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| | issue date = 10/23/2015 | | | issue date = 10/23/2015 |
| | title = LTR-15-0480 - Response to the Advisory Committee on Reactor Safeguards Reports on the Safety Aspects of the License Renewal Application for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 | | | title = LTR-15-0480 - Response to the Advisory Committee on Reactor Safeguards Reports on the Safety Aspects of the License Renewal Application for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 |
| | author name = McCree V M | | | author name = Mccree V |
| | author affiliation = NRC/EDO | | | author affiliation = NRC/EDO |
| | addressee name = Stetkar J W | | | addressee name = Stetkar J |
| | addressee affiliation = NRC/ACRS | | | addressee affiliation = NRC/ACRS |
| | docket = 05000454, 05000455, 05000456, 05000457 | | | docket = 05000454, 05000455, 05000456, 05000457 |
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| | page count = 4 | | | page count = 4 |
| | project = | | | project = |
| | stage = RAI | | | stage = Other |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 23, 2015 John W. Stetkar, Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 23, 2015 John W. Stetkar, Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| RESPONSE TO THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS REPORT ON THE SAFETY ASPECTS OF THE LICENSE RENEWAL APPLICATION FOR BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 | | RESPONSE TO THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS REPORT ON THE SAFETY ASPECTS OF THE LICENSE RENEWAL APPLICATION FOR BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 |
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| ==Dear Mr. Stetkar:== | | ==Dear Mr. Stetkar:== |
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| During the 627th meeting of the Advisory Committee on Reactor Safeguards (the Committee) held on September 9-12, 2015, the Committee completed its review of the combined license renewal application for the Byron and Braidwood stations. The Committee also reviewed the U.S. Nuclear Regulatory Commission (NRC) staff's associated final safety evaluation report (SER) for this application. | | During the 627th meeting of the Advisory Committee on Reactor Safeguards (the Committee) held on September 9-12, 2015, the Committee completed its review of the combined license renewal application for the Byron and Braidwood stations. The Committee also reviewed the U.S. Nuclear Regulatory Commission (NRC) staffs associated final safety evaluation report (SER) for this application. |
| | In the Committees final report, dated September 21, 2015, the Committee recommends the NRC renew the operating licenses for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2. The NRC staff appreciates the Committees objective and in-depth review of the license renewal application and the staffs final SER. The NRC staff acknowledged the Committees insights regarding the resolution of the following open items as documented in the final SER: |
| | * Ensuring there is adequate aging management through nondestructive testing of reactor vessel head control rod drive mechanism nozzles at the locations of wear near the J-groove welds caused by the thermal sleeve centering tabs; and |
| | * Ensuring appropriate leading candidates and representative materials are included in the evaluation for environmentally assisted fatigue cumulative usage factors for reactor coolant pressure boundary systems and components. |
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| In the Committee's final report, dated September 21, 2015, the Committee recommends the NRC renew the operating licenses for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2. The NRC staff appreciates the Committee's objective and in-depth review of the license renewal application and the staff's final SER. The NRC staff acknowledged the Committee's insights regarding the resolution of the following open items as documented in the final SER:
| | J. Stetkar The NRC staff recognizes the Committees commitment to safety and appreciates its continued support of the license renewal process. |
| * Ensuring there is adequate aging management through nondestructive testing of reactor vessel head control rod drive mechanism nozzles at the locations of wear near the J-groove welds caused by the thermal sleeve centering tabs; and
| | Sincerely, |
| * Ensuring appropriate leading candidates and representative materials are included in the evaluation for environmentally assisted fatigue cumulative usage factors for reactor coolant pressure boundary systems and components.
| | /RA Michael R. Johnson Acting for/ |
| | Victor M. McCree Executive Director for Operations cc: Chairman Burns Commissioner Svinicki Commissioner Ostendorff Commissioner Baran SECY |
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| The NRC staff recognizes the Committee's commitment to safety and appreciates its continued support of the license renewal process. Sincerely,
| | ML15267A775 (Package) ML15264A955 (Incoming) ML15274A038 (Letter) |
| /RA Michael R. Johnson Acting for/ Victor M. McCree Executive Director for Operations cc: Chairman Burns Commissioner Svinicki Commissioner Ostendorff Commissioner Baran SECY
| | OFFICE LA:RPB1:DLR* PM:RPB1:DLR* Tech Editor* OGC NAME YEdmonds JDaily JDougherty MYoung (NLO) |
| | DATE 10/01/15 10/01/15 10/01/15 10/06/15 OFFICE BC:RPB1:DLR D:DLR:NRR D:NRR EDO WDean VMcCree NAME YDiaz-Sanabria CMiller (MEvans for) (MJohnson for) |
| | DATE 10/02/15 10/07/15 10/15/15 10/ 23 /15 |
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| ML15267A775 (Package) ML15264A955 (Incoming) ML15274A038 (Letter) OFFICE LA:RPB1:DLR* PM:RPB1:DLR* Tech Editor* OGC NAME YEdmonds JDaily JDougherty MYoung (NLO) DATE 10/01/15 10/01/15 10/01/15 10/06/15 OFFICE BC:RPB1:DLR D:DLR:NRR D:NRR EDO NAME YDiaz-Sanabria CMiller WDean (MEvans for) VMcCree (MJohnson for) DATE 10/02/15 10/07/1510/15/1510/ 23 /15 Letter to J. Stetkar from V. McCree dated October 23, 2015
| | Letter to J. Stetkar from V. McCree dated October 23, 2015 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| RESPONSE TO THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS REPORT ON THE SAFETY ASPECTS OF THE LICENSE RENEWAL APPLICATION FOR BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 DISTRIBUTION : LTR-15-0480 PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRsrg Resource RidsNrrDeEvib Resource RidsNrrDeEpnb Resource RidsNrrDeEsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource RidsEdoMailCenter Resource RidsNrrMailCenter Resource RidsNrrOd Resource RidsRgn3MailCenter Resource RidsAcrsAcnw_MailCTR | | RESPONSE TO THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS REPORT ON THE SAFETY ASPECTS OF THE LICENSE RENEWAL APPLICATION FOR BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 DISTRIBUTION : LTR-15-0480 PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRsrg Resource RidsNrrDeEvib Resource RidsNrrDeEpnb Resource RidsNrrDeEsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource RidsEdoMailCenter Resource RidsNrrMailCenter Resource RidsNrrOd Resource RidsRgn3MailCenter Resource RidsAcrsAcnw_MailCTR |
| ------------------------------------- | | ------------------------------------- |
| JDaily RBaum LJames DMcIntyre, OPA JWiebe, DORL EDuncan, RIII SSheldon RIII AStone RIII ABarker RIII JMcGhee, Byron Station, RIII JDraper, Byron Station, RIII VMitlyng, RIII PChandrathil, RIII}} | | JDaily RBaum LJames DMcIntyre, OPA JWiebe, DORL EDuncan, RIII SSheldon RIII AStone RIII ABarker RIII JMcGhee, Byron Station, RIII JDraper, Byron Station, RIII VMitlyng, RIII PChandrathil, RIII}} |
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Category:Letter
MONTHYEARML24250A1182024-09-0606 September 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) IR 05000454/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Byron Station, Units 1 and 2 (Report 05000455/2024005 and 05000454/2024005) ML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, “Revise Risk Informed Completion Time (RICT) Program” Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000454/20240112024-08-0808 August 2024 Phase 2 Post- Approval License Renewal Report 05000454/2024011 IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 ML24172A1252024-07-26026 July 2024 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter IR 05000454/20240022024-07-26026 July 2024 Integrated Inspection Report 05000454/2024002 and 05000455/2024002, and Exercise of Enforcement Discretion ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) 05000456/LER-2024-001, Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open2024-07-0303 July 2024 Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions RS-24-066, Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller2024-06-25025 June 2024 Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter ML24170A7652024-06-19019 June 2024 Confirmation of Initial License Examination RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report BYRON 2024-0031, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-05-16016 May 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation ML24136A0132024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 IR 05000454/20240012024-05-10010 May 2024 Integrated Inspection Report 05000454/2024001; 05000455/2024001 and 07200068/2024001 BYRON 2024-0028, Annual Radiological Environmental Operating Report (AREOR)2024-05-0909 May 2024 Annual Radiological Environmental Operating Report (AREOR) ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) BYRON 2024-0022, 2023 Regulatory Commitment Change Summary Report2024-05-0202 May 2024 2023 Regulatory Commitment Change Summary Report ML24122A6522024-05-0101 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests IR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML24116A1192024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) IR 05000456/20240012024-04-24024 April 2024 Integrated Inspection Report 05000456/2024001 and 05000457/2024001 ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) ML24113A2892024-04-22022 April 2024 Notification of NRC Baseline Inspection and Request for Information IR 05000457/20240902024-04-19019 April 2024 Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090 BYRON 2024-0020, Annual Dose Report for 20232024-04-18018 April 2024 Annual Dose Report for 2023 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition BYRON 2024-0021, Registration of Use of Cask to Store Spent Fuel2024-04-11011 April 2024 Registration of Use of Cask to Store Spent Fuel RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors IR 05000454/20244012024-04-0303 April 2024 Cyber Security Inspection Report 05000454/2024401 and 05000455/2024401 (Public) ML24094A2692024-04-0303 April 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report, WCAP-17451-P, Revision 2, Reactor Internals Guide Tube Wear Westinghouse Domestic Fleet Operational Projections RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report BYRON 2024-0019, Registration of Use of Cask to Store Spent Fuel2024-03-28028 March 2024 Registration of Use of Cask to Store Spent Fuel ML24057A0372024-03-26026 March 2024 Proposed Alternative from Certain Requirements Contained in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI 2024-09-06
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 23, 2015 John W. Stetkar, Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
RESPONSE TO THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS REPORT ON THE SAFETY ASPECTS OF THE LICENSE RENEWAL APPLICATION FOR BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2
Dear Mr. Stetkar:
During the 627th meeting of the Advisory Committee on Reactor Safeguards (the Committee) held on September 9-12, 2015, the Committee completed its review of the combined license renewal application for the Byron and Braidwood stations. The Committee also reviewed the U.S. Nuclear Regulatory Commission (NRC) staffs associated final safety evaluation report (SER) for this application.
In the Committees final report, dated September 21, 2015, the Committee recommends the NRC renew the operating licenses for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2. The NRC staff appreciates the Committees objective and in-depth review of the license renewal application and the staffs final SER. The NRC staff acknowledged the Committees insights regarding the resolution of the following open items as documented in the final SER:
- Ensuring there is adequate aging management through nondestructive testing of reactor vessel head control rod drive mechanism nozzles at the locations of wear near the J-groove welds caused by the thermal sleeve centering tabs; and
- Ensuring appropriate leading candidates and representative materials are included in the evaluation for environmentally assisted fatigue cumulative usage factors for reactor coolant pressure boundary systems and components.
J. Stetkar The NRC staff recognizes the Committees commitment to safety and appreciates its continued support of the license renewal process.
Sincerely,
/RA Michael R. Johnson Acting for/
Victor M. McCree Executive Director for Operations cc: Chairman Burns Commissioner Svinicki Commissioner Ostendorff Commissioner Baran SECY
ML15267A775 (Package) ML15264A955 (Incoming) ML15274A038 (Letter)
OFFICE LA:RPB1:DLR* PM:RPB1:DLR* Tech Editor* OGC NAME YEdmonds JDaily JDougherty MYoung (NLO)
DATE 10/01/15 10/01/15 10/01/15 10/06/15 OFFICE BC:RPB1:DLR D:DLR:NRR D:NRR EDO WDean VMcCree NAME YDiaz-Sanabria CMiller (MEvans for) (MJohnson for)
DATE 10/02/15 10/07/15 10/15/15 10/ 23 /15
Letter to J. Stetkar from V. McCree dated October 23, 2015
SUBJECT:
RESPONSE TO THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS REPORT ON THE SAFETY ASPECTS OF THE LICENSE RENEWAL APPLICATION FOR BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 DISTRIBUTION : LTR-15-0480 PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRsrg Resource RidsNrrDeEvib Resource RidsNrrDeEpnb Resource RidsNrrDeEsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource RidsEdoMailCenter Resource RidsNrrMailCenter Resource RidsNrrOd Resource RidsRgn3MailCenter Resource RidsAcrsAcnw_MailCTR
JDaily RBaum LJames DMcIntyre, OPA JWiebe, DORL EDuncan, RIII SSheldon RIII AStone RIII ABarker RIII JMcGhee, Byron Station, RIII JDraper, Byron Station, RIII VMitlyng, RIII PChandrathil, RIII