ML17261A252

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Forwards Design Input Info,RHR-100 & 6 Oversize Drawings. Design Input Info & Drawings Available in Central Files Only
ML17261A252
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/01/1981
From: Maier J
ROCHESTER GAS & ELECTRIC CORP.
To: Crutchfield D
Office of Nuclear Reactor Regulation
Shared Package
ML17261A253 List:
References
NUDOCS 8104080417
Download: ML17261A252 (4)


Text

REGULATOR NFORMATION DISTRIBUTION TEM (BIDS)

'; 'ACCfSSION-" NBR:8104080417 DOC,DATE: 81/04/01 NOTARIZED:- NO DOCKET FACIL',:50 244 Robert Etnmet Ginna Nuclear, Pl antg Unit li Rochester G

05000244 AUTH',NAME AUTHOR AFFILIATION MAIERgJ ~ E ~

Rochester Gas 8 Electric Corp'EC IP, NAME RECIPIENT AFFILIATION CRUTCHF IELDi D ~

Oper ating Reactor s Branch 5

SUBJECT:

. Forfar ds "Design Input; Info RHR'00" L 6 oversize drawings,'esign input info 8 drawings available in Central Files g S(4'tOgb l~S +SR. Alfpf< g W~ln/OL

~0 DISTRIBUTION CODE::

A028S COPIES RECEIVED:LTR

'NCL SI E:

TITLE: Seismic Review for SEP Plants'OTES:

1 copy:SEP Sect; Ldr.

05000244 RE G.

L 01 RECIPIENT ID CODE/NAME.

ACTION:

CRUTCHFIELD 04 INTERNAL'. EQUIP QUAL" BR07 GEOSC IENCES 09" raE~

06 COPIES LTTR ENCL>

7 7

1-1 1

1 2

0 1

1 RECIPIENT ID CODE/NAME GEN ISSUES BROS HYD/GEO BR.

10.

NRC PDR 02'R ASSESS BR 11 SEP BR 12 COj IES LTTR ENCL 1

0 2

2 1

1 1

0 1

1 EXTERNAL AC S

NSIC 14 05 16 16 1

1 LPDR 03 P<t Sc Ca)

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TOTAL. NUMBER OF COPIES REQUIRED:

LTTR 35 ENCL 3$

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//////

/ /////////////

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//////////////

ROCHESTER GAS AND ELECTRIC CORPORATION o

89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E.

MA IER VICE PRESIDENT

'SEI.EPHONE AREA CODE 7IO 546-2700 Q

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Apri1 1, 1981 Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.

5 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

USNRC Letter dated February 21, 1981 SEP Seismic Piping Review R.

E. Ginna Nuclear Power Plant, Unit No.

1 Docket No. 50-244

Dear Mr. Crutchfield:

E'nclosed are three (3) copies of the piping information you requested for residual heat removal line RHR-100.

This includes the input information necessary for you to perform independent review; and summary of the results of our seismic upgrade program analyses.

Included are RHR-100 piping system engineering

data, support stiffness summary sheet, isometric drawings, piping system orthographic drawings, and pipe support drawings.

As discussed in a telephone conversation yesterday with Mr. Snaider of your staff, the same information for safety injection line SIS-210 will be provided April 6, 1981.

Very truly yours, Enclosures fcLU~~

J n E. Maier go~S

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