|
|---|
Category:Letter
MONTHYEARML21180A4162021-06-22022 June 2021
PWR Owners Group, Comments on the NRC Draft Safety Evaluation for PWROG-19047-P/NP, Revision 0, North Anna Units 1 and 2 Reactor Vessels Low Upper-Shelf Fracture Toughness Equivalent Margin Analysis (PA-MSC-1481)
ML20149K6682020-05-27027 May 2020
PWR Owners Group, Submittal of PWROG-19047-P/NP, Revision 0, North Anna, Units 1 and 2, Reactor Vessels Low Upper-Shelf Fracture Toughness, Equivalent Margin Analysis (PA-MSC-1481)
ML18192B6172019-10-0909 October 2019
Verification Letter of the Approval Versions of the Pressured Water Reactor Owners Group Topical Report BAW-1543, Revision 4, Supplement 7-A Supplement to the Master Integrated Reactor Vessel Surveillances Program
ML19106A1962019-04-29029 April 2019
Letter - Final Safety Evaluations for Baw 2192, Supplement 1NP, Revision 0, and Baw 2178, Supplement 1NP, Revision 0
ML18081A0072018-04-24024 April 2018
Letter for Draft Safety Evaluation for Pressurized Water Reactor Owners Group Topical Report WCAP-17661, Improved RAOC and CAOC Fq Surveillance Technical Specifications
ML18038A3472018-03-27027 March 2018
Transmittal Letter for Final Safety Evaluation for Pressurized Water Reactor Owners Group Topical Report BAW-1543, Revision 4, Supplement 7
ML18057A0802018-03-13013 March 2018
Acceptance for Review of the Pressurized Water Reactor Owners Group Topical Report PWROG-17018-PINP, Solid State Protection System General Warning Alarm Modification.
ML18043A5652018-03-12012 March 2018
Requests for Withholding Information from Public Disclosure the March 17, 2017, Pressurized Water Reactor Owners Group, Submission
ML18043A5082018-03-12012 March 2018
Requests for Withholding Information from Public Disclosure the December 11, 2017, Pressurized Water Reactor Owners Group, Submission
ML18044A2242018-03-0707 March 2018
Requests for Withholding Information from Public Disclosure the December 11, 2017, Pressurize Water Reactor Owners Group (Pwrog), Submission
ML18044A0652018-03-0707 March 2018
Requests for Withholding Information from Public Disclosure the October 19, 2017, Pressurized Water Reactor Owners Group (Pwrog), Submission
ML18044A0472018-03-0707 March 2018
Requests for Withholding Information from Public Disclosure the February 1, 2018, Pressurized Water Reactor Owners Group (Pwrog), Submission
ML18044A3282018-03-0707 March 2018
Requests for Withholding Information from Public Disclosure the January 2, 2014, Pressurized Water Reactor Owners Group (Pwrog), Submission
ML18053A1542018-03-0606 March 2018
Acceptance for Review of the Pressurized Water Reactor Owners Group Topical Report BAW-2192-P, Supplement 1, Revision 0, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for
ML18053A1492018-03-0606 March 2018
Acceptance for Review of the Pressurized Water Reactor Owners Group Topical Report BAW-2178-P, Supplement 1, Revision 0, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessel of B&W Owners Reactor Vessel Working Group for
ML18022A1372018-02-0606 February 2018
Verification Letter of the Approval Version of the Pressurized Water Reactor Owners Group Topical Report PWROG-14001-P, Revision 1, PRA Model for the Generation III Westinghouse Shutdown Seal
ML18029A2032017-12-19019 December 2017
PWR Owners Group - Submittal of Responses to NRC Requests for Additional Information and Revisions to Topical Report WCAP-17788-P/WCAP-17788-NP, Revision 0, Comprehensive Analysis and Test Program for GS1-191 Closure Related to Volumes 1 an
ML0715502252007-05-25025 May 2007
PWR Owners Group - Draft Revisions to Topical Report WCAP-15791 Revision 1, Risk-Informed Evaluation of Extensions to Containment Isolation Valve Completion Times, and the Final Safety Evaluation, MUHP-3010/LSC-0029/LSC-0135
ML0430001552004-10-20020 October 2004
Westinghouse Owners Group - Comparison of Crossflow and ASME Flow Section Feedwater Flow Measurement at Kewaunee Nuclear Power Plant
ML0423902142004-08-20020 August 2004
Westinghouse Owners Group Request to Withdraw WCAP-16168-NP, Risk-Informed Extension of Reactor Vessel In-Service Inspection Interval, (PA-MSC-0120)
ML0404803092004-01-30030 January 2004
WOG CE Fleet Pressurizer Heater Sleeve Inspection Program. Includes Attachment 1 - Scheduled Refueling Outages for Plants in the CE Fleet
ML0332302252003-11-12012 November 2003
Submittal of WCAP-16084-NP, Development of Risk-Informed Safety Analysis Approach and Pilot Application.
ML0307705042003-03-12012 March 2003
Request for Review of TSTF-421, Rev. 0 (MUHP-3043)
ML0233805362002-11-27027 November 2002
Transmittal of RAI Responses for WCAP-15622, Risk-Informed Evaluation of Extensions to AC Electrical Power System Completion Times (MUHP-3010)
ML0233304572002-11-27027 November 2002
Transmittal of RAI Responses for WCAP-15622, Risk-Informed Evaluation of Extensions to AC Electrical Power System Completion Times. (MUHP-3010)
2021-06-22
[Table view] |
Text
October 9, 2019 Mr. W. Anthony Nowinowski, Program Manager PWR Owners Group, Program Management Office Westinghouse Electric Company 1000 Westinghouse Drive Cranberry Township, PA 16066
SUBJECT:
VERIFICATION LETTER OF THE APPROVAL VERSION OF THE PRESSURIZED WATER REACTOR OWNERS GROUP TOPICAL REPORT BAW-1543, REVISION 4, SUPPLEMENT 7-A, SUPPLEMENT TO THE MASTER INTEGRATED REACTOR VESSEL SURVEILLANCE PROGRAM
Dear Mr. Nowinowski:
By letter dated June 29, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18184A519), Pressurized Water Reactor Owners Group (PWROG) submitted an approval (-A) version of Topical Report (TR) BAW-1543, Revision 4, Supplement 7-A, Supplement to the Master Integrated Reactor Vessel Surveillance Program, to the U.S. Nuclear Regulatory Commission (NRC) staff. PWROG has done so in accordance with our request to publish an approval version of this TR, as detailed in the transmittal letter of the NRC staffs final safety evaluation (ADAMS Accession No. ML18038A347) for the original TR.
The NRC staff has completed its review of the approval version of the TR. The NRC staff verified that Westinghouse has met the requirements and determined that the submitted -A version is acceptable for referencing in licensing applications for nuclear power plants to the extent specified, and under the limitations delineated in the accepted version of the TR.
BAW-1543, Revision 4, Supplement 7-A, is now acceptable for use in future licensing actions.
Please contact Leslie Fields of my staff at (301) 415-1186 if you have any questions on this subject.
Sincerely,
/RA/
Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Project No. 694
ML18192B617 *concurred via e-mail NRR-106 OFFICE NRR/DLP/PLPB/PM NRR/DLP/PLPB/LA* NRR/DMLR/MVIB/BC* NRR/DLP/PLPB/BC*
NAME LFields DHarrison DAlley DMorey DATE 10/09/19 7/24/18 10/10/19 10/09/19