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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
May 13, 2004 Mr. Thomas Coutu Site Vice President Kewaunee Nuclear Power Plant Nuclear Management Company, LLC N490 Highway 42 Kewaunee, WI 54216-9511
SUBJECT:
KEWAUNEE NUCLEAR POWER PLANT - ISSUANCE OF AMENDMENT RE: RELOCATION OF REQUIREMENTS FOR HYDROGEN MONITORS (TAC NO. MC1901)
Dear Mr. Coutu:
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 174 to Facility Operating License No. DPR-43 for the Kewaunee Nuclear Power Plant. This amendment revises the Technical Specifications in response to your application dated January 30, 2004.
The amendment relocates the requirements for hydrogen monitors from the Technical Specifications to the Technical Requirements Manual. A notice of availability for this technical specification improvement using the consolidated line item improvement process was published in the Federal Register on September 25, 2003 (68 FR 55416).
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next regular biweekly Federal Register notice.
Sincerely,
/RA/
Carl F. Lyon, Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-305
Enclosures:
- 1. Amendment No. 174 to License No. DPR-43
- 2. Safety Evaluation cc w/encls: See next page
ML041170474 NRR-058 OFFICE CLIIP LPM PM:PD3-1 LA:PD3-1 OGC SC:PD3-1 NAME WReckley MPadovan FLyon THarris RWeisman* LRaghavan DATE 4/14/04 4/29/04 4/29/04 4/28/04 5/10/04 5/12/04 Kewaunee Nuclear Power Plant cc:
John Paul Cowan Jonathan Rogoff Executive Vice President & Vice President, Counsel & Secretary Chief Nuclear Officer Nuclear Management Company, LLC Nuclear Management Company, LLC 700 First Street 700 First Street Hudson, WI 54016 Hudson, MI 54016 Larry L. Weyers James McCarthy Chairman, President and CEO Plant Manager Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant 600 North Adams Street N490 Highway 42 Greey Bay, WI 54307-9002 Kewaunee, WI 54216-9511 David Zellner Gerry Riste Chairman - Town of Carlton Manager, Regulatory Affairs N2164 County B Kewaunee Nuclear Power Plant Kewaunee, WI 54216 N490 Highway 42 Kewaunee, WI 54216-9511 Mr. Jeffery Kitsembel Electric Division David Molzahn Public Service Commission of Wisconsin Nuclear Asset Manager PO Box 7854 Wisconsin Public Service Corporation Madison, WI 53707-7854 600 N. Adams Street Green Bay, WI 54307-9002 Thomas Webb Nuclear Asset Manager Wisconsin Public Service Corporation 600 N. Adams Street Green Bay, WI 54307-9002 Resident Inspectors Office U. S. Nuclear Regulatory Commission N490 Hwy 42 Kewaunee, WI 54216-9510 Regional Administrator Region III U. S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351
NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-305 KEWAUNEE NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 174 License No. DPR-43
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Nuclear Management Company, LLC (NMC),
dated January 30, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions 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. 174, 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 120 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
L. Raghavan, Chief, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 13, 2004
ATTACHMENT TO LICENSE AMENDMENT NO. 174 FACILITY OPERATING LICENSE NO. DPR-43 DOCKET NO. 50-305 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 Table TS 3.5-6 Page 1 of 2 Table TS 3.5-6 Page 1 of 2 Table TS 3.5-6 Page 2 of 2 Table TS 3.5-6 Page 2 of 2 Table TS 4.1-1 Page 6 of 7 Table TS 4.1-1 Page 6 of 7
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO AMENDMENT NO. 174 TO FACILITY OPERATING LICENSE NO. DPR-43 NUCLEAR MANAGEMENT COMPANY, LLC KEWAUNEE NUCLEAR POWER PLANT DOCKET NO. 50-305
1.0 INTRODUCTION
By application to the U.S. Nuclear Regulatory Commission (NRC, Commission) dated January 30, 2004, the Nuclear Management Company, LLC (the licensee), requested changes to the Technical Specifications (TSs) for the Kewaunee Nuclear Power Plant (ADAMS Accession No. ML040420424). The proposed changes would relocate the TS requirements associated with hydrogen monitors to the Technical Requirements Manual.
The NRC has revised 10 CFR 50.44, Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors. The amended standards eliminated the requirements for hydrogen recombiners and relaxed the requirements for hydrogen and oxygen monitoring. In letters dated December 17, 2002, and May 12, 2003, the Nuclear Energy Institute (NEI)
Technical Specification Task Force (TSTF) proposed to remove requirements for hydrogen recombiners and hydrogen and oxygen monitors from the standard technical specifications (STS) (NUREGs 1430 - 1434) on behalf of the industry to incorporate the amended standards.
This proposed change is designated TSTF-447.
The NRC staff prepared this model safety evaluation (SE) for the elimination of requirements regarding containment hydrogen recombiners and the removal of requirements from TSs for containment hydrogen and oxygen monitors and solicited public comment (67 FR 50374, published August 2, 2002) in accordance with the Consolidated Line Item Improvement Process (CLIIP). The use of the CLIIP in this matter is intended to help the NRC to efficiently process amendments that propose to remove the hydrogen recombiner and hydrogen and oxygen monitor requirements from TS. Licensees of nuclear power reactors to which this model applies were informed (68 FR 55416; September 25, 2003) that they could request amendments conforming to the model, and, in such requests, should confirm the applicability of the SE to their reactors and provide the requested plant-specific verifications and commitments.
2.0 BACKGROUND
Regulatory Issue Summary 2000-06, Consolidated Line Item Improvement Process for Adopting Standard Technical Specification Changes for Power Reactors, was issued on March 20, 2000. The CLIIP is intended to improve the efficiency of NRC licensing processes.
This is accomplished by processing proposed changes to the STS in a manner that supports subsequent license amendment applications. The CLIIP includes an opportunity for the public
to comment on proposed changes to the STS following a preliminary assessment by the NRC staff and finding that the change will likely be offered for adoption by licensees. The NRC staff evaluates any comments received for a proposed change to the STS and either reconsiders the change or proceeds with announcing the availability of the change for proposed adoption by licensees. Those licensees opting to apply for the subject change to TSs are responsible for reviewing the staffs evaluation, referencing the applicable technical justifications, and providing any necessary plant-specific information. Each amendment application made in response to the notice of availability would be processed and noticed in accordance with applicable rules and NRC procedures.
The Commissions regulatory requirements related to the content of TSs are set forth in 10 CFR 50.36. This regulation requires that the TSs include items in five specific categories.
These categories include: 1) safety limits, limiting safety system settings and limiting control settings; 2) limiting conditions for operation (LCO); 3) surveillance requirements; 4) design features; and 5) administrative controls. However, the regulation does not specify the particular TSs to be included in a plants license.
Additionally, 10 CFR 50.36(c)(2)(ii) sets forth four criteria to be used in determining whether an LCO is required to be included in the TS. These criteria are as follows:
- 1. Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.
- 2. A process variable, design feature, or operating restriction that is an initial condition of a design-basis accident or transient analysis that assumes either the failure of or presents a challenge to the integrity of a fission product barrier.
- 3. A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design-basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
- 4. A structure, system or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
Existing LCOs and related surveillances included as TS requirements which satisfy any of the criteria stated above must be retained in the TSs. Those TS requirements which do not satisfy these criteria may be relocated to other licensee-controlled documents.
As part of the rulemaking that revised 10 CFR 50.44, the Commission retained requirements for ensuring a mixed atmosphere, inerting Mark I and II containments, and providing hydrogen control systems capable of accommodating an amount of hydrogen generated from a metal-water reaction involving 75 percent of the fuel cladding surrounding the active fuel region in Mark III and ice condenser containments. The Commission eliminated the design-basis loss-of-coolant accident (LOCA) hydrogen release from 10 CFR 50.44 and consolidated the requirements for hydrogen and oxygen monitoring to 10 CFR 50.44 while relaxing safety classifications and licensee commitments to certain design and qualification criteria. The Commission also relocated without change the hydrogen control requirements in
10 CFR 50.34(f) to 10 CFR 50.44 and the high point vent requirements from 10 CFR 50.44 to 10 CFR 50.46a.
3.0 EVALUATION The ways in which the requirements and recommendations for combustible gas control were incorporated into the licensing bases of commercial nuclear power plants varied as a function of when plants were licensed. Plants that were operating at the time of the Three Mile Island (TMI), Unit 2, accident are likely to have been the subject of confirmatory orders that imposed the combustible gas control functions described in NUREG-0737, Clarification of TMI Action Plan Requirements, as obligations. The issuance of plant-specific amendments to adopt these changes, which would remove hydrogen recombiner and hydrogen and oxygen monitoring controls from TS, supersede the combustible gas control specific requirements imposed by post-TMI confirmatory orders.
3.1 Hydrogen Recombiners The existing TSs for the Kewaunee Nuclear Power Plant do not include requirements for hydrogen recombiners. The licensees application did not, therefore, need to propose changes to eliminate requirements for the hydrogen recombiners.
3.2 Hydrogen Monitoring Equipment Section 50.44(b)(1), the STS, and plant-specific TSs currently contain requirements for monitoring hydrogen. Licensees have also made commitments to design and qualification criteria for hydrogen monitors in Item II.F.1, Attachment 6 of NUREG-0737 and Regulatory Guide (RG) 1.97, Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident. The hydrogen monitors are required to assess the degree of core damage during a beyond design-basis accident and confirm that random or deliberate ignition has taken place. If an explosive mixture that could threaten containment integrity exists during a beyond design-basis accident, then other severe accident management strategies, such as purging and/or venting, would need to be considered.
The hydrogen monitors are needed to implement these severe accident management strategies.
With the elimination of the design-basis LOCA hydrogen release, hydrogen monitors are no longer required to mitigate design-basis accidents and, therefore, the hydrogen monitors do not meet the definition of a safety-related component as defined in 10 CFR 50.2. RG 1.97 recommends classifying the hydrogen monitors as Category 1. RG 1.97 Category 1 is intended for key variables that most directly indicate the accomplishment of a safety function for design-basis accident events and, therefore, are items usually addressed within TSs. As part of the rulemaking to revise 10 CFR 50.44, the Commission found that the hydrogen monitors no longer meet the definition of Category 1 in RG 1.97. The Commission concluded that Category 3, as defined in RG 1.97, is an appropriate categorization for the hydrogen monitors because the monitors are required to diagnose the course of beyond design-basis accidents.
Hydrogen monitoring is not the primary means of indicating a significant abnormal degradation of the reactor coolant pressure boundary. Section 4 of Attachment 2 to SECY-00-0198, Status Report on Study of Risk-Informed Changes to the Technical Requirements of 10 CFR Part 50 (Option 3) and Recommendations on Risk-Informed Changes to 10 CFR 50.44 (Combustible
Gas Control), found that the hydrogen monitors were not risk-significant. Therefore, the staff finds that hydrogen monitoring equipment requirements no longer meet any of the four criteria in 10 CFR 50.36(c)(2)(ii) for retention in TSs and, therefore, may be relocated to other licensee-controlled documents.
However, because the monitors are required to diagnose the course of beyond design-basis accidents, each licensee should verify that it has, and make a regulatory commitment to maintain, a hydrogen monitoring system capable of diagnosing beyond design-basis accidents.
The elimination of Post-Accident Sampling System requirements from some plant-specific TSs (and associated CLIIP notices) indicated that during the early phases of an accident, safety-grade hydrogen monitors provide an adequate capability for monitoring containment hydrogen concentration. The staff has subsequently concluded that Category 3 hydrogen monitors also provide an adequate capability for monitoring containment hydrogen concentration during the early phases of an accident.
4.0 VERIFICATIONS AND COMMITMENTS As requested by the NRC in the notice of availability for this TS improvement, the licensee has addressed the following plant-specific verifications and commitments.
4.1 Each licensee should verify that it has, and make a regulatory commitment to maintain, a hydrogen monitoring system capable of diagnosing beyond design-basis accidents.
The licensee has verified that it has a hydrogen monitoring system capable of diagnosing beyond design-basis accidents. The licensee has committed to maintain the hydrogen monitors within its Technical Requirements Manual. The licensee will implement this commitment as part of the implementation of the amendment.
The NRC staff finds that reasonable controls for the implementation and for subsequent evaluation of proposed changes pertaining to the above regulatory commitments are provided by the licensees administrative processes, including its commitment management program.
Should the licensee choose to incorporate a regulatory commitment into the emergency plan, final safety analysis report, or other document with established regulatory controls, the associated regulations would define the appropriate change-control and reporting requirements.
The NRC staff has determined that the commitments do not warrant the creation of regulatory requirements which would require prior NRC approval of subsequent changes. The NRC staff has agreed that NEI 99-04, Revision 0, Guidelines for Managing NRC Commitment Changes, provides reasonable guidance for the control of regulatory commitments made to the NRC staff.
(See Regulatory Issue Summary 2000-17, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff," dated September 21, 2000.) The commitments should be controlled in accordance with the industry guidance or comparable criteria employed by a specific licensee. The NRC staff may choose to verify the implementation and maintenance of these commitments in a future inspection or audit.
5.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Wisconsin State official was notified of the proposed issuance of the amendment. The State official had no comments.
6.0 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 the amendment involves no significant hazards consideration and there has been no public comment on such finding (69 FR 9862). 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.
7.0 CONCLUSION
The NRC 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 Commissions 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: W. Reckley Date: May 13, 2004