ML18087A559

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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
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