ML17250A556

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Forwards Stress Repts for a Rhr&B Mainstream Piping Inside Containment. Analyses Are Part of Seismic Upgrade Program & Incorporate Several Proposed Piping Sys Mods.Analyses Do Not Represent Current as-built Plant Configuration.W/Encl
ML17250A556
Person / Time
Site: Ginna 
Issue date: 09/09/1980
From: White L
ROCHESTER GAS & ELECTRIC CORP.
To: Crutchfield D
Office of Nuclear Reactor Regulation
References
NUDOCS 8009160539
Download: ML17250A556 (4)


Text

REGULATO " INFORMATION DISTRIBUTION "YSTEM (RIDS)

ACCESSION NBR:9009160539 DOC ~ DATE: 80/09/09 NOTARIZED!

NO DOCKET FACIL:50 2rlrl Robert Emmet Ginna Nuclear Plantg Unit 1~ Rochester G

05000240 AUTH BYNAME AUTHOR AFF IL~IATION WHITErLeD ~

Rochester Gas 8 Electr'ic Corp.

RECIP ~ NAME RECIPIENT AFFILIATION CRUTCHFIELD p D, Operating Reactors Branch 5

I

SUBJECT:

Forwards stress r apts for A

RHR8B majnstream piping inside containment, Analyses are part of sejsmic upgrade program A80 incor por ate several pr oposed piping sys mods.Analyses do not repr esent cur rent as bui l t pl ant conf i gurat i on.bl/0 enc l.

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050002rlrl RECIPIENT ID CODE/NAME ACTION:

CRUTCHFIELD 04 INTERNAL D/DIRgHU i FAC08 I8E 06 11 REG FILE 01 COPIES LTTR ENCL 13 1

RECIPIENT ID CODE/NAME DIRr HUM FAC 07 NRC PDR 02 OR ASSESS BR 10 COPIES LTTR ENCL EXTERNAL: ACRS NSIC 09 05 16 1

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TOTAL NUMBER OF COPIES REQUIRED:

LTTR ENCL

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0 r(/fIIIEIN IIIIIIIIII mite iz irzzxiriz ROCHESTER GAS AND ELECTRIC CORPORATION D

89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON O. WHITE, JR.

VICE PRESIDENT TELEPHONE ARE* CODE 7IS 546 2700 September 9,

1980 Director of Nuclear Reactor Regulation Attention:

Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.

5 U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Ginna Piping Seismic Analysis R.E.

Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Crutchfield:

In accordance with our letter dated May 30,

1980, enclosed are three copies, of stress reports for the A Residual Heat Removal (RHR) piping inside containment and the B Main Steam (MS) piping inside containment.

The analyses are a part of our Seismic Up-grade Program and incorporate several proposed piping system modifications.

As such, the analyses do not represent the current as-built confiquration of the plant.

Further, the analyses are subject to revision'.

Very truly yours, Enclosures L.D. White, Jr.

80091605~~

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