ML18087A559: Difference between revisions
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| issue date = 04/09/2018 | | issue date = 04/09/2018 | ||
| title = 11/29/2017 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 | | title = 11/29/2017 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 | ||
| addressee name = Morey D | | addressee name = Morey D | ||
| addressee affiliation = NRC/NRR/DLP/PLPB | | addressee affiliation = NRC/NRR/DLP/PLPB | ||
| docket = 99902037 | | docket = 99902037 | ||
| license number = | | license number = | ||
| contact person = Benney B | | contact person = Benney B | ||
| case reference number = WAAP-10693 | | case reference number = WAAP-10693 | ||
| package number = ML18087A507 | | package number = ML18087A507 |
Revision as of 16:12, 17 June 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 project's 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 presentat ion 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 NAME BBenney (RLukes for) JWhitman DMorey BBenney DATE 4/9/18 4/9/18 4/9/18 4/9/18