View source for 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 Methodology

{{Adams
| number = ML14349A405
| issue date = 12/08/2014
| title = Supplemental Information Regarding License Amendment Request for Revision to Technical Specification 5.6.5 for Large Break Loss-of-Coolant Accident (LOCA) Analysis Methodology
| author name = Mccoy J
| author affiliation = Wolf Creek Nuclear Operating Corp
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000482
| license number = 
| contact person = 
| case reference number = ET 14-0038
| document type = Letter type:ET
| page count = 4
| project = 
| stage = Supplement
}}

=Text=
{{#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

==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 M/F/HCNVET An Equal Opportunity Employer

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 SS COUNTY OF COFFEY 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                    Notat                  _      _ubli_
jL~r~y   FbI~ -Stateof a Expiration Date_*/        /,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)."}}