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| number = ML19094A377 | | number = ML19094A377 | ||
| issue date = 06/19/2019 | | issue date = 06/19/2019 | ||
| title = | | title = Summary of Meeting Between the U.S. Nuclear Regulatory Commission Staff and the Electric Power Research Institute to Discuss BWRVIP-329 | ||
| author name = Holonich J | | author name = Holonich J | ||
| author affiliation = NRC/NRR/DLP/PLPB | | author affiliation = NRC/NRR/DLP/PLPB | ||
| Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:/RA/}} | {{#Wiki_filter:June 19, 2019 MEMORANDUM TO: Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation FROM: Joseph J. Holonich, Senior Project Manager Licensing Processes Branch /RA/ | ||
Division of Licensing Projects Office of Nuclear Reactor Regulation | |||
==SUBJECT:== | |||
==SUMMARY== | |||
OF THE MAY 29, 2019, MEETING BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION STAFF AND THE ELECTRIC POWER RESEARCH INSTITUTE TO DISCUSS BWRVIP-329 On May 29, 2019, the U.S. Nuclear Regulatory Commission (NRC) staff met with representatives from the Electric Power Research Institute (EPRI). The purpose of the meeting was to discuss the Boiling Water Reactor (BWR) Vessel and Internals Project (BWRVIP) plans for submittal of BWRVIP-329, "Updated Probabilistic Fracture Mechanics Analyses for BWR RPV [Reactor Pressure Vessel] Welds to Address Extended Operations." Information related to the meeting including presentations and the attendees list can be found in the Agencywide Document Access and Management System (ADAMS) package ML19094A354. | |||
In the open portion of the meeting, EPRI representatives provided background on the development of BWRVIP-329. It was explained that BWRVIP-05, BWR Reactor Pressure Vessel Shell Weld Inspection Recommendations (BWRVIP-05), was the initial report that provided a technical basis for exemption from the inspection requirements in American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI for circumferential welds in BWR reactor pressure vessels. EPRI noted that BWRVIP-05 was very beneficial in plants saving time, dose, and money. | |||
EPRI further explained that BWRVIP-329 is intended to extend these benefits to plants applying for subsequent license renewal. It is intended to be an alternative to BWRVIP-05 and BWRVIP-74, BWR Vessel and Internals Project, BWR Reactor Pressure Vessel Inspection and Flaw Evaluation Guidelines for License Renewal." The safety evaluation for BWRVIP-74 covers plant life extension from 40 to 60 years. BWRVIP-329 could be used by plants to extend life from 40 to 60 years but was not intended as a replacement for BWRVIP-05 or BWRVIP-74. | |||
In addition, EPRI explained that there were no plant-specific values in BWRVIP-329. Individual plants would use their own plant-specific information to verify that the conclusions of BWRVIP-329 apply to their plant. | |||
CONTACT: Joseph J. Holonich, NRR/DLP/PLPB 301-415-7297 | |||
D. Morey During the discussions, the NRC staff asked if EPRI considered the draft regulatory guidance on probabilistic fracture mechanics (PFM). EPRI responded that the PFM regulatory guidance and EPRI white paper had been considered in developing BWRVIP-329. | |||
In the closed portion of the meeting, EPRI provided details on the information in BWRVIP-329. | |||
During that portion, the NRC staff and EPRI representatives engaged in numerous clarification discussions and questions and answers on the proposed changes. The information discussed was proprietary, so no details of the discussions are provided. | |||
Actions from the closed portion of the meeting were: | |||
: 1) EPRI will review criteria in draft regulatory guidance on PFM to determine if there are clarifications that should be added to BWRVIP-329; | |||
: 2) EPRI will consider if the flaw distribution assumptions used as inputs to the BWRVIP-329 analysis could be further clarified; and | |||
: 3) EPRI will consider if additional explanation of the assumptions regarding shop versus field welds included in BWRVIP-329 would be beneficial. | |||
In closing the meeting, EPRI informed the NRC staff that BWRVIP-329 will be submitted in late 2019. BWRVIP-329 was needed for subsequent license renewal. It was considered a higher priority than BWRVIP-315, Vessel Internals Aging Management Evaluation for Extended Operations, and BWRVIP-316, Reactor Vessel Aging Management Evaluation for Extended Operations. | |||
Docket No. 99902016 | |||
ML19094A354 (Package); | |||
ML19094A377 (Summary) *concurrence via e-mail NRC-001 OFFICE NRR/DLP/PLPB/PM* NRR/DMLR/MVIB/BC* NRR/DLP/PLPB/BC NRR/DLP/PLPB/PM NAME JHolonich DAlley DMorey JHolonich DATE 06/18/2019 06/18/2019 06/18/2019 06/19/2019}} | |||
Latest revision as of 03:39, 30 November 2019
| ML19094A377 | |
| Person / Time | |
|---|---|
| Site: | 99902016 |
| Issue date: | 06/19/2019 |
| From: | Joseph Holonich NRC/NRR/DLP/PLPB |
| To: | Dennis Morey NRC/NRR/DLP/PLPB |
| Holonich J, NRR/DLP/PLPB, 415-7297 | |
| Shared Package | |
| ML19094A354 | List: |
| References | |
| Download: ML19094A377 (3) | |
Text
June 19, 2019 MEMORANDUM TO: Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation FROM: Joseph J. Holonich, Senior Project Manager Licensing Processes Branch /RA/
Division of Licensing Projects Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF THE MAY 29, 2019, MEETING BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION STAFF AND THE ELECTRIC POWER RESEARCH INSTITUTE TO DISCUSS BWRVIP-329 On May 29, 2019, the U.S. Nuclear Regulatory Commission (NRC) staff met with representatives from the Electric Power Research Institute (EPRI). The purpose of the meeting was to discuss the Boiling Water Reactor (BWR) Vessel and Internals Project (BWRVIP) plans for submittal of BWRVIP-329, "Updated Probabilistic Fracture Mechanics Analyses for BWR RPV [Reactor Pressure Vessel] Welds to Address Extended Operations." Information related to the meeting including presentations and the attendees list can be found in the Agencywide Document Access and Management System (ADAMS) package ML19094A354.
In the open portion of the meeting, EPRI representatives provided background on the development of BWRVIP-329. It was explained that BWRVIP-05, BWR Reactor Pressure Vessel Shell Weld Inspection Recommendations (BWRVIP-05), was the initial report that provided a technical basis for exemption from the inspection requirements in American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI for circumferential welds in BWR reactor pressure vessels. EPRI noted that BWRVIP-05 was very beneficial in plants saving time, dose, and money.
EPRI further explained that BWRVIP-329 is intended to extend these benefits to plants applying for subsequent license renewal. It is intended to be an alternative to BWRVIP-05 and BWRVIP-74, BWR Vessel and Internals Project, BWR Reactor Pressure Vessel Inspection and Flaw Evaluation Guidelines for License Renewal." The safety evaluation for BWRVIP-74 covers plant life extension from 40 to 60 years. BWRVIP-329 could be used by plants to extend life from 40 to 60 years but was not intended as a replacement for BWRVIP-05 or BWRVIP-74.
In addition, EPRI explained that there were no plant-specific values in BWRVIP-329. Individual plants would use their own plant-specific information to verify that the conclusions of BWRVIP-329 apply to their plant.
CONTACT: Joseph J. Holonich, NRR/DLP/PLPB 301-415-7297
D. Morey During the discussions, the NRC staff asked if EPRI considered the draft regulatory guidance on probabilistic fracture mechanics (PFM). EPRI responded that the PFM regulatory guidance and EPRI white paper had been considered in developing BWRVIP-329.
In the closed portion of the meeting, EPRI provided details on the information in BWRVIP-329.
During that portion, the NRC staff and EPRI representatives engaged in numerous clarification discussions and questions and answers on the proposed changes. The information discussed was proprietary, so no details of the discussions are provided.
Actions from the closed portion of the meeting were:
- 1) EPRI will review criteria in draft regulatory guidance on PFM to determine if there are clarifications that should be added to BWRVIP-329;
- 2) EPRI will consider if the flaw distribution assumptions used as inputs to the BWRVIP-329 analysis could be further clarified; and
- 3) EPRI will consider if additional explanation of the assumptions regarding shop versus field welds included in BWRVIP-329 would be beneficial.
In closing the meeting, EPRI informed the NRC staff that BWRVIP-329 will be submitted in late 2019. BWRVIP-329 was needed for subsequent license renewal. It was considered a higher priority than BWRVIP-315, Vessel Internals Aging Management Evaluation for Extended Operations, and BWRVIP-316, Reactor Vessel Aging Management Evaluation for Extended Operations.
Docket No. 99902016
ML19094A354 (Package);
ML19094A377 (Summary) *concurrence via e-mail NRC-001 OFFICE NRR/DLP/PLPB/PM* NRR/DMLR/MVIB/BC* NRR/DLP/PLPB/BC NRR/DLP/PLPB/PM NAME JHolonich DAlley DMorey JHolonich DATE 06/18/2019 06/18/2019 06/18/2019 06/19/2019