ML17326A210: Difference between revisions
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| issue date = 01/24/2018 | | issue date = 01/24/2018 | ||
| title = Summary of November 8, 2017, Closed Meeting with the Pressurized Water Reactor Owners Group to Discuss Information Related to the Topical Report PA-MSC-1481, Linde 80 Weld Low Upper-Shelf Toughness Fracture Mechanics Testing and Analysis | | title = Summary of November 8, 2017, Closed Meeting with the Pressurized Water Reactor Owners Group to Discuss Information Related to the Topical Report PA-MSC-1481, Linde 80 Weld Low Upper-Shelf Toughness Fracture Mechanics Testing and Analysis | ||
| 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 = PROJ0694 | | docket = PROJ0694 | ||
| license number = | | license number = | ||
| contact person = Benney B | | contact person = Benney B | ||
| package number = ML17278A062 | | package number = ML17278A062 | ||
| document type = Meeting Summary, Memoranda | | document type = Meeting Summary, Memoranda | ||
Revision as of 16:46, 18 June 2019
| ML17326A210 | |
| Person / Time | |
|---|---|
| Site: | PROJ0694 |
| Issue date: | 01/24/2018 |
| From: | Brian Benney NRC/NRR/DLP/PLPB |
| To: | Dennis Morey NRC/NRR/DLP/PLPB |
| Benney B | |
| Shared Package | |
| ML17278A062 | List: |
| References | |
| Download: ML17326A210 (2) | |
Text
January 24, 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 8, 2017, CLOSED MEETING WITH THE PRESSURIZED WATER REACTOR OWNERS GROUP TO DISCUSS INFORMATION RELATED TO THE TOPICAL REPORT PA-MSC-1481, "LINDE 80 WELD LOW UPPER-SHELF TOUGHNESS FRACTURE MECHANICS TESTING AND ANALYSIS"
On November 8, 2017, a closed meeting was held between the U.S. Nuclear Regulatory
Commission (NRC) staff and the Pressurized Water Reactor Owners Group (PWROG) representatives. The purpose of this meeting was for the PWROG representatives to discuss information related to the topical report (TR) PA-MSC-1481, "Linde 80 Weld Low Upper-Shelf Toughness Fracture Mechanics Testing and Analysis." The NRC staff met with the PWROG representatives to discuss the proposed supplements to BAW-2192PA and BAW-2178PA for
documentation of Time Limited Aging Analysis (TLAA) Equivalent Margins Analysis (EMA) to support 80-years for 3 plants with B&W-fabricated reactor vessels with high copper Linde 80 weld metals.
The industry proposed TR supplements BAW-2192PA and BAW-2178PA for review and acceptance by the NRC. The TR supplements will include the TLAA EMA for 3 specific B&W-fabricated reactor vessels with high copper Linde 80 weld metals for 80-years.
The NRC staff provided some pertinent feedback to the industry on the proposed approach and also expressed concern that a subsequent license renewal application would cite a TR which has not been reviewed.
A list of attendees is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML17326A209. Additional supporting materials may be found in ADAMS at Accession No. ML17349A133.
Project No. 694 CONTACT: Brian J. Benney, NRR/DLP/PLPB (301) 415-2767
Package: ML17278A062; Summary: ML17326A210; Attendees list: ML17326A209; *concurrence via e-mail NRC-001 OFFICE NRR/DLP/PLPB/PM NRR/DE/EMIB* NRR/DLP/PLPB/BC NRR/DLP/PLPB/PM NAME BBenney SRuffin DMorey BBenney DATE 1/17/18 1/22/18 1/22/18 1/24/18