ML17250B291
| ML17250B291 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/28/1993 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17250B293 | List: |
| References | |
| NUDOCS 9307080209 | |
| Download: ML17250B291 (4) | |
Text
SUBJECT:
Forwards EOPs.
ACCELERATED DOCUIVIENTDISTRIBUTIONSYSTEM REGULATOZNFORNATION DISTRIBUTION+TEN (RZDS)
ACCESSION NBR:9307080209 DOC.DATE: 93/06/28 NOTARIZED:
NO DOCKET ¹ FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.
Project Directorate I-3
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DISTRIBUTION CODE: A003D COPIES RECEIVED:LTR
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TITLE: OR/Licensing Submittal:
Suppl 1 to NUREG-0737(Generic Ltr 82-33)
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 S
RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: N~RR ORCH/HHFBll 01 EXTERNAL: NRC PDR COPIES LTTR ENCL 1
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D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTETH CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI D
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 10 ENCL 9
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ROBERT C MECREOY Vice Prerldent Clnna Nuclear Production 89 EAST AVENUE, ROCHESTER N.K 14649-0001 TELEPttOME AREA CODE 7t B 546-2700 June 28, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Mr. Allen Johnson Project Directorate I-3 Washington, D.C. 20555
Subject:
Emergency Operating Procedures R. E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen:
As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very truly yours, Robert C. Mecredy Enclosures c:
Mr. Lee Bettenhausen, USNRC, Region 1
Resident Inspector, Ginna Station emergency. pro r
9307080209~930628 PDR ADOCK 05000244 P~
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AP-CCW.1 Leakage Into the Component Cooling Loop, Rev. 8 AP-CCW.3 Loss of CCW - Plant Shutdown, Rev. 8 AP-RCC.1 Continuous Control Rod Withdrawal/Insertion, Rev. 5 AP-TURB.2 Turbine Load Rejection, Rev. 12 ES-O.O Rediagnosis, Rev. 8 FH-H.3
Response
to Steam Generator High Level, Rev. 3