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Category:Annual Operating Report
MONTHYEARML22118A5502022-04-28028 April 2022
Annual Environmental Operating Report 2021
ML21118A8202021-04-28028 April 2021
2020 Annual Radiological Environmental Operating Report
ML21088A1292021-03-29029 March 2021
10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes
ML21063A3242021-03-0101 March 2021
Biennial 50.59 Evaluation Report
ML20091K5362020-03-31031 March 2020
10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes
ML19086A1142019-03-19019 March 2019
Biennial 50.59 Evaluation Report
ML19086A1092019-03-18018 March 2019
10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes
ML18121A1352018-04-25025 April 2018
Submittal of 2017 Annual Radioactive Effluent Release Report - Report 41
ML18086A0272018-03-20020 March 2018
10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes
ML17087A2692017-03-21021 March 2017
10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes
ML15091A3822015-03-20020 March 2015
Submission of 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes
ML14126A0102014-04-25025 April 2014
Annual Environmental Operating Report
ML14119A1052014-04-23023 April 2014
Submittal of 2013 Annual Radiological Environmental Operating Report
ML14094A4272014-03-27027 March 2014
10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes
ML13225A0092013-08-0707 August 2013
Correction to 2012 Annual Radioactive Effluent Release Report 36
ML13142A3102013-04-24024 April 2013
Operating Corp. - Annual Radiological Environmental Operating Report
ML13116A3452013-04-17017 April 2013
Annual Environmental Operating Report
ML12128A4012012-04-26026 April 2012
Annual Radiological Environmental Operating Report
ML12124A2702012-04-23023 April 2012
2011 Annual Environmental Operating Report
ML12100A0832012-03-27027 March 2012
Submittal of Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes
ML11243A1462011-08-23023 August 2011
Correction to Annual Radioactive Effluent Release Report - 34
ML11123A1932011-04-27027 April 2011
Submittal of 2010 Annual Radiological Environmental Operating Report
ML1112503222011-04-27027 April 2011
Annual Radioactive Effluent Release Report - Report 34
ML1008301212010-03-16016 March 2010
Submittal of Annual Report of Emergency Core Cooling System (ECCS) Model Changes
ML0907609832009-03-13013 March 2009
CFR 50.46 Annual Report for Emergency Core Cooling System (ECCS) Model Changes for 2008
ET 07-0021, CFR 50.46 Annual Report of ECCS Model Changes2008-03-31031 March 2008
CFR 50.46 Annual Report of ECCS Model Changes
ML0708607562007-03-16016 March 2007
CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Model Changes
ML0608703932006-03-17017 March 2006
Annual Operating Report of ECCS Model Changes
ML0510302952005-04-0707 April 2005
CFR 50.46,Annual Report of ECCS Model Changes
ML0414002812004-05-13013 May 2004
Transmittal of 2003 Annual Financial Reports
ML0411200432004-04-15015 April 2004
Annual Radiological Environmental Operating Report
ML0411200752004-04-14014 April 2004
Annual Environmental Operating Report
ML0325412102003-09-0404 September 2003
Supplement to Wolf Creek Generating Station Annual 50.59 Evaluation Report
ML0312605242003-04-29029 April 2003
Annual Environmental Operating Report
2022-04-28
[Table view]
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] |
Text
Ron Benham Director Nuclear and Regulatory Affairs March 29, 2021 RA 21-0027 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Reference:
Westinghouse Letter LTR-LIS-21-35, dated February 8, 2021, Wolf Creek 10 CFR 50.46 Annual Notification and Reporting for 2020
Subject:
Docket No. 50-482: 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes Commissioners and Staff:
In accordance with 10 CFR 50.46, Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors, paragraph (a)(3)(ii), Wolf Creek Nuclear Operating Corporation (WCNOC) is submitting the attached information to fulfill the annual reporting requirement for the Wolf Creek Generating Station (WCGS).
WCNOC has reviewed the above Reference, which addresses 10 CFR 50.46 reporting information pertaining to the Emergency Core Cooling System (ECCS) Evaluation Model changes that were implemented by Westinghouse for 2020. The Evaluation Model changes and errors (except any plant-specific errors in the application of the model) have been provided to the NRC via Westinghouse letter. The review concludes that there were no plant specific changes to, or errors in, the Evaluation Models on the limiting transient peak cladding temperature (PCT) for 2020.
The Attachment provides PCT rack-up forms for the calculated Large Break Loss-of-Coolant Accident (LOCA) and Small Break LOCA PCT margin allocations in effect for the 2020 WCGS Evaluation Models. The PCT values determined in the Large Break and Small Break LOCA analyses of record, combined with all of the PCT allocations, remain below the 10 CFR 50.46(b)(1) regulatory limit of 2200 °F. Therefore, WCGS is in compliance with 10 CFR 50.46 requirements and no reanalysis or other action is required.
P.O. Box 411 l Burlington, KS 66839 l 620-364-8831
RA 21-0027 Page 2 of 2 This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4204.
Sincerely, Ron Benham RDB/rlt
Attachment:
Emergency Core Cooling System (ECCS) Evaluation Model Peak Cladding Temperature (PCT) Margin Utilization Rack-up Forms cc: S. S. Lee (NRC), w/a S. A. Morris (NRC), w/a N. OKeefe (NRC), w/a Senior Resident Inspector (NRC), w/a
Attachment RI5$27 Page 1 of 3 Emergency Core Cooling System (ECCS) Evaluation Model Peak Cladding Temperature (PCT) Margin Utilization Rack-up Forms LOCA Peak Cladding Temperature (PCT) Summary Plant Name: WOLF CREEK Utility Name: Wolf Creek NOC EM: NOTRUMP AOR
Description:
Appendix K Small Break Summary Sheet Status: Current WOLF CREEK SAP_LOCA-50.46_SAP_Base_Appendix_K_SBLOCA - 1.1 V.V PCT (°F) Reference # Note #
ANALYSIS-OF-RECORD 936 1 Delta PCT Reporting ASSESSMENTS* (°;F) Reference # Note # Year**
- 1. Loose Part Evaluation 45 2 (a) 1990 AOR + ASSESSMENTS PCT = 981.0 °F
- The licensee should determine the reportability of these assessments pursuant to 10 CFR 50.46.
- The Reporting Year refers to the annual reporting year in which this assessment was included.
REFERENCES 1 WCAP-16717-P, Rev. 0, Wolf Creek Generating Station (SAP), MSIV/MFIV Replacement Project, Small Break Loss of Coolant Accident Analysis Engineering Report, January 2007.
2 SAP-90-148/NS-OPLS-OPL-I-90-239, Wolf Creek Nuclear Operating Corporation, RCS Loose Part Evaluation, April 1990.
NOTES:
(a) This penalty will be carried to track the loose part which has not been recovered.
Attachment RI5$27 Page 2 of 3 LOCA Peak Cladding Temperature (PCT) Summary Plant Name: WOLF CREEK Utility Name: Wolf Creek NOC EM: ASTRUM (2004)
AOR
Description:
Best Estimate Large Break Summary Sheet Status: Current WOLF CREEK SAP_LOCA-50.46_SAP_Base_ASTRUM - 1.2 V.V PCT (°F) Reference # Note #
ANALYSIS-OF-RECORD 1900 1 Delta PCT Reporting ASSESSMENTS* (°;F) Reference # Note # Year**
- 2. Containment Fan Cooler Capacity 0 2,4 (a) 2014
- 3. Decay Group Uncertainty Factors
-10 3 2014 Errors AOR + ASSESSMENTS PCT = 1890.0 °F
- The licensee should determine the reportability of these assessments pursuant to 10 CFR 50.46.
- The Reporting Year refers to the annual reporting year in which this assessment was included.
REFERENCES 1 WCAP-17107-P, Revision 1, Best-Estimate Analysis of the Large-Break Loss-of-Coolant Accident for the Wolf Creek Nuclear Power Plant Using the ASTRUM Methodology, January 2014.
2 LTR-LIS-14-400, 10 CFR 50.46 Report for the Wolf Creek Large Break LOCA Evaluation of the Change in Containment Cooling Capacity, August 2014.
3 LTR-LIS-14-492, Wolf Creek Unit 1 10 CFR 50.46 Report for the Correction of the Decay Group Uncertainty Factors Errors, November 2014.
4 LTR-LIS-19-282, Wolf Creek 10 CFR 50.46 PCT Summary Sheet Updates for Replacement Fan Cooler Tube Bundles Installation and Planned Retirement of Cycle 23 Sheets, August 2019.
NOTES:
(a) The estimated effect includes the corrected fan cooler heat removal rates and implementation of replacement tube bundles in the containment fan coolers, which were installed for Cycle 24.
Attachment of RA 21-0027 Page 3 of 3 10 CFR 50.46 Reporting SharePoint Site Check:
EMs applicable to Wolf Creek:
Realistic Large Break - ASTRUM (2004)
Appendix K Small Break - NOTRUMP 2020 Issues Transmittal Letter Issue Description None None
