Letter Sequence Approval |
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MONTHYEARML0815502462008-06-18018 June 2008 Environmental Assessment and Finding of No Significant Impact Fuel Burnup Limit Project stage: Other ML0816201402008-07-0202 July 2008 Issuance of Amendment Deletion of License Condition on Fuel Burnup Project stage: Approval ML0822702822008-08-22022 August 2008 Correction of Error in Amendment No. 198 Regarding Deletion of the License Condition on Fuel Burnup Project stage: Other 2008-07-02
[Table View] |
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Category:Letter
MONTHYEARML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24136A1952024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report ML24130A0022024-05-0909 May 2024 Summary of Facility Changes, Tests and Experiments and Commitment Changes IR 05000305/20240012024-05-0202 May 2024 NRC Inspection Report No. 05000305/2024001 ML24121A2472024-04-29029 April 2024 and Three Mile Island, Unit 2 - 2023 Occupational Radiation Exposure Annual Report ML24101A0422024-04-22022 April 2024 Solutions Inc. – Exemption from Select Requirements of 10 CFR Part 73 ((Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24106A0492024-04-15015 April 2024 2023 Annual Radioactive Effluent Release Report ML24080A0702024-03-20020 March 2024 Decommissioning Trust Fund Annual Report ML24079A0162024-03-19019 March 2024 Annual Property Insurance Status Report ML24073A2312024-03-13013 March 2024 and Three Mile Island Nuclear Station, Unit 2 - Management Change ML24061A0202024-02-15015 February 2024 (Ksp) ISFSI, Submittal of Security Plan, Training and Qualification Plan and Safeguards Contingency Plan, Revision 6 ML23339A1332024-01-26026 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 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 ML23088A2752023-03-29029 March 2023 Solutions, Inc., Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E 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 ML24061A0182022-08-25025 August 2022 (Ksp) ISFSI Submittal of Security Pla11, Training and Qualification Plan and Safeguards Contingency Plan Revision 5 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 ML22160A5262022-06-28028 June 2022 Letter - KPS - Issuance of Conforming License Amendment Regarding Indirect Transfer of License from DEK, Inc. to Kewaunee Solutions, Inc 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 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 ML22091A1892022-04-0101 April 2022 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report ML22108A0352022-04-0101 April 2022 License Transfer to Kewaunee Solutions, Inc 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) 2024-06-03
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML17123A0282017-06-0707 June 2017 Enclosure 1 - KPS Amendment 220 Regarding Permanent Removal of Spent Fuel for the Spent Fuel Pool - LAR260 ML17052A5912017-05-0909 May 2017 KPS Amendment 219 - Removal of Cyber Security Requirements for Operating License ML16341C7912017-03-0202 March 2017 Enclosure 1 - Amendment to Facility Operating License ML16320A0442016-11-30030 November 2016 Amendment No. 217 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 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 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 ML0530403522011-02-24024 February 2011 Current Facility Operating License DPR-43, Tech Specs, Revised 10/07/2015 ML1101006002011-02-24024 February 2011 Renewed License ML1101005752011-02-24024 February 2011 Issuance of Renewed Facility Operating License No. DPR-043 for Kewaunee Power Station ML1033706912011-02-0202 February 2011 Part 080 ME2139 List of Acronyms and Abbreviations ML1020206622011-02-0202 February 2011 Issuance of Amendment for Conversion to Improved Technical Specifications with Beyond Scope Issues ML1002110292009-08-0303 August 2009 2009 Kewaunee Power Station Retake Examination Proposed Exam Files ML0912710592009-06-0101 June 2009 License Amendment No. 206, Containment Purge and Vent Isolation Valves Surveillance Requirement 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) ML0832906532008-12-30030 December 2008 License Amendment, Issuance of Amendment No. 201 Shield Building and Auxiliary Building Special Ventilation Train Filter Heater Requirements 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 ML0804603632008-03-28028 March 2008 Issuance of Amendment Regarding Nuclear Instrumentation System Permissive Setpoints ML0807701792008-03-28028 March 2008 Issuance of Amendments Licensing Basis Design Criteria Associated with Internal Flooding ML0728802892007-10-31031 October 2007 License Amendment Regarding Relocation of Technical Specifications Requirements ML0721300932007-08-0202 August 2007 Revised Pages of Facility Operating License No. DPR-43 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 ML0617002082006-07-17017 July 2006 Issuance of Amendment Steam Generator Tube Integrity ML0616402862006-07-12012 July 2006 Issuance of Amendment Surveillance Interval Extension ML0532100822005-11-18018 November 2005 Correction to Amendment 186 ML0521504282005-10-0404 October 2005 Issuance of License Amendment 186 Regarding Technical Specification Changes for Radioactive Effluents Control Program and Off-Site Dose Calculation Manual ML0518801062005-07-0505 July 2005 Issuance of Conforming Amendment Re Transfer of Facility Operating License from Nuclear Management Company, Wisconsin Public Service Corp and Wisconsin Power and Light Company to Dominion Energy Kewaunee, Inc ML0517100302005-06-21021 June 2005 Emergency License Amendment, Revises the TSs to Remove the Requirement to Have a Containment Spray Pump Suction Flow Path from the Containment Sump ML0516000912005-06-20020 June 2005 Issuance of Amendment Auxiliary Feedwater System ML0503902742005-04-0606 April 2005 Issuance of License Amendment 182 Relocation of Surveillance Requirements ML0505407072005-03-24024 March 2005 License Amendment, Revised Technical Specification Rod Position Indication ML0435001062005-02-15015 February 2005 Issuance of License Amendment 180 Administrative Changes to Technical Specifications ML0433800022004-12-22022 December 2004 Issuance of Amendment Deletion of Requirements for Submittal of Occupational Radiation Exposure Reports, Reports of Challenges to and Failures of the Pressurizer Power Operated Relief Valves and Safety Valves ML0431200302004-10-29029 October 2004 Administrative Change to Facility Operating License in Conjunction with the Commission Order EA-03-086 Regarding Revised Design Basis Threat... ML0514402972004-10-26026 October 2004 Revision to Emergency Action Levels, Facility Operating License as Amended Through October 21, 2004 Document ML0426400982004-10-0505 October 2004 License Amendment, Revises TS 3.3.a.2.B, by Extending Completion Time from 1 Hour to 24 Hours for an Accumulator That Is Inoperable for Any Reason Other than Failure to Meet Minimum Boron Concentration Requirements ML0416100952004-09-24024 September 2004 Issuance of Amendment No. 177 Re. Revision of TS 3.3.e, Service Water System ML0422300682004-09-22022 September 2004 License Amendment No. 176, Revise TS 3.10.f.2 to Add an Allowed Outage Time for the Individual Rod Position Indication (Irpi) System of 24 Hours with More than One Irpi Group Inoperable & Adds the Definition of Immediately to TS Section 1.0 2017-06-07
[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
July 2, 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: DELETION OF LICENSE CONDITION ON FUEL BURNUP (TAC NO. MD6085)
Dear Mr. Christian:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 198 to Facility Operating License No. DPR-43 for the Kewaunee Power Station. This amendment revises the license in response to your application dated July 2, 2007.
The amendment revises the facility operating license by removing condition 2.C(5), Fuel Burnup, which had limited the peak rod average burnup to 60 gigawatt-days per metric ton uranium until completion of an NRC environmental assessment supporting an increased limit.
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/
Jack Cushing, 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. 198 to License No. DPR-43
- 2. Safety Evaluation cc w/encls: See next page
ML081620140 Package:ML081620154 TS: ML081620196 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/DSA/SNPB OGC NRR/LPL3-1/BC NAME JCushing THarris AMendiola MSpenser LJames DATE 07/ 02 /08 07 / 01 /08 02/27/08 07/01/08 07 / 02 /08 Kewaunee Power Station cc:
Resident Inspectors Office Ms. Lillian M. Cuoco, Esq.
U.S. Nuclear Regulatory Commission Senior Counsel N490 Hwy 42 Dominion Resources Services, Inc.
Kewaunee, WI 54216-9510 120 Tredegar Street Riverside 2 Mr. Chris L. Funderburk Richmond, VA 23219 Director, Nuclear Licensing and Operations Support Mr. Stephen E. Scace Innsbrook Technical Center Site Vice President 5000 Dominion Boulevard Dominion Energy Kewaunee, Inc.
Glen Allen, VA 23060-6711 Kewaunee Power Station N 490 Highway 42 Mr. Thomas L. Breene Kewaunee, WI 54216 Dominon Energy Kewaunee, Inc.
Kewaunee Power Station Mr. Thomas J. Webb, Director N490 Highway 42 Nuclear Safety & Licensing Kewaunee, WI 54216 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. 198 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 July 2, 2007, 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. 198, are hereby incorporated in the license. The licensees 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 M. James, Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License Date of Issuance: July 2, 2008
ATTACHMENT TO LICENSE AMENDMENT NO.198 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
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. 198, 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: 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, July 26, 2005, and May 15, 2006.
(5) Deleted Amendment No. 198 3
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO AMENDMENT NO. 198 TO FACILITY OPERATING LICENSE NO. DPR-43 DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION DOCKET NO. 50-305
1.0 INTRODUCTION
By application dated July 2, 2007 (Agencywide Documents Access and Management System Accession No. ML071860075), Dominion Energy Kewaunee, Inc. (the licensee), requested a change to Facility Operating License No. 43 for the Kewaunee Power Station (KPS).
The proposed change would delete license condition, 2.C (5) Fuel Burnup, which limits the peak rod average burnup to 60 gigawatt-days per metric ton of uranium (GWD/MTU) until completion of a Nuclear Regulatory Commission (NRC) environmental assessment supporting an increased limit. Upon the deletion of license condition 2.C (5), the licensee will be able to increase the peak rod average burnup limit to 62 GWD/MTU for its VANTAGE+ fuel assemblies.
2.0 REGULATORY EVALUATION
Part 50 to Title 10 of the Code of Federal Regulations (10 CFR Part 50), establishes the fundamental regulatory requirements with respect to the domestic licensing of nuclear production and utilization facilities.
2.1 Background In January 2001, the NRC staff published Report No. NUREG/CR-6703, entitled Environmental Effects of Extending Fuel Burnup Above 60 GWD/MTU, to support the burnup increase. The KPS reactor core contains Westinghouse VANTAGE+ fuel design with a 14x14 rod array. The VANTAGE+ fuel design features ZIRLO cladding and was approved by the NRC in Westinghouse Topical Report WCAP-12610-P-A, entitled VANTAGE+ Fuel Assembly Reference Core Report. The VANTAGE+ fuel design, including the KPS fuel, was approved to a peak rod average burnup limit of 60 GWD/MTU. In letter dated May 25, 2006 (ML061420458), the NRC staff approved a request by Westinghouse that the VANTAGE+ fuel burnup limit be increased to 62 GWD/MTU, provided that the evaluation of the fuel performance is performed using the Westinghouse fuel performance code PAD 4.0. The PAD 4.0 Code, as described in a Topical Report WCAP-15063-P-A, entitled Westinghouse Improved Performance Analysis and Design Model (PAD 4.0), was approved by the NRC to a peak rod average burnup limit of 62 GWD/MTU.
2.2 Proposed Change to Operating License The licensee has proposed to delete the current license condition 2.C (5), Fuel Burnup, which states:
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.
2.3 Regulatory Requirements As stated in the KPS Updated Safety Analysis Report (USAR), the plant was designed to comply with the original owners (Wisconsin Public Service Corporations, WPSCs) 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 WPSCs 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 GDC, 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.
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.
3.0 TECHNICAL EVALUATION
3.1 Staff Position In the past, the NRC staff has approved various burnup limits for Westinghouse fuel designs and fuel performance codes. The VANTAGE fuel series, including VANTAGE+, was approved to the burnup limit of 60,000 megawatt-days/MTU (MWD/MTU; same as 60 GWD/MTU), and more recently, Westinghouse fuel performance code, PAD 4.0, was approved to the burnup limit of 62,000 MWD/MTU.
Recently, the NRC staff conducted an audit of the Westinghouse documents describing the fuel data, analytical models, and the fuel change procedures. The staff reviewed documents including several plant reload analyses. The reload analyses provided the results for all the specified acceptable fuel design limits (SAFDLs), as described in 10 CFR Part 50, Appendix A, GDC 10.
Criterion 10--Reactor design. The reactor core and associated coolant, control, and protection systems, shall be designed with appropriate margin to assure that specified acceptable fuel
design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.
The analyses were typically performed at bounding conditions such that plant thermal-mechanical safety evaluations were not required for each reload cycle. The SAFDLs include rod internal pressure, clad stress and strain, corrosion, clad fatigue, fuel melting temperature, rod growth, creep collapse, etc. The results showed that all SAFDLs were met for the bounding conditions. The staff also recognized that the SAFDLs were analyzed using the PAD 4.0 code, which was approved to a peak rod average burnup of 62,000 MWd/MTU. Based on the audit results, the staff concludes that burnup limit for WCAP-12610-P-A can be increased to 62,000 MWD/MTU provided that the evaluation of the fuel design performance is performed with PAD 4.0.
By letter dated May 25, 2006 (ML061420458), the staff approved the burnup increase for the VANTAGE fuel series. Therefore, the burnup limit of the VANTAGE+ fuel design including the Kewaunee fuel can be increased to 62,000 MWD/MTU peak rod average.
3.2 Mechanical Design The KPS fuel is comprised of a VANTAGE+ fuel design, and the design bases and methodology conform to the approved WCAP-12610-P-A. The licensee performed mechanical design analyses using the approved PAD 4.0 code. The design analyses included all SAFDLs. The results showed that all SAFDLs were met for the bounding conditions. Based on the approved PAD 4.0 code, which complies with the staff position, the NRC staff concludes that the KPS fuel burnup can be increased to 62,000 MWD/MTU peak rod average.
The new burnup limit of 62,000 MWD/MTU will be maintained through the licensees Updated Safety Analysis Report which contains the 62,0000 MWD/MTU limit, and by WCAP-12610-P-A, which has been incorporated into the Core Operating Limits Report (COLR) as described in TS 6.9.a.4.B.
3.3 License Condition 3.4 Summary The NRC staff has reviewed the licensees proposed license amendment to delete a license condition regarding fuel burnup. Based on its evaluation, as set forth above, the staff concludes that the proposed license amendment to delete the license condition 2.C (5) is 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
Environmental Assessment The NRC staff assessed the environmental impact of extending peak rod average burnup at operating plants. In January 2001, the staff published NUREG/CR-6703, entitled
Environmental Effects of Extending Fuel Burnup Above 60 GWD/MTU. The staff concluded that there were no significant adverse environmental impacts associated with increasing peak rod average burnup to 62,000 MWd/MTU. Based on the environment assessment, the staff concludes that the Kewaunee fuel can be increased to 62,000 MWd/MTU peak rod average.
Pursuant to 10 CFR Part 51.21, 51.30, 51.32, and 51.35, an Environmental Assessment and finding of no significant impact was prepared and published in the Federal Register on ,
2008 (73 FR 36134). Accordingly, based upon the environmental assessment, the Commission has determined that the issuance of this amendment will not have a significant effect on the quality of the human environment.
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 this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: S.Wu Date: July 2, 2008