ML17263A702
| ML17263A702 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/15/1994 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| PROC-940615, NUDOCS 9406220179 | |
| Download: ML17263A702 (4) | |
Text
ACCELERATED DISTRIBUTION DEMONST ATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9406220179 DOC.DATE: 94/06/15 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000244 JOHNSON,A.
Project Directorate I-3
SUBJECT:
Revised emergency operating procedures, including rev 9 to AP-CCW.l,rev 7 to AP-CVCS.l,rev 10 to AP-ELEC.l,rev 7 to
. AP-RCS.2,rev 1 to AP-ELEC.3,rev 10 to ES-l.l,rev 10 to ECA-0.1
& rev 10 to ECA-2.1.W/940615 ltr.
D D
S DISTRIBUTION CODE:
A045D COPIES RECEIVED:LTR J ENCL I SIZE:
k, NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 RECIPIENT ID CODE/NAME PD1-3 PD COPIES LTTR ENCL 1
1 RECIPIENT ID CODE/NAME JOHNSON,A COPIES LTTR ENCL 1
1 INTERNAL: AEOD/DOA/IRB NUDOCS-ABSTRACT 1
1 1
1 1
1 EXTERNAL: NRC PDR l~fysl @ L3~
NRR/DRSS/PEPB R
IL 01 NSIC 1
1 1
1'.
1 1
D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 8
ENCL 8
A D
D
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ROCHESTER GAS AND ELECTRIC CORPORATION ROBERT C MECREDY Vice Prerident Cfnna Nudear Production Lier 0 lri&
rife o
89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 TELEPttOtrE AREACODE 7t8 546 2700 June 15, 1994 Mr. Allen Johnson Project Directorate l-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 tr ly yours, Robert C. Mecred RCM/rsm c:
Mr. Lee Bettenhausen, USNRC, Region 1
Resident Inspector, Ginna Station RG8E Nuclear Safety & Licensing PjQAir Veg 940622017'7t 940615 PDR ADOCK 05000244 F
PDR g/ryP4 Z D7$ 4 /A cia
Enclosures:
AP-CCW.1 AP-CVCS.1 AP-ELEC.1 ATT-9.0 AP-RCS.2 AP-ELEC.3 ES-1 1
ECA-0.1 ECA-2.1 ECA-3.3 FR-I.1 FR-I.3 FR-P.1 E-3 Leakage Into The Component Cooling Loop CVCS Leak
. Loss of 12A and/or 12B Transformer Attachment Letdown Loss of Reactor Coolant Flow Loss of 12A and/or 12B Transformer Sl Termination Loss of All AC Power Recovery Without Sl Required Uncontrolled Depressurization of Both Steam Generators SGTR Without Pressurizer Pressure Control
Response
to High Pressurizer Level
Response
to Voids in Reactor Vessel
Response
to Imminent Pressurized Thermal Shock Condition Steam Generator Tube Rupture
I l
A Slt