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MONTHYEARML21189A0252021-07-0101 July 2021 NRR E-mail Capture - Acceptance Review - Wolf Creek Request Revision to the Emergency Plan Related to on-shift Staffing Project stage: Acceptance Review ML22069A0562022-05-18018 May 2022 Issuance of Amendment No. 232 Regarding Revision to the Emergency Plan Related to On-Shift Staffing Project stage: Approval 2021-07-01
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Category:Letter
MONTHYEARIR 05000482/20244202024-10-31031 October 2024 Security Baseline Inspection Report 05000482/2024420 ML24296B1902024-10-22022 October 2024 10 CFR 50.55a Requests for the Fifth Ten-Year Interval Inservice Testing Program 05000482/LER-2024-001-01, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-10-22022 October 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing 05000482/LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-10-21021 October 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24283A0752024-10-0909 October 2024 Notification of Commercial Grade Dedication Inspection (05000482/2025012) and Request for Information ML24199A1712024-09-17017 September 2024 Issuance of Amendment No. 241 Revise Ventilation Filter Testing Program Criteria and Administrative Correction of Absorber in Technical Specification 5.5.11 ML24260A0712024-09-12012 September 2024 License Amendment Request for a Risk-Informed Resolution to GSI-191 IR 05000482/20240102024-09-10010 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000482/2024010 (Public) ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML24248A2492024-09-0404 September 2024 Inservice Inspection Program Fourth Interval, Third Period, Refueling Outage 26 Owner’S Activity Report ML24241A2212024-08-29029 August 2024 Notice of Enforcement Discretion for Wolf Creek Generating Station ML24240A2642024-08-27027 August 2024 Corporation - Request for Notice of Enforcement Discretion Regarding Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) ML24227A5562024-08-14014 August 2024 Application to Revise Technical Specifications to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions ML24213A3352024-07-31031 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 05000482/LER-2024-001, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-07-0202 July 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing IR 05000482/20244012024-07-0202 July 2024 Security Baseline Inspection Report 05000482/2024401 ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) 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 ML23345A1602024-05-0909 May 2024 Revision of Safety Evaluation for Amendment No. 237 Request for Deviation from Fire Protection Requirements 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 ML24114A1442024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37 ML24106A1482024-04-15015 April 2024 Notification of Inspection (NRC Inspection Report 05000482/2024003) and Request for Information ML24098A0052024-04-0707 April 2024 2023 Annual Environmental Operating Report ML24089A0972024-03-29029 March 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24089A1352024-03-29029 March 2024 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes ML24074A3312024-03-14014 March 2024 Missed Quarterly Inspection Per 40 CFR 266 Subpart N IR 05000482/20240122024-03-11011 March 2024 Fire Protection Team Inspection Report 05000482/2024012 ML24080A3452024-03-11011 March 2024 7 of the Wolf Creek Generating Station Updated Safety Analysis Report ML24016A0702024-03-0808 March 2024 Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications 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) 2024-09-06
[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 ML24016A0702024-03-0808 March 2024 Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications 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 2024-08-07
[Table view] Category:Safety Evaluation
MONTHYEARML24199A1712024-09-17017 September 2024 Issuance of Amendment No. 241 Revise Ventilation Filter Testing Program Criteria and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23345A1602024-05-0909 May 2024 Revision of Safety Evaluation for Amendment No. 237 Request for Deviation from Fire Protection Requirements ML24016A0702024-03-0808 March 2024 Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications 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 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 2024-09-17
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
May 18, 2022
Mr. Cleveland Reasoner Chief Executive Officer and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION, UNIT 1 - ISSUANCE OF AMENDMENT NO. 232 REGARDING REVISION TO THE EMERGENCY PLAN RELATED TO ON-SHIFT STAFFING (EPID L-2021-LLA-0089)
Dear Mr. Reasoner:
The U.S. Nuclear Regulatory Commission (the Commission) has iss ued the enclosed Amendment No. 232 to Renewed Facility Operating License No. NPF -42 for the Wolf Creek Generating Station, Unit 1 (Wolf Creek). The amendment consists of changes to the Wolf Creek Emergency Plan in response to your application dated May 25, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21145A238). The amendment revises the Wolf Creek Radiological Emergency Response Plan to change the on-shift staffing composition.
A copy of the related Safety Evaluation is enclosed. Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Samson S. Lee, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket No. 50-482
Enclosures:
- 1. Amendment No. 232 to NPF-42
- 2. Safety Evaluation
cc: Listserv WOLF CREEK NUCLEAR OPERATING CORPORATION
WOLF CREEK GENERATING STATION, UNIT 1
DOCKET NO. 50-482
AMENDMENT TO RENEWED FACILITY OPERATING LICENSE
Amendment No. 232 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, Unit 1 (the facility) Renewed Facility Operating License No. NPF-42 filed b y the Wolf Creek Nuclear Operating Corporation (the Corporation), dated May 25, 2021, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations s et 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 author ized by this amendment can be conducted without endangering the health and s afety 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 c ommon 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 b een satisfied.
Enclosure 1
- 2. Accordingly, by Amendment No. 232, Renewed Facility Operatin g License No. NPF-42 is hereby amended to authorize revision to the Wolf Creek Radiological Emergency Response Plan as set forth in the Wolf Creek Nuclear Operating Corporations application dated May 25, 2021, and evaluated in the NRC staff safety evaluation for this amendment.
- 3. The license amendment is effective as of its date of issuanc e and shall be implemented within 180 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Andrea D. Veil, Director Office of Nuclear Reactor Regulation
Date of Issuance: May 18, 2022 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
RELATED TO AMENDMENT NO. 232 TO
RENEWED FACILITY OPERATING LICENSE NPF-42
WOLF CREEK NUCLEAR OPERATING CORPORATION
WOLF CREEK GENERATING STATION
DOCKET NO. 50-482
1.0 INTRODUCTION
By application dated May 25, 2021 (Reference 1), Wolf Creek Nuc lear Operating Corporation (the licensee) submitted a license amendment request (LAR) for U.S. Nuclear Regulatory Commission (NRC or the Commissi on) review and approval of the Wolf Creek Generating Station, Unit 1 (Wolf Creek) emergency plan. The licensees LAR proposes changes to the Wolf Creek Radiological Emergency Response Plan (RERP) on-shift staffing, pursuant to Section 50.54(q) of Title 10 of the Code of Federal Regulations (10 CFR), to:
Eliminate a dedicated shift technical advisor (STA) position b y allowing the STA functions to be combined with one or more of the required licen sed senior reactor operator (SRO) positions (a dual-role SRO/STA); and
Remove one Nuclear Station Operator (NSO).
The licensee stated that the proposed Wolf Creek RERP changes t o the total number of required on-shift personnel reduces the number of required on-s hift personnel and is considered a reduction in the effectiveness of the Wolf Creek emergency pl an that requires NRC approval pursuant to 10 CFR 50.54(q)(4). Therefore, as required under 10 CFR 50.54(q)(4), the licensee is submitting these proposed Wolf Creek RERP changes for NRC ap proval prior to implementation. The licensee stated that once the proposed RERP changes and revisions are approved, the approved amendment will be implemented within 180 days from the date of issuance.
2.0 REGULATORY EVALUATION
Following the accident at Three Mile Island (TMI) Unit 2 in Mar ch 1979, the NRC identified the need for power reactor licensees to assign an on-shift technical advisor who could provide engineering and accident assessment expertise to the shift supervisor in the event of abnormal or accident conditions. This position was designated as the STA. The qualifications for the person occupying the STA position are contained in Item I.A.1.1 of NUREG-0737, Clarification
Enclosure 2
of TMI Action Plan Requirements, dated November 1980 (Referenc e 2), Generic Letter (GL) 86-04, Policy Statement on Engineering Expertise on Shift, dated February 13, 1986 (Reference 3), and Regulatory Guide (RG) 1.8, Revision 3, Qual ification and Training of Personnel for Nuclear Power Plants, dated May 2000 (Reference 4). The Commissions Policy Statement on Engineering Expertise on Shift, as published in th e Federal Register (FR) on October 28, 1985 (50 FR 43621), provided two options for meeting the staffing requirements in 10 CFR 50.54(m)(2) and guidance in NUREG-0737, Item I.A.1.1. It allows for either an on-shift dedicated STA, who meets the STA criteria of NUREG-0737, Item I.A.1.1, or an individual assigned to each operating shift crew who is a licensed SRO on the nuclear power unit(s) to which he or she is assigned and meets the STA criteria of NUREG -0737, Item I.A.1.1. The STA qualifications should include a bachelors degree in engineerin g or equivalent, plus specific training in plant design, layout, and controls.
The planning standards in 10 CFR 50.47(b) establish the requirements that the onsite and offsite emergency response plans must meet for the NRC staff to make a finding that there is reasonable assurance that the licensee can, and will, take adequate protective measures in the event of a radiological emergency. Specifically, on-shift and a ugmented emergency response organization staffing is addressed under 10 CFR 50.47(b)(2), which states:
On-shift facility licensee responsibilities for emergency respo nse are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, ti mely augmentation of response capabilities is available, and the interfaces among various onsite response activities and offsite support and response activities are specified.
Appendix E to 10 CFR Part 50, Emergency Planning and Preparedness for Production and Utilization Facilities,Section IV, Part A, Organization, st ates, in part:
The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensees emergency organization.
The regulations at 10 CFR 50.54, Conditions of licenses, cont ains the regulation 10 CFR 50.54(q)(4), which requires prior NRC approval for chang es to a licensees emergency plan that reduces the effectiveness of the plan.
RG 1.101, Revision 2, Emergency Planning and Preparedness for Nuclear Power Reactors, dated October 1981 (Reference 5), provides guidance on methods acceptable to the NRC staff for implementing specific parts of the NRCs regulations (i.e., 10 CFR 50.47(b)(2) and Appendix E to 10 CFR Part 50, Section IV, Part A). RG 1.101 endorses NUREG-0654/FEMA-REP-1, Revision 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, dated November 1980 (Reference 6) (hereafter referred to as NUREG-065 4), which provides evaluation criteria, which serve as an acceptable means of comp lying with the planning standards set forth in 10 CFR 50.47(b). These evaluation criter ia also provide a basis for NRC licensees, and State and local governments to develop acceptable radiological emergency preparedness plans.
NUREG-0654,Section II, Planning Standards and Evaluation Crit eria, Evaluation Criteria II.B.1 and II.B.5, specifically address planning stand ard 10 CFR 50.47(b)(2).
Evaluation Criterion II.B.1 states:
Each licensee shall specify the onsite emergency organization o f plant staff personnel for all shifts and its relation to the responsibilities and duties of the normal shift complement.
Evaluation Criterion II.B.5 states, in part:
Each licensee shall specify the positions or title and major tasks to be performed by the persons to be assigned to the functional areas of emerge ncy activity. For emergency situations, specific a ssignments shall be made for al l shifts and for plant staff members, both onsite and away from the site. These assignments shall cover the emergency functions in Table B-1 entitled, Min imum Staffing Requirements for Nuclear Power Plant Emergencies. The minimum on-shift staffing levels shall be as indicated in Table B-1. The licens ee must be able to augment on-shift capabilities within a short period after declaration of an emergency. This capability shall be as indicated in Table B-1.
Office of Nuclear Security and Incident Response (NSIR)/Division of Preparedness and Response (DPR) Interim Staff Guidance (ISG), NSIR/DPR-ISG-01, Revision 0, Interim Staff Guidance, Emergency Planning for Nuclear Power Plants, dated N ovember 2011 (Reference 7), provides updated guidance for addressing emergen cy planning requirements for nuclear power plants, based on changes to emergency preparednes s regulations in 10 CFR 50.47 and Appendix E to 10 CFR Part 50, which was published on November 23, 2011 (76 FR 72560). ISG NSIR/DPR-ISG-01 provides guidance for a deta iled staffing analysis, which the NRC requires each nuclear power reactor licensee to perform, pursuant to Section IV.A.9 of Appendix E to 10 CFR Part 50, to determine if on-shift staff ma y have been assigned responsibilities that would prevent the timely performance of e mergency response functions delineated in the licensees emergency plan. Staffing analyses are required to be part of the emergency plan. As such, ISG NSIR/DPR-ISG-01 also endorsed the staffing analysis methodology contained in Nuclear Energy Institute (NEI) 10-05, Assessment of On-Shift Emergency Response Organization Staffing and Capabilities, Rev ision 0, dated June 2011 (Reference 8) and found it to be an acceptable methodology for a licensee to perform the required staffing analysis.
3.0 TECHNICAL EVALUATION
The NRC staff has reviewed the licensee's regulatory and techni cal analyses in support of the proposed changes to the Wolf Creek emergency plan described in the licensees LAR dated May 25, 2021. The NRC staff's technical evaluation is detailed below.
3.1 Evaluation of Proposed Wolf Creek RERP Change to Eliminate Dedicated STA Position
The licensee proposed to change the current Wolf Creek RERP suc h that the STA tasks could be assigned to an STA-qualified licensed SRO filling one of the required SRO positions and no longer performed by a dedicated individual. The licensee provided a justification for the proposed changes to the Wolf Creek RERP that included a technic al evaluation of the STA tasks in support of the Plant System Engineering, Repair and Co rrective Actions Major Functional Area described in NUREG-0654, Table B-1.
The licensee provided that an on-shift individual will continue to be available to provide advisory technical support to the Operations shift crews and that this i ndividual will meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.
The licensee performed an on-shift staffing analysis (OSA) in accordance with the NRC endorsed methodology contained in NEI 10-05 to validate that th is change to a dual role SRO/STA would not result in on-shift personnel being assigned r esponsibilities that would prevent the timely performance of the assigned functions. This analysis determined that the plant system engineering, repair, and corrective action functions were not adversely impacted by the proposed changes. Core thermal hydraulics and repair and corrective action major tasks will continue to be performed by qualified on-shift and augment ed personnel.
With the continued use of an on-shift individual, who meets the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift, to provide technical support to the Operations shift crew, and the results of the OSA report va lidating that the on-shift personnel are not being assigned responsibilities that would pr event the timely performance of the assigned functions, the NRC staff concludes that the proposed change will not result in a loss of function or impact the timing for the Plant System Engi neering, Repair and Corrective Actions Major Functional Area and is, therefore, acceptable.
3.2 Evaluation of Major Functional Areas for Proposed Removal o f One NSO
The licensee proposes to remove one on-shift NSO staff, decreasing the number of on-shift NSOs from seven to six. The licensee states that one NSO is use d to fill the dedicated Emergency Notification System and Off-Site Communicator (ENS/OS C Communicator) position in the current Wolf Creek RERP. The current Wolf Creek RERP req uires a single dedicated on-shift communicator, which addresses the minimum staffing requir ements of NUREG-0654 Table B-1.
The licensee states that the creation of a dual role SRO/STA wo uld allow the Work Control Senior Reactor Operator (WCSRO) to now be assigned as the ENS/O SC Communicator. This reassignment of the dedicated ENS/OSC Communicator duties allows the NSO presently filling this position to perform the accident mitigation duties current ly assigned to other NSOs. The licensee states that an analysis was performed using the WCSRO as the dedicated on-shift ENS/OSC Communicator and that the analysis did validate that on -shift personnel were not assigned responsibilities that would prevent the timely perform ance of the assigned functions.
With the continued use of an on-shift individual as the dedicat ed on-shift ENS/OSC Communicator, and the results of the OSA report validating that the on-shift personnel are not being assigned responsibilities that would prevent the timely p erformance of the assigned functions, the NRC staff concludes that the proposed change will not result in a loss of function or impact the timing for the Notification/Communication Functio nal Area Major Functional Area and is, therefore, acceptable.
3.3 Technical Summary
Based on the above, the NRC staff finds that the proposed changes to the Wolf Creek RERP continue to meet planning standard 10 CFR 50.47(b)(2) and the requirements in Section IV.A of Appendix E to 10 CFR Part 50, and as such, provide reasonable assurance that adequate protective measures can and will be taken in the event of a rad iological emergency. Therefore,
the NRC staff concludes that the proposed changes to the Wolf Creek RERP, as described in the application dated May 25, 2021, are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the State of Kansas official was notified of the proposed issuance of the amendments on January 20, 2022. The St ate official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the install ation or use of facility components 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, published in the Federal Register on August 10, 2021 (86 FR 43691), and there has been no public comment on such fin ding. Accordingly, the amendment meets the eligibility cri teria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement o r 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 publi c will not be endangered by operation in the proposed manner, (2) there is reasonable assur ance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and securi ty or to the health and safety of the public.
7.0 REFERENCES
- 1. McCoy, J. H., Wolf Creek Nuclear Operating Corporation, letter to U.S. Nuclear Regulatory Commission, Docket No. 50-482: License Amendment R equest (LAR) for Revision to the Emergency Plan, dated May 25, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21145A238).
- 2. U.S. Nuclear Regulatory Commission, Clarification of TMI Action Plan Requirements, NUREG-0737, dated November 1980 (ADAMS Accession No. ML051400209).
- 3. U.S. Nuclear Regulatory Commission, Policy Statement on Eng ineering Expertise on Shift, Generic Letter 86-04, dated February 13, 1986 (ADAMS Ac cession No. ML031150270).
- 4. U.S. Nuclear Regulatory Commission, Qualification and Train ing of Personnel for Nuclear Power Plants, Regulatory Guide 1.8, Revision 3, dated May 2000 (ADAMS Accession No. ML003706932).
- 5. U.S. Nuclear Regulatory Commission, Emergency Planning and Preparedness for Nuclear Power Reactors, Regulatory Guide 1.101, Revision 2, dated October 1981 (ADAMS Accession No. ML090440294).
- 6. U.S. Nuclear Regulatory Commission/Federal Emergency Management Agency, Criteria for Preparation and Evaluation of Radiological Emergency Respon se Plans and Preparedness in Support of Nuclear Power Plants, NUREG-0654/FE MA-REP-1, Revision 1, dated November 1980 (ADAMS Accession No. ML04042001 2).
- 7. U.S. Nuclear Regulatory Commission, Interim Staff Guidance ( ISG) NSIR/DPR/ISG-01, Revision 0, Emergency Planning for Nuclear Power Plants, date d November 2011 (ADAMS Accession No. ML113010523).
- 8. Nuclear Energy Institute, Assessment of On-Shift Emergency Response Organization Staffing and Capabilities, NEI 10-05, Revision 0, dated June 2011 (ADAMS Accession No. ML111751698).
Principal Contributor: K. Mott, NSIR
Date: May 18, 2022
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