|
---|
Category:Letter type:RS
MONTHYEARRS-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 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 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 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 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary 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 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) 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 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 RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-038, Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly2023-02-27027 February 2023 Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023 Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-118, Withdrawal of License Amendment Request to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-10-31031 October 2022 Withdrawal of License Amendment Request to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-110, Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request.2022-09-20020 September 2022 Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request. RS-22-097, License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly2022-08-31031 August 2022 License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022 Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . RS-22-072, Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0606 June 2022 Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-075, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0202 June 2022 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022 Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . RS-22-073, Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube.2022-05-19019 May 2022 Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube. RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-22-057, Constellation Radiological Emergency Plan Addendum Revision2022-04-21021 April 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists 2024-06-04
[Table view] Category:Technical Specifications
MONTHYEARRS-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 ML23122A3022023-07-20020 July 2023 Issuance of Amendments Technical Specifications 2.1.1 and 4.2.1 to Allow a Previously Irradiated Accident Tolerant Fuel Lead Test Assembly to Be Further Irradiated in Unit No. 2 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21154A0462021-07-13013 July 2021 Issuance of Amendments Nos. 222 and 222 Revision of Technical Specifications for the Ultimate Heat Sink ML21060B2812021-04-0202 April 2021 Issuance of Amendments Nos. 221, 221, 224, and 224 Regarding Technical Specifications 3.8.1, AC Sources-Operating ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20317A0012020-12-28028 December 2020 Non-Proprietary, Issuance of Amendment Nos. 219, 219, 223, and 223, Revise Loss-of-Coolant Accident Methodology in TS 5.6.5, Core Operating Limits Report (COLR) ML21008A4052020-12-17017 December 2020 Byron/Braidwood Stations - Revision 18 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications RS-20-154, Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections2020-12-16016 December 2020 Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections ML20246G8652020-09-21021 September 2020 Issuance of Amendment Nos. 222 and 222 One-Time Extension of Unit No. 2 Steam Generator Inspections (COVID-19) ML20167A0072020-09-11011 September 2020 R. E. Ginna - Issuance of Amendment Nos. 216, 216, 220, 220, and 143 - Adoption of TSTF-567, Rev. 1, Add Containment Sump Technical Specifications to Address GSI-191 Issues ML20118C4292020-06-0909 June 2020 Issuance of Amendments Revision of Technical Specifications for the Ultimate Heat Sink ML20086M2882020-04-0202 April 2020 Correction of Amendments Nos. for Amendments Revising Instrument Testing and Calibration Definitions RS-19-115, Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-20020 December 2019 Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML19190A0812019-08-28028 August 2019 Issuance of Amendments Regarding Limiting Condition of Operation for Inoperability of Snubbers RS-19-018, Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times2019-02-14014 February 2019 Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times RS-18-102, License Amendment Request for a One-Time Extension to Technical Specification 3.8.1, AC Sources-Operating, Required Action A.22018-08-10010 August 2018 License Amendment Request for a One-Time Extension to Technical Specification 3.8.1, AC Sources-Operating, Required Action A.2 ML18067A1812018-06-0404 June 2018 Correction to Technical Specification Amendment Identification Format ML16180A2512016-08-0101 August 2016 Issuance of Amendments Regarding Use of Optimized Zirlo as Fuel Cladding Material ML16133A4382016-07-26026 July 2016 Issuance of Amendments Ultimate Heat Sink Temperature Increase RS-16-034, License Amendment Request and 10 CFR 50.12 Exemption Request for the Use of Optimized Zirlo Fuel Rod Cladding2016-02-23023 February 2016 License Amendment Request and 10 CFR 50.12 Exemption Request for the Use of Optimized Zirlo Fuel Rod Cladding ML15336A7312016-01-27027 January 2016 TS 50456-Bwd-AppsABC ML15307A7762015-12-21021 December 2015 Braidwood - Issuance of Amendments Regarding Installation of New Low Degraded Voltage Relays and Timers on the 4.16 Kv Engineered Safety Features (ESF) Buses (CAC Nos. MF4051 - MF4054) ML15341A3162015-12-14014 December 2015 Correction of Technical Specifications Related to Amendment 145 ML15286A2762015-11-19019 November 2015 Technical Specifications ML15232A4412015-10-28028 October 2015 Issuance of Amendments to Utilize WCAP-16143-P, Revision 1 Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Byron/Braidwood Units 1 and 2, Dated October 2014 ML15268A4862015-10-0606 October 2015 Correction of Amendments Adopting Technical Specification Task Force Traveler TSTF-523 (TAC Nos. MF4436-MF4446) ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) ML14323A5222015-04-0808 April 2015 Issuance of Amendments Regarding the Emergency Plan Definition of Annual Training RS-14-337, Units 1 & 2 - License Amendment Request for Diesel Generator Load Rejection Surveillance Requirement2014-12-18018 December 2014 Units 1 & 2 - License Amendment Request for Diesel Generator Load Rejection Surveillance Requirement ML14239A4272014-12-0707 December 2014 Issuance of Amendments to Clarify Technical Specification 3.3.1, Reactor Trip System Instrumentation, and TS 3.3.2, Engineered Safety Feature Actuation System Instrumentation RS-14-285, License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink(Uhs)2014-11-24024 November 2014 License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink(Uhs) ML14085A5322014-07-21021 July 2014 Issuance of Amendments Adoption of TSTF-522 Ventilation System Surveillance Requirements ML13311B4812014-07-21021 July 2014 Issuance of Amendments to Revise Technical Specifications Section 3.5.3 ML14069A3372014-04-0202 April 2014 Final Response to Task Interface Agreement 2012-13, Braidwood Station Technical Specification 3.6.3 Compliance with One or More Main Steam Isolation Valves Inoperable ML13326A1072014-03-13013 March 2014 Issuance of Amendments to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program ML13281A0002014-02-0707 February 2014 Issuance of Amendments Regarding Measurement Uncertainty Recapture Power Uprate RS-13-240, License Amendment Request to Administratively Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program.2013-10-10010 October 2013 License Amendment Request to Administratively Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program. RS-13-137, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process2013-09-0303 September 2013 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process RS-13-175, Bryon, Units 1 and 2, License Amendment Request to Revise Technical Specifications Section 3.7.2, Main Steam Isolation Valves (Msivs).2013-08-21021 August 2013 Bryon, Units 1 and 2, License Amendment Request to Revise Technical Specifications Section 3.7.2, Main Steam Isolation Valves (Msivs). RS-12-009, License Amendment Request - Diesel Generator Steady State Maximum Frequency and Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel2012-05-0101 May 2012 License Amendment Request - Diesel Generator Steady State Maximum Frequency and Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel RS-12-028, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.2012-03-22022 March 2012 Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. RS-12-023, License Amendment Request to Revise Tech Specs Sections 5.5.9, Steam Generator (SG) Program, and TS 5.6.9, Steam Generator (SG) Tube Inspection Report, for Permanent Alternate Repair Criteria2012-03-20020 March 2012 License Amendment Request to Revise Tech Specs Sections 5.5.9, Steam Generator (SG) Program, and TS 5.6.9, Steam Generator (SG) Tube Inspection Report, for Permanent Alternate Repair Criteria 2024-05-28
[Table view] |
Text
Exelon Generation www.exeloncnrp .corn Exelon.
4300 Winfield Road Nuclear Warrenville, IL 60555 RS-08-118 October 1, 2008 U . S . Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos . STN 50-454 and STN 50-455 Subject : Additional Information Supporting Request to Revise Containment Tendon Surveillance Program References : 1 . Letter from P. R. Simpson (Exelon Generation Company, LLC) to U. S . NRC, "License Amendment Request to Revise Containment Tendon Surveillance Program," dated April 9, 2008
- 2. Letter from Marshall J . David (U .S. NRC) to Charles G. Pardee, "Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2 Request for Additional Information Related to Containment Tendon Surveillance Program," dated September 9, 2008 In Reference 1, Exelon Generation Company, LLC (EGC) requested an amendment to Facility Operating License Nos. NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2, and Facility Operating License Nos. NPF-37 and NPF-66 for Byron Station, Units 1 and 2. The proposed change revises Technical Specifications (TS) Section 5.5.6, "Pre-Stressed Concrete Containment Tendon Surveillance Program," and Section 5.6.8, "Tendon Surveillance Report,"
for consistency with the requirements of 10 CFR 50.55a, "Codes and standards," paragraph (g)(4) for components classified as Code Class CC . Specifically, the proposed changes replace or delete the reference to the specific ASME Code year for the tendon surveillance program with a requirement to use the applicable ASME Code and addenda as required by 10 CFR 50.55a(g)(4) .
In Reference 2, the NRC provided questions to EGC to support NRC review of Reference 1 .
The attachments of this letter provide the requested responses.
October 1, 2008 U . S . Nuclear Regulatory Commission Page 2 EGC has reviewed the information supporting a finding of no significant hazards consideration, and the environmental consideration, that were previously provided to the NRC in Attachment 1 of Reference 1 . The additional information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration . In addition, the additional information provided in this submittal does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
There are no regulatory commitments contained in this submittal . Should you have any questions concerning this letter, please contact Ms. Tricia Mattson at (630) 657-2813 .
I declare under penalty of perjury that the foregoing is true and correct. Executed on the first day of October 2008.
Respectfully, 2
Patrick R. Simpson Manager - Licensing Attachments:
- 1. Response to Request for Additional Information
- 2. Markup of Proposed Technical Specifications Pages for Braidwood Station
- 3. Markup of Proposed Technical Specifications Pages for Byron Station
- 4. Markup of Proposed Technical Specifications Bases Pages for Braidwood Station
- 5. Markup of Proposed Technical Specifications Bases Pages for Byron Station
ATTACHMENT 1 Response to Request for Additional Information Related to Request to Revise Containment Tendon Surveillance Program NRC Request 1 The NRC staff notes an inconsistency when comparing the wording used in the second sentence of revised Technical Specification (TS) Bases Section SR 3.6.1 .2 and in revised TS Section 5.5.6. Revised TS Bases Section SR 3.6.1 .2 states that "Testing and Frequency are consistent with the requirements of 10 CFR 50.55a, "Codes and standards" (Ref . 4)." Revised TS Section 5.5.6 states that "The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an alternative, exemption, or relief has been authorized by the NRC."
The NRC staff also notes an inconsistency when comparing the wording used in the second sentence of revised TS Bases Section SR 3.6.1 .2 and in Bases Section SR 3.6.1 .2 of NUREG-1431, Revision 3.1 . Bases Section SR 3.6.1 .2 of NUREG-1431 states that "Testing and Frequency are in accordance with the ASME Code,Section XI, Subsection IWL (Ref . X), and applicable addenda as required by 10 CFR 50.55a ."
Please justify or resolve these inconsistencies .
Response
To be consistent, the proposed wording describing acceptance criteria for testing and frequency will be "The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50 .55a, except where an alternative, exemption, or relief has been authorized by the NRC," for both the second sentence of revised TS Bases Section SR 3.6.1 .2, and TS Section 5.5.6. The revised markup TS Bases are attached and reflect this change. Attachments 2 through 5 provide revised TS and TS Bases mark-ups reflecting these changes.
NRC Request 2 The NRC staff notes that the reference to Regulatory Guide (RG) 1 .35.1 has been removed from revised TS Section 5.5 .6 and the revised TS Bases Section SR 3.6 .1 .2. The staff notes that the last sentence of SR 3.6.1 .2 was revised to read: "Predicted tendon lift off forces will be determined in accordance with the ASME Code,Section XI, Subsection IWL (Ref . 5), and applicable addenda as required by 10 CFR 50.55a ." The NRC staff finds that the ASME Code,Section XI, Subsection IWL does not provide guidance with regard to the determination of predicted tendon forces . Please resolve this inconsistency. Also, please provide information regarding the method that will be used for determining the predicted prestressing tendon forces for the Tendon Surveillance Programs at Braidwood and Byron .
ATTACHMENT 1 Response to Request for Additional Information Related to Request to Revise Containment Tendon Surveillance Program
Response
Predicted tendon lift off forces have been and will continue to be determined in accordance with NRC Regulatory Guide 1 .35 .1 "Determining Prestressing Forces For Inspection Of Prestressed Concrete Containments," July 1990 edition . Reference to Regulatory Guide 1 .35.1 will be retained in TS Section 5 .5.6 and the References of the Bases Section 3.6.1 .
Predicted prestressing tendon forces are calculated using the guidance contained in Regulatory Guide 1 .35.1 . The calculation for determining prestressing tendon forces utilizes the following inputs when determining prestressed losses : Initial Seating Force and date, Tendon Properties, Tendon Length, Elastic Shortening Losses, Minimum Design Stresses, Concrete Properties, Initial Stressing Date, Shrinkage Creep and Losses, Creep Function, Predicted Prestressed Losses, and Upper Bound Stresses . The revised markup TS Bases are attached and reflect this change.
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages for Braidwood Station Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 REVISED TECHNICAL SPECIFICATIONS PAGES 5.5-5
Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity . The program shall include baseline measurements prior to initial operations . The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be i n i th r,~ "p°meHts 9 ASME Beile.p -and with the-449,2 The provisions of Sk 3 .9 .2 a SR 3 .0 .3 are applicable to the Tendon Surveillance Program inspection frequencies .
5 .5 .7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c .4 .b of Regulatory Guide 1 .14, Revision l, August 1975 .
In lieu of Regulatory Position c .4 .b(1) and c .4 .b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI .
Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50 .55a, except where an alternative, exemption, or relief has been authorized by the NRC . Determining pre-stressing forces for inspections shall be consistent with the recommendations of Regulatory Guide 1 .35 .1, July 1990 .
BRAIDWOOD - UNITS 1 & 2 5 .5 - 5 Amendment 118
ATTACHMENT 3 Markup of Proposed Technical Specifications Pages for Byron Station Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 REVISED TECHNICAL SPECIFICATIONS PAGES 5.5-5
Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity . The program shall include baseline measurements prior to initial operations . The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be i n 1 th reG, H' vrnmnr l-c of Dvrorc!irn ur 11n v C, , ol (~ni-In uvuc nddnrda aryl Dnnul ater GHide~j 5T accordance The provisions of ~ 3 .9 . 2a SR 3 .0 .3 are applicable to the Tendon Surveillance Program inspection frequencies .
5 .5 .7 Reactor Coolant Pump Flywheel Infection Program This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c .4 .b of Regulatory Guide 1 .14, Revision 1, August 1975 .
In lieu of Regulatory Position c .4 .b(1) and c .4 .b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI .
Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50 .55a, except where an alternative, exemption, or relief has been authorized by the NRC . Determining pre-stressing forces for inspections shall be consistent with the recommendations of Regulatory Guide 1 .35 .1, July 1990 .
BYRON - UNITS 1 & 2 5 .5 - 5 Amendment 123
ATTACHMENT 4 Markup of Technical Specifications Bases Pages for Braidwood Station Braidwood Station, Units 1 and 2 Facility Operating License Nos . NPF-72 and NPF-77 REVISED TECHNICAL SPECIFICATIONS BASES PAGES B 3.6.1 - 3 B 3.6.1 - 6 B 3.6.1 - 7
Containment B 3 .6 .1 BASES APPLICABLE SAFETY ANALYSES (continued)
The DBAs that result in a challenge to containment OPERABILITY from high pressures and temperatures are a LOCA and a steam line break (Ref . 2) . In addition, release of significant fission product radioactivity within containment can occur from a LOCA, secondary system pipe break, or fuel handling accident (Ref . 3) . In the DBA analyses, it is assumed that the containment is OPERABLE such that, for the DBAs involving release of fission product radioactivity, release to the environment is controlled by the rate of containment leakage . The containment leakage rate, used to evaluate doses resulting from accidents, is defined in 10 CFR 50, Appendix J, Option B (Ref . 1), as La : the maximum allowable containment leakage rate at the calculated peak containment internal pressure (P ) resulting from the limiting design basis LOCA .
The allowable leakage rate represented by La forms the basis for the acceptance criteria imposed on all containment leakage rate testing . L is assumed to be 0 .20% per day in the safety analysis at = 42 .8 psig for Unit 1 and Pa = 38 .4 psig for Unit (Ref . 3) .
The radiological dose assessments performed for the design basis LOCA assume a maximum allowable containment leakage rate of 0 .20% per day . In this case, the dose limits of 10 CFR 50 .67 (Ref . 7) are not exceeded .
Satisfactory leakage rate test results are a requirement for the establishment of containment OPERABILITY .
The containment satisfies Criterion 3 of 10 CFR 50 .36(c)(2)(ii) .
LCO Containment OPERABILITY is maintained by limiting leakage to
<_ 1 .0 La , except prior to the first startup after performing a required Containment Leakage Rate Testing Program leakage test . At this time, applicable leakage limits must be met .
Compliance with this LCO will ensure a containment configuration, including the equi pment hatch, that is structurally sound and that will limit leakage to those leakage rates assumed in the safety analysis .
BRAIDWOOD - UNITS 1 & 2 B 3 .6 .1 - 3 Revision 61
Containment B 3 .6 . 1 BASES SURVEILLANCE SR 3 .6 .1 .1 REQUIREMENTS Maintaining the containment OPERABLE requires compliance with the visual examinations and leakage rate test requirements of the Containment Leakage Rate Testing Program . Failure to meet air lock and purge valve leakage limits specified in LCO 3 .6 .2 and LCO 3 .6 .3 does not invalidate the acceptability of these overall leakage determinations unless their contribution to overall Type A, B, and C leakage causes that to exceed limits . As left leakage prior to the first startup after performing a required leakage test is required to be < 0 .6 La for combined Type B and C leakage and < 0 .75 La for overall Type A leakage . At all other times between required leakage rate tests, the acceptance criteria is based on an overall Type A leakage limit of <_ 1 .0 La . At <_ 1 .0 La the dose consequences are bounded by the assumptions of the safety analysis . SR Frequencies are as required by the Containment Leakage Rate Testing Program . These periodic testing requirements verify that the containment leakage rate does not exceed the leakage rate assumed in the safety analysis .
SR 3 .6 .1 .2 This SR ensures that the structural integrity of the containment will be maintained in accordance with the provisions of the Containment Tendon Surveillance Program .
of v^ r -~,-vrrrwfCD~(1~Tvv~7~-~-7 FCC/hl/'~ll,ii 1 "4fe Lditinn E -rc aR Adda of SUhceGtinR crvir-~ c-~
E and S arrcr o bS@Gtin !rW cccrcR -- ~-~ N SEGTIOcrr-rvr YT" r~ c )
~~nrcc. .r t
(`CDF11 F5 ( j --9 Rat-9H a-RdSeGt-1-eR 1 9 ~-X~,
GeRepete d'~fGTG GC' nt ai q'TR1C, T s " (Ref . ~T" nm ent F1. P ped T~Tt CtT; ~ ed C1~teRden 14t GT 1 TQl7TT~
G,s i 1 1 be detonmi Red G9Hci stunt ri th tho
~ep w w The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50 .55a, except where an alternative, exemption, or relief has been authorized by the NRC . Determining pre-stressing forces for inspections shall be consistent with the recornendations of Regulatory Guide 1 .35 .1, July 1990 (Ref . 6) .
BRAIDWOOD - UNITS 1 & 2 B 3 .6 .1 - 6 Revision 61
Containment B 3 .6 .1 BASES REFERENCES 1. 10 CFR 50, Appendix J, Option B .
- 2. UFSAR, Chapter 15 .
- 3. UFSAR, Section 6 .2 .
- 4. 10 CFR50 .55a, "Codes and standards ."
5.
Gnntai nmonts vvi -i-c
- 6. Regulatory Guide 1 .35 .1, July 1990 .
- 7. 10 CFR 50 .67 .
ASME Code,Section XI, Subsection IWL BRAIDWOOD - UNITS 1 & 2 B 3 .6 .1 - 7 Revision 61
ATTACHMENT 5 Markup of Technical Specifications Bases Pages for Byron Station Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 REVISED TECHNICAL SPECIFICATIONS BASES PAGES B 2 .6.1 - 3 B 3.6.1 - 5 B 3.6.1 - 6
Containment B 3 .6 .1 BASES APPLICABLE SAFETY ANALYSES (continued)
The DBAs that result in a challenge to containment OPERABILITY from high pressures and temperatures are a LOCA and a steam line break (Ref . 2) . In addition, release of significant fission product radioactivity within containment can occur from a LOCA, secondary system pipe break, or fuel handling accident (Ref . 3) . In the DBA analyses, it is assumed that the containment is OPERABLE such that, for the DBAs involving release of fission product radioactivity, release to the environment is controlled by the rate of containment leakage . The containment leakage rate, used to evaluate doses resulting from accidents, is defined in 10 CFR 50, Appendix J, Option B (Ref . 1), as La : the maximum allowable containment leakage rate at the calculated peak containment internal pressure (P ) resulting from the limiting design basis LOCA .
The allowable leakage rate represented by La forms the basis for the acceptance criteria imposed on all containment leakage rate testing . La is assumed to be 0 .20% per day in the safety analysis at P = 42 .8 psig for Unit 1 and Pa = 38 .4 psig for Unit ~ (Ref . 3) .
The radiological dose assessments performed for the design basis LOCA assume a maximum allowable containment leakage rate of 0 .20% per day . In this case, the dose limits of 10 CFR 50 .67 (Ref . 7) are not exceeded .
Satisfactory leakage rate test results are a requirement for the establishment of containment OPERABILITY .
The containment satisfies Criterion 3 of 10 CFR 50 .36(c)(2)(ii) .
LCO Containment OPERABILITY is maintained by limiting leakage to
<_ 1 .0 La , except prior to the first startup after performing a required Containment Leakage Rate Testing Program leakage test . At this time, applicable leakage limits must be met .
Compliance with this LCO will ensure a containment configuration, including the equi pment hatch, that is structurally sound and that will limit leakage to those leakage rates assumed in the safety analysis .
BYRON - UNITS 1 & 2 B 3 .6 .1 - 3 Revision 55
Containment B 3 .6 . 1 BASES SURVEILLANCE SR 3 .6 .1 .1 REQUIREMENTS Maintaining the containment OPERABLE requires compliance with the visual examinations and leakage rate test requirements of the Containment Leakage Rate Testing Program . Failure to meet air lock and purge valve leakage limits specified in LCO 3 .6 .2 and LCO 3 .6 .3 does not invalidate the acceptability of these overall leakage determinations unless their contribution to overall Type A, B, and C leakage causes that to exceed limits . As left leakage prior to the first startup after performing a required leakage test is required to be < 0 .6 La for combined Type B and C leakage and < 0 .75 La for overall Type A leakage . At all other times between required leakage rate tests, the acceptance criteria is based on an overall Type A leakage limit of <_ 1 .0 La . At <_ 1 .0 La the dose consequences are bounded by the assumptions of the safety analysis . SR Frequencies are as required by the Containment Leakage Rate Testing Program . These periodic testing requirements verify that the containment leakage rate does not exceed the leakage rate assumed in the safety analysis .
SR 3 .6 .1 .2 This SR ensures that the structural integrity of the containment will be maintained in accordance with the provisions of the Containment Tendon Surveillance Program .
Testi n~-cm s n q-ul~~e q He~l~f-t~- -9 R-S i~~ th --m-c~r"crrc~
"d~zR e Peg the rcgcH4nements Gect G,9R ai nmeHtS" Rod 6l Dredi rted tendnn lift T4f Gea W411 he determi Red Genci dent with the reGemmend8tinnc ef Requra`t n r~, r, i4d c 1 .36 .-,(T c'4.
D 6) .
The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50 .55a, except where an alternative, exemption, or relief has been authorized by the NRC . Determining pre-stressing forces for inspections shall be consistent with the recommendations of Regulatory Guide 1 .35 .1, July 1990 (Ref . 6) .
BYRON - UNITS 1 & 2 B 3 .6 .1 - 5 Revision 55
Containment B 3 .6 .1 BASES REFERENCES 1. 10 CFR 50, Appendix J, Option B .
- 2. UFSAR, Chapter 15 .
- 3. UFSAR, Section 6 .2 .
- 4. 10 CFR50 .55a "Codes and CeHtai-ReRts .
standards ."
- 6. Regulatory Guide 1 .35 .1, July 1990 .
- 7. 10 CFR 50 .67 .
ASME Code,Section XI, Subsection IWL BYRON - UNITS 1 & 2 B 3 .6 .1 - 6 Revision 55