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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
==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 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)."}}

Revision as of 11:12, 16 June 2018

Wolf Creek, Supplemental Information Regarding License Amendment Request for Revision to Technical Specification 5.6.5 for Large Break Loss-of-Coolant Accident (LOCA) Analysis Methodology
ML14349A405
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 12/08/2014
From: McCoy J H
Wolf Creek
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ET 14-0038
Download: ML14349A405 (4)


Text

W9O..LF CREEKNUCLEAR OPERATING CORPORATIONJaime H. McCoy December 8, 2014Vice President EngineeringET 14-0038U. S. Nuclear Regulatory CommissionATTN: 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 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)."