ML17326A210: Difference between revisions

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{{#Wiki_filter:January 24, 2018  
{{#Wiki_filter: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
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:==
==SUBJECT:==


==SUMMARY==
==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"
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.
On November 8, 2017, a closed meeting was held between the U.S. Nuclear Regulatory  
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.
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  
Project No. 694 CONTACT: Brian J. Benney, NRR/DLP/PLPB (301) 415-2767
 
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}}
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}}

Latest revision as of 06:31, 29 October 2019

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
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