Letter Sequence Approval |
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TAC:ME8454, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil (Approved, Closed) |
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MONTHYEARML12110A0882012-04-13013 April 2012 License Amendment Request Regarding the Diesel Fuel Oil Test Program Technical Specification Project stage: Request ML12132A1012012-05-0707 May 2012 Supplemental Information on Diesel Fuel Oil Test Program Amendment Project stage: Supplement ML1214202422012-05-21021 May 2012 E-mail Millstone Power Station, Unit 2-Amendment Request for Technical Specification Change Regarding Diesel Fuel Oil Test Program Project stage: Other ML13043A1762013-03-0505 March 2013 Issuance of Amendment Adopt TSTF-374,Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Project stage: Approval 2012-05-21
[Table View] |
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Category:Letter
MONTHYEARML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) 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 . 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) ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal 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. ML23242A0142023-08-30030 August 2023 Operator Licensing Examination Approval ML23223A0552023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23223A0482023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Use Framatome Small Break and Realistic Large Break LOCA Evaluation Methodologies for Establishing COLR Limits IR 05000336/20230022023-08-0909 August 2023 Integrated Inspection Report 05000336/2023002 and 05000423/2023002 ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000336/20234012023-07-17017 July 2023 Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only) ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23193A8562023-06-28028 June 2023 Submittal of Updates to the Final Safety Analysis Reports ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23159A2202023-06-0808 June 2023 Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes IR 07200047/20234012023-06-0808 June 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401 2024-01-04
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23341A0172024-01-12012 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) ML14037A4082014-04-18018 April 2014 Issuance of Amendment Revise Technical Specification 3/4.7.11 Ultimate Heat Sink ML14073A0552014-04-0808 April 2014 Issuance of Amendment Calculated Containment Internal Pressure 2024-01-12
[Table view] Category:Safety Evaluation
MONTHYEARML23341A0172024-01-12012 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 ML18225A0202018-08-29029 August 2018 ISFSI; North Anna 1 & 2 Isfsls, and Unit 3; Surry Power 1 & 2, and Isfsls); Dominion Energy Kewaunee, Inc. (Kewaunee Power Station and Isfsi): Request for Threshold Determination Under 10 CFR 50.80 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) 2024-01-12
[Table view] |
Text
\1.J'-R REGUl UNITED STATES
,,>c.' "I r o,iii' c' 0-j).L NUCLEAR REGULATORY COMMISSION t:f (") WASHINGTON, D.C. 2055S'()001
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~ ~ March 5, 2013
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Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO.2 - ISSUANCE OF AMENDMENT RE: ADOPT TSTF-374, "REVISION TO TS 5.5.13 AND ASSOCIATED TS BASES FOR DIESEL FUEL OIL" (TAC NO. ME8454)
Dear Mr. Heacock:
The Commission has issued the enclosed Amendment No. 313 to Renewed Facility Operating License No. DPR-65 for the Millstone Power Station, Unit No.2, in response to your application dated April 13, 2012, as supplemented by letter dated May 7,2012.
The amendment would revise Technical Specification (TS) requirements related to diesel fuel oil testing consistent with NUREG-1432, Rev. 3.1, "Standard Technical Specifications, Combustion Engineering Plants," December 1, 1995, and Nuclear Regulatory Commission approved Technical Specification Task Force (TSTF) TSTF-374, "Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil," Revision O.
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, k~D~
James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-336
Enclosures:
- 1. Amendment No. 313 to DPR-65
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DOMINION NUCLEAR CONNECTICUT, INC.
DOCKET NO. 50-336 MILLSTONE POWER STATION, UNIT NO.2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 313 Renewed License No. DPR-65
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the applicant dated April 13, 2012, as supplemented by letter dated May 7,2012, 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
- 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 Renewed 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. 313, are hereby incorporated in the renewed 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 120 days of issuance.
FOR THE NUCLEARtREGULA TORY COMMISSION Sean C. Meighan, Acting Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: March 5, 2013
ATTACHMENT TO LICENSE AMENDMENT NO. 313 RENEWED FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page 3 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 6-29 6-29
- 3 Connecticut, in accordance with the procedures and limitations set forth in this renewed operating license; (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at steady-state reactor core power levels not in excess of 2700 megawatts thermal.
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 313, are hereby incorporated in the renewed license.
The licensee shall operate the facility in accordance with the Technical Specifications.
Renewed License No. DPR-65 Amendment NO.313
ADMINISTRATIVE CONTROLS 6.24 DmSEL FUEL OIL TEST PROGRAM A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards. The purpose ofthe program is to establish the following:
- a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:
- 1. An API gravity or an absolute specific gravity within limits,
- 2. A flash point and kinematic viscosity within limits for ASTM 20 fuel oil, and
- 3. A clear and bright appearance with proper color or a water and sediment content within limits.
- b. Within 31 days foHowing addition of the new fuel oil to storage tanks, verifY that the properties ofthe new fuel oil, other than those addressed in a., above, are within limits for ASTM 20 fuel oil, and
- c. Total particulate concentration of the fuel oil is $; 10 mg/L when tested every 92 days.
The provisions of Surveillance Requirements 4.0.2 and 4.0.3 are applicable to the Diesel Fuel Oil Test Program test frequencies.
6.25 PRE-STRESSED CONCRETE CONTAINMENT TENDON SURVEILLANCE PROGRAM This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations.
The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shaH be in accordance with Regulatory Guide 1.35, Revision 3, 1989.
The provisions of Surveillance Requirements 4.0.2 and 4.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.
Any abnormal degradation of the containment structure detected during the tests required by the Pre-stressed Concrete Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description ofthe tendon condition, the condition ofthe concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken. This Tendon Surveillance Report is an administrative requirement listed in Technical Specifications 6.9.2, "Special Reports."
MILLSTONE - UNIT 2 6-29 Amendment No.277, 278, 313
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 313 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION, UNIT NO.2 DOCKET NO. 50-336
1.0 INTRODUCTION
By letter dated April 13, 2012, (Agencywide Documents Access and Management System (ADAMS) Accession Number ML12110A088), as supplemented by letter dated May 7,2012 (ML12132A101), Dominion Nuclear Connecticut, Inc. (the licensee) proposed changes to the Technical Specifications (TSs) for Millstone Power Station Unit 2 (MPS2) to adopt Technical Specification Task Force (TSTF)-374. "Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil."
The proposed changes reflect modification of MPS2 existing diesel fuel oil testing program (TS 6.24), specifically to relocate the references to specific American Society for Testing and Materials (ASTM) standards for fuel oil testing to licensee controlled documents and replace the acceptable criteria of "Water and sediment s 0.05%" with the criteria of "A clear and bright appearance with proper color or a water sediment content within limits."
TSTF-374 relocates references to specific ASTM standards for fuel oil testing to licensee control/ed documents and would add alternate criteria to the "clear and bright" acceptance test for new fuel oil.
The proposed changes are consistent with Section 5.5.13 of NUREG-1431, Revision 3, "Standard Technical Specifications, Westinghouse Plants" (STS). which has incorporated Technical Specification Task Force (TSTF) Improved Standard Technical Specifications Change Traveler 374-A, Revision 0, "Revision to TS 5.5.13 and associated TS Bases for Diesel Fuel Oil."
These changes were described in a Notice of Availability published in the Federal Register on April 21,2006 (71 FR 20735).
The supplemental letter dated May 7, 2012, provided additional information that clarified the application, did not expand the scope of the application as originally noticed. and did not change the Nuclear Regulatory Commission (NRC) staff's original proposed no Significant hazards consideration determination as published in the Federal Register on June 12, 2012 (77 FR 35072).
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2.0 REGULATORY EVALUATION
The onsite electrical power system includes standby power sources, distribution systems, and vital auxiliary supporting systems to supply power to safety-related equipment. Most commercial nuclear power plants use diesel generators as the emergency power source for the safety related electrical buses. The importance of the diesel generators (or other standby power sources) is reflected in their incorporation into the NRC regulations, TSs, and other regulatory programs, including Appendix B ("Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants") to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50). The NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," addresses diesel fuel oil and other supporting systems in Section 9.5.4, "Emergency Diesel Engine Fuel Oil Storage and Transfer System Review Responsibilities."
The TSs include requirements for testing diesel fuel oil to ensure that it is of the appropriate grade and that it has not been contaminated (i.e., proper fuel oil quality). The Diesel Fuel Oil Testing Program defined in the TS includes tests for (1) the acceptability of new fuel oil for use prior to addition to the storage tanks; (2) other properties of new fuel oil that are within limits within 31 days following sampling and addition to storage tanks; and (3) total particulate concentration of the fuel oil every 31 days. The current TSs identifies particular ASTM standards and methods of performing these tests. The industry submitted TSTF-374 proposing changes to the STS (NUREGs 1430 - 1434) to provide the flexibility to address future changes in Environmental Protection Agency (EPA) regulations for fuel oil or revisions to the ASTM standards. The TSTF-374-A was reviewed and accepted by the NRC staff and has been incorporated into each of the STS NUREGs. Requirements for testing the diesel fuel oil are maintained, but references to specific ASTM standards are relocated to licensee-controlled documents and an alternative to the "clear and bright" acceptance test for new fuel is added to address changes in EPA requirements.
3.0 TECHNICAL EVALUATION
In adopting TSTF-374, the licensee proposes to remove the reference to specific ASTM standards from the TS Administrative Controls Section 6.24, "Diesel Fuel Oil Testing Program,"
as it is currently located within MSPs TS Bases, a licensee-controlled document. Although the reference to specific testing standards or methods will no longer reside in MSPs TS and currently in the Bases, the revised TS 6.24 will continue to include acceptance criteria for new and stored diesel fuel oil and refers to "applicable ASTM standards" for sampling and testing requirements.
The specific testing standards or methods are added to the TS Bases Section, which are controlled in accordance with 10 CFR 50.59, "Changes, tests, and experiments," as described in TS 6.23, "Technical Specification (TS) Bases Control Program." The licensee's testing programs for diesel fuel oil are also governed by other regulatory requirements, including Appendix B (Quality Assurance Criteria) to 10 CFR Part 50. While the relocation of selected program details provides the licensee with some flexibility to adopt practices defined in future ASTM standards, the NRC staff finds that the remaining TS, TS Bases Control Program, and other NRC regulations provide appropriate regulatory controls to ensure diesel fuel oil quality will be maintained. The plant-specific adoption of TSTF-374 also includes an alternative to the "clear and bright" test currently required for new fuel oil acceptability. The revised TS would
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allow either the "clear and bright" test or a test confirming that the fuel oil has "water and sediment content within limits." This alternative test is better suited for darker colored fuels and is recognized in ASTM standards that have been referenced in NRC~approved amendment requests. The NRC staff finds that the alternative for testing the water and sediment content will maintain or improve the inspection of new fuel oil and therefore finds the change acceptable.
The licensee included in its application the proposed revisions to the TS Bases to reflect the changes to TS 6.24 and to revise the references to the applicable ASTM standards. The changes are consistent with TSTF*374 and will be incorporated into the TS Bases in accordance with TS 6.23.
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. The NRC staff has determined that the amendment involves no significant increase in 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 (77 FR 35072 dated June 12, 2012).
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) there is reasonable assurance that 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: S. Anderson Date: March 5, 2013
March 5, 2013 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO.2 - ISSUANCE OF AMENDMENT RE: ADOPT TSTF-374, "REVISION TO TS 5.5.13 AND ASSOCIATED TS BASES FOR DIESEL FUEL OIL" (TAC NO. ME8454)
Dear Mr. Heacock:
The Commission has issued the enclosed Amendment No. 313 to Renewed Facility Operating license No. DPR-65 for the Millstone Power Station, Unit No.2, in response to your application dated April 13, 2012, as supplemented by letter dated May 7, 2012.
The amendment would revise Technical Specification (TS) requirements related to diesel fuel oil testing consistent with NUREG-1432, Rev. 3.1, "Standard Technical Specifications, Combustion Engineering Plants," December 1, 1995, and Nuclear Regulatory Commission approved Technical Specification Task Force (TSTF) TSTF-374, "Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil," Revision O.
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, Ira!
James Kim, Project Manager Plant licensing Branch 1-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-336
Enclosures:
- 1. Amendment No. 313 to DPR-65
- 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRI BUTION:
PUBLIC RidsNrrLAKGoldstein RidsNrrDssStsb Resource LPLI-1 R/F RidsNrrPMMilistone RidsNrrDirsltsb Resource RidsNrrDorlLpl1-1 Resource RidsRgn1 MailCenter RBeliany, RI RidsNrrDorfDpr Resource RidsOgcRp Resource RidsAcrsAcnw_MailCTR Resource A ccesslon N0.: ML13043A176 *SE I npu ' memo date d Fe bruary 20 , 2013 t via NRR 106 OGC (NLO wI LPLI-1/PM OFFICE LPL 1-1/PM LPL 1-1/LA STSB/BC* LPL 1-1/BC(A) comments)
NAME JKim KGoldstein RElliott* BHarris SMeighan ,IKim DATE 2/21/13 2/14/13 2/20/13 2/28/13 3/4113 3/5/13 I
C F=FICIAL RECOR .D COPY