ML17262A394
| ML17262A394 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/15/1991 |
| From: | Widay J ROCHESTER GAS & ELECTRIC CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0654, RTR-NUREG-654 NUDOCS 9102280275 | |
| Download: ML17262A394 (6) | |
Text
ACCELERATED DISTRIBUTION DEMONSTQA.TION SYSTEM REGULATORY INFORMATION DXSTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9102280275 DOC.DATE: 91/02/15 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFXLIATION WIDAY,J.A.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILXATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards close-out summary for 910215 unusual event,per NUREG-0654,FEMA-REP-.1,Rev 1 requirements.
DISTRIBUTION CODE:
IE22D COPIES RECEIVED:LTR J ENCL P
SIZE: 2-TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
S 05000244 RECXPIENT ID CODE/NAME PDl-3 LA JOHNSON,A INTERNAL: ACNW AEOD/DSP/TPAB NRR/DET/ECMB 9H NRR/DLPQ/LHFB11 NRR/DOEA/OEAB NRR/DST/SELB 8D NRR/DS SPLB8D1 RE RGN 01 EXTERNAL EG&G BRYCE iJ ~ H NRC PDR NSXC MURPHY,G.A COPIES LTTR ENCL 2
1 1
1 1
1 1
1 1
RECIPIENT ID CODE/NAME PD1-3 PD AEOD/DOA AEOD/ROAB/DSP NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7E NRR/DST/SRXB 8E RES/DSIR/EIB L ST LOBBY WARD NSIC MAYS,G NUDOCS FULL TXT COPIES LTTR ENCL D
D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE O'ASTE! CONTACT THE DOCUMENTCONTROL DESK, ROOi%1 Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
G TOTAL NUMBER OF COPIES REQUIRED:
LTTR 31 ENCL D
D
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0 l%IIIitIIl'A~it //~~illIKil47i ROCHESTER GAS AND ELECTRIC CORPORATION pj
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~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 tt:S.SPOONS',
AOS:A COO@ 7SO 546.2700 February 15, 1991 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
SUBJECT:
Follow-up Summary of Close-out of February 15, 1991 Unusual Event.
R.E.
Ginna Nuclear Power Plant Docket No. 50-244 In accordance with NUREG
- 0654, FEMA-REP-1, Rev.
1 reporting requirements which requires a written summary of "Close-out oz'lass Reduction Conditions",
the attached close-out summary for the February 15, 1991 Unusual Event is hereby submitted.
This event has in no way affected the public's health and safety.
Very Truly Yours, g p.dX.
oo(Ph A. Wide Superintendent Ginna Production JAW:dp xco U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia,
'PA 19406 Ginna USNRC Senior Resident Inspector Richard Z. Beldue 5'1022-027.i P1021g PDR ADOCK 05000244 PDH
'ATTACHMENT TO CLOSE-OUT OF FEBRUARY 15 1991 UNUSUAL EVENT On February 15, 1991, at 0845 EST with the reactor at approximately 974 full power, the Control Room operators were in the process of performing Periodic Test procedure PT-12.1 (EMERGENCY DIESEL GENERATOR lA).
As part of PT-12.1, the 1A Emergency Diesel Generator was being paralleled to 480V Safeguards Bus 18.
A few seconds after the 1A Emergency Diesel Generator breaker to Bus 18 was closed, it re-opened and simultaneously with this, both the High Side (4160V) and Lo Side (480V) Normal Feed breakers"to Bus 18 opened.
The 1A Emergency Diesel Generator continued to operate unloaded.
The loss of Bus 18 placed the plant in a
condition not permitted by the plant's technical specifications.
At approximately 0945
- EST, February 15,
- 1991, a plant shutdown was commenced to comply with plant Technical Specifications Section 3.3.4 and 3.7.
At approximately 0945, EST, February 15,
- 1991, the Operations Shift Supervisor declared an Unusual Event in accordance with EPIP 1-0,
>>Ginna Station Event Evaluation and Classification",
EAL:
Loss of Engineered Safety Features; Exceeding a Limiting Condition for Operation on a
Safety System Requiring a Plant
- Shutdown, (Tech Spec Section 3.3.4.).
All off-site notifications were made per EPIP 1-5 (Notifications).
At approximately 1123
- EST, February 15, 1991, the Normal Feed to Bus 18 was restored and the plant shutdown was terminated with reactor power at approximately 80% full power.
At approximately 1230 EST, February 15, 1991, the Plant Operating Review Committee (PORC) decided to remain in the Unusual Event condition until the lA Emergency Diesel Generator problem had been repaired and successfully loaded onto Bus 18.
At approximately 0130 EST, February 16, 1991, after resolving the lA Emergency Diesel Generator
- concerns, the Operations
,Shift Supervisor, with approval and concurrence from the Superintendent Ginna Production, the Operations Supervisor, and the Duty Engineer, declared the Unusual Event terminated in. accordance with EPIP 3-4 (Emergency Declassification and Recovery).
All off-site agencies were notified of the termination of the Unusual Event.'