ML20207N534

Forwards Proposed Revised FSAR Page 1.9-69 Re Number of Steam Generators Examined During First Inservice Insp for Review.Change Will Be Included in Next FSAR Amend

ML20207N534
Person / Time
Site:	Vogtle
Issue date:	01/09/1987
From:	Bailey J GEORGIA POWER CO., SOUTHERN COMPANY SERVICES, INC.
To:	Youngblood B Office of Nuclear Reactor Regulation
References
GN-1312, NUDOCS 8701140274
Download: ML20207N534 (2)

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• Georgia Power Company Post Offica Box 282 Waynesboro, Georgi 3 30830 Tclephone 404 554-9961 404 724-8114 Southern Company Services, Inc. #

Post Office Box 2625 Birmingham, Alabama 35202 Telephone 205 8704011 VOgtle Project Janttary 9, 1987 Director of Nuclear Reactor Regulation File: X7N16 Attention: Mr. B. J. Youngblood Log: GN-1312 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C. 20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 PROPOSED FSAR CHANGE

Dear Mr. Denton:

Georgia Power Company has conducted a review of the VEGP FSAR and the proposed Technical Specifications. As a result of this review page 1.9-69, attached, of the FSAR will be changed as indicated. This change will be included in the next FSAR amendment.

If your staff has any questions concerning the proposed changes, please do not hesitate to contact me.

Sincerely,

. A. Bailey Project Licensing Manager JAB /sm Attachment xc: R. E. Conway NRC Regional Administrator R. A. Thomas NRC Resident Inspector J. E. Joiner, Esquire D. Feig B. W. Churchill, Esquire R. W. McManus M. A. Miller (2) L. T. Gucwa B. Jones, Esquire Vogtle Project File G. Bockhold, Jr.

0989V 8701140274 870109 00 PDR ADOCK 05000424

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. o Conform except for pos'skien CM.d.. The numb 2r o f Skeam cjenerators emimec( during the first inservice. inspecMon will be, o.ccordincj VEGP-FSAR-1

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to Ote. tequite.tnend5 o{ theTec.hn'scod $peci(ic ion 5.

.9.83.2 VEGP Position 3)-Crnferr- The steam generators are designed to permit access to

/'s tubes for inspection and/or repair or plugging (if necessary).

(_ The inservice inspection program is discussed in subsection 5.4.2 and the Technical Specifications.

1.9.84 REGULATORY GUIDE 1.84, REVISION 20, NOVEMBER 1982,

(~N DESIGN AND FABRICATION CODE CASE ACCEPTABILITY - ASME

(_) SECTION III, DIVISION 1 1.9.84.1 Regulatory Guide 1.84 Position This guide lists those Section III ASME Code Cases oriented to design and fabrication that are generally acceptable to the NRC for implementation in the licensing of light-water-cooled nuclear power plants.

1.9.84.2 VEGP Position Conform.

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The NSSS Code Cases are discussed in table 1.9-3 and paragraph 5.2.1.2. Other design and fabrication code cases used for VEGP are identified in and table 1.9-1.

1.9.85 REGULATORY GUIDE 1.85, REVISION 20, NOVEMBER 1982, MATERIALS CODE CASE ACCEPTABILITY - ASME SECTION III DIVISION 1 1.9.85.1 Regulatory Guide 1.85 Position

) This guide lists those Section III ASME Code cases oriented to materials and testing that are generally acceptable to the NRC for implementation in the licensing of light-water-cooled nuclear power plants.

f$3 1.9.85.2 VEGP Position Conform.

The NSSS Code Cases are discussed in table 1.9-3 and paragraph 5.2.1.2. Other materials code cases used for VEGP

( are identified in table 1.9-2.

1.9-69 Amend. 9 8/84 l