ML20080L359

Comments on Development of Alternate Design Considerations Re Protection Against Pipe Breaks.Criteria Change Eliminating Pipe Whip Restraints,Intermediate Pipe Break Requirement & Load Combination Requirement to Be Requested

ML20080L359
Person / Time
Site:	Vogtle
Issue date:	09/26/1983
From:	Foster D GEORGIA POWER CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
GN-261, NUDOCS 8309300260
Download: ML20080L359 (2)

Text

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\rq p Frr;gi September 26, 1983 File: X6AB01 Mr. Harold R. Denton Log: GN-261 Director, Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555

References:

(1) Letter from M. Edelman (AIF) to H. Denton (NRC) dated March 28, 1983 (2) Letter from H. Denton (NRC) to M. Edelman (AIF) dated May 2, 1983 (3) Letter NS-EPR-2768 from E. P. Rahe (Westinghouse) to R. Volmer (NRC) dated May 11, 1983 (4) Letter from J. J. Ray (ACRS) to W. Dircks (NRC) dated June 14, 1983 (5) NRC Memorandum from W. Dircks (NRC) to J. J. Ray (ACRS) dated July 29, 1983 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 & 2 ALTERNATE PIPE BREAK DESIGN CONSIDERATIONS

Dear Mr. Denton:

Georgia Power Company has been following the industry and the NRC's efforts in the development of alternate design considerations with respect to pro-tection against pipe break events and is in agreement and endorses the conclusions &cumented in Reference 1 through 5 above. Further, we believe that timely consideration and action by the NRC in implementing these improved design considerations will effect both sizable benefits in cost reductions during construction and attendant significant reductions in radiation exposure to personnel during plant operation.

i Georgia Power Company currently is in the process of installing the reactor coolant loop pipe whip restraint at Plant Vogtle. In the near future, we, therefore, intend to file a request and justification for a criteria change which will allow:

(a) elimination of the pipe whip restraints from the reactor coolant loop, and (b) elimination of the associated seismic plus reactor coolant loop pipe break load combination requirement from the design of systems, structures, and components (excluding reactor coolant loop component supports) in the containment. 0gl 0309300260 030926 6 0

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O I Mr. Harold R. Denton i

September 26, 1983 l Page 2 4

This submittal will also demonstrate our need for an expeditious review and approval of the above by the end of November, 1983.

! We intend to follow the above request with a separate filing requesting a i criteria change that will eliminate the arbitrary intermediate pipe break i

requirement from the design of piping systems and also ask for the NRC's early review and approval of this additional request.

! It is our hope that the NRC gives the generic resolution of pipe break issues the appropriate level of attention and that these issues are l resolved as soon as possible. We are fully prepared to provide all necessary information, including meeting with your staff, to insure a i

clear understanding of these issues as they relate to Plant Vogtle.

j Yours,truly,p j

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'D. O. Foster 2 D0F:sw i xc: J. A. Bailey 1 0. Batum i G. Bockhold, Jr.

, H. H. Gregory, III l L. T. Gucwa l M. Malcom l W. T. Nickerson 1 J. P. O'Reilly i W. F. Sanders 1

R. A. Thomas G. F. Trowbridge, Esq.

! D. E. Dutton M. A. Miller V. J. Stello, Jr.

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