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MONTHYEARML15134A0022015-05-15015 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 Project stage: Withdrawal 2015-05-15
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Category:Code Relief or Alternative
MONTHYEARML20302A0802020-10-30030 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 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 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 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 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 ML16231A1972016-08-23023 August 2016 Relief Request I4R-02, from Requirements of ASME Code Table IWF-2500-1 VT-3 Examination for Class 1 Supports, for the Fourth 10-Year Inservice Inspection Interval ML15226A3542015-08-21021 August 2015 Relief Request, Alternative to ASME Code Case N-579, Use of Nonstandard Nuts, Class 1, 2, and 3, Mc, CS Components and Supports Construction Section III, Division1, Excess Letdown Heat Exchanger ML15216A2292015-08-10010 August 2015 Request for Relief Nos. 4VR-01 and 4GR-01 Related to ASME OM Code Requirements for Set Pressure Measurement Accuracy for Relief Valves and Frequency Specification, Fourth 10-Year Inservice Testing Program 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 ML15028A1762015-02-0909 February 2015 Correction to Relief Requests I3R-08, Reactor Pressure Vessel (RPV) Interior Attachments and I3R-09, RPV Pressure-Retaining Welds, Exam Interval Extensions, Third 10-year Inservice Inspection Interval (TAC MF3321 & MF3322) 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 ML12353A2412013-01-0404 January 2013 Relief Request I3R-07 from ASME Code Case N-729-1 for Examination of Reactor Vessel Head Penetration Welds, for Remainder of Third 10-Year Inservice Inspection Interval ET 12-0010, 10CFR50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds2012-07-0202 July 2012 10CFR50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds ML0717001842007-07-19019 July 2007 Correction to Authorization of Relief Request 13R-05 - Alternatives to Structural Weld Overlay Requirements ML0706705142007-04-0303 April 2007 Authorization of Relief Request 13R-05, Alternative to Structural Weld Overlay Requirements ML0702605382007-02-21021 February 2007 Relief Request, Third 10-Year Interval Inservice Inspection Program Relief Request I3R-01 ML0634700822006-12-27027 December 2006 Request for Relief I2R-37 and I2R-38 for the Second 10-year Interval Inservice Inspection, MD0291 and MD0292 ML0630705902006-11-20020 November 2006 Relief Request I2R-34 for the Second 10-year Interval Inservice Inspection ML0630706022006-11-20020 November 2006 Relief Request I2R-36 for the Second 10-year Interval Inservice Inspection ML0630705872006-11-20020 November 2006 Relief Request I2R-35 for the Second 10-Year Interval Inservice Inspection ET 06-0029, CFR 50.55a Request, Use of Alternative Ultrasonic Examination Method in Lieu of the Radiography Required by ASME Section III, Subarticle NC-52222006-09-0101 September 2006 CFR 50.55a Request, Use of Alternative Ultrasonic Examination Method in Lieu of the Radiography Required by ASME Section III, Subarticle NC-5222 ML0619304072006-08-0404 August 2006 Relief Request 3PR-04 for the Third 10-Year Inservice Testing Program ET 06-0027, Response to Request for Additional Information Regarding 10 CFR 50.55a Requests I2R-34, I2R-35, and I2R-362006-07-12012 July 2006 Response to Request for Additional Information Regarding 10 CFR 50.55a Requests I2R-34, I2R-35, and I2R-36 ML0613200612006-06-16016 June 2006 Relief, ASME Code Requirements Hardship, TAC MD0299 ML0613901352006-06-0202 June 2006 Relief, Relief Request I3R-03 for the Third 10-Year Interval Inservice Inspection and Examination of Snubbers ML0611403722006-05-10010 May 2006 Third 10-Year Interval Inservice Inspection Program Relief Request I3R-02 ML0606900442006-04-0404 April 2006 Relief, ASME Code Inspection Requirements for Section XI, Class 1, Table IWB-2500-1, Examination Category B-D, Item No. B3.90, Nozzles-to-Vessel Welds for the Second 10-Year Interval ML0605504472006-03-21021 March 2006 Relief Requests for the Third 10-year Pump and Valve Inservice Testing Program ML0534101282005-11-29029 November 2005 10 CFR 50.55a Request I1R-51 Regarding ASME Section XI Requirements for Examination Coverage of the Reactor Pressure Vessel Nozzle-to-Vessel Welds, and Correction to Relief Requests I2R-03 and I2R-21 for Wcnoc'S Second Inservice Inspection ET 05-0027, CFR 50.55a Request Number I2R-33 Regarding ASME Section XI Requirements for Examination Coverage of the Reactor Pressure Vessel Nozzle-to-Vessel Welds2005-11-22022 November 2005 CFR 50.55a Request Number I2R-33 Regarding ASME Section XI Requirements for Examination Coverage of the Reactor Pressure Vessel Nozzle-to-Vessel Welds ML0513803962005-05-17017 May 2005 Gs, Relief, Relief Requests 12R-29 Through 12R-32 Pertaining to Implementation of ASME Code, Section XI Requirements for Examination of Welds ML0311306362003-04-23023 April 2003 Relief Request No. I2R-23, Limited Examination on Feedwater Nozzle to Steam Generator Weld ML0309202432003-04-0202 April 2003 Relief Request No. 12R-26 Related to Limited Examination on Austenitic Stainless Steel Piping Welds with Single Side Access, MB4080 ET 02-0048, Supplemental Information for Inservice Inspection Program Alternative for Limited Examination on Feedwater Nozzle to Steam Generator Shell Weld, Relief Request L2R-232002-11-0404 November 2002 Supplemental Information for Inservice Inspection Program Alternative for Limited Examination on Feedwater Nozzle to Steam Generator Shell Weld, Relief Request L2R-23 ML0225405752002-10-0404 October 2002 Relief Request, Inservice Inspection Interval ML0133904582002-02-0707 February 2002 Relief, Request to Use Code Case N-597 (Tac No MB2453) 2020-10-30
[Table view] Category:Letter
MONTHYEAR05000482/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 ML24296B1902024-10-22022 October 2024 10 CFR 50.55a Requests for the Fifth Ten-Year Interval Inservice Testing Program 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 ML24227A5562024-08-14014 August 2024 Application to Revise Technical Specifications to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) 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 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 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 ML24109A1212024-04-18018 April 2024 (WCGS) Form 5 Exposure Report for Calendar Year 2023 ML24109A1842024-04-18018 April 2024 Cycle 27 Core Operating Limits Report 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 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 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 ML24059A1702024-02-28028 February 2024 Annual Fitness for Duty Program Performance Report, and Annual Fatigue Report for 2023 IR 05000482/20230062024-02-28028 February 2024 Annual Assessment Letter for Wolf Creek Generating Station Report 05000482/2023006 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)) 2024-09-06
[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
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 15, 2015 Mr. Adam C. Heflin President, Chief Executive Officer, and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION- REQUEST FOR RELIEF NOS. 4PR-01, 4PR-02, AND 4VR-02 FOR THE FOURTH 10-YEAR INSERVICE TESTING PROGRAM INTERVAL (TAC NO. MF4992, MF4993, AND MF4994)
Dear Mr. Heflin:
By letter dated October 8, 2014, Wolf Creek Nuclear Operating Corporation (WCNOC, the licensee) proposed alternatives 4GR-01, 4PR-01, 4PR-02, 4VR-01, and 4VR-02 to the inservice testing (IST) interval requirements of the American Society of Mechanical Engineers (ASME)
Code for Operations and Maintenance of Nuclear Power Plants (OM Code), Section IST, for the Wolf Creek Generating Station (WCGS) for the fourth 10-year interval of the IST Program. By letter dated December 16, 2014, WCNOC withdrew proposed alternative 4VR-02. This letter addresses proposed alternatives 4PR-01 and 4PR-02. The remaining proposed alternatives will be addressed by separate correspondence.
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(a)(3)(i), in 4PR-01, the licensee requested an alternative to pump testing following the guidance of ASME OM Code Case OMN-21, Revision 0, "Alternative Requirements for Adjusting Hydraulic Parameters to Specified Reference Points." In 4PR-02, the licensee requested an alternative to the requirements of ASME OM Code ISTB-3510(b)(1) as they pertain to the Centrifugal Charging Pump suction pressure gauge requirements. The licensee requested to use the proposed alternatives on the basis that they provide an acceptable level of quality and safety.
The paragraph headings in 10 CFR 50.55a were changed by Federal Register notice dated November 5, 2014 (79 FR 65776), which became effective on December 5, 2014 (e.g.,
10 CFR 50.55a(a)(3)(i) is now 50.55a(z)(1 ), and 50.55a(a)(3)(ii) is now 50.55a(z)(2)). See the cross-reference tables, which are cited in the notice, in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML14015A191 and ADAMS package Accession No. ML14211A050.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the subject requests and concludes, as set forth in the enclosed safety evaluation, that the proposed alternatives provide an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for requests 4PR-01 and 4PR-02. Therefore, the NRC staff authorizes the alternatives proposed in 4PR-01 and 4PR-02 for WCGS for the fourth 10-year IST program interval, which begins on September 4, 2015, and is scheduled to end on September 3, 2025.
A. Heflin All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject requests remain applicable.
The detailed results of the NRC staff review are provided in the enclosed safety evaluation. If you have any questions concerning this matter, please call Mr. F. Lyon of my staff at (301) 415-2296 or by electronic mail at fred.lyon@nrc.gov.
Sincerely, Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482 Enclosure Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOURTH 10-YEAR INSERVICE TESTING PROGRAM INTERVAL REQUEST FOR RELIEF NOS. 4PR-01 AND 4PR-02 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482
1.0 INTRODUCTION
By letter dated October 8, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14288A316), Wolf Creek Nuclear Operating Corporation (WCNOC, the licensee), submitted alternative requests 4PR-01 and 4PR-02 to the U.S. Nuclear Regulatory Commission (NRC). The licensee proposed alternatives to certain inservice testing (IST) requirements of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code), for the IST program at Wolf Creek Generating Station (WCGS) for the fourth 10-year IST program interval, which begins on September 4, 2015, and is scheduled to end on September 3, 2025.
The paragraph headings in 10 CFR 50.55a were changed by Federal Register notice dated November 5, 2014 (79 FR 65776), which became effective on December 5, 2014 (e.g.,
10 CFR 50.55a(a)(3)(i) is now 50.55a(z)(1), and 50.55a(a)(3)(ii) is now 50.55a(z)(2)). See the cross-reference tables, which are cited in the notice, in ADAMS at Accession No. ML14015A191 and ADAMS package Accession No. ML14211A050.
Specifically, pursuant to Title 1O of the Code of Federal Regulations (1 O CFR) Section 50.55a(a)(3)(i), the licensee requested to use the proposed alternatives in 4PR-01 and 4PR-02 on the basis that the alternatives provide an acceptable level of quality and safety.
2.0 REGULATORY EVALUATION
By Federal Register notice dated November 5, 2014 (79 FR 65776), which became effective on Deceml;>er 5, 2014, the paragraphs headings in 10 CFR 50.55a were revised. Accordingly, relief requests that had been previously covered by 10 CFR 50.55a(a)(3)(i) are now covered under the equivalent 10 CFR 50.55a(z)(1) and relief requests that had been previously covered by 10 CFR 50.55a(a)(3)(ii) are now covered under the equivalent 10 CFR 50.55a(z)(2). The regulations in 10 CFR 50.55a(z), "Alternatives to codes and standards requirements," state that alternatives to the requirements of paragraphs (b) through (h) of this section or portions thereof Enclosure
may be used when authorized by the Director, Office of Nuclear Reactor Regulation, or Director, Office of New Reactors, as appropriate. A proposed alternative must be submitted and authorized prior to implementation. The applicant or licensee must demonstrate that:
(1) Acceptable level of quality and safety. The proposed alternative would provide an acceptable level of quality and safety; or (2) Hardship without a compensating increase in quality and safety. Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in quality and safety.
The WCGS fourth 10-year IST interval begins on September 4, 2015, and is scheduled to end on September 3, 2025. The fourth interval IST program Code of record is the ASME OM Code, 2004 Edition with Addenda through OMb-2006 Addenda.
Based on the above, and subject to the NRC's findings with respect to authorizing the proposed alternatives to the ASME OM Code given below, the NRC staff finds that regulatory authority exists for the licensee to request and the Commission to authorize the alternatives requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 Licensee's Alternative Request 4PR-01 Applicable Code Requirements ISTB-5121, "Group A Test Procedure," (b) states, in part, that "The resistance of the system shall be varied until the flow rate equals the reference point."
ISTB-5122, "Group B Test Procedure," (c) states, in part, that "System resistance may be varied as necessary to achieve the reference point."
ISTB-5123, "Comprehensive Test Procedure," (b) states, in part, that "For centrifugal and vertical line shaft pumps, the resistance of the system shall be varied until the flow rate equals the reference point."
ISTB-5221, "Group A Test Procedure," (b) states, in part, that "The resistance of the system shall be varied until the flow rate equals the reference point."
ISTB-5222, "Group B Test Procedure," (c) states, that "System resistance may be varied as necessary to achieve the reference point."
ISTB-5223, "Comprehensive Test Procedure," (b) states, in part, that "The resistance of the system shall be varied until the flow rate equals the reference point."
The licensee has requested an alternative to the pump testing reference value requirements of ISTB-5121, ISTB-5122, ISTB-5123, ISTB-5221, ISTB-5222, and ISTB-5223. The components affected by this alternative request are the pumps listed in the table below. By NRC letter dated
July 15, 2014 (ADAMS No. ML14178A769), a similar alternative request was authorized for Callaway Plant, Unit 1.
Table for Pumps Affected by Alternative Request 4PR-01 ASME ASME Code OM Code Pump Number Description Pump Type Class Category PBG02A/B Boric Acid Pumps Centrifugal 3 Group A PEG01A/B/C/D Component Cooling Water Pumps Centrifugal 3 Group A PEJ01A/B Residual Heat Removal Pumps Centrifugal 2 Group A PEC01A/B Fuel Pool Cooling Pumps Centrifugal 3 Group A PAL01A/B Motor Driven Auxiliary Feedwater Centrifugal 3 Group A Pumps PAL02 Turbine Driven Auxiliary Feedwater Centrifugal 3 Group B Pump PBG05A/B Centrifugal Charging Pumps Centrifugal 2 Group B PEF01A/B Essential Service Water Pumps Vertical Line Shaft 3 Group A PEM01A/B Safety Injection Pumps Centrifugal 2 Group B PEN01A/B Containment Spray Pumps Centrifugal 2 Group B Licensee's Reason for Request The licensee stated that for pump testing, there is difficulty adjusting system throttle valves with sufficient precision to achieve exact flow reference values during subsequent IST exams, and that Section ISTB of the ASME OM Code does not allow for variance from a fixed reference value for pump testing. The licensee also noted that Section 5.3 of NUREG-1482, Revision 2, "Guidelines for lnservice Testing at Nuclear Power Plants: lnservice Testing of Pumps and Valves and lnservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants," October 2013 (ADAMS Accession No. ML13295A020), acknowledges that certain pump system designs do not allow for the licensee to set the flow at an exact value because of limitations in the instruments and controls for maintaining steady flow.
The licensee further stated that ASME OM Code Case OMN-21, "Alternative Requirements for Adjusting Hydraulic Parameters to Specified Reference Points," provides guidance for adjusting reference flow/.O.P to within a specified tolerance during inservice testing. The Code Case states that:
It is the opinion of the Committee that when it is impractical to operate a pump at a specified reference point and adjust the resistance of the system to a specified reference point for either flow rate, differential pressure or discharge pressure, the pump may be operated as close as practical to the specified reference point with the following requirements. The Owner shall adjust the system resistance to as close as practical to the specified reference point where the variance from the reference point does not exceed + 2% or - 1% of the reference point when the
reference point is flow rate, or + 1% or - 2% of the reference point when the reference point is differential pressure or discharge pressure.
Currently, differential pressure and discharge pressure are not used as a fixed parameter during IST of pumps at WCGS.
Licensee's Proposed Alternative The licensee proposes to perform future inservice pump testing in a manner consistent with the requirements as stated in ASME OM Code Case OMN-21. Specifically, testing of pumps will be performed such that flow rate is adjusted as close as practical to the reference value and within limits of +2 percent/-1 percent of the reference value.
WCGS plant operators will still strive to achieve the exact test flow reference values during testing. Typical test guidance will be to adjust flow to the specific reference value with additional guidance that if the reference value cannot be achieved with reasonable effort, the test will be considered valid if the steady state flow rate is within the limits of +2 percent/-1 percent of the reference value.
Code Case OMN-21 was approved by the ASME Operations and Maintenance Standards Committee on April 20, 2012, with an NRC representative voting in the affirmative. The applicability of Code Case OMN- 21 is the ASME OM Code 1995 Edition through 2011 Addenda. The language from Code Case OMN-21 has been included in the ASME OM Code 2012 Edition.
Using the provisions of this request as an alternative to the specific requirements of ISTB-5121, ISTB-5122, ISTB-5123, ISTB-5221, ISTB-5222, and ISTB-5223 as described above will provide adequate indication of pump performance and continue to provide an acceptable level of quality and safety.
NRC Staff Evaluation
An inquiry was submitted to the ASME OM Code Committee to determine what alternatives may be used when it is impractical to operate a pump at a specified reference point for flow rate, differential pressure, or discharge pressure. In response to the inquiry, ASME Code Case OMN-21 was developed to provide guidance on alternatives. The guidance in Code Case OMN-21 states that when it is impractical to operate a pump at a specified reference point for flow rate, differential pressure or discharge pressure, the pump may be operated as close as practical to the specified reference point with the following requirements. Code Case OMN-21 specifies that the variance from the reference point shall not exceed +2 percent or -1 percent of the reference point when the reference point is flow rate, or +1 percent or -2 percent of the reference point when the reference point is differential pressure or discharge pressure.
Code Case OMN-21 was approved by the ASME Operation and Maintenance Standards Committee on April 20, 2012, with the NRC representative voting in the affirmative. The licensee proposes to adopt Code Case OMN-21. The applicability of Code Case OM-21 is the ASME OM Code 1995 Edition through the 2011 Addenda. The language from Code Case OMN-21 has been included in the ASME OM Code, 2012 Edition.
The NRC staff notes that in certain situations, it is not possible to operate a pump at a precise reference point. The NRC staff has reviewed the alternatives proposed in ASME OM Code Case OMN-21 and found that the proposed alternatives are reasonable and appropriate when a pump cannot be operated at a specified reference point. Operation within the tolerance bands specified in ASME OM Code Case OMN-21 provides reasonable assurance that licensees will be able to utilize the data collected to detect degradation of the pumps. Based on the NRC staff's review of ASME OM Code Case OMN-21 and the licensee's commitment to use the bands specified in ASME OM Code Case OMN-21 for flow rate, the NRC staff concludes that implementation of the alternatives contained in ASME OM Code Case OMN-21 is acceptable for the pumps listed in the table above. Therefore, the NRC staff concludes that the licensee's proposed alternative provides an acceptable level of quality and safety.
3.2 Licensee's Alternative Relief Request 4PR-02 Applicable Code Requirements ISTB-3510, "Data Collection General," (b}, "Range," (1) states that "The full-scale range of each analog instrument shall be not greater than three times the reference value."
The licensee requested to use alternative instrument range requirements for centrifugal charging pumps PBG05A and PBG05B. The pumps are classified as ASME Class 2 and ASME OM Code Group B. By NRC letter dated July 15, 2014 (ADAMS Accession No. ML14178A769),
a similar alternative request was authorized for Callaway Plant, Unit 1.
Licensee's Reason for Request The licensee stated that the installed suction pressure gauges for the centrifugal charging pumps is 0-150 pounds per square inch gauge (psig). The reference values for suction pressure during IST are between 30 psig and 40 psig. As a result, the instrument range exceeds the requirement of ISTB-351 O(b)(1 ).
The licensee further stated that pump suction pressure indication is used along with pump discharge pressure indication to determine pump differential pressure. Reference values for the centrifugal charging pumps during IST are between 30 psig and 40 psig. Based on ISTB-351 O(b)(1 ), this would require as a maximum, a gauge with a range of 0 to 90 psig (3 X 30 psig) to bound the lowest reference value for pressure. Applying the accuracy requirement of+/- 2 percent for the quarterly Group B pump test, the resulting inaccuracies due to suction pressure effects would be +/- 1.8 psig (0.02 X 90 psig).
Licensee's Proposed Alternative For the Group B quarterly test, the licensee will use the installed suction pressure gauge 0 to 150 psig calibrated to less than or equal to +/- 1.2 percent such that the inaccuracies due to pressure will be less than that required by the Code (+/- 1.8 psig). The error associated with the suction gauge would then be no worse than +/- 1.8 pounds per square inch (psi) (150 X 0.012).
Use of the installed pressure gauge calibrated to less than+/- 1.2 percent is equivalent in terms of measuring differential pressure using a pressure gauge of 90 psig calibrated to +/- 2 percent.
NRC Staff Evaluation
The licensee requests an alternative to the ASME OM Code instrumentation requirements of paragraph ISTB-351 O(b)(1) for the pressure gauges that are used to measure the suction pressure of centrifugal charging pumps PBG05A and PBG05B. ASME OM Code paragraph ISTB-351 O(b)(1) requires that the full-scale range of each instrument be no greater than three times the reference value. The licensee proposes to use the installed suction pressure gauges that do not meet this requirement.
The installed suction pressure gauges for the centrifugal charging pumps have a range of 0-150 psig. The typical suction pressure reference values for the centrifugal charging pumps during testing are 30-40 psig. Use of the low-end reference value of 30 psig to calculate a reading error is conservative and appropriate for these pumps. Based on the Code-required full range of 90 psig (30 X 3) and the accuracy requirement of+/- 2 percent for the quarterly Group B pump test, the resulting inaccuracies due to suction pressure effects would be+/- 1.8 psig (0.02 X 90 psig). Therefore, the effective gauge accuracy of the installed pressure gauge when calibrated to less than or equal to+/- 1.2 percent is also +/- 1.8 psi (0.012 X 150 psig), which is equivalent to the resulting measurement accuracy for Group B tests if ASME OM Code requirements were met.
The use of the existing gauges is also supported by NUREG-1482, Revision 2, Paragraph 5.5.1, when the combination of range and accuracy yields a reading at least equivalent to the reading achieved from instruments that meet the ASME OM Code requirements. The centrifugal charging pumps' suction pressure gauges yield readings at least equivalent to the readings achieved from instruments that meet ASME OM Code requirements for Group B tests as required in ISTB-3510(b)(1 ). Therefore, the NRC staff concludes that the licensee's proposed alternative provides an acceptable level of quality and safety on the basis that the installed instrumentation provides a measurement accuracy that equals the resulting measurement accuracy for Group B tests if ASME OM Code requirements were met.
4.0 CONCLUSION
Based on the above, the NRC staff determines that the proposed alternatives 4PR-01 and 4PR-02 provide an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for proposed alternatives 4PR-01 and 4PR-02 for WCGS. Therefore, the NRC staff authorizes the proposed alternatives for WCGS for the fourth 10-year IST program interval, which begins on September 4, 2015, and is scheduled to end on September 3, 2025.
All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject requests remain applicable.
Principal Contributor: J. Huang, NRR/DE/EPNB Date: May 15, 2015
ML15134A002 *email dated OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1/LA NRR/DE/EPNB/BC N RR/DORL/LPL4-1 /BC NAME FLyon JBurkhardt DAiiey* MMarkley DATE 5/15/15 5/14/15 5/12/15 5/15/15