Letter Sequence Approval |
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TAC:MD5266, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications (Approved, Closed) |
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MONTHYEARML0720603242007-08-28028 August 2007 Issuance of Amendment 174 Adoption of TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times Project stage: Approval ML0720603282007-08-28028 August 2007 Tech Spec Pages for Amendment 174 Adoption of TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times Project stage: Other 2007-08-28
[Table View] |
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Category:Letter
MONTHYEARML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) IR 05000482/20240022024-07-18018 July 2024 Integrated Inspection Report 05000482/2024002 IR 05000482/20244012024-07-0202 July 2024 Security Baseline Inspection Report 05000482/2024401 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24162A1632024-06-11011 June 2024 Operating Corporation – Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000482/2024010) ML24150A0562024-05-29029 May 2024 Foreign Ownership, Control or Influence (FOCI) Information – Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24089A2622024-04-29029 April 2024 Financial Protection Levels ML24118A0022024-04-27027 April 2024 Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24113A1882024-04-19019 April 2024 Foreign Ownership, Control or Influence Information - Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24109A1842024-04-18018 April 2024 Cycle 27 Core Operating Limits Report ML24109A1212024-04-18018 April 2024 (WCGS) Form 5 Exposure Report for Calendar Year 2023 IR 05000482/20240012024-04-17017 April 2024 Integrated Inspection Report 05000482/2024001 ML24106A1482024-04-15015 April 2024 Notification of Inspection (NRC Inspection Report 05000482/2024003) and Request for Information ML24114A1442024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37 ML24098A0052024-04-0707 April 2024 2023 Annual Environmental Operating Report ML24089A1352024-03-29029 March 2024 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes ML24089A0972024-03-29029 March 2024 Response to NRC Regulatory Issue Summary 2024-01, “Preparation and Scheduling of Operator Licensing Examinations” ML24074A3312024-03-14014 March 2024 Missed Quarterly Inspection Per 40 CFR 266 Subpart N ML24080A3452024-03-11011 March 2024 7 of the Wolf Creek Generating Station Updated Safety Analysis Report IR 05000482/20240122024-03-11011 March 2024 Fire Protection Team Inspection Report 05000482/2024012 ML24068A1992024-03-0707 March 2024 Changes to Technical Specification Bases - Revisions 93 and 94 ML24066A0672024-03-0505 March 2024 4-2022-024 Letter - OI Closure to Licensee ML24061A2642024-03-0101 March 2024 Revision of Two Procedures That Implement the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) Commissioners IR 05000482/20230062024-02-28028 February 2024 Annual Assessment Letter for Wolf Creek Generating Station Report 05000482/2023006 ML24059A1702024-02-28028 February 2024 Annual Fitness for Duty Program Performance Report, and Annual Fatigue Report for 2023 ML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML24050A0012024-02-19019 February 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24036A0092024-02-14014 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0075 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24036A1852024-02-0505 February 2024 Correction to 2022 Annual Radioactive Effluent Release Report - Report 46 ML24032A1742024-02-0202 February 2024 Withdrawal of Requested Licensing Action Exemption from Specific Provisions in 10 CFR 73.55 ML24025A0992024-01-25025 January 2024 Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML24018A0792024-01-22022 January 2024 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd and Opportunity for a Hearing (EPID L-2024-LLA-0007) (Letter) ML24018A1382024-01-18018 January 2024 Inservice Inspection Request for Information ML24018A2482024-01-18018 January 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 238 IR 05000482/20230042024-01-11011 January 2024 Integrated Inspection Report 05000482/2023004 ML23356A0722024-01-0404 January 2024 Supplemental Information Needed for Acceptance of Requested Licensing Actions Exemption from Specific 10 CFR Part 73N Requirements (EPID L-2023-LLE-0048) (Redacted Version) WO 23-0002, Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082023-12-26026 December 2023 Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 ML23348A3662023-12-18018 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482 2024012) and Request for Information ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23331A4972023-11-27027 November 2023 Supplement to License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23325A2112023-11-20020 November 2023 Submittal of Request for Exemption from Specific Provisions in 10 CFR 73.55 ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML23292A3592023-10-19019 October 2023 License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 2024-07-31
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24212A0372024-08-0707 August 2024 Summary of July 23, 2024, Teleconference with Wolf Creek Nuclear Operating Corporation Regarding Wolf Creek Generating Station, Unit 1, Amendment No. 237, Allowing the Use of Portable Lighting ML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23201A1212023-08-0707 August 2023 Issuance of Amendment No. 236 Revision to Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML23130A2902023-07-26026 July 2023 Issuance of Amendment No. 235 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22252A1512022-11-0404 November 2022 Issuance of Amendment No. 234 Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ML22199A2942022-08-16016 August 2022 Issuance of Amendment No. 233 Removal of Table of Contents from the Technical Specifications ML22069A0562022-05-18018 May 2022 Issuance of Amendment No. 232 Regarding Revision to the Emergency Plan Related to On-Shift Staffing ML22021B5982022-02-23023 February 2022 Issuance of Amendment No. 231 Revision of Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21210A2472021-09-0303 September 2021 Issuance of Amendment No. 230 Revision of Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange ML21238A3862021-09-0202 September 2021 Correction to Issuance of Amendment No. 229 Change to Owner Licensee Names ML21095A1922021-07-20020 July 2021 Issuance of Amendment No. 229 Change to Owner Licensee Names ML21061A0782021-04-23023 April 2021 Issuance of Amendment No. 228 Regarding Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ML21053A1172021-04-0808 April 2021 1 - Issuance of Amendment No. 227 TS Change Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Based on TSTF-425 ML20276A1492020-12-0707 December 2020 Issuance of Amendment No. 226 Extension of Type a and Type C Leak Rate Test Frequencies ML19353C5002020-02-27027 February 2020 Issuance of Amendment No. 224 Revision to Technical Specification 3.3.5, - Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation, - ML19182A3452019-08-19019 August 2019 Issuance of Amendment No 222 Revise Technical Specifications to Adopt TSTF Traveler TSTF-529, Clarify Use and Application Rules ML19100A1222019-05-31031 May 2019 Issuance of Amendment No. 221 License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term ML17166A4092017-08-28028 August 2017 Issuance of Amendment No. 218, Request to Adopt Emergency Action Level (EAL) Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6 ML17024A2412017-03-24024 March 2017 Issuance of Amendment No. 217 Revision to the Cyber Security Plan Implementation Schedule ML16179A2932016-08-0303 August 2016 Issuance of Amendment No. 216, Revise Technical Specification (TS) 4.2.1 and TS 5.6.5 to Allow Use of Optimized Zirlo as Approved Fuel Rod Cladding ML16081A1942016-04-15015 April 2016 Issuance of Amendment No. 215, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.14 Consistent with TSTF-276-A, Revise DG Full Load Rejection Test ML15183A0522015-09-11011 September 2015 Issuance of Amendment No. 214, Request to Revise Fire Protection Program Related to Alternative Shutdown Capability as Described in Updated Safety Analysis Report ML15203A0052015-08-28028 August 2015 Redacted, Issuance of Amendment No. 213, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large-Break Loss-of-Coolant Accident Analysis Methodology (Astrum) ML15169A2132015-07-28028 July 2015 Issuance of Amendment No. 212, Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML14209A0232014-08-14014 August 2014 Issuance of Amendment No. 210, Modify License Condition Related to Approval of Revised Cyber Security Plan Implementation Milestone 8 Completion Date ML14156A2462014-08-0707 August 2014 Issuance of Amendment No. 209, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), to Replace Westinghouse Methodologies ML14157A0822014-07-0101 July 2014 Issuance of Amendment No. 208, Adopt TSTF-522-A, Revision 0, Revise Ventilation System to Operate for 10 Hours Per Month, Using Consolidated Line Item Improvement Process ML13282A5342013-12-0606 December 2013 Issuance of Amendment No. 207, Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System, to Reflect Mass Input Transient Analysis ML13282A1472013-12-0202 December 2013 Issuance of Amendment No. 206, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement 3.8.1.10 to Increase Voltage Limit for Diesel Generator Load Rejection Test ML13197A2102013-08-23023 August 2013 Issuance of Amendment No. 205, Revise Fire Protection License Condition and the Updated Safety Analysis Report for a Deviation from Appendix R for Volume Control Tank Outlet Valves ML12334A3122012-12-21021 December 2012 Issuance of Amendment No. 203, Revise Technical Specification 3.6.6, Containment Spray and Cooling Systems, to Replace Surveillance Requirement 3.6.6.8 with an Event-Based Frequency ML12279A2502012-12-12012 December 2012 Issuance of Amendment No. 202, Revise Physical Security License Condition and Change to Scope of Milestone 6 for the Cyber Security Plan Implementation Schedule ML12300A3092012-12-11011 December 2012 Issuance of Amendment No. 201, Revise TS 5.5.9, Steam Generator Program, and TS 5.6.10, Steam Generator Tube Inspection Report for a Permanent Alternate Repair Criteria ML12318A1452012-12-0505 December 2012 Issuance of Amendment No. 200, Revision to Technical Specifications (TS) 3.3, Instrumentation, 3.7, Plant Systems, and 3.8, Electrical Power Systems ML12289A8962012-11-19019 November 2012 Issuance of Amendment No. 199, Request to Adopt Technical Specification Task Force Traveler TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies Using Consolidated Line Item Improvement Process ML1104804612011-04-19019 April 2011 Issuance of Amendment No. 196, Correction of Typographical Error in Technical Specification 5.7.2, Administrative Controls Related to High Radiation Area ML1108405902011-04-0606 April 2011 Issuance of Amendment No. 195, Revise Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for Temporary Alternate Repair Criterion ML1105508462011-03-30030 March 2011 Issuance of Amendment No. 194, Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-1 to Identify Functions and Modes for Reactor Trip P-4 Interlock Function ML1021703352010-11-0303 November 2010 Issuance of Amendment No. 190, Revise Technical Specification 3.6.3, Containment Isolation Valves, Limiting Condition for Operation ML1025604982010-09-30030 September 2010 Issuance of Amendment No. 189, Revise Updated Safety Analysis Report to Modify Fire Protection Program for Use of Fire-Resistive Electrical Cable ML1008205172010-07-23023 July 2010 Issuance of Amendment No. 188, Revise Technical Specifications for Use of Beacon Power Distribution Monitoring System ML1006300132010-03-0505 March 2010 Issuance of Amendment No. 187, Revise TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps (Emergency Circumstances) ML0927506062009-10-19019 October 2009 Issuance of Amendment No. 186, Modify Technical Specification 5.5.9, Steam Generator Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for Alternate Repair Criteria ML0917301912009-08-0707 August 2009 License Amendment, Issuance of Amendment No. 185, Modify Technical Specifications to Adopt TSTF-511, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0917002962009-07-30030 July 2009 Issuance of Amendment 183, Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, to Extend the Surveillance Frequency on ESFAS Slave Relays from 92 Days to 18 Months ML0909607342009-05-15015 May 2009 Issuance of Amendment No. 182, Revise Technical Specification 3.5.2, ECCS - Operating, in Accordance with TSTF-325A, ECCS Conditions and Required Actions with <100% Equivalent ECCS Flow ML0906103172009-03-31031 March 2009 Issuance of Amendment No. 181, Revise Licensing Basis, Modification of the Main Steam and Feedwater Isolation System Controls ML0834302242009-01-27027 January 2009 Issuance of Amendment No. 180, Revise Technical Specification Requirements Consistent with TSTF-419, Revision 0, Revise PTLR Definition and References in ISTS 5.6.6, RCS PTLR 2024-08-07
[Table view] Category:Safety Evaluation
MONTHYEARML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23256A2882023-09-20020 September 2023 Authorization and Safety Evaluation for Alternative Request No. I4R-08 ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23201A1212023-08-0707 August 2023 Issuance of Amendment No. 236 Revision to Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML23130A2902023-07-26026 July 2023 Issuance of Amendment No. 235 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22252A1512022-11-0404 November 2022 Issuance of Amendment No. 234 Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ML22199A2942022-08-16016 August 2022 Issuance of Amendment No. 233 Removal of Table of Contents from the Technical Specifications ML22069A0562022-05-18018 May 2022 Issuance of Amendment No. 232 Regarding Revision to the Emergency Plan Related to On-Shift Staffing ML22021B5982022-02-23023 February 2022 Issuance of Amendment No. 231 Revision of Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21210A2472021-09-0303 September 2021 Issuance of Amendment No. 230 Revision of Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange ML21095A1922021-07-20020 July 2021 Issuance of Amendment No. 229 Change to Owner Licensee Names ML21061A0782021-04-23023 April 2021 Issuance of Amendment No. 228 Regarding Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ML21053A1172021-04-0808 April 2021 1 - Issuance of Amendment No. 227 TS Change Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Based on TSTF-425 ML20276A1492020-12-0707 December 2020 Issuance of Amendment No. 226 Extension of Type a and Type C Leak Rate Test Frequencies ML20302A0802020-10-30030 October 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20111A3372020-04-27027 April 2020 Request from Relief from Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-666-1 ML19353C5002020-02-27027 February 2020 Issuance of Amendment No. 224 Revision to Technical Specification 3.3.5, - Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation, - ML19291A0182019-11-12012 November 2019 Request for Relief I4R-07, Utilize Code Case N-513-4 - Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping of American Society of Mechanical Engineers Boiler and Pressure Code Section XI ML19182A3452019-08-19019 August 2019 Issuance of Amendment No 222 Revise Technical Specifications to Adopt TSTF Traveler TSTF-529, Clarify Use and Application Rules ML19100A1222019-05-31031 May 2019 Issuance of Amendment No. 221 License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term ML19052A5462019-04-0101 April 2019 Issuance of Amendment No. 220 Revision to the Emergency Plan ML18334A0132018-12-12012 December 2018 Request for Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Code Case N-666-1 ML18283A0492018-10-18018 October 2018 Request for Relief I4R-6 from ASME Code Visual Examination Requirements for Reactor Vessel Head Penetration Nozzle Weld Specified by Code Case N-729-4 ML18040A6662018-03-12012 March 2018 Letter, Order, and Safety Evaluation Order Approving Indirect Transfer of Control of Renewed Facility Operating License No. NPF-42 ML17166A4092017-08-28028 August 2017 Issuance of Amendment No. 218, Request to Adopt Emergency Action Level (EAL) Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6 ML17144A0092017-08-0202 August 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17202E9192017-08-0202 August 2017 Relief Request 14R-05 from Certain Pressure Test Requirements of the ASME Code for Reactor Pressure Vessel Leak-Off Lines for the Fourth 10 Year Inservice Inspection Interval ML17024A2412017-03-24024 March 2017 Issuance of Amendment No. 217 Revision to the Cyber Security Plan Implementation Schedule ML16320A0322016-11-30030 November 2016 Request for Relief I4R-, Alternative Risk-Informed Methodology in Selecting Class 1 and 2 Piping Welds, for the Fourth 10-Year Inservice Inspection Interval ML16179A2932016-08-0303 August 2016 Issuance of Amendment No. 216, Revise Technical Specification (TS) 4.2.1 and TS 5.6.5 to Allow Use of Optimized Zirlo as Approved Fuel Rod Cladding ML16179A4432016-08-0202 August 2016 Safety Evaluation, Request for Exemption from 10 CFR 50.46 and Appendix K to Allow Use of Optimized Zirlo as Approved Fuel Rod Cladding ML16081A1942016-04-15015 April 2016 Issuance of Amendment No. 215, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.14 Consistent with TSTF-276-A, Revise DG Full Load Rejection Test ML15183A0522015-09-11011 September 2015 Issuance of Amendment No. 214, Request to Revise Fire Protection Program Related to Alternative Shutdown Capability as Described in Updated Safety Analysis Report ML15203A0052015-08-28028 August 2015 Redacted, Issuance of Amendment No. 213, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large-Break Loss-of-Coolant Accident Analysis Methodology (Astrum) ML15169A2132015-07-28028 July 2015 Issuance of Amendment No. 212, Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML15190A2022015-07-13013 July 2015 Relief Request 13R-12, Extension of the Third Inservice Inspection Program Interval to Perform Reactor Vessel Stud Hole Ligament Examinations ML15134A0022015-05-15015 May 2015 Relief Request Nos. 4PR-01 and 4PR-02 and Withdrawal of 4VR-02, Alternative to Requirements of ASME Code Case OMN-21 and OM Code ISTB-3510(b)(1) for Pumps, Fourth 10-Year Inservice Testing Program ML15040A0202015-02-12012 February 2015 Relief Request I3R-10, Alternative from Pressure Test Requirements of ASME Code, Section XI, IWC-5220, Third 10-Year Inservice Inspection Interval ML15023A2202015-01-28028 January 2015 Relief Request 13R-11, Alternative from Pressure Test Requirements of ASME Code Section XI IWC-5220 for the Third 10-Year Inservice Inspection Interval ML14321A8642014-12-10010 December 2014 Relief Requests 13R-08, Reactor Pressure Vessel (RPV) Interior Attachments and 13R-09, RPV Pressure-Retaining Welds, Exam Interval Extensions, Third 10-year Inservice Inspection Interval ML14209A0232014-08-14014 August 2014 Issuance of Amendment No. 210, Modify License Condition Related to Approval of Revised Cyber Security Plan Implementation Milestone 8 Completion Date ML14156A2462014-08-0707 August 2014 Issuance of Amendment No. 209, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), to Replace Westinghouse Methodologies ML14157A0822014-07-0101 July 2014 Issuance of Amendment No. 208, Adopt TSTF-522-A, Revision 0, Revise Ventilation System to Operate for 10 Hours Per Month, Using Consolidated Line Item Improvement Process ML13282A5342013-12-0606 December 2013 Issuance of Amendment No. 207, Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System, to Reflect Mass Input Transient Analysis ML13282A1472013-12-0202 December 2013 Issuance of Amendment No. 206, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement 3.8.1.10 to Increase Voltage Limit for Diesel Generator Load Rejection Test ML13197A2102013-08-23023 August 2013 Issuance of Amendment No. 205, Revise Fire Protection License Condition and the Updated Safety Analysis Report for a Deviation from Appendix R for Volume Control Tank Outlet Valves ML13109A2342013-07-12012 July 2013 Safety Evaluation Regarding Wolf Creek Generating Station - Loss of Offsite Power and Augmented Inspection, Issue for Resolution 2012-004 ML13149A1712013-06-0303 June 2013 Safety Assessment in Response to Information Request Pursuant to 10 CFR 50.54(f) - Recommendation 9.3 Communications Assessment ML13078A1552013-03-20020 March 2013 License Amendment Request to Change Diesel Generator Surveillance Requirements 2024-02-27
[Table view] |
Text
August 28, 2007 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION - ISSUANCE OF AMENDMENT RE:
ADOPTION OF TSTF-491, REVISION 2, REMOVAL OF MAIN STEAM AND MAIN FEEDWATER VALVE ISOLATION TIMES (TAC NO. MD5266)
Dear Mr. Muench:
The U.S. Nuclear Regulatory Commission (NRC, or the Commission) has issued the enclosed Amendment No.174 to Facility Operating License No. NPF-42 for the Wolf Creek Generating Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated March 14, 2007 (ET 07-0004).
The amendment revised Surveillance Requirements 3.7.2.1 and 3.7.3.1 for the main steam isolation valves and main feedwater isolation valves, respectively, to replace the valve isolation times with the phrase within limits. The valve isolation times are stated in the TS Bases, which is controlled by TS 5.5.14, Technical Specification (TS) Bases Control Program. This amendment is consistent with the NRC-approved Technical Specification Task Force (TSTF)
Traveler 491, Revision 2, Removal of Main Steam and Main Feedwater Isolation Times.
There are other proposed changes to the TSs and the plant in the application dated March 14, 2007, that are not being addressed in this amendment. These will be addressed in future letters to you.
A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
Jack N. Donohew, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosures:
- 1. Amendment No. 174 to NPF-42
- 2. Safety Evaluation cc w/encls: See next page
Pkg ML072060322, Amendment/License ML072060324, TS Pages ML072060328 *SE input memo OFFIC NRR/LPL4/PM NRR/LPL4/LA ITSB/BC OGC NRR/LPL4/BC E
NAME JDonohew JBurkhardt TKobetz* AHodgdon THiltz DATE 8/22/07 8/2/07 5/17/07 8/20/07 8/23/07
Wolf Creek Generating Station cc:
Jay Silberg, Esq. Chief, Radiation and Asbestos Control Pillsbury Winthrop Shaw Pittman LLP Section 2300 N Street, NW Kansas Department of Health Washington, D.C. 20037 and Environment Bureau of Air and Radiation Regional Administrator, Region IV 1000 SW Jackson, Suite 310 U.S. Nuclear Regulatory Commission Topeka, KS 66612-1366 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Vice President Operations/Plant Manager Wolf Creek Nuclear Operating Corporation Senior Resident Inspector P.O. Box 411 U.S. Nuclear Regulatory Commission Burlington, KS 66839 P.O. Box 311 Burlington, KS 66839 Supervisor Licensing Wolf Creek Nuclear Operating Corporation Chief Engineer, Utilities Division P.O. Box 411 Kansas Corporation Commission Burlington, KS 66839 1500 SW Arrowhead Road Topeka, KS 66604-4027 U.S. Nuclear Regulatory Commission Resident Inspectors Office/Callaway Plant Office of the Governor 8201 NRC Road State of Kansas Steedman, MO 65077-1032 Topeka, KS 66612 Attorney General 120 S.W. 10th Avenue, 2nd Floor Topeka, KS 66612-1597 County Clerk Coffey County Courthouse 110 South 6th Street Burlington, KS 66839 February 2006
WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 174 License No. NPF-42
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Wolf Creek Generating Station (the facility)
Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated March 14, 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, as amended, 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 license 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 and Paragraph 2.C.(2) of Facility Operating License No. NPF-42 as indicated in the attachment to this license amendment.
- 3. The license amendment is effective as of its date of issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Thomas G. Hiltz, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License and Technical Specifications Date of Issuance: August 28, 2007
ATTACHMENT TO LICENSE AMENDMENT NO. 174 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following pages of the Facility Operating License No. NPF-42 and 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. The corresponding overleaf pages are also provided to maintain document completeness.
Facility Operating License REMOVE INSERT Technical Specifications REMOVE INSERT 3.7-7 3.7-7 3.7-9 3.7-9
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 174 TO FACILITY OPERATING LICENSE NO. NPF-42 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482
1.0 INTRODUCTION
By application dated March 14, 2007 (Agencywide Documents Access and Management System Accession No. ML070800193), Wolf Creek Nuclear Operating Corporation (the licensee) requested changes to the Technical Specifications (TSs, Appendix A to Facility Operating License No. NPF-42) for the Wolf Creek Generating Station (WCGS). The proposed changes to the TSs are the following:
- 1. Changes to TS 3.3.2, Engineered Safety Features Actuation System (ESFAS)
Instrumentation, to separate the main steam and feedwater isolation system (MSFIS) from the solid state protection system (SSPS) in ESFAS Functions 4.b and 5.a of Table 3.3.2-1.
- 2. Changes to 3.7.3, Main Feedwater Isolation Valves (MFIVs), for the addition of the main feedwater regulating valves (MFRVs), and associated MFRV bypass valves to TS 3.7.3.
- 3. Changes to Surveillance Requirements (SRs) 3.7.2.1 and 3.7.3.1 to adopt the Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force Traveler 491, Revision 2 (TSTF-491R2), Removal of Main Steam and Main Feedwater Isolation Times.
- 4. Changes to the TS Table of Contents.
The only changes to the TSs that are being addressed in this amendment are the changes in No. 3 above, the adoption of TSTF-491R2. In adopting this TSTF, the licensee proposed to revise SRs 3.7.2.1 and 3.7.3.1 for the main steam isolation valves (MSIVs) and main feedwater isolation valves (MFIVs), respectively, to replace the valve isolation times in the SRs with the phrase within limits.
The availability of TSTF-491R2 for inclusion in plant TSs was announced in the Federal Register on December 29, 2006 (71 FR 78472), as part of the NRC consolidated line item improvement process.
In Attachments IV and V to the application, the licensee identified (1) changes to the TS Bases for the proposed amendment and (2) the list of regulatory commitments. In identifying changes to the TS Bases for TSs 3.7.2 and 3.7.3, the licensee is not requesting that NRC approve these changes; however, the changes to the TS Bases and the regulatory commitment is for the entirety of the proposed license amendment request in the application dated March 14, 2007.
The identified changes to the TS Bases come under TS 5.5.14, Technical Specification (TS)
Bases Control Program, which requires that Licensees may make changes to the [TS] Bases without prior NRC approval provided the changes do no require either of the following: 1. a change to the TS incorporated in the license; or 2. a change to the update FSAR [Final Safety Analysis Report] that requires approval pursuant to 10 CFR 50.59.
2.0 REGULATORY EVALUATION
In Section 50.36 of Title 10 of the Code of Federal Regulations (10 CFR 50.36), the Commission established its regulatory requirements related to the content of the TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements (SRs);
(4) design features; and (5) administrative controls. The rule does not specify the particular requirements to be included in a plants TSs. As required by 10 CFR 50.36(c)(3), SRs are the requirements related to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met.
As required by 10 CFR 50.36(c)(2)(ii), an LCO must be included in TS for any plant structure, system, or component (SSC) meeting one of the following four criteria:
Criterion 1: Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.
Criterion 2: A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
Criterion 3: An SSC 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.
Criterion 4: An SSC which operating experience or probabilistic safety assessment has shown to be significant to public health and safety.
Those items that do not fall within or satisfy any of the above criteria are not required to be included in the TSs.
3.0 TECHNICAL EVALUATION
3.1 Proposed Changes to the Technical Specifications In its application, the licensee proposed the following changes to TS 3.7.2, Main Steam Isolation Valves (MSIVs), and TS 3.7.3, Main Feedwater Isolation Valves (MFIVs):
- Revise SR 3.7.2.1, which requires the verification of the valve isolation time of each MSIV in accordance with the inservice testing program, by replacing the criterion of < 5 seconds with the phrase within limits.
- Revise SR 3.7.3.1, which requires the verification of the valve isolation time of each MFIV in accordance with the inservice testing program, by replacing the criterion of < 5 seconds with the phrase within limits.
The surveillance requirement to verify the valve isolation time is within limits and the frequency of performing the verification is not being changed by this amendment. The proposed changes are to remove the criterion of the valve isolation time must be < 5 seconds from the TSs and refer to this time instead by the phrase within limits. The criterion of < 5 seconds would be relocated to the TS Bases for TSs 3.7.2 and 3.7.3. The requirement to verify the isolation time of the MSIVs and MFIVs, and frequency of performing the verification is not being changed.
In the application, the licensee is also proposing to replace the MSIVs and MFIVs with new valves that have longer isolation times than the current valves. This proposed extension to the valve isolation times for the MSIVs and MFIVs in the application is also not being considered in this amendment.
3.2 Background As presented in the licensees application, there is one MSIV located in each of the four main steam lines outside of the containment and, therefore, there are four MSIVs. Closing each MSIV isolates each steam generator (SG) from the other SGs and the turbine. By isolating the steam flow from the secondary side of the SG, the MSIVs prevent overcooling of the reactor core following a high-energy line break and thus protect the reactor core from being damaged from overcooling. The Wolf Creek accident analyses involving the MSIVs assume these valves close in no more than 5 seconds, and SR 3.7.2.1 is performed periodically to ensure these valves can meet this requirement.
The MFIVs isolate the nonsafety-related portions from the safety-related portions of the feedwater system to the SGs. In the event of a secondary-side pipe rupture inside containment, these valves limit the quantity of high-energy fluid that enters the containment through the break and provide a pressure boundary for the controlled addition of auxiliary feedwater to the intact loops. By isolating the feedwater flow from the affected SG, the MFIVs prevent overcooling the reactor core and overpressurizing of the containment from feedwater pump runout. Again, the Wolf Creek accident analyses involving the MFIVs assume these valves close in no more 5 seconds, and SR 3.7.3.1 is performed periodically to ensure these valves can meet this requirement.
3.3 NRC Staff Technical Evaluation In adopting TSTF-491, the licensee is proposing to replace the required valve isolation times of
< 5 seconds for the MSIVs in SR 3.7.2.1 and MFIVs in SR 3.7.3.1 with the phase within limits.
The value of < 5 seconds for the required isolation time for these valves is stated in the TS Bases for SRs 3.7.2.1 and 3.7.3.1.
The TS Bases provide the bases for the TSs. The TS Bases provide a description of the SSCs that meet the four criteria in 10 CFR 50.36(c)(2)(ii) in that an LCO for each such SSC is required to be in the TSs and explain the requirements that the SSCs must meet in the TSs. The TSs briefly state the requirements on the SSCs (e.g., the SSC must be operable) and the details to determine the SSC is operable are given in the TS Bases. The TS 3.7.2 Bases state that SR 3.7.2.1 verifies that the MSIV isolation time is < 5 seconds on an actual or simulated actuation signal from each actuator train. The TS 3.7.2 Bases state that SR 3.7.2.1 verifies that the MFIV isolation time is < 5 seconds on an actual or simulated actuation signal from each actuator train.
Therefore, it is clear in the TS Bases that the limits on the valve isolation times for the MSIVs and MFIVs are < 5 seconds.
In its application, the licensee stated that the proposed changes are consistent with the NRC-approved TS changes in TSTF-491R2, the valve isolation times that are consistent with the Wolf Creek accident analyses would be stated in the TS Bases, and any changes to the TS Bases including these valve isolation times would be controlled by TS 5.5.14. The licensee further said that TS 5.5.14 provides adequate assurance that NRC review and prior approval would be requested for changes to the TS Bases requirements, including these valve isolation times, as would be required for changes to the plant in accordance with 10 CFR 50.59. The NRC staff agrees with the statements made by the licensee. Based on this, the NRC staff concludes that the TS Bases change criteria required by TS 5.5.14 provide sufficient control over any changes to the isolation times and, therefore, having the isolation time limits in the TS bases for the MSIVs and MFIVs is acceptable.
In the licensee proposing that the specific isolation time of < 5 seconds for the MSIVs and MFIVs in SRs 3.7.2.1 (MSIVs) and 3.7.3.1 (MFIVs) be replaced by the phrase within limits, the surveillance requirement to verify that these valves close within the isolation time required by the Wolf Creek accident analyses is not being changed. Therefore, the requirement that the valves must close in < 5 seconds to be considered operable is not being changed. The rewritten SRs still meets 10 CFR 50.36(c)(3) in that SRs are requirements related to a test, calibration, or inspection to assure that the necessary quality of systems and components is maintained and the related LCOs are met. Based on this, the NRC staff concludes that the rewritten SRs 3.7.2.1 and 3.7.3.1 continue to meet 10 CFR 50.36(c)(3) even though the specific valve isolation times will be listed in the TS Bases.
3.4 Conclusion The licensee has proposed to replace the valve isolation times of < 5 seconds that is specified in SRs 3.7.2.1 (MSIV) and 3.7.3.1 (MFIV) by the phrase within limits. The valve isolation times of < 5 seconds would be specified in the TS 3.7.2 and TS 3.7.3 Bases and any changes to these valve isolation times would be controlled by TS 5.5.14. Based on the above evaluation, the NRC staff concludes that the proposed change meet 10 CFR 50.36 and, therefore, the proposed amendment is acceptable.
In Attachment IV to its application dated March 14, 2007, the licensee identified changes to the TS Bases including changes to the TS 3.7.2 and TS 3.7.3 Bases. The identified changes in Attachment IV are for the other proposed changes to the TSs in the application dated March 14, 2007, and the proposed extension of the MSIV and MFIV valve isolation times that are not being addressed in this SE. These other changes to the TSs are listed in Section 1.0 of this SE.
Therefore, these identified changes to the TS Bases can not be made to the TS Bases until these other proposed changes to the TSs and the proposed extension of the MSIV and MFIV isolation times are addressed in future letters and SEs to the licensee. This has been discussed with the licensee and the licensee agrees with this conclusion.
In its application, the licensee stated that the amendment would be implemented prior to the restart from the Refueling Outage (RO) 16, which is scheduled for the spring of 2008. This implementation is based on the other proposed changes to the TSs and the proposed extension of the MSIV and MFIV isolation times. The licensee is planning to replace the MSIVs and MFIVs in RO 16 with new valves that have longer isolation times. For this amendment, the licensee does not need to wait for RO 16 to implement the amendment. In a conference call with the NRC staff, the licensee agreed that (1) this amendment could be implemented sooner than RO 16 and (2) an implementation period of 90 days was acceptable. Because the 90-day period is a reasonable time to implement the amendment, the NRC staff concludes that the 90 days is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Kansas State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (72 FR 33785, published on June 19, 2007). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: Peter Hearn Jack Donohew Date: August 28, 2007