ASME BPV XI Interpretation Handout May 10, 2017

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1 ASME BPV XI Interpretation Handout May 10, 2017 Interpretation# and Code Change pg. 2-4 Interpretation# pg. 5 Interpretation# pg. 6 Interpretation# pg. 7 1 of 7

2 Revised Question for Question: Is it the intent that Appendix E be applied to nozzles in the reactor pressure vessel beltline region? Reply: No. 2 of 7

3 BPVC Section: SC-XI Record Number: Revision Number: 1.0 Based on Version: V IWB-3720 Unanticipated Operating Events (a) When an operating event causes an excursion outside the normal operating pressure and temperature limits defined in the plant Technical Specifications, an evaluation shall be performed to determine the effects of the out of limit condition on the structural integrity of the Reactor Coolant System. (b) Nonmandatory Appendix E provides procedures and criteria that may be used to evaluate the integrity of the reactor vessel beltline, excluding nozzles, for the out of limit condition. (c) The evaluation procedures shall be the responsibility of the Owner and shall be subject to acceptance by the regulatory authority having jurisdiction at the plant site. Date: 5/9/17 3 of 7 1 of 2

4 BPVC Section: SC-XI Record Number: Revision Number: 1.0 Based on Version: V Nonmandatory Appendix E Evaluation of Unanticipated Operating Events Article E-1000 Introduction E-1100 Scope This Nonmandatory Appendix provides acceptance criteria and guidance for performing an evaluation of the effects of an out of limit condition on the structural integrity of the reactor vessel beltline region, excluding nozzles. Showing compliance with the criteria in either E-1200 or E-1300 assures that the beltline region, excluding nozzles, has adequate structural integrity for the unit to return to service. Evaluations performed using this Nonmandatory Appendix shall meet all the requirements of the Appendix. E-1200 Acceptance Criteria 49,50 Adequate structural integrity of the reactor vessel beltline region, excluding nozzles, is assured if the following applicable criterion is satisfied throughout the event: (a) For isothermal pressure transients [i.e., ΔT c /Δt < 10 F/hr (5.5 C/hr)], the maximum pressure does not exceed the allowable values of Table E-1 at any value of T c RT NDT. Date: 5/9/17 4 of 7 2 of 2

5 Inquiry Passed WG PQSV&ET and SGNDE VII-4330(b) Level III personnel shall be recertified using the written Method, Specific, and Practical Examinations and the Demonstration Examination. Alternatively, Level III personnel may be recertified using only the written Method and Specific Examinations provided the following conditions are met: (1) The Level III candidate was previously certified or recertified using all the written examinations and the Demonstration Examination. Question: May a Level III candidate be recertified using only the written Method, and Specific Examinations, if the candidate was recertified with only method, specific, practical and demonstration examinations? Reply: Yes, provided the candidate s service was not interrupted in accordance with VII Applicability: 1995 Edition through 2017 Edition 5 of 7

6 Inquiry Record Subject: Pumps Flange Surface Examination, TABLE IWB , B-G-1, B6.190 Explanation: Inquirer Proposed Question: When the four Reactor Coolant Pumps of same design, size performing same function in system are disassembled, Is it permissible to examine only one pump flange surface (VT-1) during the interval? [applicable edition 2001 with 2003 addenda through the 2017 Edition] Inquirer Proposed Reply: <None Provided> Inquirer Background: IWB , B-G-1, NOTES: (3) Volumetric examination of bolting for heat exchangers, pumps, or valves may be conducted on one heat exchanger, one pump, or one valve among a group of heat exchanger, pumps, or valves that are similar in design, type, and function. In addition, when the component to be examined contains a group of bolted connections of similar design and size such as flanged connections, the examination may be conducted one bolted connection among the group. (4) Visual examination of bolting for heat exchangers, pumps, or valves is required only when the component is examined under Examination Category B-B, B-L-2, or B-M-2. Examination of a bolted connection is required only once during the interval. IWB , B-L-2, B12.20, Pump Internal Surface [Note 1] (1) Examinations are limited to at least one pump in each group of pumps performing similar functions in the system, e.g., recirculating coolant pumps. Inquirer: Mr. Won Park, ANSCO, 418, Munji-Dong, Yuseong-Gu, Daejeion, South Korea, wpark@ansco.kr Inquiry and response were reworded at SG WCS as follows: Is it a requirement of Table IWB , Examination Category B-G-1, that a visual VT-1 examination of the pump flange surface be performed on more than one pump performing a similar function in the system during each inspection interval? Response: No Motion for alternative intent inquiry passed WG-ISC Motion to change to intent inquiry passed SG WCS of 7

7 Inquiry Original Question 1: Regarding Appendix G to the Section XI of ASME Code, no upper limit is specified in Section G-2110 while Fig. G shows fracture toughness up to 220 ksi?in. Does 220 ksi?in mean an upper limit value for KIc? Revised Question 1: Is it a requirement of ASME Code Section XI, Appendix G that an upper limit of 220 ksiin^0.5 be applied to KIC? Reply: No Original Question 2: If it doesn't mean upper limit value, is it permissible to evaluate the RCS Pressure- Temperature Limits Curve up to the system design pressure without placing the upper limit of the fracture toughness (KIc)? Revised Question 2: If the reply to Question 1 is no, is it permissible to evaluate the RCS Pressure- Temperature Limits Curve up to the system design pressure without placing the upper limit of the fracture toughness (KIc)? Reply: Consulting (Yes) 7 of 7

Rules for Inservice Inspection of Nuclear Power Plant Components

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