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MONTHYEARML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. Project stage: Request ML22342B1462022-11-21021 November 2022 NRR E-mail Capture - Acceptance Review for TSTF 295A Project stage: Acceptance Review ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration Project stage: Approval 2022-11-21
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Category:Letter
MONTHYEARNMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 IR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-16016 January 2024 Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-0808 January 2024 Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip2024-01-0808 January 2024 Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24005A0222024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 ML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23317A1032023-11-10010 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 ML23310A0442023-11-0707 November 2023 Project Manager Assignment IR 05000317/20230402023-11-0202 November 2023 95001 Supplemental Inspection Report 05000317/2023040 and Follow-Up Assessment Letter IR 05000317/20230032023-11-0101 November 2023 Integrated Inspection Report 05000317/2023003 and 05000318/2023003 IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000317/20230902023-10-26026 October 2023 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000317/2023090 IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 ML23289A1202023-10-16016 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 ML23279A1202023-10-0606 October 2023 Response to NRC Inspection Report and Preliminary White Finding NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000317/20230502023-09-29029 September 2023 Special Inspection Report 05000317/2023050 and Preliminary White Finding and Apparent Violation ML23272A1032023-09-29029 September 2023 Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 2024-02-01
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23164A1702023-06-13013 June 2023 License Amendment Request to Adopt TSTF-59-A, Incorporate (Combustion Engineering) NPSD-994 Recommendations Into the (Safety Injection Tanks) Specification, Revision 1 ML23153A0982023-06-0202 June 2023 Emergency License Amendment Request - One-Time Extension of the Control Room Emergency Ventilation System (CREVS) Technical Specification RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling 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. ML23052A0632023-02-21021 February 2023 License Amendment Request to Modify the Long-Term Coupon Surveillance Program NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3484, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-15015 December 2022 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors ML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration NMP1L3477, License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise.2022-08-12012 August 2022 License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise. 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. NMP1L3467, License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage2022-06-29029 June 2022 License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage NMP2L2799, License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators2022-05-24024 May 2022 License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators RS-22-017, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions for Calvert Cliffs2022-04-20020 April 2022 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions for Calvert Cliffs ML22067A0772022-03-31031 March 2022 Correction of License Amendment Nos. 337 and 315 to Revise Response Time Testing Definition RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-30030 September 2021 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements 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 NMP2L2762, 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 Control2021-05-26026 May 2021 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-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments NMP1L3369, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-12-18018 December 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20329A3342020-11-24024 November 2020 Application to Revise Technical Specifications to Adopt TSTF-567 Rev 1, Add Containment Sump TS to Address GSI-191 Issues RS-20-031, License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process2020-04-30030 April 2020 License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process NMP2L2716, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-12-26026 December 2019 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML19347A7792019-12-12012 December 2019 License Amendment Request to Utilize Accident Tolerant Fuel Lead Test Assemblies ML19346E5362019-12-11011 December 2019 License Amendment Request: 10 CFR 50.90 Proposed Changes to Technical Specification (TS) 3.8.1 Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances RS-19-092, Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions2019-12-0909 December 2019 Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions ML19325C1282019-11-21021 November 2019 License Amendment Request - Revision to Technical Specification 5.5.7, Reactor Coolant Pump Flywheel Inspection Program NMP2L2706, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.2019-10-31031 October 2019 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability NMP1L3278, License Amendment Request - Administrative Changes to the Technical Specifications2019-06-26026 June 2019 License Amendment Request - Administrative Changes to the Technical Specifications RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NMP2L2699, License Amendment Request to Revise Technical Specifications Main Steam Isolation Valve Leak Rate2019-05-31031 May 2019 License Amendment Request to Revise Technical Specifications Main Steam Isolation Valve Leak Rate ML19127A0762019-05-0606 May 2019 Application to Revise Technical Specifications to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec RS-19-003, Application to Adopt TSTF-564, Safety Limit Mcpr.2019-02-0101 February 2019 Application to Adopt TSTF-564, Safety Limit Mcpr. NMP2L2694, Emergency License Amendment Request: One Time Extension to the High Pressure Core Spray Completion Time and Associated Surveillances2018-12-0606 December 2018 Emergency License Amendment Request: One Time Extension to the High Pressure Core Spray Completion Time and Associated Surveillances ML18333A0222018-11-28028 November 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors. ML18235A1992018-08-23023 August 2018 License Amendment Request: 10 CFR 50.90 Proposed Changes to Technical Specification (TS) 3.8.1 Actions A.3 and D.3 to Extend the Offsite Circuit Inoperable Completion Times from 72 Hours to ... NMP1L3192, License Amendment Request - Revise Technical Specification 3.3.1 for Primary Containment Oxygen Concentration2018-06-26026 June 2018 License Amendment Request - Revise Technical Specification 3.3.1 for Primary Containment Oxygen Concentration RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement ML18113A0902018-04-20020 April 2018 Administrative Change to Technical Specification 5.2.2, Unit Staff RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) NMP1L3188, License Amendment Request - Proposed Change to Remove Boraflex Credit from Spent Fuel Racks2018-02-0909 February 2018 License Amendment Request - Proposed Change to Remove Boraflex Credit from Spent Fuel Racks NMP1L3142, License Amendment Request - Revise Technical Specifications to Apply TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-15015 December 2017 License Amendment Request - Revise Technical Specifications to Apply TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 2023-08-21
[Table view] Category:Technical Specification
MONTHYEARRS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. ML22292A1312022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Technical Specification Bases, Rev. 69 RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration NMP1L3477, License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise.2022-08-12012 August 2022 License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise. 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-22-008, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin2022-01-24024 January 2022 Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-30030 September 2021 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML21278A2972021-09-0707 September 2021 6 to Technical Specification Bases ML21165A4062021-06-14014 June 2021 Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request NMP2L2762, 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 Control2021-05-26026 May 2021 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 JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability NMP2L2718, Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22019-12-12012 December 2019 Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 ML19346E5362019-12-11011 December 2019 License Amendment Request: 10 CFR 50.90 Proposed Changes to Technical Specification (TS) 3.8.1 Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances ML19325C1282019-11-21021 November 2019 License Amendment Request - Revision to Technical Specification 5.5.7, Reactor Coolant Pump Flywheel Inspection Program JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls ML19127A0762019-05-0606 May 2019 Application to Revise Technical Specifications to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec NMP2L2693, Technical Specification Bases, Rev. 572018-10-24024 October 2018 Technical Specification Bases, Rev. 57 ML18239A2602018-08-27027 August 2018 Supplement to Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk .. ML18235A1992018-08-23023 August 2018 License Amendment Request: 10 CFR 50.90 Proposed Changes to Technical Specification (TS) 3.8.1 Actions A.3 and D.3 to Extend the Offsite Circuit Inoperable Completion Times from 72 Hours to ... ML18172A1452018-06-21021 June 2018 Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed ... ML18262A0962018-03-0606 March 2018 Technical Specification Bases, Revisions 62 Through 63 NMP2L2664, Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22018-01-12012 January 2018 Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note2017-08-22022 August 2017 License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note ML17261A2342017-07-19019 July 2017 Bases 3.7, Plant Systems, Revisions; B 3.7.1-1 Through B 3.7.18-3 ML17261A2252017-07-19019 July 2017 Bases 3.2, Power Distribution Limits, Revisions; B 3.2.1-1 Through B 3.2.5-5 ML17261A2352017-07-19019 July 2017 Bases 3.8, Electric Power Systems, Revisions; B 3.8.1-1 Through B 3.8.10-5 ML17261A2272017-07-19019 July 2017 Bases 3.3, Instrumentation, Revisions; B 3.3.1-18 Through B 3.3.12-4 ML17261A2212017-07-19019 July 2017 Bases 2.0, Safety Limits, Revision 2; B 2.1.1-1 Through B 2.1.2-4 ML17261A2192017-07-19019 July 2017 Technical Specification Bases ML17261A2312017-07-19019 July 2017 Bases 3.5, Emergency Core Cooling System (Eccs), Revisions; B 3.5.1-1 Through B 3.5.5-5 ML17261A2232017-07-19019 July 2017 Bases 3.1, Reactivity Control Systems, Revisions; B 3.1.1-1 Through B 3.1.8-5 ML17261A2322017-07-19019 July 2017 Bases 3.0, Containment System, Revisions; B 3.0.1-1 Through B 3.0.8-4 ML17261A2292017-07-19019 July 2017 Bases 3.4, Reactor Coolant System(Rcs), Revisions; B 3.4.1-1 Through B 3.4318-8 ML17261A2382017-07-19019 July 2017 Bases 3.9, Refueling Operations, Revisions; B 3.9.1-1 Through B 3.9.6-2 ML17261A2222017-07-19019 July 2017 Basis 3.0, Limiting Condition for Operation (LCO) Applicability, Revisions; B 3.0-1 Through B 3.0-25 NMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-02-28028 February 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 ML16309A4132016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.9, Refueling Operations ML16309A4082016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.5, Emergency Core Cooling Systems (ECCS) and Reactor Core Isolation Cooling (RCIC) System ML16309A4052016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.2, Power Distribution Limits ML16309A4022016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B2.0, Safety Limits (Sls) ML16309A4012016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Table of Contents ML16309A4032016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.0, Limiting Condition for Operation (LCO) Applicability ML16309A4002016-10-24024 October 2016 Revision 47 to Technical Specification Bases, List of Effective Pages ML16266A0862016-09-22022 September 2016 License Amendment Request - Control Room Emergency Ventilation System ML16258A0802016-09-0808 September 2016 Technical Specification Bases B 3.5.1, Emergency Core Cooling System (Eccs), Safety Injection Tanks (Sits) ML16258A0762016-09-0808 September 2016 Technical Specification Bases B 3.2, Power Distribution Limits - Linear Heat Rate (Lhr) ML16258A0812016-09-0808 September 2016 Technical Specification Bases B 3.6, Containment Systems 2023-05-25
[Table view] Category:Amendment
MONTHYEARRS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration 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. 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ML18235A1992018-08-23023 August 2018 License Amendment Request: 10 CFR 50.90 Proposed Changes to Technical Specification (TS) 3.8.1 Actions A.3 and D.3 to Extend the Offsite Circuit Inoperable Completion Times from 72 Hours to ... ML18172A1452018-06-21021 June 2018 Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed ... NMP2L2664, Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22018-01-12012 January 2018 Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note2017-08-22022 August 2017 License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note NMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-02-28028 February 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 ML16266A0862016-09-22022 September 2016 License Amendment Request - Control Room Emergency Ventilation System NMP1L3027, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)2015-05-12012 May 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) NMP2L2576, License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2015-03-23023 March 2015 License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual NMP2L2563, License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change2014-11-17017 November 2014 License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change ML14191A2552014-07-10010 July 2014 Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML1109602832011-03-30030 March 2011 License Amendment Request Pursuant to 10 CFR 50.90: Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage ... ML1003405862010-01-29029 January 2010 License Amendment Request: Pressurizer Safety Valve Technical Specification Revision ML0935000902009-12-0909 December 2009 License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery - Technical Specification 3.8.4, DC Sources - Operating ML0911700492009-04-23023 April 2009 License Amendment Request for Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from Technical Specification 5.2.2 to Support Compliance with 10 CFR Part 26 ML0907802502009-03-0909 March 2009 Submittal of Amendment Request for Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency ML0906403012009-03-0303 March 2009 License Amendment Request Pursuant to 10 CFR 50.90: Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML0827502992008-09-29029 September 2008 Technical Specifications ML0821804962008-08-27027 August 2008 Technical Specifications, Amendment No. 288 ML0811601412008-04-23023 April 2008 Tech Spec Pages for Amendments 286 and 263 Modification of Technical Specification Definitions ML0731701802007-11-0808 November 2007 License Amendment Request: Modify Technical Specification Definitions ML0727007162007-09-27027 September 2007 Technical Specification Pages Re Unavailability of Barriers Using Consolidated Line Item Improvement Process ML0720504742007-07-12012 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0718403352007-06-29029 June 2007 License Amendment Request: Revise Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448 Using the Consolidated Line Item Improvement Process ML0707800592007-03-15015 March 2007 Technical Specification 4.1.1 Regarding Control Rod System Surveillance Requirements ML0536202882005-12-16016 December 2005 License Amendment Request: Proposed Changes to Technical Specification 4.1.4 Regarding Core Spray Instrumentation ML0516602072005-06-0707 June 2005 License Amendment Request: Eliminate Use of the Term Core Alterations in the Technical Specifications ML0516601952005-06-0707 June 2005 License Amendment Request: Technical Specification Changes to Modify Requirements Related to Positive Reactivity Additions ML0511100732005-04-19019 April 2005 Tech Spec Pages for Amendment 115 and 188 Reporting Requirements for Annual Radiological Environmental Operating Report ML0510204002005-04-0101 April 2005 License Amendment Request Pursuant to 1O CFR 50.90: Request for Amendment to Extend Completion Time for Emergency Uninterruptible Power Supply Inverters ML0506002672005-02-24024 February 2005 Technical Specifications, Incorporating Core Operating Limits Analytical Methodology References Into Technical Specifications ML0503904972005-02-0303 February 2005 Technical Specification Pages to Calvert Cliffs, Unit 2 - Correction to Amendment No. 246 ML0503300972005-01-27027 January 2005 License Amendment Request: Change Regarding Mode Using the Consolidated Line Item Improvement Process ML0503304712005-01-24024 January 2005 Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports ML0434400272004-12-0101 December 2004 Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports ML0431001302004-11-0303 November 2004 Units 1 & 2; Technical Specification Bases, Revisions 15. 16, 17, 18, 19, 20. 21, and 22 ML0430001872004-10-21021 October 2004 Technical Specification Page for Corrected Amendment Nos. 268 and 244 ML0424003162004-08-17017 August 2004 Unit I, License Amendment Request Pursuant to 10 CFR 50.90: Addition of 24 Hours for Restoration of Primary Containment Oxygen Concentration 2023-05-25
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Text
200 Exelon Way Kennett Square, PA 19348 www.ConstellationEnergy.com 10 CFR 50.90 October 25, 2022 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. 50-317 and 50-318 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 NRC Docket No. 50-410
Subject:
License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of [Post-Accident Monitoring] PAM Table to Allow Separate Condition Entry for Each Penetration, Revision 0 In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Constellation Energy Generation, LLC (CEG) requests amendments to the Technical Specifications (TS) for Calvert Cliffs Nuclear Power Plant (CCNPP), Units 1 and 2 and Nine Mile Point Nuclear Station (NMP), Unit 2.
The proposed changes incorporate the NRC-approved TSTF Improved Standard Technical Specifications Change Traveler TSTF-295-A, Modify Note 2 to Actions of [Post-Accident Monitoring] PAM Table to Allow Separate Condition Entry for Each Penetration, Revision 0.
This change is a clarification to the CCNPP, Units 1 and 2, and NMP, Unit 2 TS which identifies that separate condition entry is allowed for each penetration flow path for the PAM Primary Containment Isolation Valve (PCIV) position indication function. The change also clarifies in the NMP, Unit 2 TS that separate condition entry is allowed for each quadrant for the PAM Suppression Pool Water Temperature indication function.
This request is subdivided as follows.
- Attachment 1 provides an evaluation of the proposed changes.
- Attachment 2a provides the markup of the affected TS pages for CCNPP.
- Attachment 2b provides the markup of the affected TS pages for NMP, Unit 2.
- Attachment 3a provides the markup of the affected Bases pages for CCNPP (for information only).
- Attachment 3b provides the markup of the affected Bases pages for NMP, Unit 2 ( for information only).
The proposed changes have been reviewed by the Plant Operations Review Committees at CCNPP and NMP in accordance with the requirements of the CEG Quality Assurance Program.
License Amendment Request to Adopt TSTF-295-A October 25, 2022 Page 2 CEG requests approval of the proposed amendments by October 25, 2023. Once approved, the amendments shall be implemented within 90 days. This implementation period will provide adequate time for the affected station documents to be revised using the appropriate change control mechanisms.
There are no regulatory commitments contained in this submittal.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"
paragraph (b), CEG is notifying the States of Maryland and New York of this application for license amendments by transmitting a copy of this letter and its attachments to the designated State Officials.
Should you have any questions concerning this submittal, please contact Ms. Wendi E. Para at (267) 533-5208.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 25th day of October 2022.
Respectfully, David P. Helker Sr. Manager - Licensing Constellation Energy Generation, LLC Attachments: 1. Evaluation of Proposed Changes 2a. Proposed Technical Specifications Changes (Mark-Up) - Calvert Cliffs Nuclear Power Plant, Units 1 and 2 2b. Proposed Technical Specifications Changes (Mark-Up) - Nine Mile Point Nuclear Station, Unit 2 3a. Proposed Technical Specifications Bases Pages (For Information Only) -
Calvert Cliffs Nuclear Power Plant, Units 1 and 2 3b. Proposed Technical Specifications Bases Pages (For Information Only) -
Nine Mile Point Nuclear Station, Unit 2 cc: USNRC Region I, Regional Administrator w/ attachments USNRC Senior Resident Inspector, CCNPP USNRC Senior Resident Inspector, NMP USNRC Project Manager, NRR - CCNPP USNRC Project Manager, NRR - NMP S. Seaman, State of Maryland A.L. Peterson, NYSERDA B. Frymire NYSPSC
ATTACHMENT 1 Evaluation of Proposed Changes
Subject:
License Amendment Request to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration, Revision 0 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION 2.1 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 2.2 Nine Mile Point Nuclear Station, Unit 2 2.3 Optional Changes and Variations
3.0 REGULATORY EVALUATION
3.1 Applicability of Published Safety Evaluation 3.2 No Significant Hazards Consideration 3.3 Conclusions
4.0 ENVIRONMENTAL CONSIDERATION
5.0 REFERENCES
License Amendment Request to Adopt TSTF-295-A Page 1 of 5 1.0
SUMMARY
DESCRIPTION Constellation Energy Generation, LLC (CEG), proposes changes to the Technical Specifications (TS), Appendix A of Renewed Facility Operating License Nos. DPR 53 and 69, corresponding to Docket Nos. 50-317 and 50-318, for Calvert Cliffs Nuclear Power Plant (CCNPP), Units 1 and 2 (Pressurized Water Reactors (PWRs)), respectively, and Renewed Facility Operating License No. NPF-69, corresponding to Docket No. 50-410 for Nine Mile Point Nuclear Station (NMP),
Unit 2 (Boiling Water Reactor (BWR)).
The proposed changes incorporate NRC-approved Technical Specification Task Force (TSTF)
Improved Standard Technical Specifications Change Traveler TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration, Revision 0 (Reference 5.1). The changes provide clarification that separate condition entry is allowed for each penetration flow path for the Post-Accident Monitoring (PAM) Primary Containment Isolation Valve (PCIV) position indication function (all PWR and BWR plants) and for each suppression pool water temperature indication function (BWR plants only).
2.0 DETAILED DESCRIPTION NRC-approved TSTF Traveler TSTF-295-A, Revision 0, modifies all Improved Standard Technical Specifications (ISTS) to clarify that a separate Condition entry is allowed for each penetration flow path for the PAM instrumentation PCIV indication function. This change is applicable to all PWR and BWR plants (NUREGs-1430 through 1434), including CCNPP, Units 1 and 2, and NMP, Unit 2.
The PAM specification requires a minimum of one channel of PCIV position indication be operable for each active PCIV in a containment penetration flow path. This change enhances the existing TS Note which states, Separate Condition entry is allowed for each function, by clarifying that each penetration flow path should be evaluated separately for Operability of the PAM function. The change reduces the potential for a shutdown of the unit due to misinterpretation of the requirements.
TSTF-295-A also modifies the BWR-only Improved Technical Specifications to clarify that a separate Condition entry is allowed for each suppression pool quadrant water temperature indication function. This change is applicable to BWR plants only (NUREGs-1433 and 1434),
including NMP, Unit 2.
The PAM specification requires a minimum of two channels of suppression pool quadrant water temperature indication be operable. This change enhances the existing TS Note which states, Separate Condition entry is allowed for each function, by clarifying that each suppression pool quadrant should be evaluated separately for Operability of the PAM function. The change also reduces the potential for a shutdown of the unit due to misinterpretation of the requirements.
The current TS Actions provide appropriate compensatory actions for each inoperable indication function. The proposed changes do not impact any existing TS Actions or Requirements.
License Amendment Request to Adopt TSTF-295-A Page 2 of 5 The detailed site-specific changes are described below.
2.1 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 The TS Actions Note states Separate Condition entry is allowed for each Function. The change clarifies that separate condition entry is allowed for each penetration flow path for the PAM PCIV position indication function. Specifically, the proposed change in the CCNPP TS revises Table 3.3.10-1, Post-Accident Monitoring Instrumentation, by prefacing the title of Function 8, Containment Isolation Valve Position, with the phrase Penetration Flow Path.
A corresponding change to the Bases was made to add the following statement: Each penetration is treated separately and each penetration flow path is considered a separate function. Therefore, separate Condition entry is allowed for each inoperable penetration flow path.
2.2 Nine Mile Point Nuclear Station, Unit 2 The TS Actions Note states Separate Condition entry is allowed for each Function. The changes clarify that separate condition entry is allowed for each penetration flow path for the PAM PCIV position indication function and for each suppression pool quadrant temperature indication. The proposed changes in the NMP, Unit 2 TS revises Table 3.3.3.1-1, Post Accident Monitoring Instrumentation, by (1) prefacing the title of Function 8, PCIV Position, with the phrase Penetration Flow Path, and (2) modifying the title of Function 9, to be Suppression Pool Quadrant Water Temperature.
Corresponding changes to the Bases were made to clarify the connection between the existing Function 8, Penetration Flow Path, Automatic PCIV Position, and Function 9, Suppression Pool Quadrant Water Temperature, with the TS Action Note referenced above. Specifically, the following statements were added to the listed Functions in Section 3.3.3.1:
Function 8, Penetration Flow Path, Automatic PCIV Position, Each penetration is treated separately and each penetration flow path is considered a separate function. Therefore, separate Condition entry is allowed for each inoperable penetration flow path.
Function 9, Suppression Pool Quadrant Water Temperature Each suppression pool water temperature quadrant is treated separately and each quadrant is considered to be a separate function. Therefore, separate Condition entry is allowed for each inoperable quadrant.
2.3 Optional Changes and Variations The changes proposed to the TS of CCNPP, and NMP, Unit 2 are consistent with the changes made to the ISTSs by TSTF-295-A, Revision 0. Detailed below are the administrative variations from the TSTF Traveler compared with the proposed TS changes. The variations are due to individual TS numbering and language. The variations do not affect the applicability of the proposed license amendments to the changes set forth in TSTF-295-A, Revision 0 or the NRC staff's associated approval letter (Reference 5.2).
License Amendment Request to Adopt TSTF-295-A Page 3 of 5 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Variation is due to individual TS Function numbering. The variation is highlighted by bold type below:
Change made to the CEOG STSs Proposed Change to CCNPP TS (NUREG-1432) by TSTF-295-A
- 1. Revises Table 3.3.11-1, Post Accident Revises Table 3.3.10-1, Post-Accident Monitoring Instrumentation, by prefacing Monitoring Instrumentation, by prefacing the title of Function 8, Containment the title of Function 8, Containment Isolation Valve Position, with the phrase Isolation Valve Position, with the phrase Penetration Flow Path. Penetration Flow Path.
- 2. Corresponding changes to TS Bases Corresponding changes to TS Bases Section 3.3.11, Function 8 Section 3.3.10, Function 8 Nine Mile Point Nuclear Station, Unit 2 Variations are due to individual TS numbering and language. The variations are highlighted by bold type below:
Change made to the BWR-6 STSs Proposed Change to NMP, Unit 2 TS (NUREG-1434) by TSTF-295-A
- 1. Revises Table 3.3.3.1-1, Post Accident Revises Table 3.3.3.1-1, Post Accident Monitoring Instrumentation, by prefacing Monitoring Instrumentation, by prefacing the title of Function 8, Containment the title of Function 8, PCIV Position, Isolation Valve Position, with the with the phrase Penetration Flow Path.
phrase Penetration Flow Path.
- 2. Revises Table 3.3.3.1-1, Post Accident Revises Table 3.3.3.1-1, Post Accident Monitoring Instrumentation, by prefacing Monitoring Instrumentation, by revising the title of Function 13, Suppression the title of Function 9 to state, Pool Water Temperature with the Suppression Pool Quadrant Water indication location. Temperature where the suppression pool quadrant is the indication location.
- 3. Corresponding changes to TS Bases Corresponding changes to TS Bases Section 3.3.3.1, Functions 8 and 13 Section 3.3.3.1, Functions 8 and 9
3.0 REGULATORY EVALUATION
3.1 Applicability of Published Safety Evaluation TSTF-295-A, Revision 0 (Reference 5.1) was approved by the NRC in a letter dated December 21, 1999 (Reference 5.2). CEG has reviewed the letter provided to the TSTF as well as the information provided in TSTF-295-A. CEG has concluded that the justifications presented in TSTF-295-A and the approval letter prepared by the NRC staff are applicable to Calvert Cliffs Nuclear Power Plant, Units 1 and 2, and Nine Mile Point Nuclear Station, Unit 2 and justify the proposed amendments for incorporation into the associated Technical Specifications.
License Amendment Request to Adopt TSTF-295-A Page 4 of 5 3.2 No Significant Hazards Consideration Constellation Energy Generation, LLC (CEG), proposes changes to the Technical Specifications (TS), Appendix A of Renewed Facility Operating License Nos. DPR 53 and 69, corresponding to Docket Nos. 50-317 and 50-318, for Calvert Cliffs Nuclear Power Plant (CCNPP), Units 1 and 2 Pressurized Water Reactors (PWRs), respectively, and Renewed Facility Operating License No.
NPF-69, corresponding to Docket No. 50-410 for Nine Mile Point Nuclear Station (NMP), Unit 2 Boiling Water Reactor (BWR).
The proposed changes incorporate NRC-approved Technical Specification Task Force (TSTF)
Improved Standard Technical Specifications Change Traveler TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration, Revision 0 (Reference 5.1). The proposed changes provide clarification that separate condition entry is allowed for each penetration flow path for the Post-Accident Monitoring (PAM) Primary Containment Isolation Valve (PCIV) position indication function (all PWR and BWR plants) and for each suppression pool quadrant water temperature indication function (BWR plants only).
CEG has evaluated whether or not a significant hazards consideration is involved with the proposed amendments by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed changes provide clarification that separate condition entry is allowed for each penetration flow path for the PAM PCIV position indication function (all PWR and BWR plants) and for each Suppression Pool Quadrant Water Temperature indication function (BWR plants only). The proposed changes do not affect any plant equipment, test methods, or plant operation, and are not initiators of any analyzed accident sequence. The actions taken for inoperable PAM channels are not changed. Operation in accordance with the proposed TS will ensure that all analyzed accidents will continue to be mitigated as previously analyzed.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed changes provide clarification that separate condition entry is allowed for each penetration flow path for the PAM PCIV position indication function (all PWR and BWR plants) and for each Suppression Pool Quadrant Water Temperature indication function (BWR plants only). The proposed changes do not involve a physical alteration to the plant (i.e., no new or different type of equipment will be installed) or a change to the methods governing normal plant operation. The changes do not alter the assumptions made in the safety analysis.
License Amendment Request to Adopt TSTF-295-A Page 5 of 5 Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No.
The proposed changes provide clarification that separate condition entry is allowed for each penetration flow path for the PAM PCIV position indication function (all PWR and BWR plants) and for each Suppression Pool Quadrant Water Temperature indication function (BWR plants only). The proposed changes will not affect the operation of plant equipment or the function of any equipment assumed in the accident analysis. The PAM channels will continue to be operable or the existing, appropriate actions will be followed.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
3.3 Conclusions Based on the above, CEG concludes that the proposed amendments present no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
4.0 ENVIRONMENTAL CONSIDERATION
The proposed changes would revise a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed changes do not involve (i) a significant hazards consideration , (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed changes meet the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed changes.
5.1 REFERENCES
5.2 TSTF-295-A, Revision 0, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration, dated July 10, 1998, ADAMS Accession No. ML040620189 5.3 Letter dated December 21, 1999, W.D. Beckner (NRC) to J. Davis (NEI), ADAMS Accession No. ML993630256
ATTACHMENT 2a Markup of Technical Specifications Pages Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. 50-317 and 50-318 Revised Technical Specifications Page 3.3.10-4
PAM Instrumentation 3.3.10 Table 3.3.10-1 (page 1 of 2)
Post-Accident Monitoring Instrumentation CONDITIONS REQUIRED REFERENCED FROM INDICATION REQUIRED ACTION FUNCTION CHANNELS D.1
- 1. Wide Range Logarithmic Neutron Flux 2 E
- 2. Reactor Coolant Outlet Temperature 2 E
- 3. Reactor Coolant Inlet Temperature 2 E
- 4. RCS Subcooled Margin Monitor 1 N/A
- 5. Reactor Vessel Water Level 2 F
- 6. Containment Water Level (wide 2 E range)
- 7. Containment Pressure 2 E
- 8. Containment Isolation Valve 2 per E Position penetration (a)(b)
Penetration Flow Path flow path
- 9. Containment Area Radiation (high 2 F range)
- 10. Pressurizer Pressure (wide range) 2 E E
- 11. Steam Generator Pressure 2 per steam generator
- 12. Pressurizer Level 2 E
- 13. Steam Generator Water Level (wide 2 per steam E range) generator CALVERT CLIFFS - UNIT 1 3.3.10-4 Amendment No. 274 CALVERT CLIFFS - UNIT 2 Amendment No. 251
ATTACHMENT 2b Markup of Technical Specifications Pages Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 NRC Docket No. 50-410 Revised Technical Specifications Page 3.3.3.1-4
PAM Instrumentation 3.3.3.1 Table 3.3.3.1-1 (page 1 of 1)
Post Accident Monitoring Instrumentation CONDITIONS REFERENCED REQUIRED FROM REQUIRED FUNCTION CHANNELS ACTION D.1
- 1. Reactor Vessel Pressure 2 E
- 2. Reactor Vessel Water Level
- a. Fuel Zone Range 2 E
- b. Wide Range 2 E
- 3. Suppression Pool Water Level
- a. Narrow Range 2 E
- b. Wide Range 2 E
- 4. Drywell Pressure
- a. Narrow Range 2 E
- b. Wide Range 2 E
- 5. Drywell Radiation (High Range) 2 F
- 6. Drywell Air Temperature 2 E
- 7. Suppression Chamber Pressure 2 E
- 8. PCIV Position 2 per penetration E Penetration Flow Path flow path(a)(b)
- 9. Suppression Pool Water Temperature 2(c) E Quadrant (a) Not required for isolation valves whose associated penetration flow path is isolated by at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.
(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.
(c) Monitoring each suppression pool quadrant.
NMP2 3.3.3.1-4 Amendment 91, 124
ATTACHMENT 3a Markup of Technical Specifications Bases Pages (For Information Only)
Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. 50-317 and 50-318 Revised Technical Specifications Bases Page B 3.3.10-6
PAM Instrumentation B 3.3.10 BASES the containment flood level and utilize sealed reference legs to sense water level.
- 7. Containment Pressure (wide range) Monitor The containment pressure monitor is provided for verification of RCS and containment OPERABILITY.
Containment pressure instrumentation consists of three containment pressure transmitters with overlapping ranges that provide input to control room indicators.
The trans~itters are located outside the Containment and are nbt subject to a harsh environment.
Penetration Flow Path
- 8. CIV Position Indicator Containment isolation valve position indicators are provided for verification of containment OPERABILITY and integrity.
In the case of CIV position, the important information is the isolation status of the containment penetration.
The LCO requires one channel of valve position indication in the Control Room to be OPERABLE for each active CIV in a containment penetration flow path, i.e., two total channels of CIV position indication for a penetration flow path with two active valves. For containment penetrations with only one active CIV having control room indication, Note (b) requires a single channel of valve position indication to be OPERABLE. This is sufficient to redundantly verify the Each penetration is treated isolation status of each isolable penetration via separately and each indicated status of the active valve, as applicable, penetration flow path is and prior knowledge of passive valve or system boundary considered a separate status. If a penetration flow path is isolated, function. Therefore, separate position indication for the CIV(s) in the associated Condition entry is allowed for penetration flow path is not needed to determine each inoperable penetration status. Therefore, the position indication for valves flow path. in an isolated penetration flow path is not required to be OPERABLE.
The CIV position PAM instrumentation consists of ZL-505, 506, 515, 516, 2080, 2180, 2181, 3832, 3833, 4260, 5291, 5292, 6900, and 6901 (Reference 5).
CALVERT CLIFFS - UNITS 1 & 2 B 3.3.10-6 Revision 19
ATTACHMENT 3b Markup of Technical Specifications Bases Pages (For Information Only)
Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 NRC Docket No. 50-410 Revised Technical Specifications Bases Pages B 3.3.3.1-6 B 3.3.3.1-7
PAM Instrumentation B 3.3.3.1 BASES LCO 7. Suppression Chamber Pressure (continued)
Suppression chamber pressure is a Category I variable provided to determine whether or not reactor depressurization or venting of the primary containment will be required. Suppression chamber pressure is monitored in the control room from two separate pressure transmitters and is continuously displayed on a recorder and an indicator.
The range is from 0 psig to 150 psig. These instruments are the primary indication used by the operator during an accident. Therefore, the PAM Specification deals specifically with this portion of the instrument channel.
Penetration Flow Path
- 8. Primary Containment Isolation Valve (PCIV) Position PCIV (excluding check valves) position is a Category I variable provided for verification of containment integrity.
In the case of PCIV position, the important information is the isolation status of the containment penetration. The LCO requires one channel of valve position indication in the control room to be OPERABLE for each active PCIV in a containment penetration flow path, i.e., two total channels of PCIV position indication for a penetration flow path with two active valves. For containment penetrations with only one active PCIV having control room indication, Note (b) requires a single channel of valve position indication to be Each penetration is treated OPERABLE. This is sufficient to verify redundantly the separately and each isolation status of each isolable penetration via indicated penetration flow path is status of the active valve, as applicable, and prior considered a separate knowledge of passive valve or system boundary status. If a function. Therefore, separate penetration is isolated, position indication for the PCIV(s)
Condition entry is allowed for in the associated penetration flow path is not needed to determine status. Therefore, the position indication for each inoperable penetration valves in an isolated penetration is not required to be flow path. OPERABLE (Note (a)).
The indication for each PCIV is provided at the valve controls in the control room. Each indication consists of green and red indicator lights that illuminate to indicate whether the PCIV is fully open, fully closed, or in a mid-position. Therefore, the PAM Specification deals specifically with this portion of the instrumentation channel.
(continued)
NMP2 B 3.3.3.1-6 Revision 0
PAM Instrumentation B 3.3.3.1 BASES Quadrant LCO 9. Suppression Pool Water Temperature (continued)
Suppression pool water temperature is a Type A and Category I variable provided to detect a condition that could potentially lead to containment breach, and to verify the effectiveness of ECCS actions taken to prevent containment breach. The suppression pool water temperature instrumentation allows operators to detect trends in suppression pool water temperature in sufficient time to take action to prevent steam quenching vibrations in the suppression pool. Eight temperature sensors are arranged in four groups of two independent and redundant channels, located such that there is one group of sensors in each quadrant of the suppression pool. The range of the Each suppression pool suppression pool water temperature channels is from 50ºF to water temperature 250ºF.
quadrant is treated separately and each Thus, four groups of sensors are sufficient to monitor the bulk quadrant is considered average temperature of the suppression pool. The outputs for the to be a separate PAM sensors are monitored on an indicator and two recorders in the control room. One group of sensors provides input only to an function. Therefore, indicator while the other group of sensors provides input to both an separate Condition entry indicator and two recorders, but only the two recorders are required is allowed for each for this group. Both the indicator and the two recorders must be inoperable quadrant. OPERABLE to furnish two channels of PAM indication for each quadrant of the suppression pool. A selector switch is available for the indicator and a different pen recorder for each sensor is available for the two recorders so that each sensor can be monitored. The indicator and recorders are the primary indication used by the operator during an accident. Therefore, the PAM Specification deals specifically with this portion of the instrument channels.
(continued)
NMP2 B 3.3.3.1-7 Revision 0, 7 (A102), 25 (A124)