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Category:Letter
MONTHYEARML21264A5332021-09-21021 September 2021
PWR Owners Group - Transmittal of the NRC Approved Version of Topical Report, PWROG-19047-P-A/NP-A, Revision 0, North Anna Units 1 and 2 Reactor Vessels Low Upper-Shelf Fracture Toughness Equivalent Margin Analysis, PA-MSC-1481
ML21180A4162021-06-22022 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)
ML20192A2492020-07-15015 July 2020
Nonprop Final SE Cover Letter for PWROG-17018 LCF 7-10
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)
ML20134M3562020-05-26026 May 2020
Final Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report PWROG-18034-P, Revision 0, Updates to the Methodology for Evaluating the Acceptability of Baffle-Former-Barrel Bolting Distributions Under Faulted Load Condi
ML20133P6932020-05-15015 May 2020
U.S. Nuclear Regulatory Commission Verification Letter for the Pressurized Water Reactor Owners Group Topical Report PWROG-17034, Revision 0, Evaluation of the WCAP-10325-P-A Westinghouse LOCA Mass & Energy Release Methodology
ML20090A0192020-03-30030 March 2020
U.S. Nuclear Regulatory Commission Verification Letter for the Pressurized Water Reactor Owner'S Group Topical Report PWROG-17090-NP, Revision 0, Generic Rotterdam Forging and Weld Initial Upper-Shelf Energy Determination,
ML20085F6032020-03-30030 March 2020
Final Cover Letter Safety Evaluation by the Office of Nuclear Reactor Regulation for the Pressurized Water Reactor Owners Group Topical Report PWROG-17031-NP, Revision 1
ML20028D7142020-02-24024 February 2020
U.S. Nuclear Regulatory Commission Verification Letter for the Pressurized Water Reactor Owners Group Topical Report PWROG-17033, Revision 1
ML19346F8902019-12-19019 December 2019
Cover Letter by the Office of Nuclear Reactor Regulation Topical Report for PWROG-18034-P, Revision 0, Updates to the Methodology in WCAP-15029-P-A, Rev 1, Westinghouse Methodology for Evaluating the Acceptability of Baffle-Former-Barrel Bo
ML19301D0632019-10-31031 October 2019
Cover Letter for the Final Safety Evaluation for the Topical Report PWROG-15109-NP, Revision 0, PWR Pressure Vessel Nozzle Appendix G Evaluation,
ML19300A0012019-10-29029 October 2019
Cover Letter for Draft SE for Topical Report PWROG-17031-NP, Revision 1, Update for Subsequent License Renewal: WCAP-15338-A, a Review of Cracking Associated with Weld Deposited Cladding in Operating PWR Plants
ML19198A0512019-09-11011 September 2019
Final Safety Evaluation for Pressurized Water Reactor Owners Group Topical Report PWROG-17011-NP, Revision 1 Report, Update for Subsequent License Renewal: WCAP-14535A, 'Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination
ML19226A2592019-09-11011 September 2019
Draft Safety Evaluation for Pressurized Water Reactor Owners Group Topical Report PWROG-17090-NP, Revision 0 Generic Rotterdam Forging and Weld Initial Upper-Shelf Energy Determination Pressurized Water Reactor Owners Group Westinghouse Ele
ML19225D1792019-08-23023 August 2019
Verification Letter of the Approval Version of the Pressurized Water Reactor Owners Group Topical Report WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical
ML19158A2662019-06-25025 June 2019
Draft Safety Evaluation by the Office of Nuclear Reactor Regulation for Topical Report PWROG-15109-NP, Revision 0, PWR Pressure Vessel Nozzle Appendix G Evaluation
ML19106A1962019-04-29029 April 2019
Letter - Final Safety Evaluations for Baw 2192, Supplement 1NP, Revision 0, and Baw 2178, Supplement 1NP, Revision 0
ML19073A2162019-03-26026 March 2019
Acceptance for Review of the Pressurized Water Reactor Owners Group Topical Report PWROG-18034-P and PWROG-18034-NP, Revision 0, Updates to the Methodology in WCAP-15029-P-A, Rev. 1
ML19072A1032019-03-19019 March 2019
Cover Letter for Draft Safety Evaluation for Topical Report, PWROG-17011
ML18333A1242018-12-0707 December 2018
Transmittal Letter Regarding Final Safety Evaluation for BAW-2192, Supplement 1, Revision 0, and BAW-2178, Supplement 1, Revision 0
ML18311A2972018-11-30030 November 2018
Staff Re-Evaluation of Closure Path for Generic Safety Issue 191 and Generic Letter 2004-02
ML18236A3782018-09-0505 September 2018
Transmittal Letter Regarding Draft Safety Evaluation for Topical Report BAW-2192, Supplement 1, Revision 0, and Topical Report BAW-2178, Supplement 1, Revision 0
ML18186A6252018-08-22022 August 2018
Transmittal Letter Regarding Draft SE for Pressurized Water Reactor Owners Group Topical Report PWROG-16043-P, Revision 2
ML18191B3032018-07-12012 July 2018
Regulatory Audit Plan for June 26-29, 2018, Audit of Changes to Thermal Hydraulic Methodologies in Responses to Request for Additional Information for Topical Report WCAP-17788-P Comprehensive Analysis and Test Program for GSI-191 Closure
ML18170A1132018-06-14014 June 2018
PWR Owners Group - Transmittal of PWROG-17033-P (&Np), Revision 1, Update for Subsequent License Renewal: WCAP-13045, Compliance to ASME Code Case N-481 of the Primary Loop Pump Casings of Westinghouse Type Nuclear Steam Supply Systems
ML18116A0312018-06-12012 June 2018
Acceptance for Review of the Pressurized Water Reactor Owners Group Topical Report PWROG-17090-NP, Revision 0, Generic Rotterdam Forging and Weld Initial Upper-Shelf Energy Determination
ML18143B4962018-05-15015 May 2018
PWR Owners Group Transmittal of PWROG-17011-NP, Rev 1, Update for Subsequent License Renewal: WCAP-14535A, Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination and WCAP-15666-A, Extension of Reactor Coolant Pump Motor Flyw
ML18116A0292018-05-0909 May 2018
Acceptance for Review of the Pressured Water Reactor Owners Group Topical Report PWROG-17034-P Revision 0, Evaluation of the WCAP-10325-P-A Westinghouse LOCA Mass & Energy Release Methodology
ML18116A0302018-05-0909 May 2018
Acceptance for Review of the Pressurized Water Reactor Owners Group Topical Report PWROG-15109-NP, Revision 0, PWR Pressure Vessel Nozzle Appendix G Evaluation
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.
ML18043A5082018-03-12012 March 2018
Requests for Withholding Information from Public Disclosure the December 11, 2017, Pressurized Water Reactor Owners Group, Submission
ML18043A5652018-03-12012 March 2018
Requests for Withholding Information from Public Disclosure the March 17, 2017, Pressurized Water Reactor Owners Group, Submission
ML18044A0472018-03-0707 March 2018
Requests for Withholding Information from Public Disclosure the February 1, 2018, Pressurized 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
ML18044A2242018-03-0707 March 2018
Requests for Withholding Information from Public Disclosure the December 11, 2017, Pressurize 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
2021-09-21
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Text
OFFICIAL USE ONLY - PROPRIETARY INFORMATION December 7, 2018 Mr. W. Anthony Nowinowski, Executive Director PWR Owners Group, Program Management Office Westinghouse Electric Company 1000 Westinghouse Drive, Suite 380 Cranberry Township, PA 16066
SUBJECT:
FINAL SAFETY EVALUATIONS FOR BAW-2192, SUPPLEMENT 1, REVISION 0, LOW UPPER-SHELF TOUGHNESS FRACTURE MECHANICS ANALYSIS OF REACTOR VESSELS OF B&W OWNERS REACTOR VESSEL WORKING GROUP FOR LEVEL A&B SERVICE LOADS AND BAW-2178, SUPPLEMENT 1, REVISION 0, LOW UPPER-SHELF TOUGHNESS FRACTURE MECHANICS ANALYSIS OF REACTOR VESSELS OF B&W OWNERS REACTOR VESSEL WORKING GROUP FOR LEVEL C&D SERVICE LOADS
Dear Mr. Nowinowski:
By letter dated December 15, 2017, as supplemented by letters dated June 15, 2018 and June 29, 2018, the Pressurized Water Reactor Owners Group (PWROG) submitted BAW-2192, Supplement 1, Revision 0, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Level A&B Service Loads, and BAW-2178, Supplement 1, Revision 0, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Level C&D Service Loads, for review and approval by the U.S. Nuclear Regulatory Commission (NRC).
The NRC staff has completed its review of the subject topical reports (TRs). The staff concludes that BAW-2192, Supplement 1, Revision 0 and BAW-2178, Supplement 1, Revision 0 demonstrate, for the seven plants within the scope of the TRs, that there is adequate margin of safety against ductile fracture in the RPV welds for Service Level A and B loads, and for Service Level C and D loads through 80 calendar years of operation. The staff also concludes that both TRs may be referenced in subsequent license renewal applications for the plants within scope of the report, as a basis for demonstrating that the USE TLAA has been projected in accordance with Title 10 Code of Federal Regulations (CFR) 54.21(c)(1)(ii), for Linde 80 welds in those plants.
Individual licensees wishing to reference either TR as the basis for demonstrating compliance with the 10 CFR 50, Appendix G requirements related to USE must generate 80-year neutron fluence at RPV locations in accordance with NUREG-2192, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants, to demonstrate that the fluence estimates provided in Table 3-1 are applicable to their plants. This is Applicant/licensee Action Item 1.
NOTICE: The enclosure transmitted herewith contains Proprietary Information. When separated from the enclosure, this transmittal document is decontrolled.
OFFICIAL USE ONLY - PROPRIETARY INFORMATION
OFFICIAL USE ONLY - PROPRIETARY INFORMATION W. Nowinowski In accordance with the guidance provided on the NRC website, we request that the PWROG publish approved versions of TRs BAW-2192, Supplement 1, Revision 0 and BAW-2178, Supplement 1, Revision 0, within 3 months of receipt of this letter. The approved versions shall incorporate this letter and the enclosed final safety evaluation (SE) after the title page. Also, they must contain historical review information, including NRC requests for additional information (RAIs) and your responses. The approved versions shall include an -A (designating approved) following the TR identification symbol.
As an alternative to including the request for RAIs and RAI responses behind the title page, if changes to the TR were provided to the NRC staff to support the resolution of RAI responses, and if the NRC staff reviewed and approved those changes as described in the RAI responses, there are two ways that the accepted version can capture the RAIs:
- 1. The RAIs and RAI responses can be included as an Appendix to the accepted version.
- 2. The RAIs and RAI responses can be captured in the form of a table (inserted after the final SE) which summarizes the changes as shown in the approved version of the TR.
The table should reference the specific RAIs and RAI responses which resulted in any changes, as shown in the accepted version of the TR.
If future changes to the NRCs regulatory requirements affect the acceptability of these TRs, PWROG will be expected to revise the TRs appropriately or justify their continued applicability for subsequent referencing. Licensees referencing these TRs would be expected to justify their continued applicability or evaluate their plant using the revised TRs.
If you have any questions, please contact Jason Drake at 301-415-8378.
Sincerely,
/RA/
Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 99902037
Enclosures:
- 1. Safety Evaluation of BAW-2192, Supplement 1, Revision 0
- 2. Safety Evaluation of BAW-2178, Supplement 1, Revision 0 OFFICIAL USE ONLY - PROPRIETARY INFORMATION
PKGML1818332A376 LTR ML18333A124 ML18333A128 ML18333A129 Comment ML18333A131 *concurrence via e-mail NRR-106 OFFICE NRR/DLP/PLPB/PM NRR/DLP/PLPB/LA* NRR/DMLR/MVIB/BC* NRR/DLP/PLPB/BC NAME JDrake (DMorey for) DHarrison DAlley DMorey DATE 12/7/2018 12/3/2018 12/7/2018 12/7/2018