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| number = ML18087A559 | | number = ML18087A559 | ||
| issue date = 04/09/2018 | | issue date = 04/09/2018 | ||
| title = | | title = Summary of Public Meeting with the Pressurized Water Reactor Owners Group to Discuss to Discuss Industry and NRC Efforts Associated with the Scale and Impact of Uncertainty in Fluence Determinations for Reactor Vessel Internals | ||
| author name = Benney B | | author name = Benney B | ||
| author affiliation = NRC/NRR/DLP/PLPB | | author affiliation = NRC/NRR/DLP/PLPB | ||
| Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:April 9, 2018 | {{#Wiki_filter:April 9, 2018 MEMORANDUM TO: Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation FROM: Brian J. Benney, Senior Project Manager /RA/ | ||
Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation | |||
MEMORANDUM TO: Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects | |||
FROM: Brian J. Benney, Senior Project Manager /RA/ | |||
==SUBJECT:== | ==SUBJECT:== | ||
==SUMMARY== | ==SUMMARY== | ||
OF NOVEMBER 29, 2017, PUBLIC MEETING WITH THE PRESSURIZED WATER REACTOR OWNERS GROUP TO DISCUSS TO DISCUSS INDUSTRY AND NRC EFFORTS ASSOCIATED WITH THE | OF NOVEMBER 29, 2017, PUBLIC MEETING WITH THE PRESSURIZED WATER REACTOR OWNERS GROUP TO DISCUSS TO DISCUSS INDUSTRY AND NRC EFFORTS ASSOCIATED WITH THE SCALE AND IMPACT OF UNCERTAINTY IN FLUENCE DETERMINATIONS FOR REACTOR VESSEL INTERNALS On November 29, 2017, a public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) staff and the Pressurized Water Reactor (PWR) Owners Group (PWROG) representatives. The purpose of this meeting was for the PWROG representatives to discuss industry and NRC efforts associated with the Scale and Impact of Uncertainty in Fluence Determinations for Reactor Vessel Internals. | ||
The PWROG representatives met with the NRC staff to discuss and obtain feedback on the PWROG Project to Determine the Scale and Impact of the Uncertainty in Fluence Determinations for Reactor Vessel Internals to Support Subsequent License Renewal (PWROG-17050-NP). The projects goals include, identifying the factors contributing to the uncertainty in the calculation of the fluence for the reactor vessel internals (RVIs), and determining the impact of the RVI fluence calculation uncertainty on the individual MRP-227 component categorization for defining actions needed to manage material aging in the RVIs. | |||
On November 29, 2017, a public meeting was held between the U.S. Nuclear Regulatory | Westinghouse discussed contributors to the reactor pressure vessel (RPV) fluence uncertainty and parameters for the RPV fluence calculation uncertainty. | ||
The NRC staff thanked the PWROG for the presentation and provided pertinent feedback to the industry. The NRC staff looks forward to receiving the topical report. | |||
Commission (NRC) staff and the Pressurized Water Reactor (PWR) Owners Group (PWROG) representatives. The purpose of this meeting was for the PWROG representatives to discuss industry and NRC efforts associated with the | A list of attendees is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML18093A120. Additional supporting materials may be found in ADAMS at Accession No. ML18087A532. | ||
Docket No. 99902037 CONTACT: Brian J. Benney, NRR/DLP/PLPB (301) 415-2767 | |||
The PWROG representatives met with the NRC staff to discuss and obtain feedback on the PWROG Project to Determine the Scale and Impact of the Uncertainty in Fluence Determinations for Reactor Vessel Internals to Support Subsequent License Renewal (PWROG-17050-NP). The | |||
determining the impact of the RVI fluence calculation uncertainty on the individual MRP-227 component categorization for defining actions needed to manage material aging in the RVIs. Westinghouse discussed contributors to the reactor pressure vessel (RPV) fluence uncertainty and parameters for the RPV fluence calculation uncertainty. | |||
The NRC staff thanked the PWROG for the | |||
A list of attendees is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML18093A120. Additional supporting materials may be found in ADAMS at Accession No. ML18087A532. | |||
Docket No. 99902037 | |||
CONTACT: Brian J. Benney, NRR/DLP/PLPB (301) 415-2767 | |||
Package: | Package: ML18087A507; Summary: ML18087A559; | ||
*concurrence via e-mail NRC-001 OFFICE NRR/DLP/PLPB/PM NRR/DE/SRXB* NRR/DLP/PLPB/BC NRR/DLP/PLPB/PM BBenney (RLukes for) | |||
NAME JWhitman DMorey BBenney DATE 4/9/18 4/9/18 4/9/18 4/9/18}} | |||
Latest revision as of 18:05, 30 November 2019
| ML18087A559 | |
| Person / Time | |
|---|---|
| Site: | 99902037 |
| Issue date: | 04/09/2018 |
| From: | Brian Benney NRC/NRR/DLP/PLPB |
| To: | Dennis Morey NRC/NRR/DLP/PLPB |
| Benney B | |
| Shared Package | |
| ML18087A507 | List: |
| References | |
| WAAP-10693 | |
| Download: ML18087A559 (2) | |
Text
April 9, 2018 MEMORANDUM TO: Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation FROM: Brian J. Benney, Senior Project Manager /RA/
Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF NOVEMBER 29, 2017, PUBLIC MEETING WITH THE PRESSURIZED WATER REACTOR OWNERS GROUP TO DISCUSS TO DISCUSS INDUSTRY AND NRC EFFORTS ASSOCIATED WITH THE SCALE AND IMPACT OF UNCERTAINTY IN FLUENCE DETERMINATIONS FOR REACTOR VESSEL INTERNALS On November 29, 2017, a public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) staff and the Pressurized Water Reactor (PWR) Owners Group (PWROG) representatives. The purpose of this meeting was for the PWROG representatives to discuss industry and NRC efforts associated with the Scale and Impact of Uncertainty in Fluence Determinations for Reactor Vessel Internals.
The PWROG representatives met with the NRC staff to discuss and obtain feedback on the PWROG Project to Determine the Scale and Impact of the Uncertainty in Fluence Determinations for Reactor Vessel Internals to Support Subsequent License Renewal (PWROG-17050-NP). The projects goals include, identifying the factors contributing to the uncertainty in the calculation of the fluence for the reactor vessel internals (RVIs), and determining the impact of the RVI fluence calculation uncertainty on the individual MRP-227 component categorization for defining actions needed to manage material aging in the RVIs.
Westinghouse discussed contributors to the reactor pressure vessel (RPV) fluence uncertainty and parameters for the RPV fluence calculation uncertainty.
The NRC staff thanked the PWROG for the presentation and provided pertinent feedback to the industry. The NRC staff looks forward to receiving the topical report.
A list of attendees is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML18093A120. Additional supporting materials may be found in ADAMS at Accession No. ML18087A532.
Docket No. 99902037 CONTACT: Brian J. Benney, NRR/DLP/PLPB (301) 415-2767
Package: ML18087A507; Summary: ML18087A559;
- concurrence via e-mail NRC-001 OFFICE NRR/DLP/PLPB/PM NRR/DE/SRXB* NRR/DLP/PLPB/BC NRR/DLP/PLPB/PM BBenney (RLukes for)
NAME JWhitman DMorey BBenney DATE 4/9/18 4/9/18 4/9/18 4/9/18