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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] Category:Technical Specifications
MONTHYEARML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML23276B4552023-10-0303 October 2023 Technical Specification 5.6.8 – Post Accident Monitoring (PAM) Report ET 21-0010, License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-09-29029 September 2021 License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation 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 ET 18-0018, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-06-19019 June 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ML18093A9142018-03-0808 March 2018 Revision 31 to Updated Safety Analysis Report, Chapter 16, Technical Requirements Manual (Relocated Technical Specifications) 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 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 WO 15-0051, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.142015-09-23023 September 2015 License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.14 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 WO 15-0045, Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2015-07-27027 July 2015 Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report 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 ML14006A2182014-01-13013 January 2014 Correction to 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 WO 13-0089, Plant Specific Adoption of Technical Specification Task Force Traveler TSTF-522-A, Revision 0, Revised Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process2013-12-17017 December 2013 Plant Specific Adoption of Technical Specification Task Force Traveler TSTF-522-A, Revision 0, Revised Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process 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 ET 13-0023, License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2013-08-13013 August 2013 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis ML1107500362011-03-10010 March 2011 Changes to Technical Specification Bases - Revisions 45 Through 49 WO 10-0066, Correction of Typographical Error in Technical Specification 5.7.22010-10-21021 October 2010 Correction of Typographical Error in Technical Specification 5.7.2 ML1008205172010-07-23023 July 2010 Issuance of Amendment No. 188, Revise Technical Specifications for Use of Beacon Power Distribution Monitoring System ET 10-0014, Application to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-12010-04-13013 April 2010 Application to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-1 WO 10-0010, Updated Safety Analysis Report, Revision 232010-03-11011 March 2010 Updated Safety Analysis Report, Revision 23 ML1006401412010-03-0404 March 2010 Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ET 10-0011, Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps2010-03-0404 March 2010 Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ML1006400442010-03-0303 March 2010 Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps 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 ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation.2008-08-14014 August 2008 Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation. ET 08-0038, Application to Revise Technical Specification 5.6.6., Reactor Coolant System (RCS) Pressure and Temperature Limits Report (Ptlr).2008-07-10010 July 2008 Application to Revise Technical Specification 5.6.6., Reactor Coolant System (RCS) Pressure and Temperature Limits Report (Ptlr). ML0808400052008-04-0404 April 2008 Tech Pages for Amendment 178, Revision to Technical Specification 5.5.9 on the Steam Generator Program ML0803701212008-04-0303 April 2008 Tech Spec Pages for Amendment No. 177, Revise TS 3.3.2, ESFAS and TS 3.7.3, Main Feedwater Isolation Valves by Addition of Main Feedwater Regulating Valves and Associated Bypass Valves ML0729700282008-03-0303 March 2008 Tech Spec Pages for Amendment 175 Regarding Changes to Technical Specification Table 3.3.2-1 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 WO 07-0012, Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program2007-05-0303 May 2007 Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program ML0705500202007-04-17017 April 2007 Tech Spec Pages for License Amendment No. 173 Adopting TSTF-372 on Limiting Condition for Operation 3.0.8, Inoperability of Snubbers ET 07-0004, Technical Specifications, Revisions, Changes to TS 3.3.2 for Msfis I&C Digital Upgrade and Changes to TSs 3.7.2 and 3.7.3 for MSIV and Mfiv Replacement2007-03-14014 March 2007 Technical Specifications, Revisions, Changes to TS 3.3.2 for Msfis I&C Digital Upgrade and Changes to TSs 3.7.2 and 3.7.3 for MSIV and Mfiv Replacement ET 06-0053, Application for Technical Specification to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2006-12-15015 December 2006 Application for Technical Specification to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process ML0631202612006-11-0707 November 2006 Tech Spec Pages for Amendment 171 Regarding Addition of Actuator Trains to Main Steam and Feedwater Isolation Valves Technical Specifications ML0630502562006-10-31031 October 2006 Technical Specifications, Revision to Reactor Coolant System Specific Activity ML0627201792006-09-28028 September 2006 Tech Spec Pages for Amendment 167 Regarding Extended Containment Isolation Valve Completion Times ML0627000632006-09-26026 September 2006 Tech Spec Pages for Amendment 166 Regarding Changes to the Reactor Coolant System (RCS) Leakage Detection Instrumentation Methodology ET 06-0026, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program.2006-06-30030 June 2006 Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program. ET 06-0024, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation.2006-06-26026 June 2006 Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation. ML0612804712006-05-0808 May 2006 Tech Spec Pages for Amendment 164, Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process ML0611702372006-04-26026 April 2006 Technical Specifications, Extended Diesel Generator Completion Times ET 06-0015, Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process2006-03-28028 March 2006 Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process ET 06-0004, Revision to Technical Specification 5.5.9, Steam Generator Tube Surveillance Program2006-02-21021 February 2006 Revision to Technical Specification 5.5.9, Steam Generator Tube Surveillance Program 2024-02-27
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 24, 2017 Mr. Adam C. Heflin President, Chief Executive Officer, and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION-ISSUANCE OF AMENDMENT RE: REVISION TO THE CYBER SECURITY PLAN IMPLEMENTATION SCHEDULE (CAC NO. MF7998)
Dear Mr. Heflin:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 217 to Renewed Facility Operating License No. NPF-42 for the Wolf Creek Generating Station (WCGS). The amendment consists of changes to the facility operating license in response to your application dated June 14, 2016. The amendment approves the revised schedule for full implementation of the cyber security plan (CSP) from June 30, 2017, to December 31, 2017, and revises paragraph 2.E of Renewed Facility Operating License No. NPF-42 for WCGS, to incorporate the revised CSP implementation schedule.
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. Docket No. 50-482
Enclosures:
- 1. Amendment No. 217 to NPF-42 2. Safety Evaluation cc w/encls: Distribution via Listserv Sincerely, Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
WOLF CREEK GENERATING STATION -ISSUANCE OF AMENDMENT RE: REVISION TO THE CYBER SECURITY PLAN IMPLEMENTATION SCHEDULE (CAC NO. MF7998) DATED MARCH 24, 2017 DISTRIBUTION:
PUBLIC LPL4 r/f RidsACRS_MailCTR Resource RidsNrrDorllpl4 Resource ADAMS Accession No. ML 17024A241 RidsNrrLAPBlechman Resource RidsNrrPMWolfCreek Resource RidsRgn4MailCenter Resource RidsNsirCsd Resource OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NAME BSingal PBlechman w/comments DATE 02/06/17 02/06/17 OFFICE OGC /NLO NRR/DORL/LPL4/BC NAME NStAmour**
RPascarelli DATE 03/21 /17 03/24/17 OFFICIAL RECORD COPY JRycyna, NSIR/CSD *via memo dated January 5, 2017 **per email dated March 21 2017 ' NSIR/CSD/DD JBeardsley*
01/05117 NRR/DORL/LPL4/PM BSingal 03/24/17 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 217 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)
Renewed Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated June 14, 2016, 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.
Enclosure 1 2. Accordingly, the license is amended by changes as indicated in the attachment to this license amendment and paragraph 2.E of Renewed Facility Operating License No. NPF-42 is hereby amended to read, in part, as follows: The licensee shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The licensee's CSP was approved by License Amendment No. 197, as supplemented by changes approved by License Amendment No. 202, License Amendment No. 210, and License Amendment No. 217. 3. The license amendment is effective as of its date of issuance and shall be implemented within 30 days of the date of issuance.
The full implementation of CSP shall be in accordance with the implementation schedule submitted by the licensee on June 14, 2016, and approved by the NRC staff with this license amendment.
All subsequent changes to the NRG-approved CSP implementation schedule will require NRC approval pursuant to 10 CFR 50.90.
Attachment:
Changes to the Renewed Facility Operating License FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance:
March 2 4, 2o1 7 ATTACHMENT TO LICENSE AMENDMENT NO. 217 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-42 WOLF CREEK GENERATING STATION DOCKET NO. 50-482 Replace the following page of the Renewed Facility Operating License No. NPF-42 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change. Renewed Facility Operating License REMOVE 7 INSERT 7 7 (16) Additional conditions The Additional Conditions contained in Appendix D, as revised through Amendment No. 213, are hereby incorporated into this license. Wolf Creek Nuclear Operating Corporation shall operate the facility in Accordance with the Additional Conditions.
D. Exemptions from certain requirements of Appendix J to 10 CFR Part 50, and from a portion of the requirements of General Design Criterion 4 of Appendix A to 10 CFR Part 50, are described in the Safety Evaluation Report. These exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest.
Therefore, these exemptions are hereby granted pursuant to 10 CFR 50.12. With the granting of these exemptions the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
E. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The set of combined plans, which contains Safeguards Information protected under 1 O CFR 73.21, is entitled: "Wolf Creek Security Plan, Training and Qualification Plan, and Safeguard Contingency Plan," and was submitted on May 17, 2006. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The licensee's CSP was approved by License Amendment No. 197, as supplemented by changes approved by License Amendment No. 202, License Amendment No. 210, and License Amendment No. 217. F. Deleted per Amendment No. 141. G. The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims. H. The Updated Safety Analysis Report (USAR) supplement, as revised, submitted pursuant to 10 CFR 54.21 (d), shall be included in the next scheduled update to the USAR required by 10 CFR 50.71(e)(4), as appropriate, following the issuance of this renewed operating license. Until that update is complete, WCNOC may make changes to the programs and activities described in the supplement without prior Commission approval, provided that WCNOC evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section. Renewed License No. NPF-42 Amendment No. 179, 197, 202, 210, 213, 217 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 RELATED TO AMENDMENT NO. 217 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-42 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482
1.0 INTRODUCTION
By letter dated June 14, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16174A121), Wolf Creek Nuclear Operating Corporation (WCNOC, the licensee) requested a change to the renewed facility operating license for the Wolf Creek Generating Station (WCGS). The U.S. Nuclear Regulatory Commission (NRC) staff initially reviewed and approved the licensee's Cyber Security Plan (CSP) implementation schedule by Amendment No.197 dated July 27, 2011 (ADAMS Accession No. ML 111990339).
Subsequently, the NRC staff reviewed and approved Amendment No. 201, dated December 12, 2012 (ADAMS Accession No. ML 12279A250), to modify Milestone 6 to change the scope of the cyber security controls to be implemented by the committed date, and Amendment No. 210, dated August 14, 2014 (ADAMS Accession No. ML 14209A023), which extended the CSP implementation schedule.
The schedule approved by Amendment No. 210 required WCGS to fully implement and maintain all provisions of the CSP by June 30, 2017. The proposed change would revise the date of CSP Implementation Schedule Milestone 8 and paragraph 2.E in the renewed facility operating license from June 30, 2017 to December 31, 2017. Milestone 8 of the CSP implementation schedule concerns the full implementation of the CSP. The NRC issued a proposed finding that the amendment involves no significant hazards consideration, published in the Federal Register on August 16, 2016 (81 FR 54618).
2.0 REGULATORY EVALUATION
The NRC staff reviewed and approved the licensee's existing CSP implementation schedule by letter dated August 14, 2014, Amendment No. 210 to Renewed Facility Operating License No. NPF-42 for WCGS. The NRC staff considered the following regulatory requirements and guidance in its review of the license amendment request (LAR) to modify the existing CSP implementation schedule:
- Title 10 of the Code of Federal Regulations (10 CFR), Section 73.54, "Protection of digital computer and communication systems and networks," which states, in part: Enclosure 2 Each [CSP] submittal must include a proposed implementation schedule.
Implementation of the licensee's cyber security program must be consistent with the approved schedule.
- The licensee's renewed facility operating license includes a license condition that requires the licensee to fully implement and maintain in effect all provisions of the Commission-approved CSP. Review criteria provided by the NRC staffs internal memorandum, "Review Criteria for Title 10 of the Code of Federal Regulations Part 73.54, Cyber Security Implementation Schedule Milestone 8 License Amendment Requests," dated October 24, 2013 (ADAMS Accession No. ML 13295A467), to be considered for evaluating licensees' requests to postpone their cyber security program implementation date (commonly known as Milestone 8). The NRC staff does not regard the CSP milestone implementation dates as regulatory commitments that can be changed unilaterally by the licensee, particularly in light of the regulatory requirement at 10 CFR 73.54, that states, in part, that "[i]mplementation of the licensee's cyber security program must be consistent with the approved schedule." As the NRC staff explained in its letter to all operating reactor licensees dated May 9, 2011 (ADAMS Accession No. ML 110980538), the implementation of the plan, including the key intermediate milestone dates and the full implementation date shall be in accordance with the implementation schedule submitted by the licensee and approved by the NRC. All subsequent changes to the NRG-approved CSP implementation schedule, thus, will require prior NRC approval as required by 10 CFR 50.90, "Application for amendment of license, contruction permit, or early site permit." 3.0 TECHNICAL EVALUATION
3.1 Licensee's
Requested Change The NRC staff issued Amendment No. 197 to Renewed Facility Operating License No. NPF-42 by letter dated July 27, 2011. This amendment approved the CSP and associated implementation schedule, and added a license condition requiring the licensee to fully implement and maintain the Commission-approved CSP. The implementation schedule was based on a template prepared by the Nuclear Energy Institute (NEI), which was transmitted to the NRC by letter dated February 28, 2011 (ADAMS Accession No. ML 110600206).
By letter dated March 1, 2011 (ADAMS Accession No. ML 110070348), the NRC staff found the NEI template acceptable for licensees to use to develop their CSP implementation schedules.
The licensee's proposed implementation schedule for the Cyber Security Program identified completion dates and bases for the following eight milestones:
- 1) Establish the Cyber Security Assessment Team (CSAT); 2) Identify Critical Systems (CSs) and Critical Digital Assets (CDAs); 3) Install deterministic one-way devices between lower level devices and higher level devices; 4) Implement the security control "Access Control For Portable And Mobile Devices"; 5) Implement observation and identification of obvious cyber related tampering to existing insider mitigation rounds by incorporating the appropriate elements;
- 6) Identify, document, and implement technical cyber security controls in accordance with "Mitigation of Vulnerabilities and Application of Cyber Security Controls," for CDAs that could adversely impact the design function of physical security target set equipment;
- 7) Ongoing monitoring and assessment activities for those target set CDAs whose security controls have been implemented; and 8) Fully implement the CSP. Currently, Milestone 8 of the WCGS CSP requires the licensee to fully implement the CSP by June 30, 2017. By letter dated June 14, 2016, the licensee proposed to modify the Milestone 8 completion date to December 31, 2017. The licensee provided the following information pertinent to each of the criteria identified in the NRC guidance memorandum dated October 24, 2013. 1. Identification of the specific requirement or requirements of the cyber security plan that the licensee needs additional time to implement.
The licensee stated that CSP Section 3, "Analyzing Digital Computer Systems and Networks" and CSP Section 4, "Establishing, Implementing, and Maintaining the Cyber Security Program," need additional time to implement.
It further noted that these sections describe requirements for application and maintenance of cyber security controls and described the process of addressing security controls.
The licensee described specific requirements needing additional time including determining the need and implementation for automated security information and event management systems and designing/implementing these systems for monitoring activity on networks of CDAs, additional physical controls for CDAs outside the security protected area, and significant programmatic change management associated with approximately 50 procedure changes. 2. Detailed justification that describes the reason the licensee requires additional time to implement the specific requirement or requirements identified.
In its letter dated June 14, 2016, the licensee stated, in part; During October of 2015, the NRC completed an inspection of WCNOC's compliance with interim Milestones 1 through 7. The preparation for and support of these inspections has required a significant commitment of time from WCNOCs most knowledgeable subject matter experts on nuclear cyber security, exceeding the estimate previously developed and therefore, drawing those resources away from Milestone 8 implementation activities.
Also, the licensee stated that development of an endorsed written standard for interpreting and applying cyber security controls has continued to be a work-in-progress.
The release of Revision 3 of NEI 13-10, "Cyber Security Control Assessments" and then subsequently, Revision 4, appears to provide some reduction in level of effort but more time is needed to take full advantage of the guidance.
Defining the cyber security controls is resource intensive and without guidance for what "good" looks like for each control there is high risk of rework as industry interpretations change. The licensee further stated that CDA mitigation activities defined in Section 3.1.6 of the CSP, "Mitigation of Vulnerabilities and Application of Cyber Security Controls," are resource intensive, remediation activities need to be carefully considered, there are change management challenges, and the need for training on new programs, processes and procedures requires additional time to implement requirements of the CSP. 3. A proposed completion date for Milestone 8 consistent with the remaining scope of work to be conducted and the resources available.
In its letter dated June 14, 2016, the licensee stated; WCNOC is requesting a change to the Implementation Milestone 8 completion date from June 30, 2017 to December 31, 2017 to complete CDA assessments, implement design modifications based on assessment results, update existing procedures, develop new program procedures and provide training to complete full implementation of the cyber security program. 4. An evaluation of the impact that the additional time to implement the requirements will have on the effectiveness of the licensee's overall cyber security program in the context of milestones already completed.
In its letter dated June 14, 2016, the licensee stated, in part; The impact of the requested additional implementation time on the effectiveness of the overall cyber security program is considered to be very low because WCNOC has completed the interim Implementation Milestones 1 through 7 required by December 31, 2012 and the "Good Faith Letter (Reference 6 1) required actions by October 29, 2013. The completed activities provide a high degree of protection against cyber attacks while WCNOC implements the full program. Further WCNOC has transitioned from the previous cyber security program. Revisions have been made to procedures that control plant modifications, planning, and maintenance, establishing ties to cyber security procedures for CDA analysis and control of portable digital media and devices periodically connected to CDAs. 5. A discussion of the licensee's methodology for prioritizing completion of work for critical digital assets associated with significant safety, security, or emergency preparedness (SSEP) consequences and with reactivity effects in the balance of plant. 1 NRC Memorandum from B. Westreich NRC to T. Blount NRC, "Enhanced Guidance for Licensee Term Corrective Actions to Address Cyber Security Inspection Findings and Licensee Eligibility for Faith" Attempt Discretion," dated July 1, 2013 (security-related information, not publicly available). In its letter dated June 14, 2016, the licensee stated, in part; WCNOC methodology for prioritizing Implementation Milestone 8 activities is centered on considerations for SSEP, and Balance of Plant (BOP) continuity of power consequences.
The methodology is based on defense-in-depth, installed configuration of the CDAs and susceptibility to the five commonly identified threat vectors listed in the NRC Cyber Security Determination Process. Prioritization for CDA assessments begins with safety related CDAs and continues through the lower priority non-safety and emergency preparedness (EP) CDAs:
- Important to safety CDAs (including BOP CDAs that directly impact continuity of power) and control system CDAs
- Non-safety related CDAs and EP CDAs. 6. A discussion of the licensee's cyber security program performance up to the date of the license amendment request. In its letter dated June 14, 2016, the licensee stated; A Quality Assurance (QA) surveillance of interim Implementation Milestones 1 through 7 has concluded that WCNOC has an effective program an[d] additional on-going QA surveillances under the physical and cyber security programs will be conducted during the interim period. Audit/assessment issues are entered into the Corrective Action Program (CAP) and addressed for program improvement.
In October 2015, the NRC completed an inspection related to compliance with interim Milestones 1 through 7. All findings were found to meet the criteria described in the Reference 6 2 for enforcement discretion, and were entered into the CAP. On-going monitoring and time-based periodic actions provide continuing program performance monitoring.
- 7. A discussion of cyber security issues pending in the licensee's CAP. In its letter dated June 14, 2016, the licensee stated; There are presently no significant (constituting a threat to a CDA via cyber means or calling into question program effectiveness) nuclear cyber security issues pending in the CAP. Several non-significant issues identified during the recent NRC inspection described above have been entered into the CAP. All outstanding items associated with the Milestone 1-7 NRC inspection are being tracked in accordance with the WCNOC CAP. 2 NRC Memorandum from B. Westreich NRC to T. Blount NRC, "Enhanced Guidance for Licensee Term Corrective Actions to Address Cyber Security Inspection Findings and Licensee Eligibility for Faith" Attempt Discretion," dated July 1, 2013 (security-related information, not publicly available). 8. A discussion of modifications completed to support the cyber security program and a discussion of pending cyber security modifications.
The licensee listed and discussed completed modifications and listed systems pending modifications.
These are consistent with the discussion above and the CSP. 3.2 NRC Staff Evaluation The NRC staff has evaluated the licensee's application using the regulatory requirements and guidance above. The NRC staffs evaluation is below. The staff finds that the actions necessary for full compliance with the WCGS CSP are reasonable as discussed below. The licensee indicated that the activities associated with the CSP, as described in Milestones 1 through 7, were completed prior to December 31, 2012, and provide a high degree of protection against cyber attacks while WCNOC implements the full program. The NRC staff thus concludes that the activities already undertaken and completed by the licensee result in an increase to site security because the activities the licensee completed mitigate the most significant cyber attack vectors for the most significant CDAs. Therefore, the NRC has reasonable assurance that full implementation of the CSP by December 31, 2017, will provide adequate protection of the public health and safety and the common defense and security.
The licensee has stated that preparation for, and support of, NRC inspections, has required a significant commitment of time from WCNOCs most knowledgeable cyber security subject matter experts. This has drawn those subject matter experts and associated resources away from Milestone 8 implementation activities.
Also development of an endorsed written standard for interpreting and applying cyber security controls has continued to be a work-in-progress.
The release of Revision 3 of NEI 13-10 and then subsequently, Revision 4, appears to provide some reduction in level of effort needed to identify and apply those controls, but more time is needed to take full advantage of the guidance.
Finally, the licensee stated that defining the cyber security controls is resource intensive, and because industry interpretations are subject to change and without guidance for what "good" looks like for each control, there is a high risk of rework. The licensee also noted the following:
- the CDA mitigation activities defined in Section 3.1.6 of the Cyber Security Plan are resource intensive.
- remediation activities need to be carefully considered.
- there are challenges associated with management changes, and
- training on new programs, processes and procedures may be required.
The NRC staff concludes that the licensee's request for additional time to implement Milestone 8 is reasonable given the unanticipated complexity, volume, and scope of the remaining work required to fully implement its CSP. The licensee proposed a Milestone 8 completion date of December 31, 2017. The licensee stated that changing the completion date of Milestone 8 allows for sufficient time to complete CDA assessments, implement design modifications based on assessment results, update existing procedures, develop new program procedures and provide training to complete full implementation of the cyber security program. The licensee stated the methodology for prioritizing Milestone 8 activities is centered on considerations for SSEP and BOP (continuity of power) consequences.
The methodology is based on defense-in-depth, installed configuration of the CDA, and susceptibility to commonly identified threat vectors. Prioritization of CDA assessments begins with safety related CDAs and continues through the lower priority non-safety and EP CDAs as follows: safety related CDAs, physical security CDAs, important to safety CDAs (including BOP CDAs that directly impact continuity of power) and control system CDAs, and non-safety related CDAs and SSEP CDAs. The NRC staff concludes that based on the tasks described above and the limited resources with the appropriate expertise to perform these activities, the licensee's methodology for prioritizing work on CDAs is appropriate.
The staff further concludes that the licensee's request to delay final implementation of the CSP until December 31, 2017 is reasonable given the complexity of the remaining unanticipated work. 3.3 Technical Evaluation Conclusion The NRC staff concludes that the licensee's request to delay full implementation of its CSP until December 31, 2017, is reasonable for the following reasons: (i) the licensee's implementation of Milestones 1 through 7 provides mitigation for significant cyber attack vectors for the most significant CDAs as discussed in the staff evaluation above; (ii) the scope of the work required to come into full compliance with the CSP implementation schedule was much more complicated than anticipated and not reasonably foreseeable when the CSP implementation schedule was originally developed; and (iii) the licensee has reasonably prioritized and scheduled the work required to come into full compliance with its CSP implementation schedule.
Therefore, the staff finds the proposed change acceptable.
3.4 Revision
to License Condition Paragraph 2.E By letter dated June 14, 2016, the licensee proposed to modify paragraph 2.E of Renewed Facility Operating License No. NPF-42 for WCGS, which provides a license condition to require the licensees to fully implement and maintain in effect all provisions of the NRG-approved CSP. The current license condition in paragraph 2.E of the Renewed Facility Operating License No. NPF-42 for WCGS states, in part; The licensee shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The licensee's CSP was approved by License Amendment No. 197, as supplemented by changes approved by License Amendment No. 202 and License Amendment No. 210. The revised portion of the license condition in paragraph 2.E of the Renewed Facility Operating License No. NPF-42 for WCGS would state: The licensee shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The licensee's CSP was approved by License Amendment No. 197, as supplemented by changes approved by License Amendment No. 202, License Amendment No. 210, and License Amendment No. 217. 4.0 REGULATORY COMMITMENTS By letter dated June 14, 2016, the licensee made the following regulatory commitment:
Regulatory Commitments Due Date/Event Fully implement the [WCNOC] Cyber Security Plan for all SSEP December31, 2017 functions.
The above stated commitment is consistent with the revised Milestone 8 implementation date proposed by the licensee and evaluated by the NRC staff.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Kansas State official was notified of the proposed issuance of the amendment on January 23, 2017. The State official had no comments.
5.0 ENVIRONMENTAL
CONSIDERATION This is an amendment to a 10 CFR Part 50 license that relates solely to safeguards matters and does not involve any significant construction impacts. This amendment is an administrative change to extend the date by which the licensee must have its cyber security plan fully implemented.
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(12).
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) there is reasonable assurance 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 security or to the health and safety of the public. Principal Contributor:
John Rycyna, NSIR/CSD Date: March 24, 2017