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| {{#Wiki_filter:W9O..LF CREEKNUCLEAR OPERATING CORPORATIONJaime H. McCoy December 8, 2014Vice President EngineeringET 14-0038U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555 | | {{#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 |
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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 LicenseAmendment Request for Revision to Technical Specification 5.6.5 forLarge Break Loss-of-Coolant Accident (LOCA) Analysis MethodologyGentlemen:Reference 1 provided the Wolf Creek Nuclear Operating Corporation (WCNOC) application torevise the Wolf Creek Generating Station (WCGS) Technical Specifications (TS). Specification5.6.5, "CORE OPERATING LIMITS REPORT (COLR)," is revised to incorporate WCAP-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated StatisticalTreatment of Uncertainty Method (ASTRUM)," 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 conductivitydegradation (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. 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, "RealisticLOCA Evaluation Methodology Applied to the Full Spectrum of Break Size (FULLSPECTRUM LOCA Methodology)," and WCAP-17642-P, "Westinghouse PerformanceAnalysis 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/rltAttachmentcc: 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 PresidentEngineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoingdocument 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 EngineeringISUBSCRIBED and sworn to before me this day of aDCetr b.,2014.AYESHEPERjL~ r~y FbI~ -Stateof aNotat _ _ubli_Expiration /,1 Attachment to ET 14-0038Page 1 of 1LIST OF REGULATORY COMMITMENTSThe following table identifies a regulatory commitment made by Wolf Creek Nuclear OperatingCorporation in this document. Any other statements in this letter are provided for informationpurposes and are not considered regulatory commitments. Please direct questions regardingthis commitment to Mr. Steven R. Koenig, Manager Regulatory Affairs at Wolf Creek GeneratingStation, (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-P16996-P, "Realistic LOCA Evaluation Methodology Applied tothe Full Spectrum of Break Size (FULL SPECTRUM LOCAMethodology)," and WCAP-17642-P, "WestinghousePerformance Analysis and Design Model (PAD5)."}} | | |
| | 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 torevise 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 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. |
| | 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. |
| | 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 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
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Category:Letter
MONTHYEARML24248A2492024-09-0404 September 2024 Inservice Inspection Program Fourth Interval, Third Period, Refueling Outage 26 Owner’S Activity Report ML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second 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 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 IR 05000482/20244012024-07-0202 July 2024 Security Baseline Inspection Report 05000482/2024401 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24162A1632024-06-11011 June 2024 Operating Corporation – Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000482/2024010) ML24150A0562024-05-29029 May 2024 Foreign Ownership, Control or Influence (FOCI) Information – Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24089A2622024-04-29029 April 2024 Financial Protection Levels ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24118A0022024-04-27027 April 2024 Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report 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 ML24106A1482024-04-15015 April 2024 Notification of Inspection (NRC Inspection Report 05000482/2024003) and Request for Information ML24114A1442024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37 ML24098A0052024-04-0707 April 2024 2023 Annual Environmental Operating Report ML24089A1352024-03-29029 March 2024 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes ML24089A0972024-03-29029 March 2024 Response to NRC Regulatory Issue Summary 2024-01, “Preparation and Scheduling of Operator Licensing Examinations” ML24074A3312024-03-14014 March 2024 Missed Quarterly Inspection Per 40 CFR 266 Subpart N IR 05000482/20240122024-03-11011 March 2024 Fire Protection Team Inspection Report 05000482/2024012 ML24080A3452024-03-11011 March 2024 7 of the Wolf Creek Generating Station Updated Safety Analysis Report ML24068A1992024-03-0707 March 2024 Changes to Technical Specification Bases - Revisions 93 and 94 ML24066A0672024-03-0505 March 2024 4-2022-024 Letter - OI Closure to Licensee ML24061A2642024-03-0101 March 2024 Revision of Two Procedures That Implement the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) Commissioners IR 05000482/20230062024-02-28028 February 2024 Annual Assessment Letter for Wolf Creek Generating Station Report 05000482/2023006 ML24059A1702024-02-28028 February 2024 Annual Fitness for Duty Program Performance Report, and Annual Fatigue Report for 2023 ML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML24050A0012024-02-19019 February 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24036A0092024-02-14014 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0075 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24036A1852024-02-0505 February 2024 Correction to 2022 Annual Radioactive Effluent Release Report - Report 46 ML24032A1742024-02-0202 February 2024 Withdrawal of Requested Licensing Action Exemption from Specific Provisions in 10 CFR 73.55 ML24025A0992024-01-25025 January 2024 Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML24018A0792024-01-22022 January 2024 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd and Opportunity for a Hearing (EPID L-2024-LLA-0007) (Letter) ML24018A2482024-01-18018 January 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 238 ML24018A1382024-01-18018 January 2024 Inservice Inspection Request for Information 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 2024-09-04
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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
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 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 torevise 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 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.
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.
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 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)."