ML18137A171: Difference between revisions
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{{#Wiki_filter:/RA/}} | {{#Wiki_filter:July 23, 2018 | ||
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MEMORANDUM TO: Steve R. Ruffin, Chief Piping and Head Penetrations Branch Division of Materials and License Renewal Office of Nuclear Reactor Regulation FROM: Stephen E. Cumblidge, Materials Engineer /RA/ | |||
Piping and Head Penetrations Branch Division of Materials and License Renewal Office of Nuclear Reactor Regulation | |||
==SUBJECT:== | |||
==SUMMARY== | |||
OF APRIL 17, 2018 PUBLIC MEETING WITH ELECTRIC POWER RESEARCH INSTITUTE REGARDING ASME CODE SECTION XI APPENDIX R On April 17, 2018, the U.S. Nuclear Regulatory Commission staff met with representatives of the Electric Power Research Institute (EPRI). The purpose of the meeting was to discuss the conditions prohibiting the use of American Society for Mechanical Engineers Boiler and Pressure Vessel Code Section XI Appendix R. This meeting was held at Three White Flint North in Rockville Maryland and a teleconference number was provided for additional public participation. | |||
Meeting Summary The U.S. Nuclear Regulatory Commission (NRC) staff met with representatives of the Electric Power Research Institute (EPRI) to discuss the conditions prohibiting the use of American Society for Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Section XI Appendix R. Appendix R describes two methods for a licensee to apply risk-informed inservice inspections (RI-ISI) as an alternative to the inspections described in Section XI. The NRC has placed a condition in Title 10 of the Code of Federal Regulations (10 CFR) 50.55a prohibiting the use of Section XI Appendix R. This prohibition requires licensees to submit their RI-ISI plan developed using these two methods to the NRC for review and approval. The NRC has approved ASME Code Case N-716-1, which is a simplified and relatively conservative RI-ISI program, for use without the need to submit the RI-ISI plan to the NRC for review and approval. | |||
The EPRI staff is interested in determining the appropriate modifications to Appendix R that would allow for generic NRC approval. In the meeting EPRI presented information on the two RI-ISI methods described in Appendix R and the changes made to them since the last NRC review of Appendix R. The first method in Appendix R is the most complicated. It uses expert panels and probabilistic fracture mechanics calculations and allows for the fewest inspections. | |||
The second method in Appendix R is similar to the method described in ASME Code Case N- 716-1 but more complicated. Currently five nuclear power plants are using the first method CONTACT: Stephen Cumblidge, DMLR/MPHB 301-415-2823 | |||
S. Ruffin in Appendix R, approximately 50 nuclear power plants are using the second method in Appendix R, and approximately 45 are using the RI-ISI method described in ASME Code Case N-716-1. | |||
The NRC technical position was then discussed. The NRC staff technical issues were almost entirely related to the first RI-ISI method in Appendix R, with a few questions on the second RI-ISI method. The idea that the first method could be removed and ASME Code Case N-716-1 could be added to Appendix R was briefly discussed. The NRC agreed that the revised Appendix R will be reviewed, although the timing of the review is to be determined. The NRC staff agreed to determine if the resources for a near term evaluation are available by May 1, 2018. | |||
The attendance list including those who participated in the meeting by teleconference is included in Enclosure 1, and the meeting Agenda is included in Enclosure 2. There were no questions from the public. | |||
==Enclosures:== | |||
: 1. Participants List | |||
: 2. Meeting Agenda | |||
LIST OF PARTICIPANTS FOR THE APRIL 17, 2018 PUBLIC MEETING PARTICIPANTS AFFILIATION Stephen Cumblidge U.S. Nuclear Regulatory Commission (NRC) | |||
Carol Nove NRC Kevin Hacker Dominion Generation Carl Latiolais Electric Power Research Institute (EPRI) | |||
David Alley NRC Doug Kull EPRI Matthew Homiack NRC Michael Benson NRC Robert Tregoning NRC Jana Bergman Curtis-Wright Patrick O'Regan EPRI Michael Levine NRC Stephen Dinsmore NRC Douglas Jacobs PSEG Nuclear, LLC Kevin Hall Iddeal Solutions Keith Hoffman NRC Enclosure 1 | |||
==PUBLIC MEETING AGENDA== | |||
FOR APRIL 17, 2018 MEETING WITH ELECTRIC POWER RESEARCH INSTITUTE REGARDING ASME CODE SECTION XI APPENDIX R Time Topic Speaker 9:00-9:10 Open Meeting and Introductions NRC 9:10-9:40 Presentation on Appendix R EPRI 9:40-11:45 Discussion All 11:45-12:00 Public Comment Period All 12:00 Adjourn Enclosure 2 | |||
Package: ML18137A170 Summary: ML18137A171 Presentation: ML18137A173 Slides: ML18100A277 OFFICE PM:MRPB:DMLR LA: MRPB:DMLR BC:MPHB:DMLR NAME SCumblidge YEdmonds SRuffin DATE 07/23/2018 07/23/2018 07/23/2018}} | |||
Revision as of 02:53, 21 October 2019
| ML18137A171 | |
| Person / Time | |
|---|---|
| Issue date: | 07/23/2018 |
| From: | Stephen Cumblidge NRC/NRR/DMLR/MPHB |
| To: | Steve Ruffin NRC/NRR/DMLR/MPHB |
| Cumblidge S, NRR-DMLR 415-2823 | |
| Shared Package | |
| ML18137A170 | List: |
| References | |
| Download: ML18137A171 (5) | |
Text
July 23, 2018
.
MEMORANDUM TO: Steve R. Ruffin, Chief Piping and Head Penetrations Branch Division of Materials and License Renewal Office of Nuclear Reactor Regulation FROM: Stephen E. Cumblidge, Materials Engineer /RA/
Piping and Head Penetrations Branch Division of Materials and License Renewal Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF APRIL 17, 2018 PUBLIC MEETING WITH ELECTRIC POWER RESEARCH INSTITUTE REGARDING ASME CODE SECTION XI APPENDIX R On April 17, 2018, the U.S. Nuclear Regulatory Commission staff met with representatives of the Electric Power Research Institute (EPRI). The purpose of the meeting was to discuss the conditions prohibiting the use of American Society for Mechanical Engineers Boiler and Pressure Vessel Code Section XI Appendix R. This meeting was held at Three White Flint North in Rockville Maryland and a teleconference number was provided for additional public participation.
Meeting Summary The U.S. Nuclear Regulatory Commission (NRC) staff met with representatives of the Electric Power Research Institute (EPRI) to discuss the conditions prohibiting the use of American Society for Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)Section XI Appendix R. Appendix R describes two methods for a licensee to apply risk-informed inservice inspections (RI-ISI) as an alternative to the inspections described in Section XI. The NRC has placed a condition in Title 10 of the Code of Federal Regulations (10 CFR) 50.55a prohibiting the use of Section XI Appendix R. This prohibition requires licensees to submit their RI-ISI plan developed using these two methods to the NRC for review and approval. The NRC has approved ASME Code Case N-716-1, which is a simplified and relatively conservative RI-ISI program, for use without the need to submit the RI-ISI plan to the NRC for review and approval.
The EPRI staff is interested in determining the appropriate modifications to Appendix R that would allow for generic NRC approval. In the meeting EPRI presented information on the two RI-ISI methods described in Appendix R and the changes made to them since the last NRC review of Appendix R. The first method in Appendix R is the most complicated. It uses expert panels and probabilistic fracture mechanics calculations and allows for the fewest inspections.
The second method in Appendix R is similar to the method described in ASME Code Case N- 716-1 but more complicated. Currently five nuclear power plants are using the first method CONTACT: Stephen Cumblidge, DMLR/MPHB 301-415-2823
S. Ruffin in Appendix R, approximately 50 nuclear power plants are using the second method in Appendix R, and approximately 45 are using the RI-ISI method described in ASME Code Case N-716-1.
The NRC technical position was then discussed. The NRC staff technical issues were almost entirely related to the first RI-ISI method in Appendix R, with a few questions on the second RI-ISI method. The idea that the first method could be removed and ASME Code Case N-716-1 could be added to Appendix R was briefly discussed. The NRC agreed that the revised Appendix R will be reviewed, although the timing of the review is to be determined. The NRC staff agreed to determine if the resources for a near term evaluation are available by May 1, 2018.
The attendance list including those who participated in the meeting by teleconference is included in Enclosure 1, and the meeting Agenda is included in Enclosure 2. There were no questions from the public.
Enclosures:
- 1. Participants List
- 2. Meeting Agenda
LIST OF PARTICIPANTS FOR THE APRIL 17, 2018 PUBLIC MEETING PARTICIPANTS AFFILIATION Stephen Cumblidge U.S. Nuclear Regulatory Commission (NRC)
Carol Nove NRC Kevin Hacker Dominion Generation Carl Latiolais Electric Power Research Institute (EPRI)
David Alley NRC Doug Kull EPRI Matthew Homiack NRC Michael Benson NRC Robert Tregoning NRC Jana Bergman Curtis-Wright Patrick O'Regan EPRI Michael Levine NRC Stephen Dinsmore NRC Douglas Jacobs PSEG Nuclear, LLC Kevin Hall Iddeal Solutions Keith Hoffman NRC Enclosure 1
PUBLIC MEETING AGENDA
FOR APRIL 17, 2018 MEETING WITH ELECTRIC POWER RESEARCH INSTITUTE REGARDING ASME CODE SECTION XI APPENDIX R Time Topic Speaker 9:00-9:10 Open Meeting and Introductions NRC 9:10-9:40 Presentation on Appendix R EPRI 9:40-11:45 Discussion All 11:45-12:00 Public Comment Period All 12:00 Adjourn Enclosure 2
Package: ML18137A170 Summary: ML18137A171 Presentation: ML18137A173 Slides: ML18100A277 OFFICE PM:MRPB:DMLR LA: MRPB:DMLR BC:MPHB:DMLR NAME SCumblidge YEdmonds SRuffin DATE 07/23/2018 07/23/2018 07/23/2018