ML13161A094
| ML13161A094 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar, Sequoyah  |
| Issue date: | 06/06/2013 |
| From: | James Shea Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML13161A094 (2) | |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 June 6, 2013 10 CFR 50.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390
Subject:
Reference:
Notice of Intent to Implement WCAP-17721-P, Rev. 0, "Westinghouse Containment Analysis Methodology - PWR LOCA Mass and Energy Release Calculation Methodology" Westinghouse Letter LTR-NRC-13-22, "Submittal of WCAP-17721-P, Revision 0 and WCAP-1 7721-NP, Revision 0, "Westinghouse Containment Analysis Methodology - PWR LOCA Mass and Energy Release Calculation Methodology,"
(Proprietary/Non-Proprietary)," dated May 3, 2013 (ADAMS Accession No. ML13133A066).
In the reference letter, Westinghouse Electric Company submitted the proprietary and non-proprietary versions of WCAP-17721, Revision 0, "Westinghouse Containment Analysis Methodology - PWR LOCA Mass and Energy Release Calculation Methodology," dated April 2013, for NRC approval. The purpose of this letter is to identify Tennessee Valley Authority's intention to implement this methodology for performing Loss of Coolant Accident (LOCA) Mass and Energy Release analyses for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Unit 1, following NRC approval of the WCAP.
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U.S. Nuclear Regulatory Commission Page 2 June 6, 2013 WCAP-1 7721-P contains the LOCA Mass and Energy Release methodology that utilizes the WCOBRAITRAC TM Computer Code. As defined in WCAP-17721-P, the WCOBRAITRAC TM Code has been modified to calculate the Mass and Energy Releases associated with a LOCA.
WCOBRA/TRAC TM is currently used for the Westinghouse Large Break LOCA peak cladding temperature (PCT) calculations. The WCAP-1 7721-P methodology is applicable to large dry, subatmospheric, and ice condenser containments, such as existing at the Sequoyah Nuclear Plant, Units 1 and 2, and the Watts Bar Nuclear Plant, Unit 1.
There are no new regulatory commitments included in this submittal. Please address any questions regarding this submittal to Ed Schrull at (423) 751-3850.
Respectfully, Vic President, Nuclear Licensing cc:
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant, Units 1 and 2 NRC Senior Resident Inspector - Watts Bar Nuclear Plant, Unit 1