Letter Sequence Approval |
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TAC:MD6824, Revise Topical Report References in ITS 5.6.5, Colr (Approved, Closed) |
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MONTHYEARML0623703512006-08-16016 August 2006 Request for Approval of Topical Report DOM-NAF-5 Application of Dominion Nuclear Core Design and Safety Analysis Methods to the Kewaunee Power Station (Kps). Project stage: Request ML0710603922007-04-16016 April 2007 Request for Approval of Topical Report DOM-NAF-5, Application of Dominion Nuclear Core Design and Safety Analysis Methods to the Kewaunee Power Station (Kps.) Project stage: Request ML0712705812007-05-0404 May 2007 Implementation of the Dominion Statistical DNBR Methodology with VIPRE-D/WRB-1 Project stage: Request ML0726802782007-09-24024 September 2007 License Amendment Request 228 Incorporation of Dominion Nuclear Analysis and Fuel Topical Report DOM-NAF-5 Into Technical Specifications Project stage: Request ML0801804442008-01-18018 January 2008 Response to Request for Additional Information Regarding Kewaunee License Amendment Request 228 Project stage: Response to RAI ML0809100872008-03-28028 March 2008 Tech Specs Pages for Amendment 196 Nuclear Core Design and Safety Analysis Methods Project stage: Other ML0806305402008-03-28028 March 2008 Issuance of License Amendment 196 Nuclear Core Design and Safety Analysis Methods Project stage: Approval 2007-05-04
[Table View] |
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Category:Letter
MONTHYEARML23339A1332024-01-26026 January 2024 Exemption from the Req of 10 CFR Part 50.82(a)(8)(i)(A) to Use the Kewaunee Decommissioning Trust Fund for the Management of Site Restoration Activities IR 05000305/20230022023-12-27027 December 2023 NRC Inspection Report 05000305/2023002 (Drss); 07200064/2023001 (Drss) ML23332A1922023-11-28028 November 2023 Solutions, Inc., Request for Exemptions from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23278A1002023-10-0505 October 2023 Response to Request for Additional Information (RAI) Application for Kewaunee Solutions (Ks) Site Restoration Activities ML23222A1522023-08-29029 August 2023 Letter RAI KPS Exemption Site Restoration Final Repaired IR 05000305/20230012023-08-17017 August 2023 NRC Inspection Report No. 05000305/2023001-Kewaunee Power Station ML23171B0822023-07-0505 July 2023 Letter - Kewaunee Power Station - Issuance of Exemption from Certain Requirements from 10 CFR Part 20, Appendix G, Section Iii.E ML23132A0012023-05-11011 May 2023 2022 Annual Radiological Environmental Operating Report ML23116A2182023-04-26026 April 2023 2022 Annual Radioactive Effluent Release Report ML23089A3042023-03-30030 March 2023 Decommissioning Fund Status Report ML23088A2752023-03-29029 March 2023 Solutions, Inc., Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML23093A0312023-03-29029 March 2023 Solutions, Inc., Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 50.75(h)(1)(iv) for Site Restoration Activities ML23087A0402023-03-27027 March 2023 Annual Property Insurance Status Report ML23087A0292023-03-27027 March 2023 2022 Annual Report of Occupational Radiation Exposure ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23024A0122023-01-26026 January 2023 Letter to Energysolutions Transmitting Threshold Determination for Merger/Restructuring IR 05000305/20220022023-01-0303 January 2023 NRC Inspection Report Nos. 05000305/2022002(DRSS) Kewaunee Power Station ML22292A2302022-11-25025 November 2022 U.S. Nuclear Regulatory Commissions Analysis of Dominion Energy Kewaunees Decommissioning Funding Status Report for Kewaunee Power Station, Docket No. 50-305 ML22290A0052022-10-13013 October 2022 Resubmittal of Kewaunee Power Station Independent Spent Fuel Storage Installation (ISFSI) Only Emergency Plan (Ioep) and IOEP- Emergency Action Level (EAL) Basis Document, Revision 0KS ML22241A0302022-08-25025 August 2022 (Ksp) ISFSI Submittal of Security Plan, Training and Qualification Plan and Safeguards Contingency Plan, Revision 5 IR 05000305/20220012022-08-0101 August 2022 NRC Inspection Report Nos. 05000305/2022001(DNMS) - Kewaunee Power Station ML22215A1512022-07-27027 July 2022 Executed Financial Assurance Instruments for the Kewaunee License Transfer License No. DPR-43 (Docket Nos. 50-305, 72-64) ML22209A1252022-07-26026 July 2022 Amendment No. 11 to Indemnity Agreement No. B-53 for Kewaunee Power Station (KPS) - Signed by Kewaunee Solutions, Inc ML22175A1132022-06-30030 June 2022 Solutions, Inc. - Letter for Review and Acceptance of the Energysolutions, LLC Decommissioning Quality Assurance Program with Enclosure ML22160A5272022-06-28028 June 2022 Enclosure 1 - Amendment No. 221 to Renewed Facility Operating License No. DPR-43 ML22160A5282022-06-28028 June 2022 Enclosure 2 - Amendment No. 11 to Indemnity Agreement B-53 ML22160A5262022-06-28028 June 2022 Letter - KPS - Issuance of Conforming License Amendment Regarding Indirect Transfer of License from DEK, Inc. to Kewaunee Solutions, Inc ML22188A0812022-06-23023 June 2022 ISFSI, Virgil C. Summer Nuclear Station, Unit 1 & ISFSI, North Anna Power Station, Units 1 & 2 & ISFSI, Surry Power Station, Units 1 & 2 & ISFSI - Submission of Revision 32 of the Quality Assurance Topical Report ML22172A2452022-06-22022 June 2022 Notification of Planned Closing Date and Required Regulatory Approvals for the Kewaunee License Transfer Transaction ML22175A0662022-06-17017 June 2022 Designation of Additional Reviewing Official for ISFSI and 10 CFR Part 37 Program Security Background Investigations ML22166A3392022-06-13013 June 2022 Notification of Nuclear Insurance ML22138A2552022-05-10010 May 2022 Submittal of 2021 Annual Radiological Environmental Operating Report ML22158A2112022-05-10010 May 2022 Summary of Facility Changes, Tests and Experiments and Summary of Commitment Changes ML22108A0352022-04-0101 April 2022 License Transfer to Kewaunee Solutions, Inc ML22091A1892022-04-0101 April 2022 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report ML22089A2432022-03-30030 March 2022 Decommissioning Funding Status Report, Financial Test and Independent Public Accountants' Letter of Attestation ML22076A0652022-03-15015 March 2022 Energy Solutions and Dominion Energy Kewaunee - Supplement to License Transfer Application Related to Use of Existing Dominion Energy Quality Assurance Program ML22060A1912022-02-25025 February 2022 Response to Request for Additional Information Related to Submittal for Approval of the Kewaunee Solutions Decommissioning Quality Assurance Program (Dqap), Revision O for Kewaunee Power Station (KPS) ML22066A4982022-02-24024 February 2022 Nuclear Property Insurance Coverage ML22047A0572022-02-16016 February 2022 Supplement to License Transfer Application Related to Decommissioning Quality Assurance Program ML22032A3242022-02-0202 February 2022 Letter to C. Sly, Dominion, from B. Watson, NRC - Dominion Energy Kewaunee, Inc. - RAI Regarding Energysolutions Submittal for Approving Decommissioning Quality Assurance Program IR 05000305/20210012021-12-27027 December 2021 NRC Inspection Report Nos. 05000305/2021001 (Dnms); 07200064/2021001 (DNMS) ML21351A4352021-12-19019 December 2021 U.S. Nuclear Regulatory Commission'S Analysis of Dominion Energy Kewaunee, Inc.'S Decommissioning Funding Status Report for Kewaunee Power Station, Docket No. 50-305 ML21355A2972021-12-14014 December 2021 ISFSI, 10 CFR 72.30 Decommissioning Funding Plan ML21309A0152021-11-0909 November 2021 Acceptance Review of Dominion Energy Kewaunee, Inc. - Energysolutions Submittal for Approving Decommissioning Quality Assurance Program (EPID L-2021-DP3-0000) ML21301A1782021-10-28028 October 2021 Response to Request for Additional Information Regarding Application for Order Approving Transfer of Control of Kewaunee Power Station License and Conforming License ML21294A3652021-10-21021 October 2021 Changes to Decommissioning Trust Agreement ML21288A5572021-10-18018 October 2021 Energysolutions Submittal for Approving Decommissioning Quality Assurance Program (EPID L-2021-DP3-0000) ML21257A0682021-09-30030 September 2021 Request for Additional Information Regarding Application for Order Approving Transfer of Control of Kewaunee Power Station License and Conforming License Amendments ML21277A2462021-09-29029 September 2021 Resubmittal of Solutions Decommissioning Quality Assurance Program (Dqap), Revision 0 2024-01-26
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML22047A0572022-02-16016 February 2022 Supplement to License Transfer Application Related to Decommissioning Quality Assurance Program ML21131A1412021-05-10010 May 2021 Application for Order Approving Transfer of Control of KPS License and Conforming License Amendments ML19130A1952019-05-0808 May 2019 Letter - FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition ML16323A1932016-11-16016 November 2016 Resubmittal of Request for Approval of Security Plan ML16216A1872016-07-28028 July 2016 License Amendment Request 263; Load Drop Analysis for Spent Fuel Cask Handling Operations ML15261A2382015-09-14014 September 2015 License Amendment Request 259, ISFSI-Only Emergency Plan and Emergency Action Level Scheme ML15261A2362015-09-14014 September 2015 License Amendment Request 260, Proposed Changed to License and Technical Specifications to Reflect Permanent Removal of Spent Fuel from Spent Fuel Pool ML14029A0642014-01-16016 January 2014 Evaluation ETE-NAF-20130072, Revision 0, Kewaunee Spent Fuel Pool Zirconium Fire Parameter Comparison ML14029A0672014-01-16016 January 2014 Sargent & Lundy Calculation 2013-11284, Revision 0 - Maximum Cladding and Fuel Temperature Analysis for Uncovered Spent Fuel Pool ML14029A0662014-01-16016 January 2014 Calculation RA-0050, Revision 0 - Kewaunee Resin Cask Drop Dose Consequence Analysis ML14029A0652014-01-16016 January 2014 Calculation RA-0049, Revision 1, Addendum a - Kewaunee Emergency Action Levels for Post - Cessation of Power Operations ML14029A0632014-01-16016 January 2014 Kewaunee,Calculation 2013-07050, Revision 2 - Maximum Cladding Temperature Analysis for an Uncovered Spent Fuel Pool with No Air Cooling ML14029A0622014-01-16016 January 2014 Calculation RA-0044, Revision 1 - Dose Rate at the KPS Site Boundary Following a Complete Draindown of the Spent Fuel Pool ML14029A0612014-01-16016 January 2014 Enclosure 4 to 13-495A - Supporting Evaluations and Calculations ML14029A0592014-01-16016 January 2014 Enclosure 3 to 13-495A - Permanently Defueled Emergency Action Level Basis Document ML14029A0572014-01-16016 January 2014 Enclosure 2 to 13-495A - Permanently Defueled Emergency Action Level Scheme ML14029A0562014-01-16016 January 2014 Enclosure 1 to 13-495A - Permanently Defueled Emergency Plan ML14029A0552014-01-16016 January 2014 Attachment 2 to 13-495A - Comparison Matrix for Permanently Defueled Eals, Based Upon Nuclear Energy Institute (NEI) 99-01, Methodology for Development of Emergency Action Levels, Revision 6 ML14029A0542014-01-16016 January 2014 Attachment 1 to 13-495A - Discussion of Change, Technical Analysis, Significant Hazards Determination, and Environmental Considerations ML14029A0532014-01-16016 January 2014 License Amendment Request 257, Permanently Defueled Emergency Plan and Emergency Action Level Scheme NEI 99-01, Kewaunee, Attachment 2 to 13-495A - Comparison Matrix for Permanently Defueled Eals, Based Upon Nuclear Energy Institute (NEI) 99-01, Methodology for Development of Emergency Action Levels, Revision 62014-01-16016 January 2014 Kewaunee, Attachment 2 to 13-495A - Comparison Matrix for Permanently Defueled Eals, Based Upon Nuclear Energy Institute (NEI) 99-01, Methodology for Development of Emergency Action Levels, Revision 6 ML13156A0372013-05-29029 May 2013 License Amendment Request 256, Permanently Defueled License and Technical Specifications ML12248A1492012-08-29029 August 2012 Submittal of Revision to Locked Rotor Radiological Accident Analysis: License Amendment Request 244, Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications ML12219A0702012-07-30030 July 2012 License Amendment Request 254: 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 ML11222A1232011-07-25025 July 2011 License Amendment Request 244: Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications ML11137A0282011-05-0909 May 2011 License Amendment Request 252, Operation of Service Water Flow to Component Cooling Heat Exchangers ML1022904202010-08-0909 August 2010 License Amendment Request 244: Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications ML1013803992010-05-12012 May 2010 License Amendment Request 249: Conversion to Improved Technical Specifications (TAC No. ME02467) - Request to Change Proposed Service Water and Main Steam Isolation Valve Specifications ML1011101232010-04-13013 April 2010 License Amendment Request 246: Revision to Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection Limitations ML0933602472009-11-20020 November 2009 Request for Approval of Cyber Security Plan ML0924403712009-08-24024 August 2009 License Amendment Request 249, Conversion to Improved Technical Specifications ML0912710592009-06-0101 June 2009 License Amendment No. 206, Containment Purge and Vent Isolation Valves Surveillance Requirement ML0902602992009-01-23023 January 2009 License Amendment Request 247: Emergency Diesel Generator Fuel Oil Technical Specification Changes ML0825507002008-09-11011 September 2008 License Amendment Request 242: Extension of the One-time Fifteen Year Containment Integrated Leak Rate Test Interval ML0823211982008-08-18018 August 2008 Application to Use Weighting Factors for External Exposure ML0823200832008-08-14014 August 2008 License Amendment Request 229, Change Technical Specifications to Require Testing Containment Purge and Vent Isolation Valves When the Reactor Is Above Cold Shutdown ML0823410392008-08-12012 August 2008 Applicants Environmental Report, Operating License Renewal Stage ML0819902662008-07-16016 July 2008 License Amendment Request 238: Increase in Technical Specification Minimum Injection Accumulator Boron Concentration ML0819303172008-07-0707 July 2008 License Amendment Request 239 for Review and Approval of Seismic Analysis Methodology for Auxiliary Building Crane ML0810604762008-04-14014 April 2008 License Amendment Request- 224, Steam Line Isolation Function Applicability ML0809504692008-04-0404 April 2008 License Amendment Request 237: Removal of Shield Building and Auxiliary Building Special Ventilation Train Filter Heater Requirements ML0809500962008-04-0303 April 2008 Response to NRC Request for Additional Information License Amendment Request 210. Technical Specification Modifications Regarding Control Room Envelope Habitability ML0806305402008-03-28028 March 2008 Issuance of License Amendment 196 Nuclear Core Design and Safety Analysis Methods ML0731707052007-11-0909 November 2007 License Amendment Request 227 Relocation of Spent Fuel Pool Crane Technical Specification to Technical Requirements Manual ML0731804992007-11-0909 November 2007 License Amendment Request 234 - Request for Review and Approval of Methodology Change Regarding Auxiliary Building Crane Upgrade ML0727605722007-10-0202 October 2007 License Amendment Request - 232 Operability Testing of Emergency Diesel Generators ML0726802782007-09-24024 September 2007 License Amendment Request 228 Incorporation of Dominion Nuclear Analysis and Fuel Topical Report DOM-NAF-5 Into Technical Specifications ML0726201442007-09-14014 September 2007 License Amendment Request 210 - Technical Specification Modifications Regarding Control Room Envelope Habitability ML0718600752007-07-0202 July 2007 License Amendment Request - 223, Deletion of License Condition 2.C (5), Fuel Burnup ML0717002572007-06-12012 June 2007 License Amendment Request - 217 Revision to Reactor Trip Permissive Setpoints 2022-02-16
[Table view] Category:Safety Evaluation
MONTHYEARML23339A1362024-01-26026 January 2024 Safety Evaluation Re NRC Issuance of Exemption for Site Restoration ML23024A0122023-01-26026 January 2023 Letter to Energysolutions Transmitting Threshold Determination for Merger/Restructuring ML22175A1132022-06-30030 June 2022 Solutions, Inc. - Letter for Review and Acceptance of the Energysolutions, LLC Decommissioning Quality Assurance Program with Enclosure 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 ML17332A0782017-12-12012 December 2017 ISFSI; Millstone and ISFSI; North Anna and ISFSI; Surry and ISFSI - Request for Approval of Revision 24 of the Nuclear Facility Quality Assurance Program Description Topical Report, DOM-QA-1 (CAC Nos. MF9732-MF9739; EPID L-2017-LLQ-0001) ML17123A0292017-06-0707 June 2017 Enclosure 2 - Safety Evaluation Report Related to the Unloaded Spent Fuel Pool at KPS - LAR260 ML17046A3162017-04-0606 April 2017 Connecticut, Virginia, Millstone, North Anna, Surry, Submission of Revision 21 of the Quality Assurance Topical Report for NRC Approval and Submission Revision 22 for Information Only (CAC Nos. MF8128 - MF8234) 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 ML14237A0452015-02-13013 February 2015 Issuance of Amendment No. 215, Revise Operating License and Technical Specifications to the Permanently Defueled Technical Specifications Consistent with Permanent Cessation of Reactor Operation ML14279A4822014-10-31031 October 2014 Issuance of Amendment, No. 214 Revise Permanently Defueled Emergency Plan and Emergency Action Level Scheme ML14261A2232014-10-27027 October 2014 Letter and Safety Evaluation, Exemptions from Emergency Planning Requirements of 10 CFR 50.47 and 10 CFR 50 Appendix E ML14008A2972014-06-23023 June 2014 Issuance of Amendment No. 213 - Deletion of License Conditions Associated with Extended Operations ML14111A2342014-06-0909 June 2014 Issuance of Amendment No. 212 Revise Operating License and Technical Specifications to the Permanently Defueled Technical Specifications Consistent with Permanent Cessation of Reactor Operation ML14104A0462014-05-12012 May 2014 Approval of Certified Fuel Handler Training Program ML12271A3662012-10-0404 October 2012 Relief Request Number RR-2-4 Regarding Fourth 10-Year Interval Inservice Inspection Program ML12249A4412012-09-20020 September 2012 Evaluation of Relief Request Number RR-G-5 Regarding Fourth 10-Year Interval Inservice Inspection Program ML1200505532012-02-17017 February 2012 Millstone Power Station Units 2 and 3, North Anna Power Station, Units 1 and 2, Surry Power Station Units 1 and 2 - Review of Dominion Fleet Quality Assurance Topical Report, Revision 11 ML11271A1782011-10-0303 October 2011 Review of Topical Report, Revision 11 for Kewaunee Power Station and ISFSI, Millstone Power Station, Units 1, 2, & 3 and ISFSI, North Anna Power Station, Units 1 & 2 and ISFSI, Surry Power Station, Units 1 & 2 and ISFSI (Tac ME6649, ME6650, ML11192A2492011-08-31031 August 2011 Issuance of Amendment Regarding Cyber Security to Dominion Plants ML11102A0272011-07-29029 July 2011 Issuance of Amendment License Amendment Request to Change the Current Licensing Basis for Automatic Operation of Transformer Load Tap Changers ML1110105232011-04-29029 April 2011 Issuance of Amendment 208 Regarding Technical Specification Change Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection for 52.1 Effective Full Power Years ML1033605042011-02-0202 February 2011 Part 002 ME2139 Safety Evaluation and Safety Evaluation Attachments ML1020206622011-02-0202 February 2011 Issuance of Amendment for Conversion to Improved Technical Specifications with Beyond Scope Issues ML1019701932010-08-22022 August 2010 Approval of Revision to Previously Approved IST Relief Request VRR-5 ML1016200342010-06-21021 June 2010 Approval to Remove Mixing Vane Grid Restriction in Appendix B of Dominion Fleet Topical Report DOM-NAF-2-A ML0934106522009-12-22022 December 2009 Authorization of Proposed Alternative RR-1-11 Regarding Visual Examinations for Reactor Pressure Vessel Bottom-Mounted Instrument Penetrations ML0923210792009-09-28028 September 2009 Irradiated Fuel Management Program and Preliminary Decommissioning Cost Estimate ML0905707102009-04-30030 April 2009 Issuance of Amendment No. 205 Seismic Analysis Methodology for the Auxiliary Building Crane ML0905708922009-04-27027 April 2009 Issuance of Amendment No. 204 Re. One-time Extension of the 15-Year Containment Integrated Leak Rate Test Interval ML0902805812009-02-0606 February 2009 Issuance of Amendment No. 203 Regarding Diesel Generator Fuel Storage Tank Capacity Requirement ML0833607832009-01-0909 January 2009 Issuance of Amendment Steam Line Isolation Function Applicability (Tac No. MD8544) ML0829710792008-11-20020 November 2008 Issuance of Amendment to Relocate Spent Fuel Pool Crane Requirements from the Technical Specifications to the Technical Requirements Manual ML0829405472008-11-0606 November 2008 License Amendment, Increased the Minimum Required Safety Injection Accumulator Boron Concentration from 1900 parts-per-million (Ppm) to 2400 Ppm ML0816201402008-07-0202 July 2008 Issuance of Amendment Deletion of License Condition on Fuel Burnup ML0814902822008-05-20020 May 2008 Submittal of Approved Topical Report DOM-NAF-5, Revision 0.0-A, Application of Dominion Nuclear Core Design and Safety Analysis Methods to the Kewaunee Power Station (KPS) ML0807701792008-03-28028 March 2008 Issuance of Amendments Licensing Basis Design Criteria Associated with Internal Flooding ML0804603632008-03-28028 March 2008 Issuance of Amendment Regarding Nuclear Instrumentation System Permissive Setpoints ML0806305402008-03-28028 March 2008 Issuance of License Amendment 196 Nuclear Core Design and Safety Analysis Methods ML0801604122008-02-0707 February 2008 Issuance of Amendment Regarding Emergency Diesel Generator Testing ML0728802892007-10-31031 October 2007 License Amendment Regarding Relocation of Technical Specifications Requirements ML0722903732007-08-30030 August 2007 Safety Evaluation for Topical Report DOM-NAF-5 ML0721102772007-08-14014 August 2007 Reactor Vessel Surveillance Capsule Test Results for Capsule T ML0721200032007-08-0202 August 2007 Conforming License Amendment to Incorporate the Mitigation Strategies Required by Section B.5.b. of Commission Order EA-02-026 Tac No. MD4543) ML0711100062007-05-18018 May 2007 Issuance of Amendment Refueling Water Storage Tank Boron Concentration ML0712001862007-05-0101 May 2007 Issuance of License Amendment 191 Regarding Emergency Diesel Generator Rated Load Testing ML0704300202007-03-0808 March 2007 Radiological Accident Analysis ML0631800362006-12-14014 December 2006 License Amendment 189 Regarding Referencing the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Operation and Maintenance of Nuclear Power Plants ML0624205112006-08-30030 August 2006 Approval of Topical Report DOM-NAF-3 ML0617002082006-07-17017 July 2006 Issuance of Amendment Steam Generator Tube Integrity ML0616402862006-07-12012 July 2006 Issuance of Amendment Surveillance Interval Extension 2024-01-26
[Table view] |
Text
March 28, 2008 Mr. David A. Christian President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
KEWAUNEE POWER STATION - ISSUANCE OF AMENDMENT RE: NUCLEAR CORE DESIGN AND SAFETY ANALYSIS METHODS (TAC NO. MD6824)
Dear Mr. Christian:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 196 to Facility Operating License No. DPR-43 for the Kewaunee Power Station. This amendment revises the Technical Specifications (TSs) in response to your application dated September 24, 2007, as supplemented on January 18, 2008.
The amendment revises the TSs to add a reference to Dominion Topical Report DOM-NAF-5, "Application of Dominion Nuclear Core Design and Safety Analysis Methods to the Kewaunee Power Station," to the list of approved analytical methods. The amendment permits the application of the Dominion nuclear core design and safety analysis methods, including the methodology to perform core thermal-hydraulic analysis to predict critical heat flux and departure from nucleate boiling ratio for the Westinghouse 422 V+ fuel design.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely,
/RA/ Patrick D. Milano, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305
Enclosures:
- 1. Amendment No. 196 to License No. DPR-43 2. Safety Evaluation cc w/encls: See next page
ML080630540 Pkg: ML080630529 TS: ML080910087 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/SRXB/BC OGC (NLO w/edits) NRR/LPL3-1/BC NAME PMilano THarris GCranston PMoulding LJames DATE 03/26/08 3/27/08 02/26/08 03/19/08 3/28/08 Kewaunee Power Station cc: Resident Inspectors Office U.S. Nuclear Regulatory Commission N490 Hwy 42 Kewaunee, WI 54216-9510 Mr. Chris L. Funderburk Director, Nuclear Licensing and Operations Support Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 Mr. Thomas L. Breene Dominon Energy Kewaunee, Inc. Kewaunee Power Station N490 Highway 42 Kewaunee, WI 54216
Ms. Lillian M. Cuoco, Esq. Senior Counsel Dominion Resources Services, Inc. 120 Tredegar Street Riverside 2 Richmond, VA 23219
Mr. Stephen E. Scace Site Vice President Dominion Energy Kewaunee, inc. Kewaunee Power Station N 490 Highway 42 Kewaunee, WI 54216
Mr. Thomas J. Webb, Director Nuclear Safety & Licensing Dominion Energy Kewaunee, Inc. Kewaunee Power Station N 490 Highway 42 Kewaunee, WI 54216
DOMINION ENERGY KEWAUNEE, INC.
DOCKET NO. 50-305 KEWAUNEE POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 196 License No. DPR-43
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Dominion Energy Kewaunee, Inc. dated September 24, 2007, as supplemented on January 18, 2008, 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-43 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 196, 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 its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/ Lois James, Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License and Technical Specifications
Date of Issuance: March 28, 2008 ATTACHMENT TO LICENSE AMENDMENT NO. 196 FACILITY OPERATING LICENSE NO. DPR-43 DOCKET NO. 50-305
Replace the following page of the Facility Operating License No. DPR-43 with the attached revised page. The changed area is identified by a marginal line.
REMOVE INSERT Page 3 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 3.10-2 3.10-2 3.10-3 3.10-3 6.9-3 6.9-3 6.9-4 6.9-4 6.9-5 6.9-5
C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR, Chapter 1: (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, (2) is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and (3) 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 1772 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 196, are hereby incorporated in the license. The licensee shall operate the facility In accordance with the Technical Specifications.
(3) Fire Protection The licensee shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the licensee's Fire Plan, and as referenced in the Updated Safety Analysis Report, and as approved in the Safety Evaluation Reports, dated November 25, 1977, and December 12, 1978 (and supplement dated February 13, 1981) subject to the following provision:
The licensee may make changes to the approved Fire Protection Program without prior approval of the Commission, only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(4) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: A Nuclear Management Company Kewaunee Nuclear Power Plant Physical Security Plan (Revision 0)" submitted by letter dated October 18, as supplemented by letter dated October 21, 2004.
(5) Fuel Burnup The maximum rod average burnup for any rod shall be limited to 60 GWD/MTU until completion of an NRC environmental assessment supporting an increased limit. 3 Amendment No. 196 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO AMENDMENT NO. 196 TO FACILITY OPERATING LICENSE NO. DPR-43 DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION DOCKET NO. 50-305
1.0 INTRODUCTION
By application dated September 24, 2007, as supplemented by letter dated January 18, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML072680278 and ML080180444, respectively), Dominion Energy Kewaunee, Inc. (the licensee) requested changes to the Technical Specifications (TSs) for the Kewaunee Power Station (KPS). The January 18, 2008, supplement, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register on October 23, 2007 (72 FR 60034).
The proposed changes would: (1) revise the list of approved analytical methods in the core operating limits report (COLR) in TS 6.9.a.4.B, (2) use the provisions of TS Task Force (TSTF) change traveler TSTF-363-A to modify TS 6.9.a.4.B for the characterization of approved methodologies and add a new TS 6.9.a.4.E, requiring the complete identification of those methodologies in the COLR, and (3) change the nomenclature for the height dependent hot channel factor in TS Sections 3.10.b and 6.9.a.4.A. The September 24, 2007, application also requested that TS 2.1.b be modified to substitute the value of the departure from nuclear boiling ratio (DNBR) with the DNBR criterion for the departure from nucleate boiling (DNB) correlations and methodologies listed in Section 6.9 of the TSs. However, in its January 18, 2008, letter, the licensee withdrew its proposed changes to TS 2.1.b.
2.0 REGULATORY EVALUATION
Part 50 to Title 10 of the Code of Federal Regulations (10 CFR Part 50), establishes the U.S. Nuclear Regulatory Commission's (NRC's) fundamental regulatory requirements with respect to the domestic licensing of nuclear production and utilization facilities.
2.1 Background
As stated in the KPS Updated Safety Analysis Report (USAR), the plant was designed to comply with the original owner's (Wisconsin Public Service Corporation's, WPSC's) understanding of the intent of the Atomic Energy Commission (AEC) General Design Criteria (GDC) for Nuclear Power Plant Construction Permits, as proposed on July 10, 1967. In a letter dated October 2, 1967, the Atomic Industrial Forum (AIF) distributed comments on the July 1967 AEC GDC. This AIF document was adopted as WPSC's understanding of the method for complying with the AEC GDC. In addition, the licensing basis for KPS is based on the AEC safety evaluation dated July 24, 1972. In Section 3.1, "Conformance with AEC General Design Criteria," the staff performed a technical review to assess the plant against the revised General Design Criteria, issued in 1971, and found that a re-analysis of the plant was not required and that the plant design generally conformed to the intent of the criteria.
2.2 Core Design and Safety Analysis
Section 3.1.3,"Safety Limits," of the USAR states that the reactor is capable of meeting the performance objectives throughout core life under both steady state and transient conditions without violating the integrity of the fuel cladding. Thus, the release of unacceptable amounts of fission products to the coolant is prevented. The TS limiting conditions for operation specify the minimum functional capability or performance levels necessary to assure safe operation of the facility. Design parameters, which are established by safety limits in TS Section 2, are established for the nuclear, reactivity control, thermal and hydraulic, and mechanical aspects of the design.
2.3 Proposed
TS Changes
2.3.1 Changes
to TS 6.9.4.a.4, "Core Operating Limits Report"
- a. To the list of approved list of analytical methods in TS 6.9.4.a.4.B that are used to determine the core operating limits, the licensee has proposed to add:
(16) Topical Report DOM-NAF-5-A, "Application of Dominion Nuclear Core Design and Safety Analysis Methods to the Kewaunee Power Station (KPS).
and delete:
(1) Safety Evaluation by the Office of Nuclear Reactor Regulation on "Qualifications of Reactor Physics Methods For Application To Kewaunee" Report, dated August 21, 1979, report date September 29, 1978.
- b. Consistent with TSTF-363-A, "Revise Topical Report References in ITS 5.6.5, COLR," dated August 4, 2003, the licensee has proposed to delete the method revision numbers and dates from TS 6.9.4.a.4.B.
- c. The licensee has proposed to add a new TS 6.9.4.a.4.E as follows:
E. The COLR will contain the complete identification of the TS approved analytical methods used to prepare the COLR (i.e. report number, title, revision, date, and any supplements).
2.3.2 Change
of the Nomenclature for Height Dependent Hot Channel Factor The licensee proposed to change the current nomenclature for the height dependent hot channel factor (F Q EQ(z)) to a more generic nomenclature (F Q N(z)) for this core surveillance parameter as described in TS 3.10.b, "Power Distribution Limits." This proposed change affects TS 3.10.b.3.C, TS 3.10.b.5, TS 3.10.b.6, TS 3.10.b.6.C.i, TS 3.10.b.6.C.ii, TS 3.10.b.7, TS 3.10.b.7.A, TS 3.10.b.7.C, TS 6.9.a.4.A(9) and TS 6.9.a.4.A(10).
2.4 Regulatory
Requirements and Guidance The regulatory requirements and guidance that the NRC staff considered in its review of the applications are as follows:
A. KPS USAR Section 1.3 provides a list of applicable AEC GDC, as proposed on July 10, 1967. In particular, Criterion 6, "Reactor Core Design," states that the core, with its related controls and protection systems, shall be designed to function throughout its design lifetime without exceeding acceptable fuel damage limits, which have been stipulated and justified. The core and related auxiliary system designs shall provide this integrity under all expected conditions of normal operation with appropriate margins for uncertainties and for specified transient situations which can be anticipated.
B. Criterion 14, "Core Protection Systems," states that these protection systems, together with associated equipment, shall be designed to prevent or to suppress conditions that could result in exceeding acceptable fuel damage limits.
C. Section 50.36, "Technical specifications," of 10 CFR Part 50 states, "Each applicant for a license authorizing operation of a production or utilization facility shall include in his application proposed technical specifications in accordance with the requirements of this section." This regulation requires that the TSs include items in five categories: (1) safety limits, limiting safety system settings, and limiting control settings, (2) limiting conditions for operation, (3) surveillance requirements, (4) design features, and (5) administrative controls. The licensee's proposed changes to TS 3.10.b and TS 6.9.a.4 are within the limiting control settings and the administrative controls categories.
D. TSTF Change Traveler TSTF-363-A provides for a requirement to be added to the TSs to specify the complete citation in the COLR for each Topical Report, including the report number, title, revision, date, and any supplements.
3.0 TECHNICAL EVALUATION
3.1 TS 6.9.a.4.B Core Operating Limits Report (COLR)
TS 6.9.a.4.B states that only the listed NRC-reviewed and approved methodologies shall be used to determine core limits. The licensee has proposed to add the Topical Report DOM-NAF-5 (Ref. 3) and delete the existing method, "Qualifications of Reactor Physics Methods for Application to Kewaunee," issued September 1978, that was approved on August 21, 1979. The Topical Report DOM-NAF-5 has been reviewed and approved for KPS by the NRC staff in a safety evaluation dated August 30, 2007 (ADAMS No. ML072290373), to the extent specified in the Topical Report and safety evaluation and under the limitations described therein.
Because DOM-NAF-5 has been reviewed and approved by the NRC staff, it is qualified and acceptable to be listed as a COLR reference in TS 6.9.a.4.B.
3.2 Delete
Data and Revision Information from the list of Approved Methods, Relocate to COLR This TS change is based on TSTF-363-A, which allows the modification of TS 6.9.a.4.B to delete method revision numbers and dates from the current requirements in the list of approved methodologies and the addition of new TS 6.9.a.4.E, requiring complete identification of those analytical methods in the COLR. By deleting revision number and date from TS 6.9.a.4.B, subsequent revisions in the method would not need a request for a TS change, provided that the change did not affect the validity of the method. The new TS 6.9.a.4.E would read as follows: The COLR will contain the complete identification of the TS approved analytical methods used to prepare the COLR (i.e., report number, title, revision, date, and any supplements).
Because the proposed change to TS 6.9.a.4.B is consistent with TSTF-363-A and the complete identification of the methods will be included in the COLR, as required by new TS 6.9.a.4.E, the NRC staff finds the changes acceptable.
3.3 Change
the Nomenclature for Height Dependent Hot Channel Factor
The licensee has proposed that TS 3.10.b, "Power Distribution Limits," be revised to change the nomenclature for the height dependent hot channel F Q EQ(z) to F Q N(z) in the TSs to allow either the Westinghouse relaxed axial offset control (RAOC) or the Dominion relaxed power distribution control (RPDC) methods to be used at KPS. The hot channel factor is measured (under equilibrium conditions) using the monthly core maps. For non-equilibrium conditions, the value is supplemented with an axially-dependent multiplication factor (W(z) for RAOC and N(z) for RPDC), which account for bounding values of calculated non-equilibrium states. Both methods for axial offset control have been approved for use at KPS. It should be noted that allowing use of the Westinghouse RAOC approval methods does not include the Westinghouse RAOC validity criteria methodology, which is a Westinghouse method not reviewed or approved by the NRC to deal with deviations from the RAOC method acceptance criteria. In addition, the surveillance limits and the power distribution control methods applicable to a particular cycle will be documented in the COLR.
The NRC staff finds that the proposed change will facilitate the application of approved methodologies without the complication of two different names for similar parameters. Therefore, the staff finds it acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Wisconsin State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
This 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 staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent 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 this amendment involves no significant hazards consideration and there has been no public comment on such finding (72 FR 60034). Accordingly, this 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 this amendment.
6.0 CONCLUSION
The staff 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 this amendment will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
- 1. Dominion Energy Kewaunee Letter, G.T. Bischof to NRC, "License Amendment Request 228 Incorporation of Dominion Nuclear Analysis and Fuel Topical Report DOM-NAF-5 Into Kewaunee Technical Specifications" September 24, 2007.
- 2. Dominion Energy Kewaunee Letter, G.T. Bischof to NRC, "Response to Request for Additional Information Regarding Kewaunee License Amendment Request 228," January 18, 2008.
- 3. Topical Report DOM-NAF-5, "Application of Dominion Nuclear Design and Safety Analysis Methods to the Kewaunee Power Station (KPS)," by Dominion Energy Kewaunee, April 16, 2007.
- 4. NRC letter, P.D. Milano to D.A. Christian, Dominion Energy Kewaunee, "Kewaunee Power Station - Safety Evaluation for Topical Report DOM-NAF-5, (TAC No. MD2829)" August 30, 2007.
- 5. Technical Specification Task Force Change Traveler TSTF-363-A, Revision 0, "Revise Topical Report References in ITS 5.6.5, COLR," April 13, 2000 (as incorporated into NUREG-1431, Revision 2, dated April 13 2001).
Principal Contributor: L. Lois, NRR Date: March 28, 2008