ML17263A188
| ML17263A188 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/30/1993 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17263A191 | List: |
| References | |
| NUDOCS 9304080154 | |
| Download: ML17263A188 (5) | |
Text
ACCELERATED DOCUMENT DIST BVTIONSYSTEM REGULARLY INFORMATION DISTRIBUTI SYSTEM (RIDS)
ACCESSION NBR:9304080154 DOC.DATE: 93/03/30 NOTARIZED: NO DOCKET 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 k/J4 8 //5
SUBJECT:
Forwards EOPs,including Rev 6 to AP-TURB.3,Rev 7 to AP-TURB.4,Rev ll to E-l,Rev 8 to ES-O.l,Rev 8 to ES-l.l Rev 15 to ES-1.3.
DISTRIBOTION CODE:
A003D COPIES RECEIVED:LTR 2 ENCLi SIZE:
TITLE: OR/Licensing Submittal:
Suppl 1 to NUREG-0737(Generic Ltr 82-33)
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NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244
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NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT COiNTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
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ROCHESTER GAS AND ELECTRIC CORPORATION o
ROBERT C. MECREDY Vice President Glnna Nucleat Ptoduction e9 EAST AVENUE, ROCHESTER N.Y. 14649-0001 TELEPHONE AREACODE 71B 546 2700 March 30, 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. Mecred Enclosures c:
Mr. Lee Bettenhausen, USNRC, Region 1
Resident Inspector, Ginna Station 93Q408
<iQgQQP244-Qi54 930330 PD~"1.(~,:.R,;
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AP-TURB.3 AP-TURB.4 E-1 ES-0.1 ES-1.1 ES-1.3 Turbine Vibration, Rev. 6 Loss of Condenser Vacuum, Rev. 7 Loss of Reactor or Secondary Coolant, Rev. 11 Reactor Trip Response SI Termination Transfer to Cold Leg Recirculation