L-10-139, CFR 50.46 Report of Changes or Errors in ECCS Evaluation Models

CFR 50.46 Report of Changes or Errors in ECCS Evaluation Models

ML101530497
Person / Time
Site:	Davis Besse
Issue date:	05/27/2010
From:	Allen B FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-10-139
Download: ML101530497 (3)

Text

FENOC FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor, Ohio 43449 Barry S. Allen Vice President

-Nuclear 419-321-7676 Fax: 419-321-7582 May 27, 2010 L-1 0-139 10 CFR 50.46(a)(3)(ii)

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License No. NPF-3 10 CFR 50.46 Report of Changes or Errors in ECCS Evaluation Models In accordance with 10 CFR 50.46(a)(3)(ii), FirstEnergy Nuclear Operating Company (FENOC) hereby submits the annual report for changes and errors in the Emergency Core Cooling System (ECCS) evaluation model (EM) and in the application of the model used at the Davis-Besse Nuclear Power Station, Unit No. 1. The attached concludes that there were no changes or errors in the EM or in the application of the model. The report covers the period of January 1, 2009 to December 31, 2009.There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -Fleet Licensing, at (330) 761-6071.Sincerely, Barry Allen

Attachment:

Annual Report of Changes to the 10 CFR 50.46 Emergency Core Cooling System Evaluation Model and in the Application of the Model for the Davis-Besse Nuclear Power Station, Unit No. 1 cc: NRC Region III Administrator NRR Project Manager -Davis-Besse Nuclear Power Station NRC Resident Inspector

-Davis-Besse Nuclear Power Station Utility Radiological Safety Board Aou~

Attachment L-10-139 Annual Report of Changes to the 10 CFR 50.46 Emergency Core Cooling System Evaluation Model and in the Application of the Model for the Davis-Besse Nuclear Power Station, Unit No. 1 Page 1 of 2 10 CFR 50.46 (a)(3)(ii) states that each holder of an operating license shall report to the Nuclear Regulatory Commission (NRC), at least annually, each change or error in an acceptable Emergency Core Cooling System (ECCS) evaluation model (EM) or in the application of such a model that affects the calculation of peak cladding temperature (PCT).EVALUATION MODEL CHANGES AND ERRORS Babcock & Wilcox Nuclear Technologies (BWNT) Loss of Coolant Accident (LOCA)Evaluation Model No errors were identified and no changes were implemented during the reporting period.CRAFT2 LOCA Evaluation Model No errors were identified and no changes were implemented during the reporting period.EVALUATION MODEL APPLICATION CHANGES AND ERRORS No errors were identified and no changes were implemented during the reporting period.Summary A summary of the PCTs at the end of the reporting period are provided in Table 1.

Attachment L-10-139 Page 2 of 2 Table 1 10 CFR 50.46 Summary for 2009 Plant Name: Davis-Besse Unit 1 LOCA Spectrum Mk-B-HTP Utility Name: FirstEnergy Mk-BIOM Mk-BIOK Mk-B12 LBLOCA SBLOCA LBLOCA LBLOCA LBLOCA Mixed-Core Item Reporting Description PCT or (Delta PCT)# Category<2,102 OF 2,102 OF 2,099 OF 2,098 OF 1,555 OF Licensing Basis at Beginning of 2009 Estimated Analyzed Analyzed Estimated Analyzed EM RO.6 1 EM RO.6 EM RO.6 EM RO.9 EM RO.9 2009 Licensing Activity N/A N/A N/A N/A [N/A N/A N/AN/A<2,102 OF 2,102 OF 2,099 OF 2,098 °F 1,555 °F Licensing Basis at End of 2009 Estimated Analyzed Analyzed Estimated Analyzed EM RO.6 EM RO.6 EM RO.6 EM RO.9 EM RO.9 Footnotes:

(1) Evaluation Model revision number.