Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) Ops. Office Site/Cntractr CH i Brkhaven Natinal Labratry AL CH it Ls Alams Natinal Labratry Argnne Natinal Labratry East OAK Stanfrd Linear Acceleratr Center AL Sandia Natinal Labratry OAK Lawrence Berkeley Labratry OR CH Thmas Jeffersn Nat'l. Accel. Facil. Fermilab OAK Lawrence Livermre Natinal Lab. NV AL OR Battelle Memrial Institute (PNLJ EG&G Special Technlgies Lab. Jhnsn Cntrls, Inc. Oak Ridge Field Office Ttals Less than Meas. Meas. 00.,6 j 8 69,86 4 0,060,00 0 I Nte: Arrwed values indicate the greatest value in each clumn. H I 4! 8 9 4! ,948, P Ttal > Mnitred Percent f Mnitred with Meas. 'I,4 %! u 6 [ 688,98 'j ',4,40 04 ij '!,,9 ii 4%! 7%! % 6% 84% i 8% % % i ' '< % N. with Meas i ,4 Cllective (persnrem) ' The largest percentage f cllective dse at acceleratr facilities accrued at Brkhaven Natinal Labratry (BNL) where dses increased due t increased acceleratr peratins. BNL was als highest in terms f the ttal mnitred, number with measurable dse, average measurable dse, and the percentage f the cllective abve 0. rem. Avg. Meas. (rem) O.O Percent f abve 0. rem %< % % 4% %

85 s 8 lb ' f B0: Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Fuel Facilities, 996 FUEL FACILITIES Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) Ops. Office Site/Cntractr ENRICHMENT OR OAK OR OR Lckheed Martin Utility Services (Paducah) Lawrence Livermre Natinal Lab. Lckheed Martin Utility Services (Prtsmuth) Lckheed Martin Energy Sys. (K) Ttal FABRICATION CH OH OH SR OH SR SR SR SR Westinghuse Hanfrd Services Argnne Natinal Lab. West Babcck Wilcx Hanfrd FERMCO FERMCO Subcntractrs Westinghuse Savannah River C. Fernald Area Office Westinghuse S.R. Subcntractrs Wackenhut Services, Inc., SR Bechtel Cnstructin SR Duke Engineering Services Hanfrd DynCrp Hanfrd Flur Daniel Hanfrd Lckheed Martin Hanfrd NUMATEC Hanfrd Savannah River Field Office Ttal Less than Meas ,0 4,77 8,400 4,98 6 ' 68 6 ' ',00 Meas Nte: Arrwed values indicate the greatest value in each clumn. i i _ S S i I Ttal > Mnitred 47 64,988 4,0< 9,08 6, ,64 Percent f Mnitred with Meas. % 4% 9%4 % 4 % 4 7% % 6% % % 7% N. with Meas Cllective (pcrsnrcm) Meas. 0.O994 0.O O 0.O4 0.O O8 0.O O6 0.O0 0.O09 0.O06 0.O4 Percent f abve 0. rem %< 9% 8% 4 6%

86 CO B0: Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Fuel Facilities, 996 (Cntinued) t ' a D I p FUEL FACILITIES Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) Ops. Office Site/Cntractr PROCESSING Less than Meas. Meas. 00. I Westinghuse Hanfrd Services j, 7 ID Lckheed Idah Tech. C. Services,047 7, SR Service America j Flur Daniel Hanfrd 9 SR i Westinghuse Savannah River C., jj 79 j ID Idah Field Office 7 II <i ID LITCO SubcntractrsCnstructin, 4' i SR Bechtel Cnstructin SR 40 0 SR Westinghuse S.R. Subcntractrs. i j, 7 9 SR Wackenhut Services, Inc., SR 0 0 Duke Engineering Services Hanfrd j 8 SR Savannah River Field Office 7 Babcck Wilcx Hanfrd I '! j II ii i Bechtel Pwer C. SR Miscellaneus DOE Cntractrs SR i i Rust Services Hanfrd Ttal jj,64,6 Nte: Arrwed values indicate the greatest value in each clumn. Ii il Percent f Mnitred N. with Cllective Ttal with Meas. Meas > Mnitred (persnrem) !, II 4 ll,4 I ii II.00^ 9 i;»j n 66 'I j I 0 ' H i! 9 I! ii 8 I : i ll 4,.! 7%< 8% 8 <j 67% 4% % 8% ' 47% 9%! 9% % % ' 6% i 7 j 40 jj 0 87 HI 6 < 9 j 0 I J I j !' ( ( j ,498.4 O.I 0 Enrichment facilities at Prtsmuth accunted fr 79% percent f the cllective dse and Fuel Fabricatin facilities at Fernald accunted fr 9% in 996. Prcessing facilities at Lckheed Martin (Idah) and Westinghuse Savannah River accunted fr 9% f the cllective dse at this facility type. Percent f abve 0. rem %. 8% 4 < % 4

87 s Ol S? 8 I ' a t so B: Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Maintenance and Supprt, 996 MAINTENANCE AND SUPPORT Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) Ops. Office JAL I CH OAK CH CH I AL CH SR ID I AL SR OH JSR SR J J j OAK OH! Site/Cntractr Ls Alams Natinal Labratry Battelle Memrial Institute (PNL) Kaiser Eng. Hanfrd Cst Cnst Battelle Mem. Inst. Clumbus (Old) Westinghuse Hanfrd Services Lawrence Livermre Natinal Lab. 4 90,79 Brkhaven Natinal Labratry II 68 j Argnne Natinal Labratry West Lckheed Martin Hanfrd Jhnsn Cntrls, Inc. Flur Daniel Hanfrd Argnne Natinal Labratry East Bechtel Cnstructin SR Lckheed Idah Tech. C. Services ' Lckheed Martin Services, Inc. Ls Alams Area Office Babcck Wilcx Hanfrd Service America Flur Daniel Nrthwest Services EG&G Mund Subcntractrs i Westinghuse Savannah River C. Westinghuse S.R. Subcntractrs I Rust Services Hanfrd Bechtel Pwer C. i Flur Daniel Nrthwest Duke Engineering Services Hanfrd LLNL Plant Services EG&G Mund Applied Technlgies Less than Meas.,0 Nte: Arrwed values indicate the greatest value in each clumn. 606, 9 j 44 4 Ii 7 48, ! j Ij 78 Meas Ttal Percent f Mnitred N. with with Meas. Meas. Cllective > Mnitred (persnrem) j 4 4, 8, > 7 j 9! j I,8,, " 8 l ' '! I, 747 I I I I I ' I 4 4 ' ', I " I 89 l 0...,7 0 ll j j {j,09 ' ' ' I' 'j I j j 8 ' 4 68 'i I ij I! cr. II i " ' " I I i ii I ii II ii ii ll 8 j! l j 6 II II '' I! il 'I 9 '' \ ( \ l! II 8, 0 l i! M il I II P II II I' 9 ii ll ii " il ii 7:l I 8 " ', " fi " ' I " ll II. I % % % % % 4 % % 9% % % % % 9% 4% % % 4% % 4% 6% % 7% % 4% ' ] , j ! 7% 4 46% 4% 9% ; % ' I % 9% I I I I

88 CD = B: Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Maintenance and Supprt, 996 (Cntinued) MAINTENANCE AND SUPPORT Number f Individuals Receiving Radiatin Dses In Each Dse Range (rem) ' a D ' p Ops. Office ID OH AL SR AL SR SR OH OH HQ SR ID OAK LLNL Security OH NV SR SR NV Site/Cntractr Idah Field Office EG&G Mund Security Frces Sandia Natinal Labratry Being Cmputer Services DynCrp Hanfrd Wackenhut Services, Inc. SR Babcck Wilcx Prtectin, Inc. Prtectin Technlgies Ls Alams i Savannah River Field Office Miscellaneus DOE Cntractrs SR Miamisburg Area Office Miamisburg Office Subs ' DOE Headquarters S.R. Frest Statin Duke Eng. & Serv. Nrthwest, Inc. Idah Office Subs NUMATEC Hanfrd Ohi Field Office Reynlds Elec. & Engr. C. Services Richland Field Office Rust Federal Services Nrthwest SGN Eunsys Services Crp. Suthern Bell Tel. & Tel. j Univ. f Gergia Eclgy Lab. Wackenhut Services, Inc. NV j Westinghuse Hanfrd Service Subs Ttal Less than Meas ' 0/ 8 j i 7 r 9 ; 6 7'i 7 i i' l! 7 4,6 Nte. Arrwed values indicate the greatest value in each clumn. Meas , Tt.il Mnitred , Percent r Mnitred with Meas. 6% 4% 6% % % 4% % 9% 4% % 4% 0 4 ', 7% N. with Mens ,886 Cllective Ipcrsnrcm) ' Avg. Mens. (rcm ' These individuals tend t prvide maintenance and supprt services sitewide and may be lcated at mre than ne facility type during the year. Nte that, verall, nly 7% f mnitred individuals received any measurable and that these dses primarily ccurred at Hanfrd Westinghuse and Kaiser Engineers) and LANL. These three rganizatins accunted fr 6% f the cllective dse at these facilities types. The rganizatin with the largest number f mnitred individuals was LLNL, but less than I % received a measurable dse. Percent f abve 0. rem 9%

89 B: Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Reactr Facilities, 996 REACTOR FACILITIES Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) Percent f Percent Mnitred N. with Cllective f Ops. Less than Mens. O.tO Ttal with Meas. Mens. Office Site/Cntractr Mens > Mnitred pcrsnrcm) AL Sandia Natinal Labratry ' 76 4% ZO64 77%4 CH Argnne Natinal LabratryWest % % Westinghuse Hanfrd Services I 78 % ' 0.47 Battelle Memrial Institute (PNL) ID 'Lckheed Idah Tech. C.Services j! 44 9% % Kaiser Eng. Hanfrd Cst Cnst 7 4 8% CH Brkhaven Natinal Labratry J 80' 87, ; ;! ' j j 00 6 I 0 I Flur Daniel Hanfrd 68 I % J Babcck Wilcx Hanfrd 74 ( 7 ' \ " ' " I ' I " i 8 jj i Babcck Wilcx Prtectin, Inc. I ' 8% I j ll Duke Engineering Services Hanfrd I 7 j I! f \ j jj j 9!{ 7% ( \ ' 0.0, SR Wackenhut Services, Inc.SR % ! Lckheed Martin Hanfrd [ ' j 'j j J % j } 0.06 J 0.06 j Bechtel Pwer C. 8' ' ' % j NUMATEC Hanfrd ft j j '[, 'j 6 7% ' jj 0.09 J 0.09 jj SR Bechtel Cnstructin SR % I jj Flur Daniel Nrthwest Services ( 4 ij J j j 7 IJ 4% 4 I, 0.06 j 0.06 ' SR Westinghuse Savannah River C I % SGN Eunsys Services Crp. j! 8' j l )! Ij 'j l j 0 jj jj 0.00 ' 0.0 \ j ID Idah Field Office 6 7 4% SR Westinghuse S.R. Subcntractrs I 44'( ji Ij 'I j jj 7 jj % [ j 0. Ii 0.0, AL Ls Alams Natinal Labratry 4 9 6% Rust Services Hanfrd ( 6,j j, : J j jj j 7 I 6% j I, 0.0,j 0.0 i ; SR Savannah River Field Office 7 0 % J j DynCrp Hanfrd 9 jj j '!. l > 9 jl j ) ' j AL Jhnsn Cntrls, Inc. ID ijutcosubcntractrscnstructin Ij 'J " j It " l " Ii " i " ll 'I " _ ' " Lckheed Martin services. Inc. I SR Jj Miscellaneus DOE Cntractrs SR' >! jl ( j l 'j j Ij J jj jj j! j Richland Field Office I jj Rust Federal Services Nrthwest 'j j ji, i jj J ' '! ] l' j, Ttal, ,49 9% O6 4% Nte: Arrwed values Indicate the greatest value In each clumn. Lckheed Idah Tech. Services had the highest cllective, but nly the th highest average measurable. Westinghuse Savannah River C. had the largest number f individuals mnitred and number with measurable, althugh their cllective and average measurable were very lw. Sandia Natinal Lab had the highest average measurable dse as well as the highest percent abve 0. rem indicating that individuals at this site received the highest dses.

90 t B: Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Research, General, 996 Q Q_ SO Q a. S t RESEARCH, GENERAL Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) Ops. Office CH CH AL OR ID OAK Site/Cntractr Argnne Natinal Labratry East Battelle Memrial Institute (PNL) Argnne Natinal Labratry West j; Ls Alams Natinal Labratry Westinghuse Hanfrd Services Lckheed Martin Energy Sys. (ORNL) Lckheed Idah Tech. C. Services ij Lawrence Livermre Natinal Lab. CH CH New Brunswick Labratry Brkhaven Natinal Labratry ' 46 jj 0 OAK' Lawrence Berkeley Labratry j 4 SR Westinghuse S.R. Subcntractrs SR Westinghuse Savannah River C. i 6 86 SR Bechtel Cnstructin SR 9 AL Inhalatin Txiclgy Research Inst. J 4 6 Flur Daniel Nrthwest Services AL Sandia Natinal Labratry ',694 l 7 6 Babcck Wilcx Hanfrd OR Oak Ridge Inst. frsci. & Educ. (ORISE) j 4'j 6 SR Miscellaneus DOE Cntractrs SR 6 0 CH Ames Labratry (Iwa State) 7 0 l! 7 SR Savannah River Field Office 9 4 SR Wackenhut Services, Inc. SR jl J_ti Nte. Arrwed values indicate the greatest value in each clumn. j Less than Meas., j,0 47 II 6, j 98 Meas. OO.l II ll P 0 il * 4 i 9! II 6 ( "I 4 i J " ll " " II " 4 ' 4 il " II li " j ll i ". I " II il " 8 II " 4 '!'. II i II II " ij I " ii i ll " II " l.! " " ll " i! II ll ' il I!,l. > l I I " L_ Ttal Mnitred, jj 664, II " 7,66< 687 II ll jl 7 6 f,0 8 \ 9 J!,88 6 jl 6 46 ; " i 7 _ Percent f Mnitred with Meas. % II 6% 4% jj 9% 8% 4% I' % 4% 9% 8 %< I 4% 4% i % 4%, % %,' 7% 6% t 4% 6%! 47% 44% [ N. with Meas H I j 8 ; 7 46 j; 40 ] 44 7 { 4 ; 6 ', 0 7,! 4 "J Cllective (persnrem) 8.47 ji [j j jj '> , j Avg. Percent Meas. f abve (rem) 0. rem { 69% j i % 8% % 6% % 8%

91 OS S lb. I ' a & B: Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Research, General, 996 (Cntinued) RESEARCH, GENERAL Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) Ops. Office! I ID SR j jsr J JAL I'D JAL AL jlw JAL NV I OAK Site/Cntractr SGN Eurisys Services Crp. Duke Engineering Services Hanfrd Idah Field Office Univ. f Gergia Eclgy Labratry ; Babcck Wilcx Prtectin, Inc. Bechtel Pwer C. Diversc DynCrp Hanfrd ; Flur Daniel Hanfrd Flur Daniel Nrthwest Jhnsn Cntrls, Inc. Kaiser Eng. Hanfrd Cst Cnst LITCO Subcntractrs Cnstructin Lckheed Martin Hanfrd Ls Alams Area Office Nat. Renewable Energy Lab (NREL) GO Nevada Miscellaneus Cntractrs NUMATEC Hanfrd Prtectin Technlgies Ls Alams Reynlds Elec. & Engr. C. NTS Rust Services Hanfrd Univ. f Cal./SF Lab f Radilgy Ttal Less than Meas Ttal Meas > Mnitred 0 : I, 4 I: 8; ij 7 : 9 ; I; Nte: Arrwed values indicate the greatest value in each clumn. 4 9 ' ' l' ; '!: l 4 jl II 4 j ii 7 ; 9'! ' li j ; i j l! sj: 7,866, I i; J j 0,96 il Percent f Mnitred with Meas. 9% 8% % 4% ' % N. with Meas. : 6 ', ; j ": M 9 l Cllective (persnrem) , j I j "I j 9.7 Avg. Meas. (remj _ Percent f abve 0. rem ij jj jj jj ll jj j. jj ) Ij i % ta The cllective and the highest number f individuals with measurable was highest atianl. The highest average measurable and highest percent abve 0. rem was at AIMLEast. ORNL had the highest number f emplyees mnitred (7,66) but nly 8% f these individuals received a measurable dse.

92 t is B4: Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Research, Fusin, 996 RESEARCH, FUSION Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) ps. Office Site/Cntractr OAK JjLawrence Livermre Natinal Labratry jj 9 CH Princetn Plasma Physics Labratry 0 84 AL J Sandia Natinal Labratry ii 4 'I 7 AL Ls Alams Natinal Labratry 0 'Ttal / 66 j Nte: Arrwed values indicate the greatest value in each clumn. Percent f Mnitred N. with Cllective Less than Meas Ttal with Meas. Meas. Meas > Mnitred (persnreml 4 9 ii i 7 i % Jl ' < % % j 7, % ' / , / % t R ' a S D a. a LLNL and the Princetn Plasma Physics Labratry were the primary cntributrs t the cllective in 996. The cllective dse fr this facility type is the lwest fr all facility types.

93 en 8 B: Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Waste Prcessing, 996 WASTE PROCESSING Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) I ' a & ps. Office I OR j I SR ID Site/Cntractr DynCrp Hanfrd Bechtel Natinal, Inc. (FUSRAP) Bechtel Pwer C. Duke Engineering Services Hanfrd i Westinghuse Hanfrd Services Kaiser Eng. Hanfrd Cst Cnst Service America Lckheed Idah Tech. C. Services CH Brkhaven Natinal Labratry OR MrrisnKnudsen (WSSRAP) CH Argnne Natinal Labratry East JAL AL SR j OAK j SR Flur Daniel Hanfrd Ls Alams Natinal Labratry Babcck Wilcx Hanfrd i Rust Federal Services Nrthwest Sandia Natinal Labratry Westinghuse Savannah River C. Lckheed Martin Hanfrd Lawrence Livermre Natinal Lab. SGN Eurisys Services Crp. Flur Daniel Nrthwest Services Rust Services Hanfrd Bechtel Cnstructin SR NUMATEC Hanfrd Less than Meas , j 70 09, Meas. OO.l I i ' \ Percent f Mnitred Ttal with Meas. > Mnitred , ', ' % 7% 9% % 6% % % 68% 6% 9% ' 4% 7% % 7% 9% % 4% % 8% 47% % N. with Meas Cllective (pcrsnrcm) Avg. Meas. (rem) Percent f abve 0. rem % % % % 4 Nte: Arrwed values indicate the greatest value in each clumn. t

94 t B: Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Waste Prcessing, 996 (Cntinued) t R a ' a i a. ' ' a I WASTE PROCESSING Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) Ops. Office AL ID SR SR SR SR SR SR AL AL NV NV NV SR NV AL Site/Cntractr jj Carlsbad Area Misc. Cntractrs Idah Field Office ' Flur Daniel Nrthwest Westinghuse S.R. Subcntractrs ; Wackenhut Services, Inc. SR Suthern Bell Tel. & Tel. Savannah River Field Office Miscellaneus DOE Cntractrs SR Diversc Babcck Wilcx Prtectin, Inc. Battelle Memrial Institute (PNL) Duke Eng. & Services Nrthwest, Inc. Jhnsn Cntrls, Inc. Lckheed Martin Services, Inc. Ls Alams Area Office Nevada Field Office Nevada Miscellaneus Cntractrs Raythen Services Nevada Richland Field Office S.R. Frest Statin i Science Applicatins Int'l. Crp.NV WIPP Prject Integratin Office Ttal Less than Meas ! 8 j i i: 6 i! 7l ; Meas. OO.l ,06,0 Nte: Arrwed values indicate the greatest value in each clumn , 96 l 4."_ l. J'. Ttal Mnitred j j 9 7, [ i 6 ' 7 ; " Percent f Mnitred with Meas. % jj % 8% j 44% jj 0 4 % j) 9% jj jj jl! jj jj! jj N. with Meas. 4! It 9 jj 7 ji "il il ii "i' P ': Cllective (persnrem) 0.0 jj jj jj jj ji jj " II ll I; i j 9,48 ' 6% i[,4 jl jj Avg. Meas. (rem) jj j j ii ii jj ii i: ii Ii 0.09 Ij Westinghuse Savannah River Cmpany (WSRC) and Westinghuse Hanfrd Services were the tw highest cntributrs f cllective. WSRC had the highest number f emplyees mnitred as well as the highest number with measurable althugh their average measurable dse ranked 7 th. DynCrp Hanfrd had the highest average measurable dse due t having nly ne persn with measurable dse. Percent f abve 0. rem 8%

95 8 I ' a & t vi B6: Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Weapns Fabricatin, 996 WEAPONS FABRICATION Number f Individuals Receiving Radiatin Dses in Each Dse Range [remj Ops. Office Site/Cntractr Less than Meas. I 0.0 I 0.S 0.S0 0.7.OOI Ttal Meas > Mnitred Percent f Mnitred with Meas. N. with Meas. Cllective (persnrem) SR Westinghuse Savannah River C % < OH EG&G Mund Applied Technlgies % % < JRFO Rcky Flats Prime Cntractrs 7, ,9 87% 4, AL Masn& HangerAmanll, ,096 % % JSR Westinghuse S.R. Subcntractrs SR Wackenhut Services, Inc. SR % JSR Bechtel Cnstructin SR % OAK Lawrence Livermre Natinal Lab % % INV Reynlds Elec. & Engr. C. NTS % l RFO Rcky Flats Subcntractrs ,0 47% RFO Rcky Flats Office % t AL Albuquerque Field Office % JSR Miscellaneus DOE Cntractrs SR % , OR Lckheed Martin Energy Sys. (Yl ) 8,67 0 9,94 6% I RFO Rcky Flats Office Subs 8 69 % j AL Sandia Natinal Labratry % JAL Kirtland Area Office % j AL Martin Marietta Specialty Cmp. Inc % j OH EG&G Mund Subcntractrs. ' / SR Savannah River Field Office 0 6% JAL Ls Alams Natinal Labratry 9 0 % AL Albuquerque Transprtatin Divisin (AL Amanll Area Office AL Battelle Pantex JNV Defense Nuclear AgencyKirtland AFB 7 7 > NV EG&G Las Vegas " I NV Envirnmental Prat. Agency (NERC) OH Miamisburg Area Office. 'OH Miamisburg Office Subs 4 4 NV Nevada Miscellaneus Cntractrs ' OH Ohi Field Office ' NV Raythen Services Nevada 'NV Raythen Services Subcntractrs! NV Reynlds Elec. & Engr. C. Services 4 4 L _ T?* a '_.,46 4, ,464 %, j 7% Nte: Arrwed values indicate the greatest value in each clumn. Rcky Flats Prime Cntractrs were respnsible fr the highest cllective while keeping the average measurable dse at rem. WSRC had the highest average measurable dse and secnd highest cllective dse indicating that individuals received the highest dses at this rganizatin. Yl cntinued t have the highest number mnitred with nly 6% actually receiving a measurable dse. (rem) Percent Of

96 t B7: Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Other, 996 OTHER Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) t R a S a s a a. a a I Ops. Office HQ AL ID HQ CH HQ AL OH HQ OAK ID AL OR HQ AL OH CH OR AL ID RFO CH Site/Cntractr Nuclear Assurance Crp (NAC) Kaiser Eng. Hanfrd Cst Cnst Albuquerque Office Subs Lckheed Idah Tech. C Services Battelle Memrial Institute (PNL) CenTech Nrth Krea Argnne Natinal Labratry East DOE Nrth Krea Prject Bechtel Pwer C. Jhnsn Cntrls, Inc EG&G Mund Applied Technlgies Pacific Nrthwest Lab. Krea Westinghuse Hanfrd Services Lawrence Livermre Natinal Lab. LITCO Subcntractrs Cnstructin Ls Alams Area Office Martin Marietta (Paducah) DOE Headquarters Prtectin Technlgies Ls Alams West Valley Nuclear Services, Inc. Flur Daniel Hanfrd Brkhaven Natinal Labratry Lckheed Martin/MK Fergusn C Ls Alams Natinal Labratry Duke Engineering Services Hanfrd Idah Field Office Babcck Wilcx Hanfrd Rcky Flats Office Chicag FieldjDffice Less than Meas. Nte Arrwed values indicate the greatest value in each clumn.,0 ' 8 ' ,09 4 4,404 70,,0,9, Meas t i 9. 4 i ? I I jl 7 0 l I ' "ii! i ij i.!. i. f i i i i Percent f Mnitred Ttal with Meas. > Mnitred ' 9 6 ; i,8 ji 96 " II 80 ^ , j,64 0! 7,6,,47 ',974, ^ 9% 6% 9 I % % j 8% % ' % 0 4! % %, % 7% 9% ' 4% 7% 8% % % % % 4% % % % N. with Meas , 6 94 j 7' ' Cllective (persnrem).70 ', j' jj 'j ' j 'j { i ' ' Avg. Meas. (rem) j ' j ' i I j Percent f abve 0. rem 88% 4 6% 4% 77% 4 4% % % 6% 9% % 6%

97 t 8 I ' a a t t B7: Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Other, 996 (Cntinued) OTHER Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) Ops. Office AL i OR j CH AL j HQ AL J SR ID j SR CH j AL AL SR SR j SR OR SR SR Site/Cntractr Masn & Hanger Amarill Babcck Wilcx Prtectin, Inc. RMI Cmpany Richland Field Office Battelle Memrial Inst. Clumbus (Old) Westinghuse Hanfrd Service Subs Sandia Natinal Labratry Rust Services Hanfrd US Dept. f State Nrth Krea MKFergusn Subs UMTRA Bechtel Cnstructin SR ChemNuclear Getech Wackenhut Services, Inc. SR Argnne Natinal Labratry West AlliedSignal, Inc. MKFergusn C. UMTRA Westinghuse S.R. Subcntractrs Westinghuse Savannah River C. Savannah River Field Office Jacbs Envirnmental Restratin Team Miscellaneus DOE Cntractrs SR S.R. Army Crps f Engineers Less than Meas. 9 96, Meas i Flur Daniel Nrthwest 40 i SR University f Gergia Eclgy Lab. OH EG&G Mund Subcntractrs 6 OR Lckheed Martin Energy Systems (K) j CH Envirnmental Meas. Lab. 8 6 OAK Rckwell Internatinal, RcketdyneETEC 4 [ ID Babcck & Wilcx Idah, Inc. Nte: Arrwed values indicate the greatest value in each clumn. 0 Percent f Mnitred Ttal with Meas. anitred 9 % 6, , % % 8% % 7% 4% 4 ' % 6%, % % 0 4 4% 4% % 7% % % 6% 4% i % 7% 8% % 8% 7% N. with Meas I 6 Cllective (persnrem) O O O 0.0O Avg. Meas. (rem) Percent f abve 0. rem

98 t ti R a a i a. a I OTHER Ops. Office OH NV NV NV AL OR OH OH NV NV NV NV SR SR B7: Distributin f by Facility Type Listed in Descending Order f Average Measurable fr Other, 996 (Cntinued) Number f Individuals Receiving Radiatin Dses in Each Dse Range (remj Site/Cntractr Less than Meas. Meas. 00. Battelle Memrial Institute Clumbus Being Cmputer Services Defense Nuclear AgencyKirtland AFB Duke Eng. & Services Nrthwest, Inc. i DynCrp Hanfrd EG&G Las Vegas ' EG&G Santa Barbara Flur Daniel Nrthwest Services Hanfrd Envirnmental Health Fun. Kansas City Area Office Lckheed Martin Energy Systems (Yl ) Lckheed Martin Hanfrd Lckheed Martin Services, Inc. Miamisburg Area Office ; Miamisburg Office Subs Nevada Field Office Nevada Miscellaneus Cntractrs NUMATEC Hanfrd. Reynlds Elec. & Engr. C. NTS Reynlds Elec. & Engr. C. Services I Rust Federal Services Nrthwest Service America, SGN Eurisys Services Crp. Suthern Bell Tel. & Tel. OAKj U. fcal./davis, Radibilgy LabLEHR OH West Valley Area Office, Ttal Nte: Arrwed values indicate the greatest value in each clumn. Percent f Avg. Mnitred N. with Cllective Meas Ttal with Meas. Meas > Mnitred (pcrsnrcm) (rem) 0, 8 i! j 6 i 6 6 \ 9 i 9 i 4 f 4* 7jj 60ji * ' 4,79 i ' ' j j' I, j jj I I (; jl f _I_J,4j[ jj 0.O67 Lckheed Martin/MK Fergusn (MKF), Lckheed Martin Utility Services (Paducah), and LLNL reprted large numbers f mnitred individuals at "Other" facility types in 996. Lckheed Idah Tech C. Services had the highest cllective dse and Nuclear Assurance Crp (NAC) had the highest average measurable and highest percentage abve 0. rem. NAC, Lckheed Idah, PNL, MKF and BNL all had individuals wh received dse greater than.0 rem. This facility type accunted fr apprximately f the mnitred emplyees, which has cntinued t escalate ver the past years. Many rganizatins reprt cleanup activities under this facility type as well as subcntractr persnnel mnitred at multiple facility types during the year. ll 8%

99 t > g I a & t Acceleratr Facility Type Nuclide* h Fuel Fabncatln Fuel Prcessing Fuel/Uranium Enrichment Maintenance and Supprt Other Reactr Research, Fusin Research. General Waste Prcessing Weapns Fab. and Testing Ttals B8: Internal Dse by Facility Type and Nuclide, Hydrgen Other i Uranium Ttal Hydrgen Thrium Uranium Ttal Amencium ' I Hydrgen Mixed Plutnium Ttal Other Technetium Thrium Uranium Ttal I Amerlclum t j Hydrgen j ' Mixed and Other I Plutnium i! Thrium \ Uranium I Ttal Hydrgen Other Plutnium Uranium Ttal ' Hydrgen Ttal Hydrgen Ttal I Ameridum Hydrgen, Mixed! Other Plutnium ' Uranium i, Ttal Hydrgen Mixed Other Plutnium Uranium Ttal Hydrgen Plutnium Uranium Ttal N. f Individuals with New Intakes* S f ,90 ' ' i ,848 ' Intakes gruped by nuclide. Intakes Invlving multiple nuclides were gruped Int "mixed". Nuclides where fewer than 0 Individuals had Intakes were gruped as "ther". "Individuals may be cunted mre than nce. Nte: Arrwed values Indicate the greatest value In each clumn ,99 4. Cllective CEDE (pcrsnrcml Average CEDE (rem) I i , 0.4, ' , ' The nuclide with the highest cllective CEDE and average CEDE is fr Plutnium at Fuel Prcessing facilities, This is primarily due t the single CEDE dse f. rem which ccurred at Savannah River. The secnd highest cllective CEDE fr a nuclide was fr Thrium intakes which ccurred at Prtsmuth which reprted under Fuel/Uranium Enrichment facilities. Trends cncerning internal dses may be misleading due t the relatively small number f individuals receiving dse and the tendency fr any intake t result in a significant CEDE dse

100 B9a: Distributin f by Labr Categry, 994 Ttal Effective Dse Equivalent () Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) Labr Categry Less than Meas. Meas Ttal Mnitred Percent f Mnitred with Meas. N. with Meas. Cllective [persnrem) Average Meas. rem) Agriculture < Cnstructin 6,8, , 7%, Labrers, ,948 4% Management 6,4, ,46 %, Misc. 7,70, ,8 8%, Prductin,4, ,64 47%<, Scientists 8,06 4, ,07 4 6%,0H Service 4,79, ,480 %, Technicians 8,69, ,99 % 4, t I ' I Transprt Unknwn Ttals,76 4,077 9,! 46,706, 44,47 Nte: Arrwed values indicate the greatest value in each clumn ,64 8,4 6, 9% 4% % 478 4,7, , ' ' I p

101 CO S B9b: Distributin f by Labr Categry, 99 Ttal Effective Dse Equivalent () Number f Individuals Receiving Radiatin Dses in Each Dse Range rem) Labr Categry Less than Meas Ttal Mnitred Percent f Mnitred with Meas. N. with Measurable Cllective [persnrem) Average Measurable (rem Agriculture 7 60 % Cnstructin,9, , 8%, Labrers, , Management,76, ,9 9%, Misc.,7, ,669 4%, Prductin,88, ,67 4% 4, Scientists 7,4, ,86 4 %, Service 4, ,98 9% Technicians 8,9, ,48 %, Transprt, ,48 % Unknwn 4,7, , %, O.0 < it ' Ttals 0,66 9,7,4 L Nte: Arrwed values indicate the greatest value in each clumn., ,76 9%,6, ba c

102 D B9c: Distributin f by Labr Categry, 996 Ttal Effective Dse Equivalent () Number f Individuals Receiving Radiatin Dses in Each Dse Range (rem) Labr Categry Agriculture Cnstructin Labrers Management Misc. Prductin Scientists Service j Less than Meas. 8,00 867,448 6,80 4,8 8,47 4,48 Meas. 00 7,9 49,08 4,0,790, : I i ! " 6 I 80 i ' 7 i r i 9 I * S.4 I 'i i i Ttal Mnitred ] 6 0,788,409 il 6,660!!,8 6,7 4,987 Percent f Mnitred with Meas. % 4% II 8%<!! 7% / ll 6/ % N. with Meas.,88 8;j 4 Ij,,0<j,44 J,004 /,80 j. 69 Cllective Ipersnrem) Avg. Meas. (rem)! ! ' I Technicians Transprt 7,94,79, I 6 *,.9 ' jj,,80 % j, %,76 } t R D 8" Unknwn Ttals,80 00,494,079 8,79 64,44 Nte: Arrwed values indicate the greatest value in each clumn. 0! 6,00 9,6 99 ll 80 i i ' i i,8,9 ' 70/0 ji, It 8% 09.97,7, O a. " ' a I p Scientists cntinue t be the largest number f mnitred individuals by labr categry while labrers and prductin wrkers have the highest percentage mnitred individuals receiving measurable dse. Technicians received the highest cllective and highest average measurable dse. "Unknwn" and "Miscellaneus" categries cntribute large numbers f wrkers and cllective dse. These individuals tend t be subcntractrs wh d nt prvide infrmatin n ccupatinal categries t the reprting rganizatins.

103 CO 8 4 B0: Internal Dse by Labr Categry, Labr Categry Number f Individuals with New Intakes* Cllective CEDE (persnrem) Average CEDE rem) 996 I D II Cnstructin Labrers Management Misc. Prductin Scientist Service Technicians Transprt Unknwn Ttals , i 0 ' 4 9,8 *! , I i 'J > j 4. j i Only included intakes that ccurred during the mnitring year. Individuals may be cunted mre than nce. Nte: Arrwed values indicate the greatest value in each clumn ' , i j The tw primary cllective dse cntributrs by labr categry fr were Miscellaneus and Unknwn. Prductin and technician wrkers receive the highest dse fr specified labr categry. In 996, the cnstructin categry is increasing due t cnstructin/demlitin wrk in prgress. Prductin was the highest cllective CEDE in 996 due t a single intake f Plutnium at SRS resulting in a dse f. rem. Trends cncerning internal dses may be misleading due t the relatively small number f individuals receiving dse and the tendency fr any intake t result in a significant cmmitted dse (CEDE)

104 C B: Dse Distributin by Labr Categry and Occupatin, 996 C R s. a Q i ' p Labr Categry Agriculture Cnstructin Labrers Management Misc. Prductin Scientists Service Technicians Transprt Unknwn Ttals Occupatin Frest Wrkers Grundskeepers Misc. Agriculture Carpenters Electricians Masns Mechanics/Repairers Miners/Drillers Misc. Repair/Cnstructin Painters Pipe Fitter Handlers/Labrers/Helpers Admin. Supprt and Clerical Manager Administratr Sales Military Miscellaneus Machine Setup/Operatrs Machinists Misc. Precisin/Prductin Operatrs, Plant/System/Util. Sheet Metal Wrkers Welders and Slderers Dctrs and Nurses Engineer Health Physicist Misc. Prfessinal Scientist Firefighters Fd Service Emplyees Janitrs Misc. Service Security Guards Engineering Technicians Health Technicians Misc. Technicians Radiatin Mnitrs/Techs. Science Technicians Technicians Bus Drivers Equipment Operatrs Misc. Transprt Pilts Truck Drivers Unknwn Lss Than Meas.,760 8, , ,908 9, , , ,8 44 7,8 9, ,67,464 89,87,9 86, ,80 00,494 Nte' Arrwed v alues indicate the greatest value in each clumn Meas. < , , , ,079 8, III 9 64 J M I L J n,00 Tw f the three largest cllecti /e lat r categc >ries wer Miscell ineus and U nknw n. Ths ; highest individual dse (. rem) was received bv an individual redrted as an Operatr a t a Prdu :tin faci litv. Ove rail, th e rdi jctin c nd te :hnician labr catearies had the hiahest averaae 7 I I I?j L?? I Ttal 4 >4 Mnitred 8 44,87 4,707 7, ,409 6,7 0,86 7 7,806< 0 9 6, , ,0 0, ,06 I 7,904 4,6,0,6,86 8, ,8 _JL0 l[_ J Jl J I,9 Percent with Meas. % 4% % % 8% % % 7% 4 8% 6% 8% 6% % 6% % 9% 8% 6% % 4% % % % % % % 9% 6<M 7% 7% % % 49% 9% 7% 8"/ N. with Meas ,0< 7 7 9, , , ,,7 Cllective ! 4.8 i.889 < < ' i ,6.90 Average Meas O.I 9< O.07

105 t B: Internal Dse Distributin by Site and Nuclide, = Operatins/ Field Office Nuclide Meas. 0.0O Number f Individuals Receiving Dses in Each Dse Range c 0.0 Ttal Individuals with Meas.» CEDE Cllective CEDE (persnrem) Average CEDE (rem) I ' Albuquerque Chicag Idah Oakland Oak Ridge Ohi Rcky Flats Richland Savannah River Ops. and Other Facilities Ls Alams Nat'l. Lab (LANL) Pantex Plant (PP) Ops. and Other Facilities Argnne Nat'l. Lab East (ANLE) _j_ Brkhaven Nat'l. Lab (BNL) Idah Site J Lawrence Berkeley Lab. (LBL) I Lawrence Livermre_NatI Lab. (LLNL) Ops. and Other Facilities Oak Ridge Site Paducah Gaseus Diff. Plant (PGDP) Prtsmuth Gaseus Diff. Plant (PORTS) Fernald Envirnmental MgmL Prject Mund Plant Rcky Flats Eng. Tech. Site (RFETS) jhanfrd~s7te~~ Savannah River Site (SRS) Hydrgen Hydrgen Plutnium Uranium Hydrgen Americium Hydrgen Other Plutnium Americium Hydrgen i Other i Plutnium i Hydrgen [ Plutnium Uranium Hydrgen Hydrgen i Thrium Uranium Hydrgen Other Technetium Uranium Uranium Thrium Thrium, Uranium Hydrgen,i Uranium \ Plutnium Uranium Other ^ Plutnium Americium Hydrgen Plutnium i 6J ' 8 4 I6 6 8' , ' 0 ' i., L _.!' , 0 7 " " _ ii r. 4 '_ t ' 7,i 8, ]4 i " r ~ "0.06 " i, 0.0, r _ Ttals,4 0 4,99... II _ M t The highest average internal dses were at LANL as a result f tw high dses frm intakes f Plutnium. The highest cllective dses were at SRS fllwed by Prtsmuth Gaseus Diffusin Plant, LANL, Oak Ridge Site, and Idah, respectively. The highest individual dse (. rem) ccurred at SRS resulting frm an intake f Plutnium.

106 B: Crrelatin f Occupatinal Radiatin Expsure with Nuclear Weapns Prductin 'i w i u i i ^ i y i i l i I IntermediateRange Nuclear Frces Treaty Sined. /87 Office f Envirnmental Restratin and Waste Management Established & Strategic Arms Reductin Treaty Signed 7/9 Chernbyl Nuclear Reactr Meitdwn Occurred 4^86 DOE Reprts N DOE Reactr is Prducing Tritium tr Nuclear Weapns DOE Sec. Testifies that the U S is Nt Building Any Nuclear Weapns & B8 DOE Occupatinal Radiatin Expsure

107 B: Crrelatin f Occupatinal Radiatin Expsure with Nuclear Weapns Prductin (Cntinued) Facility Ttal Cllective DDE (persnrem) Fuel Prcessing [j)j Maintenance & Supprt Other El Reactr H Research General E Waste Prcessing/Mgmt INEL TOTAL 69 ' i _ _ , _ , 8 '< I Acceleratr 0 0 Maintenance & Supprt 0 0 Other Reactr 0 0 Reseach, Fusin 0 0 Research, General Waste Prcessing/Mgmt 0 0 Weapns Fab & Testing 0 0_ LANL TOTAL Q_ _JL " Fuel Prcessing Fuel/Uranium Enrichment Other Research, General Weapns Fab & Testing Oak Ridge Site TOTAL J7 8 _49_ \ , ' 0 0^ &% 7, ' 4 _9j?_ IS « Weapns Fab & Testing Rcky Flats TOTAL Fuel Fabricatin Fuel Prcessing Maintenance & Supprt Other Reactr Research General Waste Prcessing/Mgmt Hanfrd Site TOTAL Fuel Fabricatin Fuel Prcessing Maintenance & Supprt Other Reactr Research, General Waste Prcessing/Mgmt Weapns Fab & Testing SRS TOTAL * Des nt Include Schenectady Naval Reactr Office r Pittsburgh Naval Reaar Office TOTAL FOR SIX SITES DOE OVERALL TOTAL* Percentages f Sites t DOE Overall,70,4,70, ,0, ,9 8,40 79% _ I 67 7 H, 6 9,, v,40 6] _ ,94, ,4 8,09 79%,9 6,06 8% ,98,7 8 J ,9, 8% J4,4 L II ,79,0 8 ( * 97 ) 97 I ,60,76 \ 77% i' I _ XJ44,04,4 9 J T I 8 90 _ I , } 8,600,809 76% 76% 77% 76% IS ,94,60 7% 996 Reprt Additinal Data B9

108 B: Crrelatin f Occupatinal Radiatin Expsure with Nuclear Weapns Prductin (Cntinued) The NReactr clsed at the Hanfrd Site in January 987, fllwed by the shutdwn f bth the PUREX and U0 plants in 988, and the shutdwn f the PFP in 989. DOE reprted in mid988 that n DOE reactr was prducing tritium fr nuclear weapns. The CReactr at the SRS was shut dwn in 987. The LReactr at SRS was restarted in 98 and shutdwn again in 988. The PReactr and the KReactr at SRS were shut dwn in 988 and never restarted except fr a brief KReactr test run in 99. The prductin f nuclear weapns materials at SRS ended in 99. A large decrease in the cllective dse at the Hanfrd Site fr the "Reactr" and"other" facility types ccurs between 987 and 988. The verall decrease in cllective dse at the Hanfrd Site frm 987 t 988 is dramatic. Cllective dse fr the "ReactrtJ) and "Other" facility types at the SRS decreased between 986 and 987. The verall decrease fr the SRS indicates that there is a slwdwn in activity at the SRS. Rcky Flats PFP peratins were curtailed in 989 and many ther functins suspended in the subsequent years with a ttal halt in plutnium peratins in 99. The plant began preparatins t resume activities in 99, but a change in missin t shut dwn, decntaminate, and decmmissin ccurred in 99. The Office f Envirnmental Restratin and Waste Management (EM) was established in Nvember 989. The K Plant at Oak Ridge was shut dwn in 98 and became an EM site in 99. The bulk shielding and twer shielding reactrs at ORNL were shut dwn in 988 and 99, respectively. The missin f they Plant has been changed t the dissassembly f nuclear weapns. The Secretary f Energy testified befre Cngress in May 99 that the United States was nt building any nuclear weapns fr the first time since 94. The high pressure tritium facility at LANL was shut dwn in 990 and the wrk scpe at the Idah Chemical Prcessing Plant (ICPP) (INEL) was reduced in 99. The cllective dse at the Rcky Flats Site decreased by 88% frm 986 t 990. it increased in 99 as a result f the abrted resumptin effrt, and has slwly decreased between 99 and 994. The cllective dse at the Oak Ridge Site decreased frm 986 t 99 and increased slightly in 99. In general, the K Plant is reprted as a "Fuel/Uranium Enrichment" facility type, ORNL is reprted as a "Research, General" facility type, and the Y Plant is reprted as a "Weapns, Fab & Testing" facility type. The shutdwn f the K Plant ccurred befre 98. The shutdwn f the experimental reactrs at ORNL crrelates with a cllective dse decrease in the "Research, General" facility type frm 987 t 990. TheY Plant,"Weapn,Fab & Testing" facility type cllective dse decreased between 986 and This crrelates with the end f weapns assembly The basic missin at the LANL has nt changed and INEL has many missins with the US Navy. The cllective dse shwn fr these sites shws gradual decrease. LANL cllective dse decreases 8% frm 98 t 99. INEL shws a decrease f mre than 79% during this perid but this decrease is nt cnsistent frm year t year. During the reprting perid 99994, the DOE verall cllective DDE increased by %. The cllective DDE at the Hanfrd, Rcky Flats, and Oak Ridge Sites decreased and the cllective DDE at the SRS has remained abut cnstant. The cllective dse increased at INEL and LANL as a result f increased activities at the ICPP, and increased thrughput fr satellite heat surces at the LANL plutnium facilities. As can be seen frm this analysis, changes in missin and peratinal status can have a large impact n the ccupatinal dse at DOE. B40 DOE Occupatinal Radiatin Expsure

109 Facility Type Cde Descriptins DOE Order 484. [0] requires cntractrs t indicate fr each reprted individual the facility cntributing the predminant prtin f that individual's effective dse equivalent. In cases when this cannt be distinguished, the facility type indicated shuld represent the facility type wherein the greatest prtin f wrk service was perfrmed. The facility type indicated must be ne f general facility categries shwn in Exhibit Cl. Because it is nt always a straightfrward prcedure t determine the apprpriate facility type fr each individual, the assignment f an individual t a particular facility type is a plicy decisin f each cntractr. The facility descriptins that fllw indicate the types f facilities included in each categry Als included are the types f wrk perfrmed at the facilities and the surces f the majrity f the radiatin expsures. Acceleratr The DOE administers apprximately a dzen labratries that perfrm significant acceleratrbased research. The acceleratrs range in size frm small singlerm electrstatic devices t a 4mile circumference synchrtrn, and their energies range frm kev t TeV The differences in acceleratr types,sizes, and energies result in differences in the radiatin types and dse rates assciated with the acceleratr facilities. In general, radiatin dses t emplyees at the facilities are attributable t neutrns and Xrays, as well as muns at sme larger facilities. Dse rates inside the primary shielding can range up t 0. rem/h as a result f Xray prductin near sme machine cmpnents. Outside the shielding, hwever,xray expsure rates are very lw, and neutrn dse rates are generally less than 0.00 rem/h. Average annual dses at these facilities are slightly higher than the verall average fr DOE; hwever, the cllective dse is lwer than the cllective dse fr mst ther DOE facility categries because f the relatively small number f emplyees at acceleratr facilities. Regarding internal expsures, tritium and shrtlived airbrne activatin prducts exist at sme acceleratr facilities, althugh annual internal dses are generally quite lw. Fuel/Uranium Enrichment The DOE invlvement in the nuclear fuel cycle generally begins with uranium enrichment peratins and facilities []. The current methd f enrichment is istpic separatin using the gaseus diffusin prcess, which invlves diffusing uranium thrugh a prus membrane and using the different atmic weights f the uranium istpes t achieve separatin. Exhibit Cl: Facility Type Cdes Facility Type Cde, Acceleratr Descriptin Fuel/Uranium Enrichment Fuel Fabricatin Fuel Prcessing Maintenance and Supprt (Site Wide] Reactr Research, General Research, Fusin Waste Prcessing/Mgmt. Weapns Fab. and Testing Other 996 Reprt Facility Type Cde Descriptins Cl

110 Althugh current facility designs and physical cntrls result in lw dses frm internally depsited uranium, the primary radilgical hazard is the ptential fr inhalatin f airbrne uranium []. Because f the lw specific activity f uranium, external dse rates are usually a few millirem per hur r less. Mst f the external dses that are received are attributable t gamma expsures, althugh neutrn expsures can ccur, especially when wrk is perfrmed near highly enriched uranium. Bth the average and cllective external dses at these facilities are amng the lwest f any DOE facility categry. Fuel Fabricatin Activities at fuel fabricatin facilities invlve the physical cnversin f uranium cmpunds t usable frms, usually rdshaped metal. Radiatin expsures t persnnel at these facilities are attributable almst entirely t gamma and beta radiatin. Hwever, beta radiatin is cnsidered the primary external radiatin hazard because f high beta dse rates (up t several hundred mrad per hur) at the surface f uranium rds []. Fr example, physical mdificatin f uranium metal by varius metalwrking peratins, such as machining and lathing peratins, requires prtectin against beta radiatin expsures t the skin, eyes, and extremities. Average external dses at fuel fabricatin facilities are generally higher than at ther types f DOE facilities; hwever, cllective dses are relatively lw because the number f emplyees is lw. Internal dses frm inhalatin f uranium are kept very lw. Fuel Prcessing The DOE administers several facilities that reprcess spent reactr fuel. These facilities separate the plutnium prduced in reactrs fr use in defense prgrams. They als separate the fissin prducts and uranium; the fissin prducts are nrmally designated as radiactive waste prducts, while the uranium can be refabricated fr further use as fuel. The very high radiactivity f fissin prducts in spent nuclear fuel results in emplyees at fuel prcessing facilities cnsistently having amng the highest average dses f any DOE facility type. Hwever, the cllective dse at these facilities is less significant because f the small ttal number f emplyees. Penetrating dses are attributable primarily t gamma phtns, althugh sme neutrn expsures d ccur. Skin and extremity dses frm handling samples are als significant, althugh nly a few emplyees typically receive skin dses greater than rem/year. Strict cntrls are in place at fuel reprcessing facilities t prevent internal depsitins; hwever, several measurable intakes typically ccur per year. Plutnium istpes represent the majrity f the internal depsitins, and annual effective dse equivalents frm the depsitins are typically less than 0. rem. Maintenance and Supprt Mst DOE sites have facilities dedicated t maintaining and supprting the site. In additin, sme emplyees may be classified under this facility type if their main functin is t prvide site maintenance and supprt, even thugh they may nt be lcated at a single facility dedicated t that purpse. C DOE Occupatinal Radiatin Expsure

111 Because many maintenance and supprt activities at DOE sites d nt invlve wrk near surces f inizing radiatin, the average dse equivalent per mnitred emplyee is typically amng the lwest f any facility type. Hwever, thse emplyees wh d perfrm wrk near radiatin surces receive relatively high average annual dses, as is indicated by the relatively high average annual dse per emplyee wh receives a measurable expsure. Als, cllective dses are relatively high because there is a large number f these emplyees relative t the number classified under ther facility types, The surces f inizing radiatin expsure are primarily gamma phtns. Hwever, variatins in the types f wrk perfrmed and wrk lcatins result in expsures f all types, including expsures t beta particles, xrays, neutrns, and airbrne radiactivity. Reactr The DOE and its predecessrs have built and perated dzens f nuclear reactrs since the mid940s. These facilities have included plutnium and tritium prductin reactrs, prttype reactrs fr energy prductin, research reactrs, reactrs designed fr special purpses such as prductin f medical radiistpes, and reactrs designed fr the prpulsin f naval vessels. In 99, many f the DOE reactrs were nt perating. As a result, persnnel expsures at DOE reactr facilities were attributable primarily t gamma phtns and beta particles frm cntaminated equipment and plant areas, spent reactr fuel, activated reactr cmpnents, and ther areas cntaining fissin r activatin prducts encuntered during plant maintenance and decmmissining peratins. Neutrn expsures d ccur at perating reactrs, althugh the resulting dses are a very small fractin f the cllective penetrating dses. Gamma dse rates in sme plant areas can be very high (up t several rems per hur), requiring extensive prtective measures. The average and cllective external dses relative t ther facility types are highly dependent n the status f reactr peratins. Inhalatin f airbrne radiactive material is a cncern in sme plant areas. Hwever, prtective measures, such as area ventilatin r use f respiratryprtectin equipment, result in lw internal dses. Research, General The DOE cntractrs perfrm research at many DOE facilities, including all f the natinal labratries. Research is perfrmed in general areas including bilgy bichemistry, health physics, materials science, envirnmental science, epidemilgy, and many thers. Research is als perfrmed in mre specific areas such as glbal warming, hazardus waste dispsal, energy cnservatin, and energy prductin. The spectrum f research invlving inizing radiatin r radiactive materials being perfrmed at DOE facilities results in a wide variety f radilgical cnditins. Depending n the research perfrmed, persnnel may be expsed t virtually any type f external radiatin, including beta particles, gamma phtns, 996 Reprt Facility Type Cde Descriptins C

112 xrays, and neutrns. In additin, there is the ptential fr inhalatin f radiactive material. Area dse rates and individual annual dses are highly variable. Relative t ther facility types, average annual individual dses are slightly abve average at general research facilities. The cllective dse equivalent is higher than at mst ther facility types because f the many individuals emplyed at general research facilities. Research, Fusin DOE currently perates bth majr and small facilities that participate in research n fusin energy. In general, bth penetrating and shallw radiatin dses are minimal at these facilities because the dse rates near the equipment are bth lw and intermittent. The external dses that d ccur are attributable primarily t xrays frm energized equipment. Relative t ther DOE facility types, average individual dses and cllective dses are typically the lwest at fusin research facilities. Regarding internal expsures, airbrne tritium is a cncern at sme fusin research facilities, althugh the current level f peratin results in minimal dses. Waste Prcessing/ Management Mst DOE sites have facilities dedicated t the prcessing and dispsal f radiactive waste. In general, the dse rates t emplyees when handling waste are very lw because f the lw specific activities r the effectiveness f shielding materials. As a result, very few emplyees at these facilities receive annual dses greater than 0. rem. At tw DOE sites, hwever, largescale waste prcessing facilities exist t prperly dispse f radiactive waste prducts generated during the nuclear fuel cycle. At these facilities, radiatin dses t sme emplyees can be relatively high, smetimes exceeding rem/ year. Penetrating dses at waste prcessing facilities are attributable primarily t gamma phtns; hwever, neutrn expsures are significant at the largescale facilities. Skin dses are generally nt a significant prblem. Overall, average annual dses at waste prcessing/ management facilities are amng the highest f any DOE facility type, which is attributable primarily t the tw largescale facilities and the shift in DOE missin frm natinal defense prductin t waste management and envirnmental restratin. The annual cllective dses are clser t the average f all facility types, hwever, because f the relatively small number f emplyees at this type f facility. Weapns Fabricatin and Testing The primary functin f a facility in this categry is t fabricate weapnsgrade material fr the prductin r testing f nuclear weapns. At the testing facilities, radiatin dses received by persnnel are generally minimal because f the strict cntrls ver persnnel access t testing areas, althugh extremity dses can be relatively high frm handling neutrn DOS Occupatinal Radiatin Expsure

113 activated materials. Radiatin dses are a greater cncern at facilities where weapns and weapnsgrade nuclear material are handled. At these facilities, neutrn radiatin dse rates can be significant when prcessing relatively small quantities f ^Pu r larger quantities f mixed plutnium istpes [6]. Penetrating dses frm gamma phtns and plutnium xrays can als be significant in sme situatins, as can skin and extremity dses frm plutnium xrays. Overall, average individual annual dses at these facilities are slightly higher than the DOE average. The cllective dses received by emplyees at these facilities are generally higher than the cllective dses at ther facility types because f the large number f individuals emplyed. Als f significant cncern at these facilities is inhalatin f plutnium, where inhalatin f very small amunts can result in dses exceeding limits. T prevent plutnium intakes, strict cntrls are in place including prcess cntainment, cntaminatin cntrl prcedures, and air mnitring and biassay prgrams [6]. As a result, significant internal expsures are very rare at these facilities. Other Individuals included in this facility type can be generally classified under three categries: () thse wh wrked in a facility that did nt match ne f the ten facility types described abve; () thse wh did nt wrk fr any appreciable time at any specific facility such as transient wrkers; r () thse fr whm facility type was nt indicated n the reprt frms. Examples f a facility type nt included in the ten described abve include cnstructin and irradiatin facilities. In general, emplyees classified under this facility type receive annual dses significantly less than the annual dses averaged ver all DOE facilities. Hwever, the wide variatin in the type f wrk perfrmed by these individuals results in a wide variatin in the types and levels f expsures. Althugh expsures t gamma phtns are predminant, sme individuals may be expsed t beta particles, xrays, neutrns, r airbrne radiactive material. 996 Reprt Facility Type Cde Descriptins C

114 CS This page intentinally left blank. D0E Occupatinal Radiatin Expsure

115 Limitatins f Data The fllwing is a descriptin f the limitatins f the data currently available in the DOE Radiatin Expsure Mnitring System (REMS). While these limitatins have been taken int cnsideratin in the analysis presented in this reprt, readers shuld be alert t these limitatins and cnsider their implicatins when drawing cnclusins frm these data. Individual Dse Recrds vs Dse Distributin Prir t 987, expsure data were reprted frm each facility in terms f a statistical dse distributin wherein the number f individuals receiving a dse within specific dse ranges was reprted. The cllective dse was then calculated frm the distributin by multiplying the number f individuals in each dse range by the midpint value f the dse range. Starting in 987, reprts f individual expsures were cllected that recrded the specific dse fr each mnitred individual. The cllective dse can be accurately determined by summing the ttal dse fr each individual. The dse distributin reprting methd prir t 987 resulted in up t a verestimatin f cllective dse. The reasn is that the distributin f dses within a range is usually skewed tward the lwer end f the range. If the midpint f the range is multiplied by the number f peple in the range, the prduct verestimates the cllective dse. Mnitring Practices Radiatin mnitring practices differ widely frm site t site and are based n the radiatin hazards and wrk practices at each site. Sites use different dsimeters and have different plicies n which wrkers t mnitr. While all sites have achieved cmpliance with the DOE Labratry Accreditatin Prgram (DOELAP),which standardizes the quality f dsimetry measurements, there are still differences in the dsimeters used that can cntribute t differences in the cllective dse frm site t site. The number f mnitred individuals can significantly impact the site's cllective dse. Sme sites supply dsimeters t virtually all wrkers. While this tends t inflate the number f mnitred wrkers with n dse, it als can add a large number f very lw dse wrkers t the ttal number f wrkers with measurable dse, thereby lwering the site's average measurable dse. Even at lw dses, these wrkers add significantly t the site cllective dse. In cntrast, ther sites nly mnitr wrkers wh exceed the mnitring requirement threshld ( f the dse limit). This tends t reduce the number f mnitred wrkers and reprts nly thse wrkers receiving dses in the higher dse ranges. This can decrease the site's cllective dse while increasing the average measurable dse. AEDE vs CEDE Prir t 990, the dse resulting frm penetrating inizing radiatin (external dse) and the dse resulting frm the intake f radinuclides (internal dse), was reprted separately In 99, the DOE changed the internal dse calculatin methdlgy frm annual effective dse equivalent (AEDE) t the 0year cmmitted effective dse equivalent (CEDE). The ttal effective dse equivalent () then became the sum f the CEDE and the deep dse equivalent (DDE). This reprt presents data frm 99 thrugh 996. Internal AEDE data are reprted fr 99 and internal CEDE data are reprted fr 99,994,99,and 996. Where pssible, the legacy cmpnent f 996 Reprt Limitatins f Data

116 the AEDE data is highlighted when presenting data that are trended fr the years 990 t 99. See Sectin.4 fr a discussin f this change in requirements. Occupatin Cdes Each individual's dse recrd includes the ccupatin cde fr the individual while he r she wrked at the DOE site during the mnitring year. Occupatinal cdes typically represent the ccupatin the individual held at the end f the calendar year and may nt represent the ccupatin where the majrity f dse was received if the individual held multiple ccupatins during the year. The ccupatin cdes are very brad categrizatins and are gruped int nine general categries. Each year a percentage (up t ) f the ccupatins are listed as unknwn, r as miscellaneus. The definitins f each f the labr categries are subject t interpretatin by the reprting rganizatin and/r the individual's emplyer. Facility Type The facility type is als recrded with each dse recrd fr the mnitring year. It is intended t reflect the type f facility where the individual received mst f their ccupatinal radiatin expsure during the mnitring year. While the facility types are clearly defined (see Appendices A and C), the reprting rganizatins ften have difficulty tracking which facility type cntributed t the majrity f the individual's expsure. Certain individuals tend t wrk in the prximity f several different facility types thrughut the mnitring year and are ften included in the "Maintenance and Supprt (Sitewide)" facility type. The facility type fr temprary cntract wrkers and visitrs is ften nt reprted and is defaulted t "unknwn." In additin t these uncertainties, the phase f peratin f the facility types is nt currently reprted. A facility type f "acceleratr" may be reprted when in fact, the acceleratr has nt been in peratin fr a cnsiderable time and may be in the prcess f stabilizatin,decmmissining, r decntaminatin. In additin, several sites have cmmented that they have difficulty assigning the facility type, because many f the facilities are n lnger peratinal. Fr example, sme sites cmmented that a reactr that is being decmmissined is n lnger cnsidered a "reactr" facility type. Other sites cntinue t categrize a facility based n the riginal intent r design f the facility, regardless f its current status. DOE Headquarters will be reviewing the Facility Type cdificatin scheme and mdifying the reprting requirements t standardize the use f facility type classificatins and imprve the quality f the data and the data analysis. Organizatin Cde Facilities reprt data t the central repsitry based n an "rganizatin cde". This cde identifies the Operatins r Field Office, the reprting facility, and the cntractr r subcntractr that is reprting the expsure infrmatin. The rganizatin cde changes ver time as DOE Offices are rerganized. In sme cases, new Operatins r Field Offices are created, in ther cases a Field Office may change rganizatins and begin reprting with anther Field Office. Tw such changes are ntewrthy within the past several years. The Fernald Field Office began reprting independently in 99. Prir t 99 it reprted under the Oak Ridge Field Office. In 994, Fernald was incrprated int the newly created Ohi Field Office. The Ohi Field Office began reprting in 994. Fr this reasn, the DOE Occupatinal Radiatin Expsure

117 Fernald data are shwn under the Ohi Field Office. The Mund Plant and West Valley Prject als changed Operatins Office during the past years and are nw shwn under the Ohi Field Office. Ftntes indicate the change in Operatins Offices. Naval Reactr Facilities The expsure infrmatin fr the Schenectady and Pittsburgh Naval Reactr facilities is nt included in this reprt. Readers shuld nte that the dse infrmatin fr the verall DOE cmplex presented in this reprt may differ frm ther reprts r surces f infrmatin because f the exclusin f these data. Updates t the Data The data in the REMS database are subject t crrectin and update n a cntinual basis. Data fr prir years are subject t crrectin as well as the data fr the mst recent year included in this reprt. Crrectins will be reflected in subsequent annual reprts. Fr the mst uptdate status f radiatin expsure infrmatin, cntact: Ms.NirmalaRa REMS Prject Manager U.S. Department f Energy Office fwrker Prtectin Prgrams and Hazards Management (EH) Germantwn.MD 0874 Expsure infrmatin fr Naval Reactr prgrams can be fund in the mst recent versin f the fllwing series f reprts (where XX represents the reprt year): NTXX "Occupatinal Radiatin Expsure frm U.S. Naval Nuclear Plants and Their Supprt Facilities", NTXX "Occupatinal Radiatin Expsure frm U.S. Naval Reactrs' Department f Energy Facilities". 996 Reprt

118 D4 This page intentinally left blank. DOE Occupatinal Radiatin Expsure

119 Access t Radiatin Expsure Infrmatin Radiatin Expsure Mnitring System The data used t cmpile this reprt were btained frm the DOE Radiatin Expsure Mnitring System (REMS), which serves as the central repsitry f radiatin expsure infrmatin fr DOE Headquarters. Recently the REMS has undergne an extensive redesign effrt in cmbinatin with the effrts invlved in revising the annual reprt. One f the main gals f the redesign effrt is t allw researchers better access t the REMS data. Hwever, there is cnsiderable diversity in the gals and needs f these researchers. Fr this reasn, a multitiered apprach has been develped t allw researchers flexibility in accessing the REMS data. Exhibit El lists the varius ways f accessing the DOE radiatin expsure infrmatin cntained in REMS. A descriptin is given fr each access methd as well as requirements fr access and skill sets needed fr each methd. Descriptins f the intended research audience and experience level (fr cmputer systems) are als prvided.t btain further infrmatin, a cntact name and phne number are prvided. A brief summary f the multitier access t the REMS infrmatin is shwn in Exhibit El. The data cntained in the REMS system are subject t peridic update. Data fr the current r previus years may be updated as crrectins r additins are submitted by the sites. Fr this reasn, the data presented in published reprts may nt agree with the current data in the REMS database. These updates typically have a relatively small impact n the data and shuld nt affect the general cnclusins and analysis f the data presented in this reprt. Cmprehensive Epidemilgic Data Resurce Of interest t researchers in radiatin expsure is the health risk assciated with wrker expsure t radiatin. While the health risk frm ccupatinal expsure is nt treated in this reprt.it has been extensively researched by DOE. The Cmprehensive Epidemilgic Data Resurce (CEDR) serves as a central resurce fr radiatin health risk studies at the DOE. Epidemilgic studies n health effects f radiatin expsures have been supprted by the DOE fr mre than 0 years. The results f these studies, which initially fcused n the evaluatin f mrtality amng wrkers emplyed in the nuclear weapns cmplex, have been published in scientific literature. Hwever, the data cllected during the cnduct f the studies were nt widely shared. CEDR has nw been established as a publicuse database t braden independent access and use f these data. At its intrductin in 99, CEDR included primarily ccupatinal studies f the DOE wrkfrce, including demgraphic, emplyment, expsure, and mrtality fllwup infrmatin n mre than 40,000 wrkers. In the past years, the prgram's hldings have been expanded t include data frm bth ccupatinal and cmmunity health studies, such as thse examining the impact f fallut frm nuclear weapns testing, cmmunity dse recnstructins, data frm the decades f fllwup n atmic bmb survivrs, and health surveillance reprts n current DOE wrkers. CEDR accmplishes this by a hierarchical structure that accmmdates analysis and wrking files generated during a study, as well as files f dcumentatin that are critical fr understanding the data. CEDR prvides easy access t its hldings thrugh the Internet r dialup cnnectins, phne ^ IS 8 * 996 Reprt Access t Radiatin Expsure Infrmatin El

120 and mail interchanges, and prvides an extensive catalg f its hldings. CEDR has becme a unique resurce cmprising the majrity f data that exist n the risks f radiatin expsure. Fr further infrmatin cncerning the CEDR system, cntact: Ms. Barbara G. Brks Prgram Manager Office f Epidemilgic Studies, EH6 U.S. Department f Energy 990 Germantwn Rad Germantwn.MD barbara.brks@hq.de.gv Or access the CEDR internet web page at \E DOE Occupatinal Radiatin Expsure

121 t 8 Exhibit E: Methds f Accessing REMS Infrmatin Experience Requirements REMS Infrmatin Access Methd Knwledge f REMS Data Cmputer Expertise System Adminstratr Setup Sftware Requirements Eligibility Requirements T Get Access Hardcpy Annual Reprt Nne. Data explained in reprt. N/A N/A Nne. Nne. Cntact EH t request that yu be added t Annual Reprt mailing list. Web Page Lw. General knwledge/interest in radiatin data. Minimal cmputer skills. Only a knwledge f hw t use the Web brwser, and an Internet cnnectin. Medium. Supply LAN cnnectin t Internet r Internet Prvider. Supprt Web brwser. Internet access. Web brwser client sftware. Nne. Cnnect t http.7/ rems.eh.de.gv/ InfMaker Predefined reprts Medium. Need t knw the data limitatins f the data in REMS, and what the expsure data represent. Minimal. Familiarity with Windws applicatins. Need t understand difference between Query and Reprts. Medium. Clientserver cmputer cnfiguratin can be cmplex, but this is a netime effrt. InfMaker supprt prvided by DOE HQ. Internet access (TCP/IP). Oracle SQLNet. PwerSft InfMaker. [Oracle SNS sftware if Categry I user) N requirements fr Categry users 4. Categry users must get "need t knw" Privacy Act authrizatin frm EH'. Cntact OIM t request access. EH authrizatin required fr Categry I users. InfMakerAd Hc Queries High. Need t thrughly understand the data dictinary, relatinships and structure f the database. Umitatins f the data. Medium (t High). Sme knwledge f SQL highly recmmended. Shuld be familiar with "Reprt generatin"type sftware. Medium. Clientserver cmputer cnfiguratin can be cmplex, but this is a netime effrt. InfMaker supprt prvided by DOE HQ. Internet access (TCP/IP). Oracle SQLNet. PwerSft InfMaker. (Oracle SNS sftware if Categry userj N requirements fr Categry users 4. Categry I users must get "need t knw" Privacy Act authrizatin frm EH'. Cntact OIM t request access. EH authrizatin required fr Categry users. >»' ' t p Client query tl ther than InfMaker Running SQL n the REMS Server High. Need t thrughly understand the data dictinary, relatinships and structure f the database. Umitatins f the data. High. Need t thrughly understand the data dictinary, relatinships and structure f the database. Umitatins f the data. High. Need t be skilled In SQL and cnnecting t the system. Need t be skilled In the use f whatever query tl Is used. High. Need t be skilled in SQL and cnnecting t the system. Medium. Supprt fr LAN cnnectin t Internet r Internet Prvider. Supprt user query sftware. Medium. Supprt fr LAN cnnectin t Internet r Internet Prvider. Supprt TELNet sftware. Internet access (TCP/IP). Oracle SQLNet. ODBC Drivers. Query Tl client. [Oracle SNS sftware if Categiy I user) Internet access (TCP/IP). TeLNet sftware. N requirements fr Categry users 4. Categry users must get "need t knw" Privacy Act authrizatin frm EH'. Categry use nly. TeLNet authrizatin required fr firewall. Cntact OIM t request access. EH authrizatin required fr Categry I users. Cntact OIM t request access. EH cntact Ms. Nirmala Ra at Phne: (0) 9097, Fax: (0) 90777, Nimi.Ra@hq.de.gv OIM cntact Mr. Pat Heinig at Phne: (0) Fax: (0) 9008 See REMS User Manual fr detailed sftware Categry All data in the REMS system, including Privacy Act data such as name and scial security number f the mnitred individual. Categry Access t nnsensitive radiatin mnitring infrmatin per mnitred Individual. See REMS Reference Manual fr details.