ML13030A144

Request for RAI Concerning the Revising Technical Specifications Associated with the Low Temperature Overpressure Protection System and the Pressure-Temperature Limits Report

ML13030A144
Person / Time
Site:	Farley
Issue date:	02/01/2013
From:	Ellen Brown Plant Licensing Branch II
To:	Pierce C Southern Nuclear Operating Co
Brown E
References
TAC ME9256, TAC ME9257
Download: ML13030A144 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 1, 2013 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.

P.O. Box 12951 Bin 038 Birmingham, AL 35201-1295

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2- REQUEST FOR ADDITIONAL INFORMATION CONCERNING THE REVISING THE TECHNICAL SPECIFICATIONS ASSOCIATED WITH THE LOWTEMPERATURE OVERPRESSURE PROTECTION SYSTEM AND THE PRESSURE TEMPERATURE LIMITS REPORT (TAC NOS. ME9256 AND ME9257)

Dear Mr. Pierce:

By letter dated August 15, 2012, Southern Nuclear Company (SNC or the licensee), submitted a license amendment request for the Joseph M. Farley Nuclear Plant (FNP). Based on the implementation of new 54 effective power years (EFPY) pressure and temperature limit curves, corresponding changes to the FNP Technical Specifications (TS) associated with the lower temperature overpressure protection system and other limits are proposed.

A response to the enclosed Request for Additional Information (RAJ) is needed before the Nuclear Regulatory Commission staff can complete the review. This request was discussed with Mr. Ken McElroy of your staff on January 28,2013, and it was agreed that SNC would respond by March 15,2013. If you have any questions, please feel free to contact me at (301) 415-2315.

Sincerely IRA!

Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364

Enclosure:

RAI cc: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION REVISING THE TECHNICAL SPECIFICATIONS ASSOCIATED WITH THE PRESSURE-TEMPERATURE LIMITS REPORT SOUTHERN NUCLEAR COMPANY JOSEPH M. FARLEY NUCLEAR PLANT DOCKET NOS. 50- 384 AND 50-364

1. Discuss whether the proposed 54 effective full power years pressure - temperature limit curves, and the methodology used to develop these curves, considered all reactor vessel materials (beltline and non-beltline) and replacement ferritic reactor coolant pressure boundary materials (e.g. those installed subsequent to original construction for example, replacement steam generators), consistent with the requirements of Title 10 to the Code of Federal Regulations, Part 50, Appendix G.

Enclosure

ML13030A144

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