Letter Sequence Other |
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Results
Other: ML21092A091, ML21194A408, ML21231A182, ML21314A218, ML21346A000, ML21363A165, NL-20-021, Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device, RS-21-077, License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink
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MONTHYEARNL-20-021, Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-03-24024 March 2020 Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device Project stage: Other ML20084Q1912020-03-24024 March 2020 New York State Motion for Leave to Amend Contentions NY-2 and NY-3 Project stage: Request ML20108E9482020-04-17017 April 2020 Acceptance Review Determination for Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device Project stage: Acceptance Review ML20184A0012020-07-0606 July 2020 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML21363A1582020-07-31031 July 2020 E-mail from A. Peterson,Nyserda to R. Guzman, NRC, Informal Questions Indian Point Unit 3, HI-LIFT Crane License Amendment Request Project stage: Request ML20233B0152020-08-20020 August 2020 Request for Additional Information (E-mail Dated 8/20/20) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device Project stage: RAI ML20268C2352020-09-24024 September 2020 Request for Additional Information (E-mail Dated 9/24/20) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device Project stage: RAI NL-20-070, Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-10-0202 October 2020 Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device Project stage: Response to RAI ML21363A1602020-10-22022 October 2020 E-mail from A. Peterson, NYSERDA, to R. Guzman, NRC, Informal Questions Indian Point Unit 3, HI-LIFT Crane License Amendment Request Project stage: Request NL-20-078, Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-11-0909 November 2020 Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device Project stage: Response to RAI ML21013A0142020-12-21021 December 2020 Clarification Call for Draft RAIs (E-mail Dated 12/21/20) License Amendmet Request to Revise Licensing Basis for New Auxiliary Lifting Device Project stage: Draft RAI ML21013A0152021-01-12012 January 2021 Draft Request for Additional Information (E-mail Dated 1/12/2021) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device Project stage: Draft RAI ML21019A5672021-01-19019 January 2021 Second Round Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device Project stage: RAI ML21363A1642021-01-19019 January 2021 E-mail from A. Peterson, NYSERDA, to R. Guzman, NRC, Informal Questions Indian Point Unit 3, HI-LIFT Crane License Amendment Request Project stage: Request NL-21-014, Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2021-01-26026 January 2021 Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device Project stage: Request ML21060B6022021-03-11011 March 2021 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML21078A5102021-03-19019 March 2021 E-mail from P. Couture to R. Guzman) Hi-Lift Crane Proposed License Amendment Request Confirmatory Information Project stage: Request ML21363A1652021-03-23023 March 2021 3/23/2021 E-mail from R. Guzman, NRC, to A. Peterson, NYSERDA, State Comments for IP3 HI-LIFT Crane License Amendment Request Project stage: Other ML21092A0912021-04-0202 April 2021 E-mail NRR Review Hour Estimate Change Supporting the Hi-Lift Crane Proposed License Amendment Request Review Project stage: Other ML21096A3332021-04-0606 April 2021 E-mail Dated 4/6/2021, Transmittal of Draft Safety Evaluation for Proposed License Amendment Revision to Licensing Basis to Incorporate the Installation and Use of of New Auxiliary Lifting Device Project stage: Draft Approval ML21111A3612021-04-21021 April 2021 4/21/2021 Letter from A. Peterson (NYSERDA) to R. Guzman (Nrc), New York State Comments Indian Point Energy Center Unit 3 License Amendment Request (HI-LIFT Crane) Project stage: Request ML21112A2672021-04-22022 April 2021 Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (Public Redacted Version) Project stage: RAI NL-21-039, Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary2021-05-20020 May 2021 Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Project stage: Response to RAI ML21194A4082021-07-13013 July 2021 (7-13-2021) E-mail NRR Review Hour Estimate Change Supporting the Hi-Lift Crane Proposed License Amendment Request Review Project stage: Other RS-21-077, License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink2021-08-0202 August 2021 License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink Project stage: Other ML21231A1822021-08-26026 August 2021 Unit, No. 3 - Audit Plan in Support of Review of License Amendment Request Regarding the Installation and Use of a New Auxiliary Lifting Device Project stage: Other ML21252A0172021-09-0303 September 2021 NRR E-mail Capture - NRC Acceptance Review - Braidwood - License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink Project stage: Acceptance Review ML21337A2952021-12-0303 December 2021 Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (E-mail Dated 12/3/2021) Project stage: RAI ML21346A0002021-12-16016 December 2021 Unit, No. 3 - Regulatory Audit Summary Concerning License Amendment Request to Install and Use a New Auxiliary Lifting Device Project stage: Other ML22003A1932022-01-0303 January 2022 Response to Requests for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device Project stage: Response to RAI ML21314A2182022-01-18018 January 2022 Audit Plan in Support of Review of License Amendment Request Regarding the Ultimate Heat Sink Project stage: Other ML22028A1032022-01-28028 January 2022 E-mail Dated 1/28/2022, Transmittal of Draft Safety Evaluation for Proposed License Amendment Revision to Licensing Basis to Incorporate the Installation and Use of of New Auxiliary Lifting Device Project stage: Draft Approval ML21091A3052022-02-28028 February 2022 Issuance of Amendment No. 272 Revision to Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device (EPID L-2020-LLA-0051) (Non-Proprietary) Project stage: Approval 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 Project stage: Response to RAI BW230019, Steam Generator Eddy Current Inspection Report Refueling Outage 23 (A1R23) - October 20222022-10-31031 October 2022 Steam Generator Eddy Current Inspection Report Refueling Outage 23 (A1R23) - October 2022 Project stage: Request ML22314A2412022-12-16016 December 2022 Withdrawal of an Amendment Request - Letter - Project stage: Withdrawal ML22314A2502022-12-19019 December 2022 Withdrawal of an Amendment Request - FRN - Project stage: Withdrawal 2021-03-23
[Table View] |
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Category:Audit Plan
MONTHYEARML22265A0132022-09-28028 September 2022 Steam Generator License Renewal Response to Commitment 10 - Audit Plan ML22214A0042022-08-0202 August 2022 Audit Plan to Support the Review of Amendments to Revise Criticality Safety Analysis Methodologies (Epids L-2022-LLA-0085, L-2021-LLA-0124, and L-2021-LLA-0159) ML21314A2182022-01-18018 January 2022 Audit Plan in Support of Review of License Amendment Request Regarding the Ultimate Heat Sink ML19133A0862019-05-20020 May 2019 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF-505, Revision 2 ML19031C8452019-01-25025 January 2019 Audit Plan for Exelon Generation Company, Llc. License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies at Braidwood Station, Units 1 and 2 - Renewed Facility Operating License Nos. NPF-72 and NPF-77 ML17177A4462017-07-0606 July 2017 Audit Plan for Licensee Responses Concerning Seismic Hazard Reevaluations Related to Request for Information -(50.54(F) Letter) Regarding Recommendation 2.1 of the Near-Term Task Force ML16259A1892016-12-0505 December 2016 Nuclear Regulatory Commission Plan for the Audit of Mitigation Strategies Assessment Submittals Related to Order EA-12-049, Order to Modify Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML16189A3282016-07-12012 July 2016 NRC Plan for the Audit of Exelon Generation'S Mitigation Strategies Assessment Submittals Relating to Order EA-12-049 for Braidwood Station, Dresden Nuclear Power Station, Peach Bottom Units 2 and 3, and Three Mile Island, Unit 1 ML14356A0042014-12-30030 December 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML14083A6202014-03-26026 March 2014 Nuclear Regulatory Commission Audits of Licensee Responses to Reliable Spent Fuel Pool Instrumentation Order EA-12-051 ML13182A0482013-07-10010 July 2013 Audit Plan for Braidwood and Byron Licensee Action Taken to Resolve Turbine Building High Energy Line Break Non-Conformance 2022-09-28
[Table view] Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 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 ML23348A2162023-12-15015 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference 05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023 Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case ML23321A0442023-11-17017 November 2023 Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline 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 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums 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 IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 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. ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 ML23234A2462023-08-25025 August 2023 Confirmation of Initial License Examination IR 05000456/20230022023-08-0303 August 2023 Integrated Inspection Report 05000456/2023002 and 05000457/2023002 ML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III 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 ML23110A1152023-06-12012 June 2023 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2023-LLA-0042) (Letter) 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. ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23132A0472023-05-12012 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ML23130A0072023-05-10010 May 2023 Submittal of Core Operating Limits Report Cycle 24, Rev. 16 IR 05000456/20230012023-05-0808 May 2023 Integrated Inspection Report 05000456/2023001 and 05000457/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23118A0202023-04-28028 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 ML23095A1292023-04-0505 April 2023 Steam Generator Tube Inspection Report for Refueling Outage 23 ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 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 2024-02-02
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML22364A0242023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246 ML22210A0312022-08-30030 August 2022 Issuance of Amendments Nos. 230, 230, 230, and 230, Respectively, Regarding Adoption of Technical Specifications Task Force Traveler (TSTF) 501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML22173A1812022-08-11011 August 2022 Issuance of Amendment No. 229 to Remove License Condition ML22173A2142022-08-10010 August 2022 Issuance of Amendments Nos. 228 and 228 Revision of Technical Specifications for the Ultimate Heat Sink ML22145A5862022-06-0303 June 2022 R. E. Ginna Correction to Pages Issued for Amendments Nos. 225, 225, 227, 227, & 148, Respectively, Regarding Issues Identified in Westinghouse Documents 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 ML22026A4892022-03-22022 March 2022 Issuance of Amendment Nos. 225, 225, 227, 227, and 148, Respectively, Regarding Issues Identified in Westinghouse Documents (EPID L-2021-LLA-0066) Nonproprietary ML22021B6592022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000) (Letter) ML22031A2762022-02-0101 February 2022 Issuance of Indemnity Agreement Amendments-Enclosure 2 ML22021B6602022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000)-Enclosure 1 ML21314A2182022-01-18018 January 2022 Audit Plan in Support of Review of License Amendment Request Regarding the Ultimate Heat Sink ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21154A0462021-07-13013 July 2021 Issuance of Amendments Nos. 222 and 222 Revision of Technical Specifications for the Ultimate Heat Sink ML21090A0152021-04-0707 April 2021 Correction to Amendment Nos. 219 and 219 Regarding Revision of Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML21060B2812021-04-0202 April 2021 Issuance of Amendments Nos. 221, 221, 224, and 224 Regarding Technical Specifications 3.8.1, AC Sources-Operating ML21054A0082021-03-10010 March 2021 Issuance of Amendment Nos. 220 and 220 One-Time Deferral of Steam Generator Tube Inspections 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) ML20245E4192020-09-24024 September 2020 Issuance of Amendments Nos. 218 and 218 Revision of Technical Specifications for the Ultimate Heat Sink ML20163A0462020-09-18018 September 2020 Issuance of Amendments Nos. 217, 217, 221, and 221, Revise Technical Specification 5.6.6 to Allow Use of Areva Np Topical Report BAW-2308 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 ML20149K6982020-09-10010 September 2020 Issuance of Amendment Nos. 215, 215, 219, and 219 Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20118C4292020-06-0909 June 2020 Issuance of Amendments Revision of Technical Specifications for the Ultimate Heat Sink ML20111A0002020-05-0101 May 2020 Issuance of Amendment No. 209, Revision Technical Specification 5.5.9, Steam Generator (SG) Program, for One-Time Revision to Frequency of SG Tube Inspections (Exigent Circumstances) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20034G5462020-03-12012 March 2020 Issuance of Amendments Revising Instrument Testing and Calibration Definitions ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML19266A5272019-10-0808 October 2019 Issuance of Amendments to Eliminate Second Completion Times from Technical Specifications ML19190A0812019-08-28028 August 2019 Issuance of Amendments Regarding Limiting Condition of Operation for Inoperability of Snubbers ML19170A3112019-06-19019 June 2019 Redacted Braidwood Station, Units 1 & 2, and Byron Station, Units 1 & 2, Amendment 28 to Fire Protection Report, Appendix 5.1 (Public Version Pages 1-76 and 129-287) ML19168A1192019-06-17017 June 2019 Redacted Braidwood Station, Units 1 & 2, Amendment 28 to Fire Protection Report, Chapter 2.4, Safe Shutdown Analysis. (Public Version Pages 1-19 and 1726-1742) RS-19-017, Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control2019-06-14014 June 2019 Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control ML18302A2272018-12-12012 December 2018 Issuance of Amendments No. 200 and 205 Regarding Axial Flux Difference Technical Specifications ML18291A9802018-11-0808 November 2018 Issuance of Amendment Nos. 199 Regarding Use of TORMIS for Assessing Tornado Missile Protection ML18264A0922018-10-22022 October 2018 Issuance of Amendment Nos. 198, 198, 204, and 204, Respectively, Regarding Adoption of Title 10 of the Code of Federal Regulations Section 50.69 CAC Nos. MG0201, MG0202, MG0203, and MG0204; EPID-L 2017-LLA-0285) ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18065A5292018-06-27027 June 2018 Issuance of Amendments Regarding Clarification of Rod Position Requirements (CAC Nos. MF9951-9954; EPID L-2017-LLA-0249) ML18067A1812018-06-0404 June 2018 Correction to Technical Specification Amendment Identification Format ML18054B4362018-04-30030 April 2018 Issuance of Amendments Regarding Control Room Ventilation Temperature Control System (CAC Nos. MF9932, MF9933, MF9934, and MF9935; EPID L-2017-LLA-0247) ML17163A3552017-08-31031 August 2017 Calvert Cliff, Clinton, Dresden, LaSalle, Limerick, Nine Mile Point, Peach Bottom, Quad Cities, R. E. Ginna, and Three Miles Island - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules(Cac Nos. MF9470-MF9490) ML17088A7032017-07-0505 July 2017 Issuance of Amendments to Regarding Request to Delete Obsolete License Conditions and Make Administrative Changes to Technical Specifications (CAC Nos. MF9338-MF9341) ML17073A0672017-05-26026 May 2017 Issuance of Amendments Revising the Technical Specification Requirements for the Inservice Testing Program (CAC Nos. MF8238 - MF8256) 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 ML15336A0332016-01-27027 January 2016 Renewed License 2023-07-26
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January 18, 2022 Mr. David P. Rhoades Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2 - AUDIT PLAN IN SUPPORT OF REVIEW OF LICENSE AMENDMENT REQUEST REGARDING THE ULTIMATE HEAT SINK (EPID L-2021-LLA-0141)
Dear Mr. Rhoades:
By letter dated August 2, 2021, Exelon Generation Company, LLC (Exelon) submitted a license amendment request (LAR) for Braidwood Station, Units 1 and 2 (Braidwood). In its LAR, Exelon proposed adding two Required Actions and associated Completion Times to Technical Specification (TS) 3.7.9, "Ultimate Heat Sink [UHS]," for an inoperable UHS due to the average water temperature.
During the initial review of the LAR, the U.S. Nuclear Regulatory Commission (NRC) staff identified several items that require further clarification and detailed explanations. The NRC staff will conduct a regulatory audit to support its review of the LAR in accordance with the enclosed audit plan. A regulatory audit is a planned activity that includes the examination and evaluation of primarily non-docketed information. The audit will be conducted to increase the NRC staffs understanding of the LAR and identify information that will require docketing to support the NRC staffs regulatory finding.
The audit will be conducted on January 28, 2022, using audio/video conferencing. The logistics and scope of this audit were discussed with your staff on December 3, 2021. The audit plan is enclosed.
D. Rhoades If you have any questions, please contact me by telephone at 301-415-6606 or by e-mail to Joel.Wiebe@nrc.gov.
Sincerely,
/RA/
Joel S. Wiebe, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456 and STN 50-457
Enclosure:
Audit Plan cc: Listserv
AUDIT PLAN BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING LICENSE AMENDMENT REQUEST REGARDING THE ULTIMATE HEAT SINK BRAIDWOOD STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-456 AND STN 50-457 EPID L-2021-LLA-0141
1.0 BACKGROUND
By letter dated August 2, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21214A331), Exelon Generation Company, LLC (Exelon or licensee) submitted a license amendment request (LAR) for Braidwood Station, Units 1 and 2 (Braidwood). In its LAR, Exelon proposed adding two Required Actions and associated Completion Times to Technical Specification (TS) 3.7.9, "Ultimate Heat Sink [UHS]," for an inoperable UHS due to the average water temperature.
During the initial review of the LAR, the U.S. Nuclear Regulatory Commission (NRC or Commission) staff identified several items that require further clarification and detailed explanations. The NRC staff will conduct a regulatory audit to support its review of the LAR in accordance with this audit plan. A regulatory audit is a planned activity that includes the examination and evaluation of primarily non-docketed information. The audit will be conducted to increase the NRC staffs understanding of the LAR and identify information that will require docketing to support the NRC staffs regulatory finding.
2.0 REGULATORY AUDIT BASES The NRC staff will perform the audit to support its evaluation of whether the licensees request can be approved per Title 10 of the Code of Federal Regulations (10 CFR), Section 50.92, Issuance of Amendment, which states, in part, that, In determining whether to issue an amendment to a license, , the Commission will be guided by the considerations which govern issuance of initial licenses. Applicable regulations considered in that review include 10 CFR, Section 50.34, Contents of Applications; Technical Information, and applicable general design criteria (GDC) from Appendix A to 10 CFR Part 50 (i.e., GDCs 2, 5, and 44).
In the Braidwood Updated Final Safety Analysis Report, Section 3.1.1 (ADAMS Accession No. ML21137A212), the licensee concludes that Braidwood fully satisfies, and is in compliance with, the GDC.
10 CFR, paragraph 50.36(c)(2), states that limiting conditions for operation (LCOs) are the lowest functional capability or performance levels of equipment required for safe operation of the facility, and when an LCO is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the LCO can be met.
Enclosure
Paragraph 50.36(c)(3) of 10 CFR states that surveillance requirements (SRs) are requirements relating to test, calibration, or inspection, to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met.
Regulatory Guidance NUREG-0800 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [light-water reactor] Edition, Section 9.2.5, Ultimate Heat Sink, Revision 2, July 1981 (ADAMS Accession No. ML052350549),Section IV, Acceptance Criteria and Evaluation Findings, contains the following, in part:
GDC 2, as related to structures housing the system and the system itself being capable of withstanding the effects of natural phenomena such as earthquakes, tornadoes, hurricanes, and floods. Acceptance is based on meeting the guidance of Regulatory Guide 1.29, Revision 3 (ADAMS Accession No. ML003739983), Position C-1 and Regulatory Guide 1.27. Revision 2 (ADAMS Accession No. ML003739969), Positions C-2 and C-3.
GDC 5, as related to shared systems and components important to safety being capable of performing required safety functions.
GDC 44, as related to UHS requirements. Acceptance is based upon meeting the guidance of Regulatory Guide 1.27 and demonstrating the capability to transfer heat loads from safety-related SSCs [structure, system, and components] to the heat sink under both normal operating and accident conditions.
3.0 REGULATORY AUDIT SCOPE AND METHODOLOGY The proposed amendment utilizes existing margin in Design Analysis to offset the increase in the TS SR UHS temperature based on actual or projected plant conditions at the time of entry into the new TS Required Actions A.1.1 and A.1.2. Braidwood, Units 1 and 2, License Amendment No. 222, dated July 13, 2021, (ADAMS Accession No. ML21154A046) used existing margin in Design Analyses to offset the increase in UHS temperature up to 102.8 °F (degrees Fahrenheit). The NRC staff wants to see an example of how the TS would be implemented for a hypothetical projected UHS temperature of 103.5 °F.
4.0 INFORMATION AND OTHER MATERIAL NECESSARY FOR THE AUDIT The NRC staff requests the licensee to have the following information readily available and accessible for the NRC staffs review:
Information related to:
An example engineering analysis that demonstrates how the Required Action A.1.1 would be implemented for an hypothetical projected UHS temperature of 103.5 °F. This example engineering analysis is not expected to have the reviews and approvals required by an actual engineering analysis, but it is expected that the design margins used in the engineering analysis be actual currently available margins. In the event the currently available margin is not sufficient to allow the UHS to reach 103.5 °F, the maximum currently attainable UHS temperature should be demonstrated.
Discussion Topics:
- 1. The NRC staff needs information related to the purpose of Required Action A.1.2.
- 2. The proposed Required Action A.1.1 allows changes to a TS value without NRC approval. The maximum analyzed temperature limit calculation methodology is not included in the Braidwood TS. This does not meet the intent of 50.36.
The policy statement on TS (58 FR 39132) states The purpose of Technical Specifications is to impose those conditions or limitations upon reactor operation necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety by identifying those features that are of controlling importance to safety and establishing on them certain conditions of operation which cannot be changed without prior Commission approval. By moving the maximum allowable temperature to a licensee controlled document, this would allow changes to the conditions of operation without NRC approval.
TSTF-330-A, Rev. 3 Allowed Outage Time - Ultimate heat sink provides an approved methodology similar to what is being pursued by the licensee. Discuss whether the TSTF-330-A approach was considered and why the current less conservative approach was chosen.
- 3. Required Action A will be entered during the day as the ambient temperature increases and the UHS becomes inoperable due to high average water temperature. As the ambient temperature decreases and the UHS cools, Required Action A will likely be exited during the night. The following day as the ambient temperature increases, the Action will be re-entered, and then re-exited with no action besides waiting for the ambient temperature to decrease. This is inconsistent with the intent of the Use and Application rules as stated in Section 1.3 of the Braidwood TS.
From Braidwood TS Section 1.3:
It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.
The NRC staff will determine after completing the audit whether it needs to request any additional information to be placed on the docket.
5.0 AUDIT TEAM The audit team will consist of the following NRC staff from NRR:
Mr. Joel Wiebe, Plant Licensing Branch III Mr. Gordon Curran Jr., Containment and Plant Systems Branch (SCPB)
Mr. Chang Li, SCPB
Mr. Robert Beaton, Nuclear Systems Performance Branch (SNSB)
Mr. Santosh Bhatt, SNSB Mr. Joshua Wilson, Technical Specifications Branch (STSB)
Ms. Caroline Tilton, STSB 6.0 LOGISTICS The audit will be conducted using audio/video conferencing via TEAMS. The NRC staff requests the licensee to have the information discussed in Section 4.0 readily available for the audit. The NRC staff requests the licensee to have its staff available at a mutually agreeable time to present and discuss the information identified in Section 4.0. The NRC staff will not take possession of any of the information made available by the licensee for discussion. If information is needed to be placed on the docket in order for the NRC staff to make a decision regarding the acceptability of the August 2, 2021, submittal, the information will be requested via a subsequent request for additional information.
7.0 DELIVERABLES After the audit, the NRC staff will develop any requests for information which it will provide the licensee via separate docketed correspondence. The NRC staff intends to issue an audit summary within 30 days of completion of the audit.
ML21314A218 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/SCPB/BC(A)
NAME JWiebe SRohrer SJones DATE 11/9/2021 11 /10/2021 12/1/2021 OFFICE NRR/DSS/SNSB/BC NRR/DSS/STSB/BC(A) NRR/DORL/LPL3/BC NAME SKrepel NJordan NSalgado DATE 11/15/2021 12/2/2021 12 /7/2021 OFFICE NRR/DORL/LPL3/PM NAME JWiebe DATE 1/18/2022