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MONTHYEARML0134403382002-01-11011 January 2002 Issuance of Amendment 263 Changes to TS Definitions for Core Alteration & Refueling Operations (Tac No. MB1779) Project stage: Approval ML0201103752002-01-11011 January 2002 Technical Specifications Pages for Amendment 263 Changes to TS Definitions for Core Alteration & Refueling Operations Project stage: Other 2002-01-11
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Category:Letter
MONTHYEARIR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) IR 05000336/20244402024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) ML24004A1052024-01-0404 January 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010 ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23352A0202023-12-18018 December 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23334A2242023-11-30030 November 2023 Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation ML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23317A2702023-11-13013 November 2023 Core Operating Limits Report, Cycle 23 IR 05000336/20230032023-11-0606 November 2023 Integrated Inspection Report 05000336/2023003 and 05000423/2023003 ML23298A1652023-10-26026 October 2023 Requalification Program Inspection IR 05000336/20234202023-10-0404 October 2023 Security Inspection Report 05000336/2023420 and 05000423/2023420 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis IR 05000245/20230012023-09-19019 September 2023 Safstor Inspection Report 05000245/2023001 IR 05000336/20230102023-09-0808 September 2023 Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010 IR 05000336/20230052023-08-31031 August 2023 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005) ML23248A2132023-08-30030 August 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature. 2024-08-06
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures ML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML23058A4542023-03-16016 March 2023 Issuance of Amendment Nos. 345 and 285 Regarding Adoption of Technical Specification Task Force-359, Increase Flexibility in Mode Restraints ML23005A1702023-01-17017 January 2023 Correction to Issuance of Amendment No. 283 to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definition ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD ML22041A0102022-03-0101 March 2022 V.C. Summer 1, Issuance of Amendment Nos. 283 (Millstone), 291 and 274 (North Anna), and 221 (Summer) to Revise TSs to Adopt TSTF-569 Revision of Response Time Testing Definition ML22007A1512022-02-16016 February 2022 Issuance of Amendment No. 282 Regarding Shutdown Bank Technical Specification Requirements and Alternate Control Rod Position Monitoring Requirements ML21326A0992022-01-0707 January 2022 Issuance of Amendment No. 281 Regarding Revised Reactor Core Safety Limit to Reflect Topical Report WCAP-177642-P-A, Revision 1 ML21262A0012021-11-0909 November 2021 Issuance of Amendment No. 280 Regarding Measurement Uncertainty Recapture Power Uprate ML21227A0002021-10-0505 October 2021 Issuance of Amendment No. 279 Regarding Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss-of-Coolant Accident ML21222A2302021-09-0909 September 2021 Issuance of Amendment No. 343 Revision to Technical Specifications for Steam Generator Inspection Frequency (L-2020-LLA-0227) ML21043A1622021-03-25025 March 2021 Issuance of Amendment No. 278 Regarding Revision to Battery Surveillance Requirements ML21026A1422021-02-23023 February 2021 Issuance of Amendment No. 342 Revision to Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20275A0002020-10-14014 October 2020 Issuance of Amendment No. 277 to Revise Technical Specification 6.8.4.g to Allow a One-Time Deferral of the Steam Generator Inspections ML20237H9952020-09-29029 September 2020 Issuance of Amendment No. 341 Revision to Technical Specification 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program ML20191A0042020-08-0707 August 2020 Issuance of Amendment No. 340 Revised Technical Specification Limits for Primary and Secondary Coolant Activity ML20161A0002020-07-15015 July 2020 Issuance of Amendment No. 276 Regarding Revision to the Integrated Leak Rate Type a and Type C Test Intervals ML20140A3692020-06-24024 June 2020 Issuance of Amendment No. 339 Extension of Technical Specification 3.8.1.1, A.C. Sources - Operating, Allowed Outage Time ML19340A0252020-01-30030 January 2020 Issuance of Amendment No. 337 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components of Nuclear Power Reactors ML19305D2482019-12-31031 December 2019 Issuance of Amendments Adoption of Emergency Action Level Schemes Per NEI 99-01, Rev. 6 ML19150A3672019-05-30030 May 2019 Current Facility Operating License No. DPR-21, Tech Specs, Revised 5/30/2019 ML19126A0002019-05-28028 May 2019 Issuance of Amendment No. 273 Regarding Technical Specification Changes for Spent Fuel Storage and New Fuel Storage ML19042A2772019-03-21021 March 2019 Issuance of Amendment No. 272 Regarding Revision to Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels ML18246A0072018-09-25025 September 2018 Issuance of Amendment No. 335 Regarding Revision to the Integrated Leak Rate Type a and Type C Test Intervals ML18038B2002018-02-26026 February 2018 Issuance of Amendment Nos. 118, 334, and 271 to Revise Licensee'S Name (CAC Nos. MF9844, MF9845, and MF9848; EPID L-2017-LLA-0245 and EPID L-2017-LLA-0346) ML17025A2182017-01-24024 January 2017 Issuance of Amendment Realistic Large Break Loss-of-Coolant Accident Analysis ML16308A4852016-12-22022 December 2016 Issuance of Amendment No. 331 Revision to Emergency Core Cooling System Technical Specification and Final Safety Analysis Report Ch. 14 to Remove Charging ML16249A0012016-09-30030 September 2016 Issuance of Amendments Small Break Loss of Coolant Accident Reanalysis ML16206A0012016-08-0404 August 2016 Issuance of Amendment No. 270 to Revise Technical Specification 5.6.3, Fuel Storage Capacity ML16131A7282016-07-28028 July 2016 Issuance of Amendment 268 Adopting Dominion Core Design and Safety Analysis Methods and Addressing the Issues Identified in Three Westinghouse Communication Documents ML16193A0012016-07-28028 July 2016 Issuance of Amendments Removal of Severe Line Outage Detection from the Offsite Power System ML16189A0762016-06-29029 June 2016 Supplement to Information Regarding License Amendment Request for Removal of Severe Line Outage Detection from the Offsite Power System ML16003A0082016-06-23023 June 2016 Issuance of Amendment No. 327 Proposed Technical Specification Changes for Spent Fuel Storage ML16068A3122016-03-31031 March 2016 Issuance of Amendment No. 326 to Revise Technical Specifications for Containment Leak Rate Testing ML16011A4002016-01-29029 January 2016 Issuance of Amendments Nos. 325 and 267 to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML15288A0042015-11-30030 November 2015 Issuance of Amendment No. 266: Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation Test Times and Completion Times ML15280A2422015-10-29029 October 2015 Issuance of Amendment No. 324 Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program, Adoption of TSTF-425,Rev 3 ML15245A4822015-10-0707 October 2015 Millstone Power Station, Surry Power Station, and North Anna Power Station - Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML15225A0102015-08-28028 August 2015 Issuance of Amendment No. 264 Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves ML15246A1422015-08-27027 August 2015 Connecticut, Inc. Millstone Power Station Unit 3 Supplement to License Amendment Request to Revise Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves ML15225A0082015-08-26026 August 2015 Issuance of Amendment No. 322 Revision to the Final Safety Analysis Report - Examination Requirements for ANSI B31.1.0 Piping Welds ML15187A3262015-07-29029 July 2015 Issuance of Amendment No. 321, Adoption of TSTF-426, Revision 5, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C ML15187A1862015-07-28028 July 2015 Issuance of Amendment No. 263, Regarding Technical Specification Changes to Auxiliary Feedwater System (MF4692) ML15187A0112015-07-27027 July 2015 Issuance of Amendment No. 262, Refueling Water Storage Tank Allowable Temperatures ML15093A0022015-05-20020 May 2015 Issuance of Amendment No. 320, Delete Technical Specification Index and Make Other Editorial and Administrative Changes ML15098A0342015-05-20020 May 2015 Issuance of Amendment No. 261, Delete Technical Specification Index and Make Other Editorial and Administrative Changes ML15093A4412015-05-18018 May 2015 Issuance of Amendment No. 319, Use of Areva M5 Alloy Clad Fuel Assemblies ML14178A5992014-07-11011 July 2014 Issuance of Amendment Proposed Changes to Technical Specification 3/4 7.5, Ultimate Heat Sink (Tac MF1780) 2024-06-04
[Table view] Category:Safety Evaluation
MONTHYEARML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML23058A4542023-03-16016 March 2023 Issuance of Amendment Nos. 345 and 285 Regarding Adoption of Technical Specification Task Force-359, Increase Flexibility in Mode Restraints ML21320A0072022-09-0707 September 2022 Review of Appendix E to DOM-NAF-2, Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code (EPID L-2021-LLT-0000) (Non-Proprietary) ML22201A5082022-07-28028 July 2022 Authorization and Safety Evaluation for Alternative Request No. IR-04-09 ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD ML22039A3392022-03-0303 March 2022 Request for Alternative Frequency to Supplemental Valve Position Verification Testing Requirements in the Fourth 10-year Valve Inservice Testing Program ML22041A0102022-03-0101 March 2022 V.C. Summer 1, Issuance of Amendment Nos. 283 (Millstone), 291 and 274 (North Anna), and 221 (Summer) to Revise TSs to Adopt TSTF-569 Revision of Response Time Testing Definition ML22007A1512022-02-16016 February 2022 Issuance of Amendment No. 282 Regarding Shutdown Bank Technical Specification Requirements and Alternate Control Rod Position Monitoring Requirements ML21326A0992022-01-0707 January 2022 Issuance of Amendment No. 281 Regarding Revised Reactor Core Safety Limit to Reflect Topical Report WCAP-177642-P-A, Revision 1 ML21262A0012021-11-0909 November 2021 Issuance of Amendment No. 280 Regarding Measurement Uncertainty Recapture Power Uprate ML21284A0062021-10-29029 October 2021 Authorization and Safety Evaluation for Alternative Request No. RR-05-04 and IR-4-02 ML21227A0002021-10-0505 October 2021 Issuance of Amendment No. 279 Regarding Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss-of-Coolant Accident ML21222A2302021-09-0909 September 2021 Issuance of Amendment No. 343 Revision to Technical Specifications for Steam Generator Inspection Frequency (L-2020-LLA-0227) ML21174A0202021-08-0202 August 2021 Relief Request for Limited Coverage Examinations Performed in the Fourth 10-Year Inservice Inspection Interval ML21167A3552021-07-16016 July 2021 Authorization and Safety Evaluation for Alternative Request No. RR-05-06 ML21167A2112021-06-30030 June 2021 Relief Request for Limited Coverage Examinations Performed in the Third 10-Year Inservice Inspection Interval (EPID L-2020-LLR-0081 Through L-2020-LLR-0088) ML21075A0452021-03-26026 March 2021 Request to Utilize Code Case N-885 ML21043A1622021-03-25025 March 2021 Issuance of Amendment No. 278 Regarding Revision to Battery Surveillance Requirements ML21026A1422021-02-23023 February 2021 Issuance of Amendment No. 342 Revision to Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20312A0022020-12-10010 December 2020 Relief Request for Limited Coverage Examinations Performed in the Third 10-Year Inservice Inspection Interval (EPID L-2020-LLR-0027 Through L-2020-LLR-0032) ML20312A0012020-12-10010 December 2020 Relief Requests for Limited Coverage Examinations Performed in the Fourth 10-Year Inservice Inspection Interval ML20287A4712020-10-20020 October 2020 Proposed Alternative RR-05-05 to the Requirements of the ASME Code Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML20275A0002020-10-14014 October 2020 Issuance of Amendment No. 277 to Revise Technical Specification 6.8.4.g to Allow a One-Time Deferral of the Steam Generator Inspections ML20237H9952020-09-29029 September 2020 Issuance of Amendment No. 341 Revision to Technical Specification 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program ML20252A0072020-09-15015 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI ML20191A0042020-08-0707 August 2020 Issuance of Amendment No. 340 Revised Technical Specification Limits for Primary and Secondary Coolant Activity ML20189A2062020-07-16016 July 2020 Relief Request IR-4-03 Concerning Non-Code Methodology to Demonstrate Structural Integrity of Class 3 Moderate-Energy Piping ML20161A0002020-07-15015 July 2020 Issuance of Amendment No. 276 Regarding Revision to the Integrated Leak Rate Type a and Type C Test Intervals ML20140A3692020-06-24024 June 2020 Issuance of Amendment No. 339 Extension of Technical Specification 3.8.1.1, A.C. Sources - Operating, Allowed Outage Time ML20080K5082020-03-24024 March 2020 Alternative Request RR-05-03 for the Fifth 10-Year Inservice Inspection Interval ML19340A0252020-01-30030 January 2020 Issuance of Amendment No. 337 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components of Nuclear Power Reactors ML19305D2482019-12-31031 December 2019 Issuance of Amendments Adoption of Emergency Action Level Schemes Per NEI 99-01, Rev. 6 ML19338G3722019-12-18018 December 2019 Alternative Requests RR-05-01 and RR-05-02 for the Fifth 10-Year Inservice Inspection Interval ML19340A0012019-12-18018 December 2019 Proposed Alternative Request IR-4-01 Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML19340A0002019-12-13013 December 2019 Relief Request IR-3-39, Proposed Alternative to ASME Code Weld Preheat Requirements ML19126A0002019-05-28028 May 2019 Issuance of Amendment No. 273 Regarding Technical Specification Changes for Spent Fuel Storage and New Fuel Storage ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML19042A2772019-03-21021 March 2019 Issuance of Amendment No. 272 Regarding Revision to Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels ML18290A6022018-11-13013 November 2018 Alternative Requests Related to the Fifth and Fourth 10-Year Interval Pump, Valve, and Snubber Inservice Testing Programs, Respectively (EPID L-2018-LLR- 0012 Through EPID L-2018-LLR-0022) ML18275A0122018-10-0404 October 2018 Alternative Request P-06 for the 'C' Charging Pump Test Frequency ML18246A0072018-09-25025 September 2018 Issuance of Amendment No. 335 Regarding Revision to the Integrated Leak Rate Type a and Type C Test Intervals ML18252A0032018-09-17017 September 2018 Alternative Requests RR-04-27 and IR-3-38 for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography 2024-06-04
[Table view] Category:Technical Specifications
MONTHYEARML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures ML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML21280A3282021-10-0707 October 2021 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions ML20275A0002020-10-14014 October 2020 Issuance of Amendment No. 277 to Revise Technical Specification 6.8.4.g to Allow a One-Time Deferral of the Steam Generator Inspections ML20237H9952020-09-29029 September 2020 Issuance of Amendment No. 341 Revision to Technical Specification 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program ML20261H5982020-09-17017 September 2020 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20191A0042020-08-0707 August 2020 Issuance of Amendment No. 340 Revised Technical Specification Limits for Primary and Secondary Coolant Activity ML19126A0002019-05-28028 May 2019 Issuance of Amendment No. 273 Regarding Technical Specification Changes for Spent Fuel Storage and New Fuel Storage ML19042A2772019-03-21021 March 2019 Issuance of Amendment No. 272 Regarding Revision to Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels ML18100A0552018-04-0404 April 2018 License Amendment Request to Revise Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels ML17038A0062017-02-0101 February 2017 Technical Specifications 2016 Annual Report ML17025A2182017-01-24024 January 2017 Issuance of Amendment Realistic Large Break Loss-of-Coolant Accident Analysis ML16354A4242016-12-14014 December 2016 License Amendment Request to Revise Technical Specification Surveillance Requirement 4.1.3.1.2 for Control Element Assembly 39 for the Remainder of Cycle 24 ML16208A0512016-07-26026 July 2016 Clean Technical Specifications (TS) Pages for Millstone Power Station 1 (Docket No. 05000245), Administrative Changes for TS (L53121) ML16068A3122016-03-31031 March 2016 Issuance of Amendment No. 326 to Revise Technical Specifications for Containment Leak Rate Testing ML16011A4002016-01-29029 January 2016 Issuance of Amendments Nos. 325 and 267 to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML15288A0042015-11-30030 November 2015 Issuance of Amendment No. 266: Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation Test Times and Completion Times ML15280A2422015-10-29029 October 2015 Issuance of Amendment No. 324 Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program, Adoption of TSTF-425,Rev 3 ML15245A4822015-10-0707 October 2015 Millstone Power Station, Surry Power Station, and North Anna Power Station - Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML15225A0102015-08-28028 August 2015 Issuance of Amendment No. 264 Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves ML15225A0082015-08-26026 August 2015 Issuance of Amendment No. 322 Revision to the Final Safety Analysis Report - Examination Requirements for ANSI B31.1.0 Piping Welds ML15187A3262015-07-29029 July 2015 Issuance of Amendment No. 321, Adoption of TSTF-426, Revision 5, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C ML15187A1862015-07-28028 July 2015 Issuance of Amendment No. 263, Regarding Technical Specification Changes to Auxiliary Feedwater System (MF4692) ML15187A0112015-07-27027 July 2015 Issuance of Amendment No. 262, Refueling Water Storage Tank Allowable Temperatures ML15209A7292015-07-21021 July 2015 Response to Second Request for Additional Information Regarding Proposed Technical Specification Change for Spent Fuel Storage ML15098A0342015-05-20020 May 2015 Issuance of Amendment No. 261, Delete Technical Specification Index and Make Other Editorial and Administrative Changes ML15093A0022015-05-20020 May 2015 Issuance of Amendment No. 320, Delete Technical Specification Index and Make Other Editorial and Administrative Changes ML15093A4412015-05-18018 May 2015 Issuance of Amendment No. 319, Use of Areva M5 Alloy Clad Fuel Assemblies ML15044A0442015-02-0909 February 2015 Revised Response to Request for Additional Information Regarding License Amendment Request for Proposed Technical Specification Changes of the Refueling Water Storage Tank Allowable Temperatures ML15021A1282015-01-15015 January 2015 Proposed License Amendment Requests to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML14301A1122014-10-22022 October 2014 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 ML14154A0912014-05-28028 May 2014 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.5, Ultimate Heat Sink. ML14073A0552014-04-0808 April 2014 Issuance of Amendment Calculated Containment Internal Pressure ML13346A7672013-12-18018 December 2013 Correction Letter to License Amendment Nos. 256 and 257 ML13155A1402013-05-28028 May 2013 Response to Request for Additional Information Regarding Proposed Technical Specifications Changes for Spent Fuel Storage ML13133A0332013-05-0303 May 2013 License Amendment Request for Changes to Technical Specification 3/4.7.11, Ultimate Heat Sink. ML13133A0322013-05-0303 May 2013 License Amendment Request for Changes to Technical Specification 3/4.7.5 Ultimate Heat Sink. ML12284A2132012-10-0404 October 2012 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 ML12250A6642012-08-28028 August 2012 Correction to Proposed Technical Specifications to Adopt TSTF-510 ML12219A0732012-07-31031 July 2012 Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process ML12220A0122012-07-31031 July 2012 Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process ML12202A0402012-07-17017 July 2012 License Amendment Request Regarding Removal of a License Condition, Proposed Technical Specifications Bases Change and FSAR Change for Ultimate Heat Sink Temperature Measurement ML12110A1142012-04-12012 April 2012 License Amendment Request for Permanent Alternate Repair Criteria for Steam Generator Tube Inspection and Repair ML12097A2002012-04-0202 April 2012 License Amendment Request to Revise Snubber Surveillance Requirements ML12032A2242012-01-25025 January 2012 License Amendment Request to Relocate TS Surveillance Frequencies to License Controlled Program in Accordance with TSTF-425, Revision 3 ML11329A0032011-11-17017 November 2011 Proposed License Amendment and Exemption Request for Use of Optimized Zirlo Rod Cladding ML11193A2242011-07-0505 July 2011 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3, Attachment 3 Through Attachment 6, Marked-up TS Pages and TS Bases Pages ML11193A2232011-07-0505 July 2011 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3, Attachment 1 Through Attachment 3, Marked-up TS Page Changes 3/4 6-22 ML1102802082011-01-20020 January 2011 License Amendment Request to Revise Technical Specification (TS) 6.8.4.g, Steam Generator (SG) Program, and TS 6.9.1.7, Steam Generator Tube Inspection Report for Temporary Alternate Repair Criteria (H*) 2024-06-04
[Table view] |
Text
January 11, 2002 Mr. J. A. Price Vice President - Nuclear Technical Services - Millstone Dominion Nuclear Connecticut, Inc.
c/o Mr. David A. Smith Rope Ferry Road Waterford, CT 06385
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE: CHANGES TO TECHNICAL SPECIFICATION DEFINITIONS FOR CORE ALTERATION AND REFUELING OPERATIONS (TAC NO. MB1779)
Dear Mr. Price:
The Commission has issued the enclosed Amendment No. 263 to Facility Operating License No. DPR-65 for the Millstone Nuclear Power Station, Unit No. 2, in response to your application dated April 11, 2001, as supplemented September 26 and November 16, 2001.
The amendment revises Technical Specifications 1.12, Core Alteration; 3.9.1, Refueling Operations - Boron Concentration; 3.9.2, Refueling Operations - Instrumentation; and 3.9.11, Refueling Operations - Water Level - Reactor Vessel. The amendment also revises the Technical Specifications Bases to reflect the changes to the definitions.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
John T. Harrison, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-336
Enclosures:
- 1. Amendment No. 263 to DPR-65
- 2. Safety Evaluation cc w/encls: See next page
January 11, 2002 Mr. J. A. Price Vice President - Nuclear Technical Services - Millstone Dominion Nuclear Connecticut, Inc.
c/o Mr. David A. Smith Rope Ferry Road Waterford, CT 06385
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE: CHANGES TO TECHNICAL SPECIFICATION DEFINITIONS FOR CORE ALTERATION AND REFUELING OPERATIONS (TAC NO. MB1779)
Dear Mr. Price:
The Commission has issued the enclosed Amendment No. 263 to Facility Operating License No. DPR-65 for the Millstone Nuclear Power Station, Unit No. 2, in response to your application dated April 11, 2001, as supplemented September 26 and November 16, 2001.
The amendment revises Technical Specifications 1.12, Core Alteration; 3.9.1, Refueling Operations - Boron Concentration; 3.9.2, Refueling Operations - Instrumentation; and 3.9.11, Refueling Operations - Water Level - Reactor Vessel. The amendment also revises the Technical Specifications Bases to reflect the changes to the definitions.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
John T. Harrison, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-336
Enclosures:
- 1. Amendment No. 263 to DPR-65
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC EAdensam JHarrison ACRS CAnderson, RI PDI-2 R/F JClifford TClark GHill (2) AAttard OGC WBeckner KKavanagh NRR-058 *SE provided 11/30/01; no major changes made.
Accession No. ML013440338 **See previous concurrence OFFICE PDI-2/PM PDI-2/LA D/RTSB* OGC** PDI-2/SC NAME JHarrison TClark WBeckner RHoefling REnnis for JClifford DATE 1-9-02 1-9-02 11-30-01 1-8-02 1-9-02 OFFICIAL RECORD COPY
Millstone Nuclear Power Station Unit 2 cc:
Ms. L. M. Cuoco Dominion Nuclear Connecticut, Inc.
Senior Nuclear Counsel Rope Ferry Road Dominion Nuclear Connecticut, Inc. Waterford, CT 06385 Rope Ferry Road Waterford, CT 06385 Mr. D. A. Christian Senior Vice President - Nuclear Operations Edward L. Wilds, Jr., Ph.D. and Chief Nuclear Officer Director, Division of Radiation Innsbrook Technical Center - 2SW Department of Environmental Protection 5000 Dominion Boulevard 79 Elm Street Glen Allen, VA 23060 Hartford, CT 06106-5127 Mr. C. J. Schwarz Regional Administrator, Region I Master Process Owner - Operate the Asset U.S. Nuclear Regulatory Commission Dominion Nuclear Connecticut, Inc.
475 Allendale Road Rope Ferry Road King of Prussia, PA 19406 Waterford, CT 06385 First Selectmen Mr. John Markowicz Town of Waterford Co-Chair 15 Rope Ferry Road Nuclear Energy Advisory Council Waterford, CT 06385 9 Susan Terrace Waterford, CT 06385 Charles Brinkman, Manager Washington Nuclear Operations Mr. Evan W. Woollacott ABB Combustion Engineering Co-Chair 12300 Twinbrook Pkwy, Suite 330 Nuclear Energy Advisory Council Rockville, MD 20852 128 Terry's Plain Road Simsbury, CT 06070 Senior Resident Inspector Millstone Nuclear Power Station Mr. D. A. Smith c/o U.S. Nuclear Regulatory Commission Process Owner - Regulatory Affairs P.O. Box 513 Dominion Nuclear Connecticut, Inc.
Niantic, CT 06357 Rope Ferry Road Waterford, CT 06385 Mr. W. R. Matthews Vice President and Senior Nuclear Ms. Nancy Burton Executive - Millstone 147 Cross Highway Dominion Nuclear Connecticut, Inc. Redding Ridge, CT 00870 Rope Ferry Road Waterford, CT 06385 Ernest C. Hadley, Esquire P.O. Box 1104 West Falmouth, MA 02574-1104 Mr. P. J. Parulis Process Owner - Oversight
Millstone Nuclear Power Station Unit 2 cc:
Mr. G. D. Hicks Master Process Owner - Training Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 R. P. Necci Vice President - Nuclear Operations - Millstone Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385
DOMINION NUCLEAR CONNECTICUT, INC.
DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 263 License No. DPR-65
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the applicant dated April 11, 2001, as supplemented September 26, 2001, and November 16, 2001, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 263, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of issuance, and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA REnnis for/
James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 11, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 263 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 1-3 1-3 3/4 9-1 3/4 9-1 3/4 9-2 3/4 9-2 3/4 9-11 3/4 9-11 B 3/4 9-1 B 3/4 9-1
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 263 TO FACILITY OPERATING LICENSE NO. DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 DOCKET NO. 50-336
1.0 INTRODUCTION
By letter dated April 11, 2001, as supplemented September 26 and November 16, 2001, the Dominion Nuclear Connecticut, Inc., (the licensee), submitted a request for changes to the Millstone Nuclear Power Station, Unit No. 2 (MP2) Technical Specifications (TSs). Specifically, the licensee requested revisions to the following TSs: TS 1.12, Core Alterations; TS 3.9.1, Refueling Operations - Boron Concentration; TS 3.9.2, Refueling Operations -
Instrumentations; and TS 3.9.11, Refueling Operations - Water Level - Reactor Vessel. The licensee also proposed to modify the TSs Bases to incorporate the proposed changes. The September 26 and November 16, 2001, letters provided clarifying information that did not change the initial proposed no significant hazards consideration determination or expand the scope of the original Federal Register notice.
2.0 BACKGROUND
The Industry and the Nuclear Regulatory Commission (NRC) staff have been working to improve the improved Standard Technical Specifications (STS) NUREGs which has resulted in the development of generic changes. These changes are issued by the NEI Technical Specifications Task Force (TSTF) using a process developed by the industry and approved by the NRC. The licensee is proposing changes to their TSs which adopt the STS as modified by TSTF-47 Revision 0, TSTF-272 Revision 1, and TSTF-20 Revision 0.
TSTF-47 Revision 0 deletes the words or manipulation from the definition of Core Alterations since it is improbable that components such as fuel, reactivity control components or sources could be manipulated without moving the component. TSTF-47 Revision 0 was approved by the NRC staff in a letter dated September 18, 1996.
TSTF-272 Revision 1 clarified STS 3.9.1 and the Bases to state that boron concentration limits do not apply to the refueling canal and refueling cavity when these areas are not connected to the reactor coolant system (RCS). STS 3.9.1 limits the boron concentrations of the RCS, the refueling canal, and the refueling cavity during refueling to ensure that the reactor remains subcritical during MODE 6. When the refueling canal and refueling cavity are isolated from the RCS, no potential for dilution exists. Therefore, in this condition, it is not necessary to place a
limit on the boron concentration in the refueling cavity and the refueling canal. TSTF-272 Revision 1 was approved by the NRC staff in a letter dated March 14, 1997.
TSTF-20 Revision 0 deleted Required Action A.3 from STS 3.9.7, Refueling Cavity Water Level. The completion of Required Actions A.1 and A.2 results in exiting the Mode of Applicability. Therefore, Required Action A.3 is not necessary. TSTF-20 Revision 0 was approved by the NRC staff in a letter dated March 13, 1997.
The effect of the proposed changes is the following: TS 1.12 is modified with the adoption of TSTF-47 Revision 0; TS 3.9.1 is revised with the adoption of TSTF-272 Revision 1; TS 3.9.2 is revised; and TS 3.9.11 is modified with the adoption of TSTF-20 Revision 0. Other plant-specific changes were also proposed for these TSs. The MP2 TS Bases will also be modified as a result of the proposed changes.
3.0 EVALUATION 3.1 Revision to TS Definition 1.12, Core Alteration The licensee proposed to revise TS Definition 1.12 as follows:
CORE ALTERATIONS shall be the movement of any fuel, sources or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
The proposed revision changes the current CORE ALTERATION definition from movement of any component to the movement of fuel, sources and reactivity control components. This revised definition specifically addresses components that affect reactivity. The CORE ALTERATION definition is used in limiting conditions for operation (LCOs) Applicabilities to establish requirements for nuclear instrumentation to monitor neutron flux and changes in core reactivity. The purpose of this definition is to protect from, or mitigate, a reactivity excursion event. The revised definition also contains an additional statement relating to the suspension of core alterations, which allows core alterations to continue until a component has been moved to a safe position. The proposed change ensures that if core alterations are required to be suspended by a TS, the time in which a component is in a transit location is minimized.
The staff has reviewed the proposed revision to TS Definition 1.12. Because movement of components other than fuel, sources, or reactivity control components is not considered a core alteration, and the revision allows continued movement of a component to establish a safer configuration, the staff concludes that the proposed revision to the CORE ALTERATION definition is acceptable. Additionally, the proposed revision incorporates the generic changes approved in TSTF-47 Revision 0.
3.2 Revisions to TS 3.9.1, Refueling Operations - Boron Concentrations TS LCO 3.9.1 provides the requirements for boron concentration in the RCS and the refueling canal in MODE 6. Specifically, LCO 3.9.1 requires that with the reactor vessel head unbolted or removed, the boron concentration of the RCS and the refueling canal shall be maintained sufficient to ensure that the more restrictive of the following reactivity conditions is met: either a
Keff of 0.95 or less; or a boron concentration of greater than or equal to 1,720 ppm. The licensee requested several changes to TS 3.9.1.
Amendment 201 to the MP2 TS revised TS 3.9.1 to allow a one-time change during the mid-cycle 13 shutdown. This change consisted of removing the requirement for uniform boration in the RCS and allowing the boron concentration of the water volumes in the steam generators and the connecting piping to be as low as the MODE 5 requirement of 1,300 ppm (SR 4.9.1.3). In order to restore TS 3.9.1 to the original state prior to the mid-cycle 13 shutdown, the licensee proposed to delete the footnote ** associated with the LCO and surveillance requirements (SR) 4.9.1.2. Footnote ** states that for cycle 13 mid-cycle core offload activities, it is acceptable for the boron concentration of the water volumes in the steam generators and connecting piping to be as low as 1,300 ppm. The licensee also proposed to delete SR 4.9.1.3 which requires the boron concentration in the cold leg side of the steam generators to be greater than or equal to 1,300 ppm prior to entering MODE 6. Additionally, the licensee proposed to add the words of all filled portions in front of the words Reactor Coolant System in the LCO and SR 4.9.1.2 to restore the original intent of the TS. However, the licensee did not elect to reinstate the requirement to maintain uniform boron concentration. The licensee stated that the boron concentration is normally uniform as a result of diffusion and forced circulation; and, therefore, the additional requirement is not necessary.
The staff has reviewed the proposed changes to TS 3.9.1 described above, and concluded that the proposed changes result in the restoration of the pre-cycle 13 TS conditions and, therefore, are acceptable. The staff also agrees that the pumping action of the Shutdown Cooling System in the RCS and the natural circulation due to thermal driving heads in the reactor vessel and refueling cavity result in a uniform boron concentration. Therefore, adding the word uniform in front of boron concentration in TS 3.9.1 is not required. This position is also consistent with NUREG-1432 Revision 2, Standard Technical Specifications, Combustion Engineering Plants.
The licensee proposed to delete the words with the reactor vessel head unbolted or removed from the LCO. As stated above, TS 3.9.1 is applicable in MODE 6. MODE 6 (REFUELING**)
is defined in Table 1.1 of the MP2 TS. The REFUELING footnote ** further defines MODE 6 as fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed. This definition is not being changed. Therefore, the staff finds this change acceptable because the words with the reactor vessel head unbolted or removed are not necessary in the LCO since they are specified in the definition of MODE 6.
TS 3.9.1 APPLICABILITY is MODE 6* where the footnote
- states that the reactor shall be maintained in MODE 6 whenever the reactor vessel head is unbolted or removed and fuel is in the reactor vessel. The licensee has proposed to remove the footnote*. The proposed change would result in the applicability being MODE 6, As discussed in section B, this change is also acceptable since Table 1.1 of the MP2 TS defines MODE 6, as fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
The licensee proposed to delete the statement the provisions of specification 3.0.3 are not applicable from the ACTION statement. LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4.
Since TS 3.9.1 is applicable only in MODE 6, the staff finds the proposed change acceptable.
This change is also consistent with NUREG-1432 Revision 2.
The licensee proposed to add a NOTE to the APPLICABILITY statement that states that the LCO 3.9.1 limits only apply to the refueling canal when it is connected to the reactor coolant system. The staff finds the proposed change acceptable because it is not necessary to place a limit on the boron concentration in the refueling cavity and the refueling canal because no potential for a dilution event exists when the refueling canal is isolated from the RCS.
Additionally, the proposed revision incorporates the generic changes approved in TSTF-272 Revision 1.
The licensee proposed to delete the discussion of boron concentration for the Cycle 13 mid-cycle core offload activities in the MP2 Bases. In its place, the licensee proposed to add a discussion of the LCO 3.9.1 NOTE which states that the limits on boron concentration are only applicable to the refueling canal when this volume is connected to the RCS. The staff has reviewed the proposed changes to the TS 3.9.1 Bases and finds them consistent with the related TS changes previously described.
3.3 Revisions to TS 3.9.2 TS LCO 3.9.2 provides the requirements for source range neutron flux monitors in MODE 6.
Specifically, LCO 3.9.2 requires that two source range neutron flux monitors be operating, each with continuous visual indication in the control room and one with audible indication in the containment. The licensee requested several changes to TS 3.9.2.
The licensee proposed two administrative changes to TS 3.9.2. The phrase as a minimum will be deleted from the LCO. Since the LCO states the minimum requirements of the TS, the staff finds that the phrase as a minimum is redundant and not necessary. Additionally, the licensee proposed that the word operating be replaced by OPERABLE. The staff finds this change acceptable because the monitors must be operable in order to meet the second part of the LCO which requires continuous visual and audible indication.
As discussed above, TS LCO 3.9.2 currently requires that two source range neutron flux monitors be operating with continuous visual indication in the control room and one with audible indication in the containment. The licensee proposed to extend the requirement for audible indication to be in the control room along with the containment. As such, one monitor is required to have audible indication in the containment and control room. The basis for the proposed change is that personnel are not required to be in containment at all times during MODE 6. The staff finds the proposed change acceptable because audible indication in the control room will provide additional assurance that any increases in reactor core neutron flux levels during MODE 6 are identified in a timely manner.
TS 3.9.2 ACTION statement requires suspension of core alterations or positive reactivity changes when one or two source range neutron flux monitors are inoperable. The licensee proposed to divide the ACTION statement into two. ACTION a will address the inoperability of one source range neutron flux monitor and will require immediate suspension of all operations involving core alterations and positive reactivity additions. Proposed ACTION a is consistent with the current TS 3.9.2 ACTION and, therefore, is acceptable. Proposed ACTION b will address the inoperability of two source range neutron flux monitors. Proposed ACTION b will require immediate action to restore one monitor to OPERABLE status and will require that the boron concentration of the RCS be verified to satisfy the requirements of LCO 3.9.1 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. Proposed ACTION b provides alternate
monitoring requirements that adequately compensate for inoperable monitors and permit unlimited operation in Actions. The staff finds the proposed changes acceptable because the combination of the these two proposed actions ensure that core alterations do not occur when one or more neutron flux monitors are inoperable. These changes are also consistent with NUREG-1432 Revision 2.
SRs 3.9.2.a and 3.9.2.b require that each source range neutron flux monitor shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 7 days, and a CHANNEL FUNCTIONAL TEST within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the start of CORE ALTERATIONS. The licensee proposed to replace the requirements of SRs 3.9.2.a and 3.9.2.b with one SR 3.9.2.b which would require the performance of a channel calibration at least once per 18 months. The licensee stated that the channel functional test only provides indication of the neutron flux level in the core, while the channel calibration would ensure the instrument channels are properly aligned. Additionally, the proposed SRs for the Source Range Neutron Flux Monitor in MODE 6 are consistent with the existing requirements for the Wide Range Logarithmic Neutron Flux Monitors in MODES 3, 4, and 5 (TS SR 4.3.1.1.1). TS SR 4.3.1.1.1 also requires a Channel Check on a per shift frequency. The staff finds this change acceptable because the replacement of the 7-day and 8-hour Channel Functional Test surveillance requirements for the Source Range Neutron Flux Monitors with an 18-month Channel Calibration surveillance provides sufficient demonstration of the OPERABILITY of the channels during MODE 6 and is consistent with the Wide Range Monitor TS. The proposed change is also consistent with NUREG-1432 Revision 2.
The licensee proposed to add a footnote to TS SR 4.9.2.b. Footnote
- would state that neutron detectors are excluded from channel calibration. The proposed footnote is consistent with the existing requirements of SR 4.3.1.1.1, Table 4.3-1 and, therefore, is acceptable. The proposed footnote is also consistent with NUREG-1432 Revision 2.
The licensee also proposed to add the words and verification of audible counts to SR 3.9.2.c.
This administrative change would eliminate any confusion associated with the current wording which could be interpreted as requiring the channel check to include audio count rate indication.
This proposed change is consistent with the wording of LCO 3.9.2 and, therefore, is acceptable.
Additionally, the licensee proposed to delete the words during CORE ALTERATIONS from SR 3.9.2.c. The staff finds this change acceptable because this is a more restrictive change since SR 3.9.2.c would be performed once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while in MODE 6 versus only being performed during Core Alterations.
The licensee did not propose any Bases changes for the TS 3.9.2 changes described above.
3.4 Revisions to TS 3.9.11 TS 3.9.11 currently requires that 23 feet of water shall be maintained over the top of the reactor pressure vessel while irradiated fuel assemblies are seated within the reactor pressure vessel.
The licensee has proposed to revise the LCO to state the following: As a minimum, 23 feet of water shall be maintained over the top of the reactor vessel flange. Additionally, the licensee proposed to replace the Applicability and Action statements in their entirety. The proposed Applicability and Action statements are as follows:
Applicability: During CORE ALTERATIONS, except during latching and unlatching of control rod drive shafts.
During movement of irradiated fuel assemblies within containment.
Action: With the water level less than that specified above, immediately suspend CORE ALTERATIONS and immediately suspend movement of irradiated fuel assemblies within containment.
As previously noted, the applicability is expanded to include core alterations, except during latching and unlatching of control rod drive shafts and the movement of irradiated fuel assemblies within containment. The action requirements are modified to be consistent with the proposed applicability. The proposed changes do not result in any technical changes to the requirements to maintain sufficient reactor vessel water level and, therefore, are acceptable.
These changes also incorporate the changes made by TSTF-20 and are consistent with NUREG-1432 Revision 2.
The licensee also proposed to modify TS SR 4.9.11 to require verification of refueling cavity water level at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The current SR would require verification of water level 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of fuel movement and at least once per 7 days thereafter. This proposed frequency change does not change the requirement that the refueling cavity has sufficient water level or that the water level is verified prior to the start of core alterations or movement of irradiated fuel assemblies within containment. SRs must be met prior to entering the applicability of the specification. Therefore, the water level of the reactor vessel cavity will be verified prior to the start of core alterations or movement of irradiated fuel within containment. Additionally, SR 4.9.11 will be performed on a more frequent basis since the frequency is proposed to be every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> versus every 7 days. Therefore, the staff finds the proposed changes to SR 4.9.11 acceptable.
The licensee also stated that the proposed changes to TS 3.9.11 are consistent with the analysis of record for a fuel handling accident inside containment. As such, the proposed changes ensure that the consequences of this accident are not increased and will not adversely affect the health and safety of the public. The licensee did not propose any Bases changes for the TS 3.9.11 changes described above.
The staff has reviewed the licensees submittals and supporting documentation. Based on our review, the staff concludes that the proposed changes to TSs 1.12, 3.9.1, 3.9.2, and 3.9.11 for MP2 are acceptable; and, the changes to the Bases are consistent with the associated TS changes.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Connecticut State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes SRs.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (66 FR 31705). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: K. Kavanagh Date: January 11, 2002