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| | issue date = 03/06/2018 | | | issue date = 03/06/2018 |
| | title = 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 | | | title = 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 |
| | author name = Morey D C | | | author name = Morey D |
| | author affiliation = NRC/NRR/DLP/PLPB | | | author affiliation = NRC/NRR/DLP/PLPB |
| | addressee name = Nowinowski W A | | | addressee name = Nowinowski W |
| | addressee affiliation = Westinghouse Electric Co | | | addressee affiliation = Westinghouse Electric Co |
| | docket = 99902037, PROJ0694 | | | docket = 99902037, PROJ0694 |
| | license number = | | | license number = |
| | contact person = Benney B J | | | contact person = Benney B |
| | document report number = BAW-2178-P | | | document report number = BAW-2178-P |
| | document type = Letter | | | document type = Letter |
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| =Text= | | =Text= |
| {{#Wiki_filter:March 6, 2018 | | {{#Wiki_filter:March 6, 2018 Mr. W. Anthony Nowinowski, Program Manager PWR Owners Group, Program Management Office Westinghouse Electric Company 1000 Westinghouse Drive, Suite 380 Cranberry Township, PA 16066 |
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| Mr. W. Anthony Nowinowski, Program Manager PWR Owners Group, Program Management Office Westinghouse Electric Company 1000 Westinghouse Drive, Suite 380 Cranberry Township, PA 16066 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| 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 VESSELS OF B&W OWNERS REACTOR VESSEL WORKING GROUP FOR LEVELS C & D SERVICE LOADS | | 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 VESSELS OF B&W OWNERS REACTOR VESSEL WORKING GROUP FOR LEVELS C & D SERVICE LOADS |
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| ==Dear Mr. Nowinowski:== | | ==Dear Mr. Nowinowski:== |
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| By letter dated December 15, 2017 (Agencywide Documents Access and Management System Accession No. ML17354A011), the Pressurized Water Reactor Owners Group (PWROG) submitted Topical Report (TR) BAW-2178-P, Supplement 1, Revision 0, "Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Levels C & D Service Loads," to the U.S. Nuclear Regulatory Commission (NRC) staff for review. | | By letter dated December 15, 2017 (Agencywide Documents Access and Management System Accession No. ML17354A011), the Pressurized Water Reactor Owners Group (PWROG) submitted Topical Report (TR) BAW-2178-P, Supplement 1, Revision 0, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Levels C & D Service Loads, to the U.S. Nuclear Regulatory Commission (NRC) staff for review. |
| | | The NRC staff has found that the material presented is sufficient to begin our review. The NRC staff expects to issue its request for additional information by June 1, 2018, and issue its draft safety evaluation (SE) in August 2018. This schedule information takes in consideration the NRCs current review priorities and available technical resources and may be subject to change. |
| The NRC staff has found that the material presented is sufficient to begin our review. The NRC staff expects to issue its request for additional information by June 1, 2018, and issue its draft safety evaluation (SE) in August 2018. This schedule information takes in consideration the NRC's current review priorities and available technical resources and may be subject to change. If modifications to these dates are deemed necessary, we will provide appropriate updates to this information. Section 170.21 of Title 10 of the Code of Federal Regulations requires that TRs are subject to fees based on the full cost of the review. | | If modifications to these dates are deemed necessary, we will provide appropriate updates to this information. Section 170.21 of Title 10 of the Code of Federal Regulations requires that TRs are subject to fees based on the full cost of the review. |
| | | As with all TRs, the SE will be reviewed by the NRCs Office of the General Counsel (OGC) to determine whether it falls within the scope of the Congressional Review Act (CRA). During the course of this review, OGC considers whether any endorsement or acceptance of a TR by the NRC amounts to a rule as defined in the CRA. If this initial review concludes that the SE, with its accompanying TR, may be a rule, the NRC will forward the package to the Office of Management and Budget (OMB) for further review and consideration. Any review by OMB would impact the schedule for the issuance of the final SE. |
| As with all TRs, the SE will be reviewed by the NRC's Office of the General Counsel (OGC) to determine whether it falls within the scope of the Congressional Review Act (CRA). During the course of this review, OGC considers whether any endorsement or acceptance of a TR by the NRC amounts to a rule as defined in the CRA. If this initial review concludes that the SE, with its accompanying TR, may be a rule, the NRC will forward the package to the Office of Management and Budget (OMB) for further review and consideration. Any review by OMB would impact the schedule for the issuance of the final SE. | |
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| W. If you have questions regarding this matter, please contact Brian Benney at (301) 415-2767. | | W. A. Nowinowski If you have questions regarding this matter, please contact Brian Benney at (301) 415-2767. |
| Sincerely, /RA/ Dennis Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 99902037 | | Sincerely, |
| | /RA/ |
| | Dennis Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 99902037 |
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| ML18053A149; *concurred via e-mail NRR-106 OFFICE NRR/DLP/PLPB/PM NRR/DLP/PLPB/LA* NRR/DE/EMIB/BC* NAME BBenney DHarrison SRuffin DATE 3/5/18 2/27/18 2/26/18 OFFICE NRR/DLP/PLPB/BC NAME DMorey DATE 3/6/18}} | | ML18053A149; *concurred via e-mail NRR-106 OFFICE NRR/DLP/PLPB/PM NRR/DLP/PLPB/LA* NRR/DE/EMIB/BC* |
| | NAME BBenney DHarrison SRuffin DATE 3/5/18 2/27/18 2/26/18 OFFICE NRR/DLP/PLPB/BC NAME DMorey DATE 3/6/18}} |
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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 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 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 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 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 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 ML18044A3282018-03-0707 March 2018 Requests for Withholding Information from Public Disclosure the January 2, 2014, 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 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 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) 2021-09-21
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March 6, 2018 Mr. W. Anthony Nowinowski, Program Manager PWR Owners Group, Program Management Office Westinghouse Electric Company 1000 Westinghouse Drive, Suite 380 Cranberry Township, PA 16066
SUBJECT:
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 VESSELS OF B&W OWNERS REACTOR VESSEL WORKING GROUP FOR LEVELS C & D SERVICE LOADS
Dear Mr. Nowinowski:
By letter dated December 15, 2017 (Agencywide Documents Access and Management System Accession No. ML17354A011), the Pressurized Water Reactor Owners Group (PWROG) submitted Topical Report (TR) BAW-2178-P, Supplement 1, Revision 0, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Levels C & D Service Loads, to the U.S. Nuclear Regulatory Commission (NRC) staff for review.
The NRC staff has found that the material presented is sufficient to begin our review. The NRC staff expects to issue its request for additional information by June 1, 2018, and issue its draft safety evaluation (SE) in August 2018. This schedule information takes in consideration the NRCs current review priorities and available technical resources and may be subject to change.
If modifications to these dates are deemed necessary, we will provide appropriate updates to this information. Section 170.21 of Title 10 of the Code of Federal Regulations requires that TRs are subject to fees based on the full cost of the review.
As with all TRs, the SE will be reviewed by the NRCs Office of the General Counsel (OGC) to determine whether it falls within the scope of the Congressional Review Act (CRA). During the course of this review, OGC considers whether any endorsement or acceptance of a TR by the NRC amounts to a rule as defined in the CRA. If this initial review concludes that the SE, with its accompanying TR, may be a rule, the NRC will forward the package to the Office of Management and Budget (OMB) for further review and consideration. Any review by OMB would impact the schedule for the issuance of the final SE.
W. A. Nowinowski If you have questions regarding this matter, please contact Brian Benney at (301) 415-2767.
Sincerely,
/RA/
Dennis Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 99902037
ML18053A149; *concurred via e-mail NRR-106 OFFICE NRR/DLP/PLPB/PM NRR/DLP/PLPB/LA* NRR/DE/EMIB/BC*
NAME BBenney DHarrison SRuffin DATE 3/5/18 2/27/18 2/26/18 OFFICE NRR/DLP/PLPB/BC NAME DMorey DATE 3/6/18