ML20249C375

Informs That Pressure Temp Limits Repts & CEOG Rept CE NSPD-1039,rev 2, Best Estimate Copper & Nickel Values in CE Fabricated Reactor Vessel Welds, Dtd June 1997 Provide Info Requested on 980403

ML20249C375
Person / Time
Site:	Farley
Issue date:	06/19/1998
From:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, NUDOCS 9806290149
Download: ML20249C375 (2)

Text

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.cO Dave Morty Stuthern Nucl:ar l Vice President ' Op: rating C mpany

! Farley Project P.O. Box 1295 Birmingham. Alabama 35201

, , Tel 205.992.5131 SOUTHERN June 19,1998 M Energy to ServeYourWorld"

~ Docket Nos.: 50-348 10 CFR 50.60 50-364' l-

' U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington,DC 20555 Joseph M. Farley Nuclear Plant Generic Letter 92-01 Request For Addiliqui Information Regarding Reactor Vessel Integrity

. Ladies and Genti: men:

By letter daied April 3,1998; the NRC Staffissued a request for additional information

' concerning reactor pressure vessel integrity at the Joseph M. Farley Nuclear Plant. The focus of the request for additional information was the impact of Combustion Engineering Owners' Group report CE NPSD-1039, Revision 2, ."Best Estimate Copper and Nickel Values in CE Fabricated Reactor Vessel Welds," dated June 1997. In part, the letter states, "In July 1997, the Combustion Engineering Owners' Group (CEOG) provided a report with additional RPV

- weld chemistry data for RPVs fabricated by' CE. This additional RPV weld chemistry data may affect previous RPV integrity anslyses supplied by licensees with CE fabricated RPVs. j

-If a question does not apply to your situation, please indicate this in your RAI response along '

- with your technical basis.' ..".

In the same time frame as the request for additional information, the NRC Staff approved a -

technical specification amendment for Farley Nuclear Plant for application of a prescure

- temperature limits report (PTLR). As was stated in Southern Nuclear's letter dated December 18,1997, the best estimate copper and nickel values determined by the gU -  ;

Combustion Engineering Owners' Group were used in developing the PTLR. Consequently,

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the focus of the request for additional information is not applicable to Farley Units 1 and 2 i since the CEOG best estimate values were used to develop the pressure temperature limits.

This position was confirmed with members of the NRC Staff by conference call on May 15, r-1998.

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L The PTLRs for Farley Units 1 and 2 were submitted to the NRC Staff by letter dated May 19,1998. The PTLRs along with the Combustion Engineering Owners' Group report CE NPSD-1039, Revision 2, ."Best Estimate Copper and Nickel Values in CE Fabricated Reactor

Vessel Welds," dated June 1997, provide the information requested.

990M290149 990619 9 ADOCK 05000348 PDR p PDR

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. U.S.. Nuclear Regulatory Commission Page 2

- If there are any questions, please advise.

Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY h M/

Dave Morey REM / cit:RPVRAI_. DOC cc: Mr.L. A.Reyes, RegionII Administrator Mr. J. I. Zimmerman, NRR Project Manager Mr. T. M. Ross, Plant Sr. Resident Inspector 1.

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