ML121080277
| ML121080277 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/20/2012 |
| From: | Peter Bamford Plant Licensing Branch 1 |
| To: | Harden P FirstEnergy Nuclear Operating Co |
| Bamford, Peter J., NRR/DORL 415-2833 | |
| References | |
| TAC ME8203, TAC ME8204 | |
| Download: ML121080277 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 20, 2012 Mr. Paul A Harden Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB 1 P. O. Box 4, Route 168 Shippingport, PA 1S077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 - CLOSEOUT OF INFORMATION REQUEST PURSUANT TO 10 CFR SO.S4(f) RELATED TO THE ESTIMATED EFFECT ON PEAK CLADDING TEMPERATURE RESULTING FROM THERMAL CONDUCTIVITY DEGRADATION IN THE WESTINGHOUSE FURNISHED REALISTIC EMERGENCY CORE COOLING SYSTEM EVALUATION (TAC NOS. ME8203 AND ME8204)
Dear Mr. Harden:
By letter dated February 16, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued a letter (Agencywide Documents Access and Management System (ADAMS) Accession No. ML120400672), in accordance with Title 10 of the Code of Federal Regulations (10 CFR),
Part SO, Section SO.S4(f). Pursuant to this regulation, the NRC staff requested that you provide information regarding the effect of a potentially significant error, as defined in 10 CFR S0.46(a}(3)(i), associated with thermal conductivity degradation (TCD), on peak cladding temperature in the Westinghouse-furnished realistic emergency core cooling system evaluation models. The requested information would enable the NRC staff to determine compliance with the Beaver Valley Power Station (BVPS) licensing basis, which includes the requirements of 10 CFR S0.46(a)(3)(ii), concerning the reporting of errors and changes to the emergency core cooling system evaluation model.
Specifically, the February 16, 2012, letter required that you provide information within 30 days, as follows:
(1)
An estimation of the effect of the TCD error on the peak fuel cladding temperature calculation for the emergency core cooling system evaluations at BVPS, Units 1 and 2.
(2)
A description of the methodology and assumptions used to determine the estimates.
This description shall include consideration of experimental data relevant to TCD and specific information regarding any computer code model changes which were necessary to address these data.
By letter dated March 16,2012 (ADAMS Accession No. ML12079A111), you submitted a response to the 10 CFR SO.S4(f) information request for BVPS, Units 1 and 2. The NRC staff has reviewed your submitted information and determined that for BVPS, Units 1 and 2, your response provides the information required to be responsive to the issues discussed above. In
P. Harden
-2 addition, the NRC staff determined that your response, which included a report pursuant to 10 CFR 50.46(a)(3)(ii), demonstrates that your facility has complied with the applicable reporting requirements. Based on these considerations, the NRC staff considers the subject action under 10 CFR 50.54(f) to be complete, and TAC Nos. ME8203 and ME8204 are being closed.
The NRC staff continues to review the BVPS, Units 1 and 2, 10 CFR 50.46(a)(3) report, and will advise you by separate correspondence if further information is required. TAC Nos. ME8409 and ME8410 have been opened to track this review.
If you have any questions on this matter, please contact me at 301-415-2833.
Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412 cc: Distribution via Listserv
P. Harden
~ 2 addition, the NRC staff determined that your response, which included a report pursuant to 10 CFR 50.46(a)(3)(ii), demonstrates that your facility has complied with the applicable reporting requirements. Based on these considerations, the NRC staff considers the subject action under 10 CFR 50.54(f) to be complete, and TAC Nos. ME8203 and ME8204 are being closed.
The NRC staff continues to review the BVPS, Units 1 and 2, 10 CFR 50.46(a)(3) report, and will advise you by separate correspondence if further information is required. TAC Nos. ME8409 and ME8410 have been opened to track this review.
If you have any questions on this matter, please contact me at 301-415~2833.
Sincerely, Ira!
Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412 cc: Distribution via Listserv DISTRIBUTION:
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