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| {{#Wiki_filter:W9O..LF CREEKNUCLEAR OPERATING CORPORATION Jaime H. McCoy December 8, 2014Vice President Engineering ET 14-0038U. S. Nuclear Regulatory Commission ATTN: Document Control DeskWashington, DC 20555 | | {{#Wiki_filter:W9O..LF CREEK NUCLEAR OPERATING CORPORATION Jaime H. McCoy December 8, 2014 Vice President Engineering ET 14-0038 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 |
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| ==Reference:== | | ==Reference:== |
| : 1) Letter ET 14-0008, dated February 26, 2014, from J. P. Broschak, WCNOC, to USNRC | | : 1) Letter ET 14-0008, dated February 26, 2014, from J. P. Broschak, WCNOC, to USNRC |
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| ==Subject:== | | ==Subject:== |
| | | Docket No. 50-482: Supplemental Information Regarding License Amendment Request for Revision to Technical Specification 5.6.5 for Large Break Loss-of-Coolant Accident (LOCA) Analysis Methodology Gentlemen: |
| Docket No. 50-482: Supplemental Information Regarding LicenseAmendment Request for Revision to Technical Specification 5.6.5 forLarge Break Loss-of-Coolant Accident (LOCA) Analysis Methodology Gentlemen: | | Reference 1 provided the Wolf Creek Nuclear Operating Corporation (WCNOC) application to revise the Wolf Creek Generating Station (WCGS) Technical Specifications (TS). Specification 5.6.5, "CORE OPERATING LIMITS REPORT (COLR)," is revised to incorporate WCAP-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," to the list of analytical methods used to determine the core operating limits. The Reference 1 application was a plant specific best-estimate large break LOCA analysis that accounted for the effects of fuel thermal conductivity degradation (TCD).During a teleconference on November 10, 2014, the Nuclear Regulatory Commission (NRC)staff indicated that there is not a NRC approved Large Break LOCA methodology that accounts for TCD. The NRC indicated that for the WCNOC application, the NRC would either approve a plant specific methodology or would accept a license condition to perform a re-analysis in accordance with 10 CFR 50.46(a)(3)(ii) when an approved methodology is available. |
| Reference 1 provided the Wolf Creek Nuclear Operating Corporation (WCNOC) application torevise the Wolf Creek Generating Station (WCGS) Technical Specifications (TS). Specification 5.6.5, "CORE OPERATING LIMITS REPORT (COLR)," | | By electronic mail on November 19, 2014, WCNOC agreed to provide a regulatory commitment for performing a large break LOCA re-analysis with a NRC approved evaluation methodology that includes the effects of TCD. As such, the following regulatory commitment is provided: WCNOC will submit a schedule for performing a large break LOCA re-analysis that applies a NRC approved methodology, which includes the effects of fuel thermal conductivity degradation, within 6 months of NRC approval of WCAP-16996-P, "Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Size (FULL SPECTRUM LOCA Methodology)," and WCAP-17642-P, "Westinghouse Performance Analysis and Design Model (PAD5)." P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNVET ET 14-0038 Page 2 of 3 WCAP-16996-P, Revision 0, was submitted to the NRC on November 23, 2010 by Westinghouse letter LTR-NRC-10-73. |
| is revised to incorporate WCAP-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," | | WCAP-17642-P, Revision 0, was submitted to the NRC on October 29, 2013 by Westinghouse letter LTR-NRC- 13-72.The additional information does not expand the scope of the application and does not impact the no significant hazards consideration determination presented in Reference 1.In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," a copy of this submittal is being provided to the designated Kansas State official.The Attachment provides the regulatory commitment. |
| to the list of analytical methods used todetermine the core operating limits. The Reference 1 application was a plant specific best-estimate large break LOCA analysis that accounted for the effects of fuel thermal conductivity degradation (TCD).During a teleconference on November 10, 2014, the Nuclear Regulatory Commission (NRC)staff indicated that there is not a NRC approved Large Break LOCA methodology that accountsfor TCD. The NRC indicated that for the WCNOC application, the NRC would either approve aplant specific methodology or would accept a license condition to perform a re-analysis inaccordance with 10 CFR 50.46(a)(3)(ii) when an approved methodology is available. | | If you have any questions concerning this matter, please contact me at (620) 364-4156, or Mr. Steven R. Koenig at (620) 364-4041.Sincerely, V77 Jaime H. McCoy JHM/rlt Attachment cc: T. A. Conley (KDHE), w/a M. L. Dapas (NRC), w/a C. F. Lyon (NRC), w/a N. F. O'Keefe (NRC), w/a Senior Resident Inspector (NRC), w/a ET 14-0038 Page 3 of 3 STATE OF KANSAS COUNTY OF COFFEY SS Jaime H. McCoy, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.Bv Z/)X414 Jaime A. McCoy Vice P resident Engineering I SUBSCRIBED and sworn to before me this day of aDCetr b.,2014.AYESHEPER jL~ r~y FbI~ -Stateof a Notat _ _ubli_Expiration /,1 Attachment to ET 14-0038 Page 1 of 1 LIST OF REGULATORY COMMITMENTS The following table identifies a regulatory commitment made by Wolf Creek Nuclear Operating Corporation in this document. |
| Byelectronic mail on November 19, 2014, WCNOC agreed to provide a regulatory commitment forperforming a large break LOCA re-analysis with a NRC approved evaluation methodology thatincludes the effects of TCD. As such, the following regulatory commitment is provided:
| |
| WCNOC will submit a schedule for performing a large break LOCA re-analysis thatapplies a NRC approved methodology, which includes the effects of fuel thermalconductivity degradation, within 6 months of NRC approval of WCAP-16996-P, "Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Size (FULLSPECTRUM LOCA Methodology)," | |
| and WCAP-17642-P, "Westinghouse Performance Analysis and Design Model (PAD5)."P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831An Equal Opportunity Employer M/F/HCNVET ET 14-0038Page 2 of 3WCAP-16996-P, Revision 0, was submitted to the NRC on November 23, 2010 byWestinghouse letter LTR-NRC-10-73. | |
| WCAP-17642-P, Revision 0, was submitted to the NRCon October 29, 2013 by Westinghouse letter LTR-NRC-13-72.The additional information does not expand the scope of the application and does not impactthe no significant hazards consideration determination presented in Reference 1.In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," | |
| a copy ofthis submittal is being provided to the designated Kansas State official. | |
| The Attachment provides the regulatory commitment. | |
| If you have any questions concerning thismatter, please contact me at (620) 364-4156, or Mr. Steven R. Koenig at (620) 364-4041. | |
| Sincerely, V77Jaime H. McCoyJHM/rltAttachment cc: T. A. Conley (KDHE), w/aM. L. Dapas (NRC), w/aC. F. Lyon (NRC), w/aN. F. O'Keefe (NRC), w/aSenior Resident Inspector (NRC), w/a ET 14-0038Page 3 of 3STATE OF KANSASCOUNTY OF COFFEYSSJaime H. McCoy, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf ofsaid Corporation with full power and authority to do so; and that the facts therein stated are trueand correct to the best of his knowledge, information and belief.Bv Z/)X414Jaime A. McCoyVice P resident Engineering ISUBSCRIBED and sworn to before me this day of aDCetr b.,2014.AYESHEPER jL~ r~y FbI~ -Stateof aNotat _ _ubli_Expiration /,1 Attachment to ET 14-0038Page 1 of 1LIST OF REGULATORY COMMITMENTS The following table identifies a regulatory commitment made by Wolf Creek Nuclear Operating Corporation in this document. | |
| Any other statements in this letter are provided for information purposes and are not considered regulatory commitments. | | Any other statements in this letter are provided for information purposes and are not considered regulatory commitments. |
| Please direct questions regarding this commitment to Mr. Steven R. Koenig, Manager Regulatory Affairs at Wolf Creek Generating | | Please direct questions regarding this commitment to Mr. Steven R. Koenig, Manager Regulatory Affairs at Wolf Creek Generating Station, (620) 364-4041.REGULATORY COMMITMENT DUE DATE WCNOC will submit a schedule for performing a large break Within 6 months of LOCA re-analysis that applies a NRC approved methodology, NRC approval of which includes the effects of fuel thermal conductivity WCAP-16996-P and degradation, within 6 months of NRC approval of WCAP- WCAP-17642-P 16996-P, "Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Size (FULL SPECTRUM LOCA Methodology)," and WCAP-17642-P, "Westinghouse Performance Analysis and Design Model (PAD5)."}} |
| : Station, (620) 364-4041.
| |
| REGULATORY COMMITMENT DUE DATEWCNOC will submit a schedule for performing a large break Within 6 months ofLOCA re-analysis that applies a NRC approved methodology, NRC approval ofwhich includes the effects of fuel thermal conductivity WCAP-16996-P anddegradation, within 6 months of NRC approval of WCAP- WCAP-17642-P 16996-P, "Realistic LOCA Evaluation Methodology Applied tothe Full Spectrum of Break Size (FULL SPECTRUM LOCAMethodology)," | |
| and WCAP-17642-P, "Westinghouse Performance Analysis and Design Model (PAD5)."}} | |
Letter Sequence Supplement |
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|
MONTHYEARML14064A3292014-02-26026 February 2014
NP-Attachment to LTR-LIS-13-557, Rev 0, Application of Westinghouse Best-Estimate Large Break LOCA Methodology to the Wolf Creek Generating Station
Project stage: Request
ET 14-0008, Application for Amendment to Revise Specification 5.6.5, Core Operating Limits Report (Colr), for Large Break Loss-of-Coolant Accident Analysis Methodology2014-02-26026 February 2014
Application for Amendment to Revise Specification 5.6.5, Core Operating Limits Report (Colr), for Large Break Loss-of-Coolant Accident Analysis Methodology
Project stage: Request
ML14120A0202014-04-30030 April 2014
NRR E-mail Capture - Acceptance Review
Project stage: Acceptance Review
ML14182A3762014-07-14014 July 2014
Request for Withholding from Public Disclosure - 1/21/14 Affidavit Executed by J. Gresham, Westinghouse LTR-LIS-13-557P-Attachment, Revision 0 Provided as Enclosure 1 to 2/26/14 License Amendment Request
Project stage: Other
ML14324A0132014-11-19019 November 2014
NRR E-mail Capture - Question on LAR to Add Astrum to COLR
Project stage: Other
ML14324A8582014-11-20020 November 2014
NRR E-mail Capture - Question on LAR to Add Astrum to COLR (Wolf Creek TAC No. MF3518)
Project stage: Other
ET 14-0038, Supplemental Information Regarding License Amendment Request for Revision to Technical Specification 5.6.5 for Large Break Loss-of-Coolant Accident (LOCA) Analysis Methodology2014-12-0808 December 2014
Supplemental Information Regarding License Amendment Request for Revision to Technical Specification 5.6.5 for Large Break Loss-of-Coolant Accident (LOCA) Analysis Methodology
Project stage: Supplement
ET 15-0002, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology2015-01-21021 January 2015
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology
Project stage: Response to RAI
ML15076A3132015-03-18018 March 2015
Request for Withholding Information from Public Disclosure - 1/15/2015 Affidavit Executed by J. Gresham, Westinghouse, Two Attachments to LTR-LIST-15-11, Revision 1
Project stage: Withholding Request Acceptance
ML15091A3822015-03-20020 March 2015
Submission of 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes
Project stage: Request
WO 15-0044, Proposed License Condition Regarding License Amendment Request for Revision to Technical Specification 5.6.5 for Large Break Loss-of-Coolant Accident (LOCA) Analysis Methodology2015-07-15015 July 2015
Proposed License Condition Regarding License Amendment Request for Revision to Technical Specification 5.6.5 for Large Break Loss-of-Coolant Accident (LOCA) Analysis Methodology
Project stage: Request
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)
Project stage: Approval
2014-07-14
[Table View] |
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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] |
Text
W9O..LF CREEK NUCLEAR OPERATING CORPORATION Jaime H. McCoy December 8, 2014 Vice President Engineering ET 14-0038 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Reference:
- 1) Letter ET 14-0008, dated February 26, 2014, from J. P. Broschak, WCNOC, to USNRC
Subject:
Docket No. 50-482: Supplemental Information Regarding License Amendment Request for Revision to Technical Specification 5.6.5 for Large Break Loss-of-Coolant Accident (LOCA) Analysis Methodology Gentlemen:
Reference 1 provided the Wolf Creek Nuclear Operating Corporation (WCNOC) application to revise the Wolf Creek Generating Station (WCGS) Technical Specifications (TS). Specification 5.6.5, "CORE OPERATING LIMITS REPORT (COLR)," is revised to incorporate WCAP-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," to the list of analytical methods used to determine the core operating limits. The Reference 1 application was a plant specific best-estimate large break LOCA analysis that accounted for the effects of fuel thermal conductivity degradation (TCD).During a teleconference on November 10, 2014, the Nuclear Regulatory Commission (NRC)staff indicated that there is not a NRC approved Large Break LOCA methodology that accounts for TCD. The NRC indicated that for the WCNOC application, the NRC would either approve a plant specific methodology or would accept a license condition to perform a re-analysis in accordance with 10 CFR 50.46(a)(3)(ii) when an approved methodology is available.
By electronic mail on November 19, 2014, WCNOC agreed to provide a regulatory commitment for performing a large break LOCA re-analysis with a NRC approved evaluation methodology that includes the effects of TCD. As such, the following regulatory commitment is provided: WCNOC will submit a schedule for performing a large break LOCA re-analysis that applies a NRC approved methodology, which includes the effects of fuel thermal conductivity degradation, within 6 months of NRC approval of WCAP-16996-P, "Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Size (FULL SPECTRUM LOCA Methodology)," and WCAP-17642-P, "Westinghouse Performance Analysis and Design Model (PAD5)." P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNVET ET 14-0038 Page 2 of 3 WCAP-16996-P, Revision 0, was submitted to the NRC on November 23, 2010 by Westinghouse letter LTR-NRC-10-73.
WCAP-17642-P, Revision 0, was submitted to the NRC on October 29, 2013 by Westinghouse letter LTR-NRC- 13-72.The additional information does not expand the scope of the application and does not impact the no significant hazards consideration determination presented in Reference 1.In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," a copy of this submittal is being provided to the designated Kansas State official.The Attachment provides the regulatory commitment.
If you have any questions concerning this matter, please contact me at (620) 364-4156, or Mr. Steven R. Koenig at (620) 364-4041.Sincerely, V77 Jaime H. McCoy JHM/rlt Attachment cc: T. A. Conley (KDHE), w/a M. L. Dapas (NRC), w/a C. F. Lyon (NRC), w/a N. F. O'Keefe (NRC), w/a Senior Resident Inspector (NRC), w/a ET 14-0038 Page 3 of 3 STATE OF KANSAS COUNTY OF COFFEY SS Jaime H. McCoy, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.Bv Z/)X414 Jaime A. McCoy Vice P resident Engineering I SUBSCRIBED and sworn to before me this day of aDCetr b.,2014.AYESHEPER jL~ r~y FbI~ -Stateof a Notat _ _ubli_Expiration /,1 Attachment to ET 14-0038 Page 1 of 1 LIST OF REGULATORY COMMITMENTS The following table identifies a regulatory commitment made by Wolf Creek Nuclear Operating Corporation in this document.
Any other statements in this letter are provided for information purposes and are not considered regulatory commitments.
Please direct questions regarding this commitment to Mr. Steven R. Koenig, Manager Regulatory Affairs at Wolf Creek Generating Station, (620) 364-4041.REGULATORY COMMITMENT DUE DATE WCNOC will submit a schedule for performing a large break Within 6 months of LOCA re-analysis that applies a NRC approved methodology, NRC approval of which includes the effects of fuel thermal conductivity WCAP-16996-P and degradation, within 6 months of NRC approval of WCAP- WCAP-17642-P 16996-P, "Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Size (FULL SPECTRUM LOCA Methodology)," and WCAP-17642-P, "Westinghouse Performance Analysis and Design Model (PAD5)."
