ML17263A584
| ML17263A584 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/14/1994 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17263A585 | List:
|
| References | |
| NUDOCS 9404190095 | |
| Download: ML17263A584 (4) | |
Text
~~ACCELERATED DISTjK3UTION DEMONSTIWTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9404190095 DOC.DATE: 94/04/14 NOTARIZED: NO DOCKET I FACXL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFXLIATION JOHNSON,A.
Project Directorate I-3 /
SUBJECT:
Forwards Ginna Station emergency operating procedures c
DISTRIBUTXON CODE:
A003D COPIES RECEIVED.LTR ENCL SIZE:~~M ~
D TITLE: OR/Licensing Submittal:
Suppl 1 to NUREG-0737(Generic Ltr 82-33)
S NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 /
RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: N RgH HHFB EG FI E 01 EXTERNAL: NRC PDR COPXES LTTR ENCL 1
1 2
2 1
1 1
1 1
1 RECXPIENT XD CODE/NAME PD1-3 PD OC/LFDCB RES/DSIR/EIB NSIC COPIES LTTR ENCL 1
1 1
0 1
1 1
1 D
D 8
D NOTE TO ALL"RIDS" RECIPIENTS:
D D
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPXES REQUIRED:
LTTR 10 ENCL 9
zsizv(zisrj sirzsu(z sais zz zzuxirsr(u ZZ.::::
ROCHESTER GAS AND ELECTRIC CORPORATION 0
89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERTG MECREDY Vice Prerident Ctnna Nuclear Production TELEPHONE ArtEACOOE 7 to 546-2700 April 14, 1994 Mr. Allen Johnson Project Directorate I-3 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Emergency Operating Procedures R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very truly yours, Robert C. Mecredy RCM/rsm c:
Mr. Lee Bettenhausen, USNRC, Region 1
Resident Inspector, Ginna Station RG8E Nuclear Safety 8 Licensing 0
940419'00'Tt5
'Tt40414 PDR
'DOCK '05000244 P,'?",.",
l t
4
~~:rqnri g
Enclosures:
AP-RCS.4 AP-Turb.4 ATT-14.6 E-0 E-3 ES-0.0 ES-0.1 ES-0.2 ES-0.3 ES-1.1 ES-1.2 ES-1.3 ES-3.1 ES-3.2 ES-3.3 ECA-0.0 ECA-0.1 ECA-0.2 ECA-1.1 ECA-2.1 ECA-3.1 ECA-3.2 ECA-3.3 FR-C.1 FR-C.2 FR-P.1 FR-S.1 FR-S.2 Shutdown L'oca Loss of Condenser Vacuum Attachment RHR Press Reduction Reactor Trip or Safety Injection Steam Generator Tube Rupture Rediagnosis Reactor Trip Response Natural Circulation Cooldown Natural Circulation Cooldown with Steam Void In Vessel Sl Termination Post Loca Cooldown and Depressurization Transfer To Cold Leg Recirculation Post-SGTR Cooldown Using Backfill Post-SGTR Cooldown Using Blowdown Post-SGTR Cooldown Using Steam Dump Loss of All AC Power Loss of All AC Power Recovery Without Sl Required Loss of All AC Power Recovery With Sl Required Loss of Emergency Coolant Recirculation Uncontrolled Depressurization of Both Steam Generators SGTR With Loss of Reactor Coolant-Subcooled Recovery Desired SGTR With Loss of Reactor Coolant-Saturated Recovery Desired SGTR Without Pressurizer Pressure Control
Response
to Inadequate Core Cooling
Response
to Degraded Core Cooling
Response
to Imminent Pressurized Thermal Shock Condition
Response
to Reactor Restart/ATWS
Response
to Loss of Core Shutdown