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| {{#Wiki_filter:ENCLOSURE 1REVISED PAGES OF FACILITY OPERATING LICENSE NO. NPF-42DOCKET NO. 50-482Replace the following pages of the Facility Operating License No. NPF-42. The revised pagesare identified by the date of the letter issuing these pages and contain marginal lines indicatingthe areas of change. Facility Operating LicenseREMOVEINSERT 5 5 6 6 | | {{#Wiki_filter:ENCLOSURE 1 REVISED PAGES OF FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following pages of the Facility Operating License No. NPF-42. The revised pages are identified by the date of the letter issuing these pages and contain marginal lines indicating the areas of change. |
| -- 7 (7)NUREG-0737 Supplement 1 Conditions (Section 22, SER)Deleted per Amendment No. 141.(8)Post-Fuel-Loading Initial Test Program (Section 14, SER Section 14, SSER #5)Deleted per Amendment No. 141.(9)Inservice Inspection Program (Sections 5.2.4 and 6.6, SER)Deleted per Amendment No. 141.(10)Emergency PlanningDeleted per Amendment No. 141.(11)Steam Generator Tube Rupture (Section 15.4.4, SSER #5)Deleted per Amendment No. 141.(12)LOCA Reanalysis (Section 15.3.7, SSER #5)Deleted per Amendment No. 141.(13)Generic Letter 83-28Deleted per Amendment No. 141.(14)Surveillance of Hafnium Control Rods (Section 4.2.3.1 (10), SER and SSER #2)Deleted per Amendment No. 141.(15)Mitigation Strategy lDevelop and maintain strategies for addressing large fires and explosions that linclude the following key areas:
| | Facility Operating License REMOVE INSERT 5 5 6 6 |
| ll(a)Fire fighting response strategy with the following elements:
| | -- 7 |
| l1. Pre-defined coordinated fire response strategy and guidance l2. Assessment of mutual aide fire fighting assets l3. Designated staging areas for equipment and materials l4. Command and control l5. Training of response personnel lAmendment No. 4, 108, 141Revised by letter dated August 2, 2007 (b)Operations to mitigate fuel damage considering the following:
| | |
| l1. Protection and use of personnel assets l2. Communications l3. Minimizing fire spread l4. Procedures for implementing integrated fire response strategy l5. Identification of readily available, pre-staged equipment l6. Training on integrated fire response strategy l7. Spent fuel pool mitigation measures l(c)Actions to minimize release to include consideration of:
| | (7) NUREG-0737 Supplement 1 Conditions (Section 22, SER) |
| l1. Water spray scrubbing l2. Dose to onsite responders l(16)Additional Conditions lThe Additional Conditions contained in Appendix D, as revised throughAmendment No. 163, 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 aportion 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 theCommission-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 10 CFR 73.21, is entitled: "Wolf Creek Security Plan, Training and Qualification Plan, and Safeguard Contingency Plan," and was submitted on May 17, 2006.Amendment No. 4, 108, 141, 163Revised by letter dated October 28, 2004Revised by letter dated February 13, 2007Revised by letter dated August 2, 2007 lF.Deleted per Amendment No. 141.G.The licensees shall have and maintain financial protection of such type and in suchamounts 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.This license is effective as of the date of issuance and shall expire at Midnight onMarch 11, 2025.For the Nuclear Regulatory Commission"Original Signed By"Harold R. Denton, DirectorOffice of Nuclear Reactor RegulationAttachments/Appendices:1. Attachment 1 - Deleted
| | Deleted per Amendment No. 141. |
| | (8) Post-Fuel-Loading Initial Test Program (Section 14, SER Section 14, SSER #5) |
| | Deleted per Amendment No. 141. |
| | (9) Inservice Inspection Program (Sections 5.2.4 and 6.6, SER) |
| | Deleted per Amendment No. 141. |
| | (10) Emergency Planning Deleted per Amendment No. 141. |
| | (11) Steam Generator Tube Rupture (Section 15.4.4, SSER #5) |
| | Deleted per Amendment No. 141. |
| | (12) LOCA Reanalysis (Section 15.3.7, SSER #5) |
| | Deleted per Amendment No. 141. |
| | (13) Generic Letter 83-28 Deleted per Amendment No. 141. |
| | (14) Surveillance of Hafnium Control Rods (Section 4.2.3.1 (10), SER and SSER #2) |
| | Deleted per Amendment No. 141. |
| | (15) Mitigation Strategy l Develop and maintain strategies for addressing large fires and explosions that l include the following key areas: l l |
| | (a) Fire fighting response strategy with the following elements: l |
| | : 1. Pre-defined coordinated fire response strategy and guidance l |
| | : 2. Assessment of mutual aide fire fighting assets l |
| | : 3. Designated staging areas for equipment and materials l |
| | : 4. Command and control l |
| | : 5. Training of response personnel l Amendment No. 4, 108, 141 Revised by letter dated August 2, 2007 |
| | |
| | (b) Operations to mitigate fuel damage considering the following: l |
| | : 1. Protection and use of personnel assets l |
| | : 2. Communications l |
| | : 3. Minimizing fire spread l |
| | : 4. Procedures for implementing integrated fire response strategy l |
| | : 5. Identification of readily available, pre-staged equipment l |
| | : 6. Training on integrated fire response strategy l |
| | : 7. Spent fuel pool mitigation measures l (c) Actions to minimize release to include consideration of: l |
| | : 1. Water spray scrubbing l |
| | : 2. Dose to onsite responders l (16) Additional Conditions l The Additional Conditions contained in Appendix D, as revised through Amendment No. 163, 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 10 CFR 73.21, is entitled: Wolf Creek Security Plan, Training and Qualification Plan, and Safeguard Contingency Plan, and was submitted on May 17, 2006. |
| | Amendment No. 4, 108, 141, 163 Revised by letter dated October 28, 2004 Revised by letter dated February 13, 2007 Revised by letter dated August 2, 2007 |
| | |
| | l 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. This license is effective as of the date of issuance and shall expire at Midnight on March 11, 2025. |
| | For the Nuclear Regulatory Commission Original Signed By Harold R. Denton, Director Office of Nuclear Reactor Regulation Attachments/Appendices: |
| | : 1. Attachment 1 - Deleted |
| : 2. Attachment 2 - Deleted | | : 2. Attachment 2 - Deleted |
| : 3. Attachment 3 - Deleted | | : 3. Attachment 3 - Deleted |
| : 4. Appendix A - TechnicalSpecifications (NUREG-1136)5. Appendix B - EnvironmentalProtection Plan6. Appendix C - Antitrust Conditions | | : 4. Appendix A - Technical Specifications (NUREG-1136) |
| : 7. Appendix D - Additional ConditionsDate of issuance: June 4, 1985Amendment No. 108, 141,Revised by letter dated August 2, 2007}} | | : 5. Appendix B - Environmental Protection Plan |
| | : 6. Appendix C - Antitrust Conditions |
| | : 7. Appendix D - Additional Conditions Date of issuance: June 4, 1985 Amendment No. 108, 141, Revised by letter dated August 2, 2007}} |
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MONTHYEARML0721105172007-08-0202 August 2007 Conforming License Amendment to Incorporate the Mitigation Strategies Required by Section B.5.b. of Commission Order EA-02-026 (Tac No. MD4641) Project stage: Other ML0720802112007-08-0202 August 2007 Revised Pages of Facility Operating License No. NPF-42 Project stage: Other 2007-08-02
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Category:Letter
MONTHYEARML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) IR 05000482/20240022024-07-18018 July 2024 Integrated Inspection Report 05000482/2024002 IR 05000482/20244012024-07-0202 July 2024 Security Baseline Inspection Report 05000482/2024401 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24162A1632024-06-11011 June 2024 Operating Corporation – Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000482/2024010) ML24150A0562024-05-29029 May 2024 Foreign Ownership, Control or Influence (FOCI) Information – Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24089A2622024-04-29029 April 2024 Financial Protection Levels ML24118A0022024-04-27027 April 2024 Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24113A1882024-04-19019 April 2024 Foreign Ownership, Control or Influence Information - Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24109A1842024-04-18018 April 2024 Cycle 27 Core Operating Limits Report ML24109A1212024-04-18018 April 2024 (WCGS) Form 5 Exposure Report for Calendar Year 2023 IR 05000482/20240012024-04-17017 April 2024 Integrated Inspection Report 05000482/2024001 ML24106A1482024-04-15015 April 2024 Notification of Inspection (NRC Inspection Report 05000482/2024003) and Request for Information ML24114A1442024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37 ML24098A0052024-04-0707 April 2024 2023 Annual Environmental Operating Report ML24089A1352024-03-29029 March 2024 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes ML24089A0972024-03-29029 March 2024 Response to NRC Regulatory Issue Summary 2024-01, “Preparation and Scheduling of Operator Licensing Examinations” ML24074A3312024-03-14014 March 2024 Missed Quarterly Inspection Per 40 CFR 266 Subpart N ML24080A3452024-03-11011 March 2024 7 of the Wolf Creek Generating Station Updated Safety Analysis Report IR 05000482/20240122024-03-11011 March 2024 Fire Protection Team Inspection Report 05000482/2024012 ML24068A1992024-03-0707 March 2024 Changes to Technical Specification Bases - Revisions 93 and 94 ML24066A0672024-03-0505 March 2024 4-2022-024 Letter - OI Closure to Licensee ML24061A2642024-03-0101 March 2024 Revision of Two Procedures That Implement the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) Commissioners IR 05000482/20230062024-02-28028 February 2024 Annual Assessment Letter for Wolf Creek Generating Station Report 05000482/2023006 ML24059A1702024-02-28028 February 2024 Annual Fitness for Duty Program Performance Report, and Annual Fatigue Report for 2023 ML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML24050A0012024-02-19019 February 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24036A0092024-02-14014 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0075 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24036A1852024-02-0505 February 2024 Correction to 2022 Annual Radioactive Effluent Release Report - Report 46 ML24032A1742024-02-0202 February 2024 Withdrawal of Requested Licensing Action Exemption from Specific Provisions in 10 CFR 73.55 ML24025A0992024-01-25025 January 2024 Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML24018A0792024-01-22022 January 2024 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd and Opportunity for a Hearing (EPID L-2024-LLA-0007) (Letter) ML24018A1382024-01-18018 January 2024 Inservice Inspection Request for Information ML24018A2482024-01-18018 January 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 238 IR 05000482/20230042024-01-11011 January 2024 Integrated Inspection Report 05000482/2023004 ML23356A0722024-01-0404 January 2024 Supplemental Information Needed for Acceptance of Requested Licensing Actions Exemption from Specific 10 CFR Part 73N Requirements (EPID L-2023-LLE-0048) (Redacted Version) WO 23-0002, Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082023-12-26026 December 2023 Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 ML23348A3662023-12-18018 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482 2024012) and Request for Information ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23331A4972023-11-27027 November 2023 Supplement to License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23325A2112023-11-20020 November 2023 Submittal of Request for Exemption from Specific Provisions in 10 CFR 73.55 ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML23292A3592023-10-19019 October 2023 License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 2024-07-31
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24212A0372024-08-0707 August 2024 Summary of July 23, 2024, Teleconference with Wolf Creek Nuclear Operating Corporation Regarding Wolf Creek Generating Station, Unit 1, Amendment No. 237, Allowing the Use of Portable Lighting ML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23201A1212023-08-0707 August 2023 Issuance of Amendment No. 236 Revision to Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML23130A2902023-07-26026 July 2023 Issuance of Amendment No. 235 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22252A1512022-11-0404 November 2022 Issuance of Amendment No. 234 Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ML22199A2942022-08-16016 August 2022 Issuance of Amendment No. 233 Removal of Table of Contents from the Technical Specifications ML22069A0562022-05-18018 May 2022 Issuance of Amendment No. 232 Regarding Revision to the Emergency Plan Related to On-Shift Staffing ML22021B5982022-02-23023 February 2022 Issuance of Amendment No. 231 Revision of Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21210A2472021-09-0303 September 2021 Issuance of Amendment No. 230 Revision of Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange ML21238A3862021-09-0202 September 2021 Correction to Issuance of Amendment No. 229 Change to Owner Licensee Names ML21095A1922021-07-20020 July 2021 Issuance of Amendment No. 229 Change to Owner Licensee Names ML21061A0782021-04-23023 April 2021 Issuance of Amendment No. 228 Regarding Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ML21053A1172021-04-0808 April 2021 1 - Issuance of Amendment No. 227 TS Change Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Based on TSTF-425 ML20276A1492020-12-0707 December 2020 Issuance of Amendment No. 226 Extension of Type a and Type C Leak Rate Test Frequencies ML19353C5002020-02-27027 February 2020 Issuance of Amendment No. 224 Revision to Technical Specification 3.3.5, - Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation, - ML19182A3452019-08-19019 August 2019 Issuance of Amendment No 222 Revise Technical Specifications to Adopt TSTF Traveler TSTF-529, Clarify Use and Application Rules ML19100A1222019-05-31031 May 2019 Issuance of Amendment No. 221 License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term ML17166A4092017-08-28028 August 2017 Issuance of Amendment No. 218, Request to Adopt Emergency Action Level (EAL) Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6 ML17024A2412017-03-24024 March 2017 Issuance of Amendment No. 217 Revision to the Cyber Security Plan Implementation Schedule ML16179A2932016-08-0303 August 2016 Issuance of Amendment No. 216, Revise Technical Specification (TS) 4.2.1 and TS 5.6.5 to Allow Use of Optimized Zirlo as Approved Fuel Rod Cladding ML16081A1942016-04-15015 April 2016 Issuance of Amendment No. 215, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.14 Consistent with TSTF-276-A, Revise DG Full Load Rejection Test ML15183A0522015-09-11011 September 2015 Issuance of Amendment No. 214, Request to Revise Fire Protection Program Related to Alternative Shutdown Capability as Described in Updated Safety Analysis Report ML15203A0052015-08-28028 August 2015 Redacted, Issuance of Amendment No. 213, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large-Break Loss-of-Coolant Accident Analysis Methodology (Astrum) ML15169A2132015-07-28028 July 2015 Issuance of Amendment No. 212, Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML14209A0232014-08-14014 August 2014 Issuance of Amendment No. 210, Modify License Condition Related to Approval of Revised Cyber Security Plan Implementation Milestone 8 Completion Date ML14156A2462014-08-0707 August 2014 Issuance of Amendment No. 209, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), to Replace Westinghouse Methodologies ML14157A0822014-07-0101 July 2014 Issuance of Amendment No. 208, Adopt TSTF-522-A, Revision 0, Revise Ventilation System to Operate for 10 Hours Per Month, Using Consolidated Line Item Improvement Process ML13282A5342013-12-0606 December 2013 Issuance of Amendment No. 207, Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System, to Reflect Mass Input Transient Analysis ML13282A1472013-12-0202 December 2013 Issuance of Amendment No. 206, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement 3.8.1.10 to Increase Voltage Limit for Diesel Generator Load Rejection Test ML13197A2102013-08-23023 August 2013 Issuance of Amendment No. 205, Revise Fire Protection License Condition and the Updated Safety Analysis Report for a Deviation from Appendix R for Volume Control Tank Outlet Valves ML12334A3122012-12-21021 December 2012 Issuance of Amendment No. 203, Revise Technical Specification 3.6.6, Containment Spray and Cooling Systems, to Replace Surveillance Requirement 3.6.6.8 with an Event-Based Frequency ML12279A2502012-12-12012 December 2012 Issuance of Amendment No. 202, Revise Physical Security License Condition and Change to Scope of Milestone 6 for the Cyber Security Plan Implementation Schedule ML12300A3092012-12-11011 December 2012 Issuance of Amendment No. 201, Revise TS 5.5.9, Steam Generator Program, and TS 5.6.10, Steam Generator Tube Inspection Report for a Permanent Alternate Repair Criteria ML12318A1452012-12-0505 December 2012 Issuance of Amendment No. 200, Revision to Technical Specifications (TS) 3.3, Instrumentation, 3.7, Plant Systems, and 3.8, Electrical Power Systems ML12289A8962012-11-19019 November 2012 Issuance of Amendment No. 199, Request to Adopt Technical Specification Task Force Traveler TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies Using Consolidated Line Item Improvement Process ML1104804612011-04-19019 April 2011 Issuance of Amendment No. 196, Correction of Typographical Error in Technical Specification 5.7.2, Administrative Controls Related to High Radiation Area ML1108405902011-04-0606 April 2011 Issuance of Amendment No. 195, Revise Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for Temporary Alternate Repair Criterion ML1105508462011-03-30030 March 2011 Issuance of Amendment No. 194, Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-1 to Identify Functions and Modes for Reactor Trip P-4 Interlock Function ML1021703352010-11-0303 November 2010 Issuance of Amendment No. 190, Revise Technical Specification 3.6.3, Containment Isolation Valves, Limiting Condition for Operation ML1025604982010-09-30030 September 2010 Issuance of Amendment No. 189, Revise Updated Safety Analysis Report to Modify Fire Protection Program for Use of Fire-Resistive Electrical Cable ML1008205172010-07-23023 July 2010 Issuance of Amendment No. 188, Revise Technical Specifications for Use of Beacon Power Distribution Monitoring System ML1006300132010-03-0505 March 2010 Issuance of Amendment No. 187, Revise TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps (Emergency Circumstances) ML0927506062009-10-19019 October 2009 Issuance of Amendment No. 186, Modify Technical Specification 5.5.9, Steam Generator Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for Alternate Repair Criteria ML0917301912009-08-0707 August 2009 License Amendment, Issuance of Amendment No. 185, Modify Technical Specifications to Adopt TSTF-511, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0917002962009-07-30030 July 2009 Issuance of Amendment 183, Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, to Extend the Surveillance Frequency on ESFAS Slave Relays from 92 Days to 18 Months ML0909607342009-05-15015 May 2009 Issuance of Amendment No. 182, Revise Technical Specification 3.5.2, ECCS - Operating, in Accordance with TSTF-325A, ECCS Conditions and Required Actions with <100% Equivalent ECCS Flow ML0906103172009-03-31031 March 2009 Issuance of Amendment No. 181, Revise Licensing Basis, Modification of the Main Steam and Feedwater Isolation System Controls ML0834302242009-01-27027 January 2009 Issuance of Amendment No. 180, Revise Technical Specification Requirements Consistent with TSTF-419, Revision 0, Revise PTLR Definition and References in ISTS 5.6.6, RCS PTLR 2024-08-07
[Table view] |
Text
ENCLOSURE 1 REVISED PAGES OF FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following pages of the Facility Operating License No. NPF-42. The revised pages are identified by the date of the letter issuing these pages and contain marginal lines indicating the areas of change.
Facility Operating License REMOVE INSERT 5 5 6 6
-- 7
(7) NUREG-0737 Supplement 1 Conditions (Section 22, SER)
Deleted per Amendment No. 141.
(8) Post-Fuel-Loading Initial Test Program (Section 14, SER Section 14, SSER #5)
Deleted per Amendment No. 141.
(9) Inservice Inspection Program (Sections 5.2.4 and 6.6, SER)
Deleted per Amendment No. 141.
(10) Emergency Planning Deleted per Amendment No. 141.
(11) Steam Generator Tube Rupture (Section 15.4.4, SSER #5)
Deleted per Amendment No. 141.
(12) LOCA Reanalysis (Section 15.3.7, SSER #5)
Deleted per Amendment No. 141.
(13) Generic Letter 83-28 Deleted per Amendment No. 141.
(14) Surveillance of Hafnium Control Rods (Section 4.2.3.1 (10), SER and SSER #2)
Deleted per Amendment No. 141.
(15) Mitigation Strategy l Develop and maintain strategies for addressing large fires and explosions that l include the following key areas: l l
(a) Fire fighting response strategy with the following elements: l
- 1. Pre-defined coordinated fire response strategy and guidance l
- 2. Assessment of mutual aide fire fighting assets l
- 3. Designated staging areas for equipment and materials l
- 4. Command and control l
- 5. Training of response personnel l Amendment No. 4, 108, 141 Revised by letter dated August 2, 2007
(b) Operations to mitigate fuel damage considering the following: l
- 1. Protection and use of personnel assets l
- 2. Communications l
- 3. Minimizing fire spread l
- 4. Procedures for implementing integrated fire response strategy l
- 5. Identification of readily available, pre-staged equipment l
- 6. Training on integrated fire response strategy l
- 7. Spent fuel pool mitigation measures l (c) Actions to minimize release to include consideration of: l
- 1. Water spray scrubbing l
- 2. Dose to onsite responders l (16) Additional Conditions l The Additional Conditions contained in Appendix D, as revised through Amendment No. 163, 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 10 CFR 73.21, is entitled: Wolf Creek Security Plan, Training and Qualification Plan, and Safeguard Contingency Plan, and was submitted on May 17, 2006.
Amendment No. 4, 108, 141, 163 Revised by letter dated October 28, 2004 Revised by letter dated February 13, 2007 Revised by letter dated August 2, 2007
l 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. This license is effective as of the date of issuance and shall expire at Midnight on March 11, 2025.
For the Nuclear Regulatory Commission Original Signed By Harold R. Denton, Director Office of Nuclear Reactor Regulation Attachments/Appendices:
- 1. Attachment 1 - Deleted
- 2. Attachment 2 - Deleted
- 3. Attachment 3 - Deleted
- 4. Appendix A - Technical Specifications (NUREG-1136)
- 5. Appendix B - Environmental Protection Plan
- 6. Appendix C - Antitrust Conditions
- 7. Appendix D - Additional Conditions Date of issuance: June 4, 1985 Amendment No. 108, 141, Revised by letter dated August 2, 2007