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Category:Letter
MONTHYEARML24025A0992024-01-25025 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 ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23277A2772023-10-11011 October 2023 Regulatory Audit Summary Concerning Review of Request Number CI3R-01 for Proposed Alternative Inspection Frequency for Containment Unbonded Post Tensioning System Components ML23284A2392023-10-11011 October 2023 NRC Initial Operator Licensing Examination Approval 05000482/2023301 ML23276B4552023-10-0303 October 2023 Technical Specification 5.6.8 Post Accident Monitoring (PAM) Report ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L ML23256A2062023-09-14014 September 2023 Withdrawal of Requested Licensing Action Exemption from Specific 10 CFR Part 73 Requirements ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23243A0002023-08-31031 August 2023 Wolf Generating Station - Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements IR 05000482/20230052023-08-23023 August 2023 Updated Inspection Plan for Wolf Creek Nuclear Operating Corporation, Unit 1 (Report 05000482/2023005) - Mid-Cycle Letter 2023 ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 ML23221A3932023-08-0909 August 2023 Submittal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML23220A4222023-08-0808 August 2023 Supplement to License Amendment Request (LAR) for Deviation from Fire Protection Program 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 IR 05000482/20230022023-07-11011 July 2023 Integrated Inspection Report 05000482/2023002 ML23167A0042023-06-26026 June 2023 Audit Plan to Support Review of Request for Alternative Containment Inservice Inspection Frequency IR 05000482/20234012023-06-21021 June 2023 Security Baseline Inspection Report 05000482/2023401 ML23171B1312023-06-20020 June 2023 Additional Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components WO 23-0014, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) ML23135A1172023-05-0808 May 2023 Redacted Version of Revision 36 to Updated Safety Analysis Report ML23117A2112023-04-27027 April 2023 Annual Exposure Report (2022) ML23117A1342023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report Report 46 2024-01-04
[Table view] Category:Technical Specifications
MONTHYEARML23276B4552023-10-0303 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 ET 06-0012, Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidate Line Item Improvement Process2006-02-21021 February 2006 Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidate Line Item Improvement Process 2023-10-03
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Text
Robert J. Bayer Plant Manager October 3, 2023 000154 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Docket No. 50-482: Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report Commissioners and Staff:
The Attachment provides the Post Accident Monitoring (PAM) Report for the inoperability of one channel of the Reactor Coolant System (RCS) Cold Leg Temperature (Wide Range) Function for greater than 30 days. Wolf Creek Generating Station (WCGS) Technical Specification (TS) 5.6.8, "PAM Report," requires the submittal of the report within 14 days after entry into Condition B of Limiting Condition for Operation (LCO) 3.3.3, "Post Accident Monitoring (PAM)
Instrumentation." Condition B of TS 3.3.3 was entered on September 22, 2023. This condition was entered due to an RCS cold leg wide range temperature channel (Table 3.3.3-1, Function
- 3) being inoperable.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4015, or Dustin Hamman at (620) 364-4204.
Sincerely, Robert J. Bayer RJB/nwl
Attachment:
Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report cc: S. S. Lee (NRC), w/a J. D. Monninger (NRC), w/a G. E. Werner (NRC), w/a Senior Resident Inspector (NRC), w/a WC Licensing Correspondence, wo/a - WO 23-000154 P.O. Box 411 l Burlington, KS 66839 l 620-364-8831
Attachment to 000154 Page 1 of 2 Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report Background Information:
On August 23, 2023, at 1954 Central Standard Time (CST), Technical Specification (TS) 3.3.3, Post Accident Monitoring (PAM) Instrumentation, Condition A was entered when the Reactor Coolant System (RCS) Cold Leg Temperature (Wide Range) Function was determined to be inoperable. TS Table 3.3.3-1, Function 3, RCS Cold Leg Temperature (Wide Range), requires 2 channels to be OPERABLE. Required Action A.1 of TS 3.3.3 requires restoring the required channel to OPERABLE status within 30 days. If the Required Action and associated Completion Time of Condition A are not met, TS 3.3.3 Condition B is entered. On September 22, 2023, the station entered into LCO 3.3.3 Condition B. LCO 3.3.3 Required Action B.1 requires initiation of action in accordance with TS 5.6.8, PAM Report, and requires that a report be submitted within 14 days of entry into Condition B.
The primary purpose of the PAM instrumentation is to display unit variables that provide information required by the control room operators during accident situations. This information provides the necessary support for the operator to take the manual actions for which no automatic control is provided and that are required for safety systems to accomplish their safety functions for Design Basis Accidents (DBAs).
RCS Cold Leg Temperatures (Wide Range) are Type A, Category 1 variables provided for verification of core cooling and long-term surveillance. RCS hot and cold leg temperatures provide input to the core subcooling monitor or may be used to manually determine RCS subcooling margin. RCS subcooling margin will allow termination of safety injection (SI), if still in progress, or reinitiation of SI if it has been stopped. RCS subcooling margin is also used for unit stabilization and cooldown control. In addition, RCS cold leg temperature is used in conjunction with RCS hot leg temperature to verify the unit conditions necessary to establish natural circulation in the RCS.
Each of the four cold legs has one wide range, thermowell-mounted resistance temperature detector (RTD). These are separate from the narrow range RTDs providing input to the Reactor Protection System. The wide range channels provide indication over a range of 0°F to 700°F.
Loops 1 and 2 have hot and cold leg wide range Class 1E temperature indications in the control room.
Preplanned Alternate Methods of Monitoring RCS Parameters:
The loop 2 cold leg wide range temperature indication (BB TI-423B) is functioning at this time and providing valid data. Additional PAM instrumentation that provides for verification of core cooling and long-term surveillance include RCS hot leg temperature (Function 2), RCS Wide Range Pressure (Function 4), reactor vessel indication (Function 5), and core exit temperature (Functions 14, 15, 16, and 17).
Cause of Inoperability:
On August 23, 2023, Control Room operators observed annunciator 056A, RCS SATURATE, and 056B, RCS <50 SUBCOOL, in alarm. ALR 00-056A, RCS Saturate, was performed and found that BB TI-413B, Loop 1 Cold Leg Wide Range Temperature, failed HIGH.
Troubleshooting activities determined the RTD (BB TE-413B) failed. The exact cause of the RTD failure is unknown at this time and will be evaluated upon equipment replacement.
Attachment to 000154 Page 2 of 2 Plans and Schedule for Restoring the Instrumentation Channels of the Function to Operable Status:
Troubleshooting was performed and the RTD was found to be open. As the RCS loop 1 cold leg wide range temperature RTD (BB TE-413B) is installed in a thermowell in the primary piping located behind the secondary shield wall, replacement of the RTD at power cannot be performed due to radiological conditions in this area which prohibit access by plant personnel.
Planning is ongoing to replace the failed RTD in Refueling Outage 26 (Spring 2024).