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MONTHYEARML1009004602010-03-30030 March 2010 Submittal of License Amendment Request, Extension of Completion Time for an Inoperable Diesel Generator - Technical Specification 3.8.1, AC Sources - Operating Project stage: Request ML1011803792010-04-28028 April 2010 Unit No.2 - E-mail from R. Guzman to J. Dosa Acceptance Review for LAR - Inoperable DG 14-Day Completion Time Extension Project stage: Acceptance Review ML1012601662010-05-0606 May 2010 E-mail from R. Guzman to J. Dosa Acceptance Review Revised Questions for License Amendment Requesting 14 Day Completion Time Extension for Inoperable EDG Project stage: Acceptance Review ML1012307272010-05-11011 May 2010 Acceptance Review Determination of License Amendment Request Extension of Completion Time for Inoperable Diesel Generator Project stage: Acceptance Review ML1016004522010-06-0101 June 2010 Submittal of Supplemental Information in Support of License Amendment Extension of Completion Time for an Inoperable Diesel Generator Project stage: Supplement ML1016003832010-06-11011 June 2010 Acceptance Review of License Amendment Request and Supplemental Information Extension of Completion Time for an Inoperable Diesel Generator Project stage: Acceptance Review ML1031302612010-11-0909 November 2010 Request for Additional Information, Extension of Completion Time for Inoperable Diesel Generator, Electrical Engineering Review Project stage: RAI ML1031303272010-12-15015 December 2010 Request for Additional Information Extension of Allowed Outage Time for Inoperable Diesel Generator, Probabilistic Risk Assessment Project stage: RAI ML1101101652010-12-29029 December 2010 Response to NRC Request for Additional Information on License Amendment Request Pursuant to 10 CFR 50.90: Extension of the Completion Time for an Inoperable Diesel Generator Project stage: Response to RAI ML1102502712011-01-14014 January 2011 License Amendment Request Pursuant to 10 CFR 50.90: Extension of the Completion Time for an Inoperable Diesel Generator - Response to NRC Request for Additional Information Project stage: Response to RAI ML1103906562011-02-0808 February 2011 E-mail from R.Guzman to D.Vandeputte - Request for Additional Information Div 3 EDG CT Extension LAR - PRA Review Project stage: RAI ML1105305442011-02-22022 February 2011 E-mail from R. Guzman to D. Vandeputte - Supplemental Request for Additional Information Extension of Completion Time for Inoperable DG Project stage: RAI ML1106704242011-02-25025 February 2011 License Amendment Request Pursuant to 10 CFR 50.90: Extension of the Completion Time for an Inoperable Diesel Generator - Supplemental Information Responding to NRC Follow-up Probabilistic Risk Assessment Review Question Project stage: Supplement ML1107006342011-03-11011 March 2011 E-mail from R. Guzman to S. Som Regarding Supplemental Information from Licensee Regarding License Amendment Request for Completion Time Extension - Division 3 DG Project stage: Other ML1106910202011-03-15015 March 2011 Supplemental Request for Additional Information, Extension of Completion Time for Inoperable Diesel Generator, Electrical Engineering Review Project stage: RAI ML11119A1372011-04-27027 April 2011 License Amendment Request Pursuant to 10 CFR 50.90: Extension of Completion Time for Inoperable Diesel Generator-Supplemental Information Responding to NRC Follow-up Electrical Engineering Branch Review Questions Project stage: Supplement ML1117414582011-06-23023 June 2011 E-mail from R. Guzman to J. Dosa Requesting Supplemental Information Boral Monitoring Program NMP2 Extended Power Uprate LAR Project stage: Other ML1116603882011-07-11011 July 2011 Request for Additional Information, Extension of Completion Time for Inoperable Diesel Generator, Technical Specifications Review Project stage: RAI ML11214A2142011-07-25025 July 2011 License Amendment Request, Extension of the Completion Time for Inoperable Diesel Generator - Response to NRC Request for Additional Information Project stage: Response to RAI ML1122200812011-08-0909 August 2011 E-mail from Alyse Peterson to Richard Guzman NRC Request for State Consultation for Proposed Amendment Regarding Allowed Outage Time Extension for Division 1 or Division 2 Diesel Generator Inoperable Project stage: Request ML1130400692011-10-31031 October 2011 E-mail from R. Guzman to A. Peterson NRC Response to State Comments for Proposed Amendment Regarding Allowed Outage Time Extension for Division 1 or Division 2 Diesel Generator Inoperable Project stage: Other ML1122001552011-10-31031 October 2011 Issuance of Amendment Regarding Extension of Completion Time for Inoperable Division 1 or Division 2 Diesel Generator Project stage: Approval 2011-10-31
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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 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations 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)) 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 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 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 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 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 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 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 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 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums 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 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 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 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 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 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations 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 ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 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 NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined 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 IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[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. 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 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 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 NMP2L2693, Technical Specification Bases, Rev. 572018-10-24024 October 2018 Technical Specification Bases, Rev. 57 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 ML16309A4002016-10-24024 October 2016 Revision 47 to Technical Specification Bases, List of Effective Pages ML16309A4022016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B2.0, Safety Limits (Sls) ML16309A4032016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.0, Limiting Condition for Operation (LCO) Applicability ML16309A4012016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Table of Contents 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 ML16309A4132016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.9, Refueling Operations ML16309A4052016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.2, Power Distribution Limits ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. NMP1L3070, License Amendment Request - Reactivity Anomalies Surveillance2016-03-18018 March 2016 License Amendment Request - Reactivity Anomalies Surveillance NMP2L2592, Supplemental Information Regarding TSTF-425 License Amendment Request2015-09-24024 September 2015 Supplemental Information Regarding TSTF-425 License Amendment Request 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) ML15089A2312015-03-26026 March 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) NMP1L3010, 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)2015-03-26026 March 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 ML12156A3632012-06-0101 June 2012 Emergency License Amendment Request Pursuant to 10 CFR 50.90: Revision of the Main Steam Isolation Valve Allowable Leakage Rate Limit ML11306A2982011-10-27027 October 2011 Submittal of Revision 22 to the Final Safety Analysis Report (Updated), 10 CFR 50.59 Evaluation Summary Report, Technical Specifications Bases Changes, and Report Consistent with 10 CFR 54.37(b) ML11214A2142011-07-25025 July 2011 License Amendment Request, Extension of the Completion Time for Inoperable Diesel Generator - Response to NRC Request for Additional Information 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 ... 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 ML0931602572009-10-26026 October 2009 Submittal of Revision 21 to the Final Safety Analysis Report (Updated), 10 CFR 50.59 Evaluation Summary Report, Technical Specifications Bases Changes, and Report Consistent with 10 CFR 54.37(b) 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 ML0802501622008-01-24024 January 2008 Response to NRC Request for Additional Information Regarding Nine Mile Point Nuclear Station, Unit No. 1, Revision of Rod Worth Minimizer Limiting Condition for Operation During Startup ML0726401032007-09-19019 September 2007 License Amendment Request for Adoption of TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities. ML0721906052007-07-30030 July 2007 Application for Technical Specification Change TSTF-477, Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process ML0721205922007-07-23023 July 2007 Application for Technical Specification Improvement to Adopt TSTF-476, Revison 1, Improved BPWS Control Rod Insertion Process (NEDO-33091), Using the Consolidated Line Item Improvement ML0721205872007-07-23023 July 2007 License Amendment Request Pursuant to 10 CFR 50.90: Revision of Rod Worth Minimizer Limiting Condition for Operation During Startup - Technical Specification Section 3.1.1.b ML0720504232007-07-12012 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 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 ML0707800592007-03-15015 March 2007 Technical Specification 4.1.1 Regarding Control Rod System Surveillance Requirements ML0630406022006-10-19019 October 2006 License Amendment Request Pursuant to 10 CFR 50.90: Revision to Control Rod System Surveillance Requirements - Technical Specification 4.1.1 2023-05-25
[Table view] Category:Bases Change
MONTHYEARML22292A1312022-10-0505 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. 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 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-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 NMP2L2693, Technical Specification Bases, Rev. 572018-10-24024 October 2018 Technical Specification Bases, Rev. 57 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 ML16309A4032016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.0, Limiting Condition for Operation (LCO) Applicability 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 ML16309A4002016-10-24024 October 2016 Revision 47 to Technical Specification Bases, List of Effective Pages ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. NMP1L3070, License Amendment Request - Reactivity Anomalies Surveillance2016-03-18018 March 2016 License Amendment Request - Reactivity Anomalies Surveillance NMP2L2592, Supplemental Information Regarding TSTF-425 License Amendment Request2015-09-24024 September 2015 Supplemental Information Regarding TSTF-425 License Amendment Request ML15089A2312015-03-26026 March 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) NMP1L3010, 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)2015-03-26026 March 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) 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 ML12156A3632012-06-0101 June 2012 Emergency License Amendment Request Pursuant to 10 CFR 50.90: Revision of the Main Steam Isolation Valve Allowable Leakage Rate Limit ML11306A2982011-10-27027 October 2011 Submittal of Revision 22 to the Final Safety Analysis Report (Updated), 10 CFR 50.59 Evaluation Summary Report, Technical Specifications Bases Changes, and Report Consistent with 10 CFR 54.37(b) ML11214A2142011-07-25025 July 2011 License Amendment Request, Extension of the Completion Time for Inoperable Diesel Generator - Response to NRC Request for Additional Information ML0931602572009-10-26026 October 2009 Submittal of Revision 21 to the Final Safety Analysis Report (Updated), 10 CFR 50.59 Evaluation Summary Report, Technical Specifications Bases Changes, and Report Consistent with 10 CFR 54.37(b) ML0802501622008-01-24024 January 2008 Response to NRC Request for Additional Information Regarding Nine Mile Point Nuclear Station, Unit No. 1, Revision of Rod Worth Minimizer Limiting Condition for Operation During Startup ML0726401032007-09-19019 September 2007 License Amendment Request for Adoption of TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities. ML0721906052007-07-30030 July 2007 Application for Technical Specification Change TSTF-477, Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process ML0721205872007-07-23023 July 2007 License Amendment Request Pursuant to 10 CFR 50.90: Revision of Rod Worth Minimizer Limiting Condition for Operation During Startup - Technical Specification Section 3.1.1.b ML0721205922007-07-23023 July 2007 Application for Technical Specification Improvement to Adopt TSTF-476, Revison 1, Improved BPWS Control Rod Insertion Process (NEDO-33091), Using the Consolidated Line Item Improvement ML0720504232007-07-12012 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 ML0630406022006-10-19019 October 2006 License Amendment Request Pursuant to 10 CFR 50.90: Revision to Control Rod System Surveillance Requirements - Technical Specification 4.1.1 ML0236505402002-12-19019 December 2002 License Amendment Request Pursuant to 10 CFR 50.90: Update and Clarification of Shutdown Margin Requirements ML17037C4131977-07-22022 July 1977 Letter Enclosing Application for Amendment to Operating License and Proposed Changes to Technical Specifications Concerning Changes in Management and Organization ML17037C4141977-07-18018 July 1977 Letter Enclosing an Application for Amendment to Operating License and Proposed Changes to the Technical Specifications to Provide for More Flexible Operation and Concerning Load Line Limit Analysis ML17037C4181977-05-19019 May 1977 Letter Enclosing an Application to Amend Operating License and a Requested Change in the Technical Specifications Relating to Instrumentation Used to Monitor Drywell Suppression Chamber Differential Pressure and Suppression .. ML17037C1751975-12-24024 December 1975 Letter Regarding Approved Model Technical Specifications Relating to Hydraulic Snubbers and an Enclosed Copy of Revised Model Technical Specifications and Bases ML17037C2721975-01-21021 January 1975 Letter Transmitting Four Proposed Changes to the Technical Specifications Concerning Changes in Plant Organization and Set Points for Reactor Water Levels ML17037C3331972-04-21021 April 1972 Letter Responding to the March 21, 1972 Letter Requesting Additional Information Regarding Proposed Changes to the Technical Specifications and Bases ML17037C3351971-06-18018 June 1971 Letter Responding to the April 14, 1971 Letter Regarding Change No. 4 to the Technical Specifications and Enclosing a New Printing with Changes No. 1 and 3 and a Number of Additional Changes ML18018B0801969-08-22022 August 1969 Appendix a to Provisional Operating License DPR-17 Technical Specifications and Bases 2022-08-12
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Sam Belcher P.O. Box 63 Vice President-Nine Mile Point Lycoming, New York 13093 315.349.5200 315.349.1321 Fax CENGSM a joint venture of Energy* *' eDF 0 Constellation NINE MILE POINT NUCLEAR STATION July 25, 2011 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
Nine Mile Point Nuclear Station Unit No. 2; Docket No. 50-410 License Amendment Request Pursuant to 10 CFR 50.90: Extension of the Completion Time for an Inoperable Diesel Generator - Response to NRC Request for Additional Information (TAC No. ME3736)
REFERENCES:
(a) Letter from S. Belcher (NMPNS) to Document Control Desk (NRC), dated March 30, 2010, License Amendment Request Pursuant to 10 CFR 50.90:
Extension of the Completion Time for an Inoperable Diesel Generator -
Technical Specification 3.8. 1, AC Sources - Operating (b) Letter from T. A. Lynch (NMPNS) to Document Control Desk (NRC), dated June 1, 2010, License Amendment Request Pursuant to 10 CFR 50.90: Extension of the Completion Time for an Inoperable Diesel Generator - Response to NRC Acceptance Review Comments (TAC No. ME3736)
(c) Letter from R. V. Guzman (NRC) to S. L. Belcher (NMPNS), dated July 11, 2011, Request for Additional Information Regarding Nine Mile Point Nuclear Station, Unit No. 2 - Re: Technical Specification Review for Extension of Completion Time for Inoperable Diesel Generator (TAC No. ME3736)
Nine Mile Point Nuclear Station, LLC (NMPNS) hereby transmits supplemental information requested by the NRC in support of a previously submitted request for amendment to Nine Mile Point Unit 2 (NMP2)
Renewed Operating License NPF-69. The initial request, dated March 30, 2010 (Reference a), as supplemented by Reference (b), proposed to modify Technical Specification (TS) 3.8.1, "AC Sources -
Operating," to extend the Completion Time for an inoperable Division I or Division 2 diesel generator
Document Control Desk July 25, 2011 Page 2 (DG) from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 14 days. The supplemental information, provided in Attachment 1 to this letter, responds to the request for additional information (RAI) documented in the NRC's letter dated July 11, 2011 (Reference c). A revised list of regulatory commitments is provided in Attachment 2. Associated changes to the marked-up TS Bases pages are provided in Attachment 3.
This supplemental information does not affect the No Significant Hazards Determination analysis provided by NMPNS in Reference (a). Pursuant to 10 CFR 50.91(b)(1), NMPNS has provided a copy of this supplemental information to the appropriate state representative.
Should you have any questions regarding the information in this submittal, please contact John J. Dosa, Director Licensing, at (315) 349-5219.
Very truly yours, STATE OF NEW YORK TO WIT:
COUNTY OF OSWEGO I, Sam Belcher, being duly sworn, state that I am Vice President-Nine Mile Point, and that I am duly authorized to execute and file this response on behalf of Nine Mile Point Nuclear Station, LLC. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other Nine Mile Point employees and/or consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.
Subscribed and sworn before me, a Notary Public in and for the State of New York and County of OGS4ej0 ,this 2-!S dayof ,,J't ,2011.
WITNESS my Hand and Notarial Seal: b/,oc44-/a)4w Notary Public My Commission Expires:
Date ft8bhi Ui I2is h dr$Wm onV m lCot Reg ft 0100929220 SB/DEV #4 oumink"as 0hu Ana=$9
i Document Control Desk July 25, 2011 Page 3 Attachments: 1. Nine Mile Point Unit 2 - Response to NRC Request for Additional Information Regarding the Proposed Extension of the Completion Time for an Inoperable Diesel Generator from 72 Hours to 14 Days
- 2. List of Regulatory Commitments
- 3. Changes to Technical Specification Bases (Mark-up) - Revised cc: Regional Administrator, Region I, NRC Project Manager, NRC Resident Inspector, NRC A. L. Peterson, NYSERDA
ATTACHMENT 1 NINE MILE POINT UNIT 2 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PROPOSED EXTENSION OF THE COMPLETION TIME FOR AN INOPERABLE DIESEL GENERATOR FROM 72 HOURS TO 14 DAYS Nine Mile Point Nuclear Station, LLC July 25, 2011
ATTACHMENT 1 NINE MILE POINT UNIT 2 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PROPOSED EXTENSION OF THE COMPLETION TIME FOR AN INOPERABLE DIESEL GENERATOR FROM 72 HOURS TO 14 DAYS By letter dated December 29, 2010, as supplemented by letter dated April 27, 2011, Nine Mile Point Nuclear Station, LLC (NMPNS) responded to NRC Electrical Engineering Branch (EEEB) RAI-4. Also, by letter dated January 14, 2011, NMPNS responded to NRC probabilistic risk assessment (PRA) review RAI-1. Both of these RAIs were concerned with: (1) assurances that the Division 3 (High Pressure Core Spray - HPCS) diesel generator (DG) would be operable during the proposed extended Completion Time (CT) for an inoperable Division 1 or Division 2 DG; and (2) actions that would be taken if the Division 3 DG became inoperable after entering the extended CT.
The NMPNS responses to EEEB RAI-4 and PRA RAI-1 noted that, prior to utilizing the extended CT (greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and up to 14 days), operability of the HPCS system and the Division 3 DG (as required by existing Nine Mile Point Unit 2 (NMP2) Technical Specifications (TS) 3.5.1 and 3.8.1, respectively) would be confirmed, with no planned maintenance or testing activities scheduled. The NMPNS responses also described the TS-required actions that would be taken if the Division 3 DG became inoperable after entering the extended CT for the Division 1 or Division 2 DG. Based on TS 3.8.1 Condition E for two required DGs inoperable (including the associated TS Bases), NMPNS concluded that the longest time that the Division 3 DG could be inoperable prior to initiating a TS-required plant shutdown would be 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br />.
NMPNS has reviewed the TS Review RAI-1, RAI-2, and RAI-3 transmitted by NRC letter dated July 11, 2011. Consistent with discussions between NRC and NMPNS staff members during a conference call on June 22, 2011, these RAIs collectively identify two basic NRC staff concerns, which can be summarized as follows:
A. Justify the propriety of: (1) declaring the HPCS system inoperable at the end of the 24-hour CT specified in TS 3.8.1 Condition E for two required DGs inoperable; and (2) utilizing the 4-hour CT of TS 3.8.1 Condition B.2 for subsequently determining that required redundant features are inoperable. [Reference NRC TS Review RAls 1.a, 1.b, 1.c, 1.d, 2, and 3]
B. The List of Regulatory Commitments associated with the proposed license amendment (described in Attachments 2 and 3 of NMPNS letter dated January 14, 2011) states: "The HPCS system is available and no planned maintenance or testing activities are scheduled." However, the NMPNS response to RAI-1 in the same January 14, 2011 letter states that "operability of the HPCS system and the Division 3 (HPCS) DG will be confirmed ... " Provide the definition for "available" and explain the difference between availability and operability as used in these statements. [Reference NRC TS Review RAI-1 .e]
NMPNS responses for each of the above two identified concerns are provided below.
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ATTACHMENT 1 NINE MILE POINT UNIT 2 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PROPOSED EXTENSION OF THE COMPLETION TIME FOR AN INOPERABLE DIESEL GENERATOR FROM 72 HOURS TO 14 DAYS
- NMPNS Response - Concern A [Reference NRC TS Review RAIs L.a, Lb1.Lc 1.A. 2. and 31 After further consideration, NMPNS is revising the response to EEEB RAI-4 (initially submitted by NMPNS letter dated December 29, 2010, and supplemented by NMPNS letter dated April 27, 2011) and PRA RAI- 1 (initially submitted by NMPNS letter dated January 14, 2011). The revised response, applicable to both of the referenced RAIs, is provided below.
Revised Response - EEEB RAI-4 and PRA RAI-1 As noted in the March 30, 2010 NMPNS submittal, prior to utilizing the extended DG CT (greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and up to 14 days), operability of the HPCS system and the Division 3 (HPCS) DG will be confirmed, with no planned maintenance or testing activities scheduled. This confirmation is a pre-requisite for entering the extended DG CT. The basis for this requirement is the technical evaluation for the proposed license amendment, which credits the capability to utilize the Division 3 DG as an alternate source of AC power as a defense-in-depth feature and credits operability of the HPCS system and the Division 3 DG in the risk assessment.
The TS operability requirements applicable to the HPCS system are contained in TS 3.5.1 for the HPCS system and in TS 3.8.1 for the Division 3 DG. Both the HPCS system and the Division 3 DG are required to be operable in Modes 1, 2, and 3. As specified in TS 3.8.1, if the Division 3 DG became inoperable during the time that the Division 1 or Division 2 DG was already inoperable, Required Action E. 1 would require that the Division 3 DG be restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The NMP2 TS Bases for TS 3.8.1 Condition E (which are essentially identical to the Bases shown in the approved Standard Technical Specifications, NUREG- 1434, Revision 3), state the following regarding the 24-hour CT of TS 3.8.1 Condition E:
"At the end of this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, the Division 3 system (HPCS System) could be declared inoperable (see Applicability Note) and this Condition could be exited with only one required DG remaining inoperable. However, with a Division 1 or 2 DG remaining inoperable and the HPCS declared inoperable, a redundant required feature failure exists, according to Required Action B.2."
[underlining added]
Given the operability confirmations performed prior to entering the extended CT for the Division 1 or Division 2 DG, subsequent discovery of a condition that causes the Division 3 DG to be declared inoperable is not likely. However, if such a situation were to occur, the Division 3 DG must be restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in accordance with TS 3.8.1 Condition E. If the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> CT is not met, TS 3.8.1 Condition F would be entered requiring initiation of a plant shutdown. NMPNS has determined that it would not be appropriate to declare the HPCS system inoperable at the end of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, as indicated by the "could" statements in the TS Bases for TS 3.8.1 Condition E, since:
- The cause for declaring the HPCS system inoperable (i.e., the inoperability of the Division 3 DG) is known and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> would have already been used to evaluate and repair the condition.
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ATTACHMENT 1 NINE MILE POINT UNIT 2 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PROPOSED EXTENSION OF THE COMPLETION TIME FOR AN INOPERABLE DIESEL GENERATOR FROM 72 HOURS TO 14 DAYS
- It would be known ahead of time that declaring the HPCS inoperable will result in the inoperability of redundant required features, according to TS 3.8.1 Condition B, Required Action B.2, and the associated TS Bases. No additional time to make this determination would be needed or warranted.
The existing TS requirements are deemed adequate to limit the time to restore the Division 3 DG to operable status in the event it became inoperable after entering the extended CT for a Division 1 or Division 2 DG. To underscore these TS requirements, and to assure that plant operator training on these requirements occurs as part of the implementation actions for the proposed license amendment request (in accordance with existing NMPNS processes for implementing the TS and procedure changes), the List of Regulatory Commitments associated with the license amendment request is revised to include a commitment consistent with the above discussion, as shown in Attachment 2 to this letter (Commitment No. 2a). The initial sentence of Commitment No. 2 is also revised to state: "Prepare or revise appropriate procedures and training to include..." The underlined portion has been added.
0 NMPNS Response - Concern B [Reference NRC TS Review RAI Le]
The TS term "OPERABLE" is defined in TS Section 1.1 as follows:
"A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s)."
As described in the Bases for TS SR 3.0.1, systems and components are assumed to be OPERABLE when associated Surveillance Requirements specified in the TS have been met.
The term "availability" is used both in the 10 CFR 50.65 ("Maintenance Rule") monitoring process and in the performance indicator (PI) process. NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," describes an approach to meet the requirements of 10 CFR 50.65 that has been endorsed by the NRC in Regulatory Guide 1.160 (with certain provisions and clarifications). Based on the definitions contained in Appendix B of NUMARC 93-01, a structure, system, or component (SSC) is available if it is capable of performing its intended function(s).
Availability of a SSC includes consideration of established success criteria and mission times. The baseline PRA used to perform the risk evaluation for the proposed extension of the CT for an inoperable Division I or Division 2 DG uses plant operating data gathered in accordance with the requirements of 10 CFR 50.65 to establish the availability and reliability of plant SSCs that are modeled in the PRA. Since the configuration risk management controls itemized in the List of Regulatory Commitments for the proposed license amendment were derived from the risk evaluation, they were composed using the "available" term rather than OPERABLE.
Nuclear Energy Institute document NEI 99-02, "Regulatory Assessment Performance Indicator Guideline," provides definitions and guidance for the purpose of reporting performance indicator data as 3 of 4
ATTACHMENT 1 NINE MILE POINT UNIT 2 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PROPOSED EXTENSION OF THE COMPLETION TIME FOR AN INOPERABLE DIESEL GENERATOR FROM 72 HOURS TO 14 DAYS part of the NRC power reactor licensee assessment process. NRC Inspection Manual Chapter 0608 notes that NEI 99-02 is jointly produced by the NRC and NEI. As stated in NEI 99-02, a system or component that is considered to be OPERABLE is also considered to be available; however, the opposite may not be true.
To eliminate any potential uncertainty regarding application of the configuration risk management controls, NMPNS is revising the List of Regulatory Commitments associated with the license amendment request by replacing "available" with "operable" for those systems and components that are required by the TS; i.e., the HPCS system, the reactor core isolation cooling (RCIC) system, the Division 1 and Division 2 residual heat removal (RHR) pumps, the low pressure core spray (LPCS) pump, the redundant reactivity control system, and the standby liquid control system. The revised List of Regulatory Commitments is provided in Attachment 2 to this letter. The TS Bases changes that were included in the January 14, 2011 NMPNS submittal (Attachment 3, INSERT B for TS Bases page B 3.8.1-10) are also revised in a similar manner, as shown in Attachment 3 to this letter. This change in terminology does not have any impact on the risk evaluations that have been performed to support the proposed license amendment.
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ATTACHMENT 2 LIST OF REGULATORY COMMITMENTS Nine Mile Point Nuclear Station, LLC July 25, 2011
ATTACHMENT 2 LIST OF REGULATORY COMMITMENTS The following table is an update to the list of regulatory commitments that was originally provided in Attachment I of the Nine Mile Point Nuclear Station, LLC (NMPNS) letter dated March 30, 2010 and subsequently revised in Attachment 2 of the NMPNS letter dated January 14, 2011. Any other statements in this submittal represent intended or planned actions. They are provided for information purposes and are not considered to be regulatory commitments.
SCHEDULED REGULATORY COMMITMENT COMPLETION DATE
- 1. Complete the modification and associated implementing procedures to 90 days following provide the Division 3 diesel generator (DG) with a source of backup cooling NRC approval of the water from the fire protection water supply system and its associated diesel- license amendment driven fire water pumps. request. [Completed]
- 2. Prepare or revise appropriate procedures and training to include provisions 90 days following for implementing compensatory measures and configuration risk NRC approval of the management controls when entering an extended DG completion time (CT) license amendment (greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and up to 14 days), including the following: request.
- a. The other two DGs are operable and no planned maintenance or testing activities are scheduled on those two DGs. Should the Division 3 DG become inoperable after entering the extended DG CT, plant shutdown will be initiated if the Division 3 DG cannot be restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (unless the applicable TS Condition is exited by restoring the Division I or Division 2 DG to operable status).
- b. No planned maintenance or testing activities are scheduled in Scriba Substation, the Nine Mile Point Unit 2 (NMP2) 115 kV switchyard, or on the 115 kV power supply lines and transformers which could cause a line outage or challenge offsite power availability.
- c. The high pressure core spray (HPCS) system is operable and no planned maintenance or testing activities are scheduled.
- d. The reactor core isolation cooling (RCIC) system is operable and no planned maintenance or testing activities are scheduled.
- e. The NMP2 and Nine Mile Point Unit 1 (NMPl) diesel-driven fire pumps and the cross-tie between the NMP2 and NMP 1 fire protection water supply systems are available to provide a backup cooling water supply to the Division 3 DG and no planned maintenance or testing activities are scheduled.
- f. The Division 1 and Division 2 residual heat removal (RHR) pumps and the low pressure core spray (LPCS) pump are operable and no planned maintenance or testing activities are scheduled.
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ATTACHMENT 2 LIST OF REGULATORY COMMITMENTS SCHEDULED REGULATORY COMMITMENT COMPLETION DATE
- g. Both divisions of the redundant reactivity control system and the standby I liquid control system (equipment required for mitigation of anticipated transients without scram (ATWS) events) are operable and no planned maintenance or testing activities are scheduled.
- h. The stability of existing and projected grid conditions will be confirmed prior to planned entry into the extended DG CT by contacting the transmission system operator (TSO).
- i. Operating crews will be briefed on the DG work plan. As a minimum, the briefing will include the following important procedural actions that could be required in the event a loss of offsite power (LOOP), station blackout (SBO), or fire condition occurs:
- Alignment of the fire protection water supply system to provide cooling water to the Division 3 DG.
- Establishing the cross-connection to allow the Division 3 DG to power either Division 1 or Division 2 loads.
- Utilizing the portable generator as a backup source of AC power to one of the Division 1 or Division 2 battery chargers.
- Utilizing the portable power supplies to maintain operability of the safety relief valves (SRVs).
- Closing containment isolation valves in the drywell floor drain and equipment drain lines.
- j. The extended DG CT will not be entered for planned maintenance if severe weather conditions (high winds, tornado, or heavy snow/ice) with the potential to degrade or limit offsite power availability are present, or if official weather forecasts are predicting such conditions to occur.
- k. Except for the room housing the inoperable DG, no hot work permits will be active for the control building or the normal switchgear rooms.
- 1. A portable generator is available as a temporary backup source of AC power to one of the Division 1 or Division 2 battery chargers and is pre-staged within the protected area near the NMP2 control building.
- m. Four portable power supplies are available for use to facilitate operation of safety relief valves to maintain RPV pressure control for an extended SBO condition and are verified to be functional.
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ATTACHMENT 3 CHANGES TO TECHNICAL SPECIFICATION BASES (MARK-UP)
REVISED The mark-up for NMP2 Technical Specification Bases page B 3.8.1-10, previously provided in of the January 14, 2011 NMPNS submittal, is revised. Specifically, the list of compensatory measures and configuration risk management controls in "INSERT B" is modified. This Bases page is provided for information only.
Nine Mile Point Nuclear Station, LLC July 25, 2011
AC Sources-Operating B 3.8.1 BASES ACTIONS B.2 (continued) required feature. Additionally, the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time takes into account the capacity and capability of the remaining AC sources,-reasonable time for repairs, and low probability of a DBA occurring during this period.
B.3.1 and B.3.2 Required Action B.3.1 provides an allowance to avoid unnecessary testing of OPERABLE DGs. If it can be determined that the cause of the inoperable DG does not exist on the OPERABLE DG(s), SR 3.8.1.2 does not have to be performed. If the cause of inoperability exists on other DGs, the other DGs are declared inoperable upon discovery, and Condition E or G of LCO 3.8.1 is entered, as applicable.
Once the failure is repaired, and the common cause failure no longer exists, Required Action B.3.1 is satisfied. If the cause of the initial inoperable DG cannot be confirmed not to exist on the remaining DG(s), performance of SR 3.8.1.2 suffices to provide assurance of continued OPERABILITY of those DG(s).
In the event the inoperable DG is restored to OPERABLE status prior to completing either B.3.1 or B.3.2, the Deficiency Event Report Program will continue to evaluate the common cause possibility. This continued evaluation, however, is no longer under the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> constraint imposed while in Condition B.
According to Generic Letter 84-15 (Ref. 9), 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is reasonable time to confirm that the OPERABLE DG(s) are not affected by the same problem as the inoperable DG.
B.4 I *ninuein ~ndi 11*B fur d period tha - Id(,-
17L
_... In6 g
- the remaining OPERABLE DGs and i 51 e circuits are adequate to supply electrical power to the onsite Class 1E distribution system. 'The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> yser Completion Time takes into account the capacity and capability of the remaining AC sources, a reasonable time for repairs, and the low probability of a DBA occurring during this period. I,--- ( rontinued )
NMP2 B 3.8.1-10 Revision *1_3
INSERT A (for TS Bases page B 3.8.1-10) [Unchanged]
Although Condition B applies to a single inoperable DG, several Completion Times are specified for this Condition.
The first Completion Time applies to an inoperable Division 3 DG.
INSERT B (for TS Bases page B 3.8.1-10) [Revised]
This Completion Time begins only "upon discovery of an inoperable Division 3 DG" and, as such, provides an exception to the normal "time zero" for beginning the allowed outage time "clock" (i.e., for beginning the clock for an inoperable Division 3 DG when Condition B may have already been entered for another equipment inoperability and is still in effect).
The second Completion Time (14 days) applies to an inoperable Division 1 or Division 2 DG and is a risk-informed Completion Time based on a plant-specific risk analysis. The extended Completion Time would typically be used for voluntary planned maintenance or inspections but can also be used for corrective maintenance. However, use of the extended Completion Time for voluntary planned maintenance should be limited to once within an operating cycle (24 months) for each DG (Division 1 and Division 2). When utilizing an extended DG Completion Time (greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and up to 14 days), the compensatory measures and configuration risk management controls listed below shall be implemented. For planned maintenance utilizing an extended Completion Time, these measures and controls shall be implemented prior to entering Condition B. For an unplanned entry into an extended Completion Time, these measures and controls shall be implemented without delay.
- 1. The other two DGs are operable and no planned maintenance or testing activities are scheduled on those two DGs.
- 2. No planned maintenance or testing activities are scheduled in Scriba Substation, the NMP2 115 kV switchyard, or on the 115 kV power supply lines and transformers which could cause a line outage or challenge offsite power availability.
- 3. The HPCS system is operable and no planned maintenance or testing activities are scheduled.
- 4. The RCIC system is operable and no planned maintenance or testing activities are scheduled.
- 5. The NMP2 and NMP1 diesel-driven fire pumps and the cross-tie between the NMP2 and NMP 1 fire protection water supply systems are available to provide a backup cooling water supply to the Division 3 DG and no planned maintenance or testing activities are scheduled.
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INSERT B (continued)
- 6. The Division 1 and Division 2 residual heat removal (RHR) pumps and the low pressure core spray (LPCS) pump are operable and no planned maintenance or testing activities are scheduled.
- 7. Both divisions of the redundant reactivity control system and the standby liquid control system (equipment required for mitigation of anticipated transients without scram (ATWS) events) are operable and no planned maintenance or testing activities are scheduled.
- 8. The stability of existing and projected grid conditions will be confirmed prior to planned entry into the extended DG CT by contacting the transmission system operator (TSO).
- 9. Operating crews will be briefed on the DG work plan. As a minimum, the briefing will include the important procedural actions that could be required in the event a LOOP, SBO, or fire condition occurs.
- 10. The extended DG CT will not be entered for planned maintenance if severe weather conditions (high winds, tornado, or heavy snow/ice) with the potential to degrade or limit offsite power availability are present, or if official weather forecasts are predicting such conditions to occur.
- 11. Except for the room housing the inoperable DG, no hot work permits will be active for the control building or the normal switchgear rooms.
- 12. A portable generator is available as a temporary backup source of AC power to one of the Division 1 or Division 2 battery chargers and is pre-staged within the protected area near the NMP2 control building.
- 13. Four portable power supplies are available for use to facilitate operation of safety relief valves to maintain RPV pressure control for an extended SBO condition and are verified to be functional.
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