ML20082S732
| ML20082S732 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/10/1991 |
| From: | Woodard J ALABAMA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19302F145 | List: |
| References | |
| NUDOCS 9109170262 | |
| Download: ML20082S732 (2) | |
Text
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Docket Nos. 50-348 50-364 U. S. Nuclear Regulatory Commission ATIN:
Document Control Desk Washington, DC 20555 Joseph M. Farley Nuclear Plant VANTAGE-5 Fuel Desian Amendment Gentlemen:
By letter dated July 15, 1991, Alabama Power Company proposed a technical specification amendment for Farley Nuclear Plant Units 1 and 2 to allow the use of VANTAGE-5 fuel assemblies in future reloads.
NRC letter dated August 8, 1991 requested additional information pertaining to the determination of a 60F peak cladding temoerature (PCT) penalty which results from a reduced steam generator ube area due to a combined safe I
shutdown earthquake (SSE) and loss of coolant accident (LOCA) loading effect.
The NRC letter also requested that the information include the impact of various reactor coolant system (RCS) piping breaks.
Previously, as an interim administrative measure, a 500F PCT penalty was assessed against the Farley large break LOCA analysis in the increased steam generator tube plugging (15%) amendment request to ensure that the 22000F licensing limit would not be exceeded due to a potential generic issue associated with steam generator flow area reduction resulting from combined SSE and LOCA loads.
(Refer to WCAP-12659 and WCAP-12694.) The 500F penalty was an initial conservative assessment for the most limiting RCS pipe break based on available generic information.
Subsequently, a 60F penalty, which was reported in the VANTAGE-5 fuel design amendment request, was substantiated based on farley specific work. The technical basis for determining this Farley specific PCT penalty is contained in attached WCAP-13064 (proprietary) and WCAP-13065 (non-proprietary), "J. H. Farley Nuclear Plant Units 1 and 2 Response to NRC Request for Additional Information on Steam Generator Flow Area Reduction Due to Combined LOCA and SSE Loads." WCAP-13064 and WCAP-13065 also address the treatment of RCS piping breaks and the accumulator and pressurizer surge branch line breaks, which bound all other RCS branch lines.
While not explicitly addressed ir. WCAP-13064 and WCAP-13065, justification for further mitigation of this 60F PCT penalty could now be prcvided as a result of the recent NRC approval of the Leak-Befnre-Break analysis for Farley Ur.it 1 and Unit 2.
For the bounding branch line brcak, f.e., the accumulator line break, the total flow area reduction is 0.0M.
This negligible flow area reduction would result in an insignificant PCT penalty.
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Nuclear Regulatory Commission Page 2 Westinghouse authorization letter CAW-91-203 and accompanying affidavit, Proprietary Information Notice, and Copyright Notice are also enclosed with i
the attachments. WCAP-13064 contains information proprietary to Westinghouse Electric Corporation which is supported by the affidavit signed by Westinghouse, the owner of the information.
The affidavit sets forth the basis on which the information may be withheld from public i
disclosure by the Connission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations. Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Connission's regulations.
Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse affidavit should reference letter CAW-91-203 and should be addressed to R. P. DiPiazza, Manager of Nuclear Safety Licensing, Westinghouse Electric Corporation, P. O. Box 355, Pittsburgh, Pennsylvania, 15230-0355.
Should you require any additional information, please advise.
I Respectfully submitted, ALABAMA POWER COMPANY h,4 rk.h NJ.
Woodard
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