ML17251A176
ML17251A176 | |
Person / Time | |
---|---|
Site: | Ginna ![]() |
Issue date: | 07/18/1988 |
From: | Spector S ROCHESTER GAS & ELECTRIC CORP. |
To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
References | |
NUDOCS 8807260357 | |
Download: ML17251A176 (4) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8807260357 DOC.DATE: 88/07/18 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1,'ochester G
AUTH.NAME
'UTHOR AFFXLIATION SPECTOR,S.M.
Rochester Gas -& Electric Corp.
RECIP.NAME 'ECIPIENT AFFXLIATION Document Control Branch (Document Control Desk)
SUBJECT:
RO:on 880716,electrical fault caused five main breakers in substation to trip open.
Ii DISTRIBUTION CODE:
IE22D COPIES,RECEIVED:LTR ENCL SIZE:
TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:License Exp date in accordance'with'10CFR2,'2.'109(9/19/72).
DOCKET 05000244 S
05000244-'ECIPIENT ID CODE/NAME PD1-3 LA STAHLE, C INTERNAL: ACRS MICHELSON AEOD/DOA AEOD/DSP/ROAB ARM/DCTS/DAB NRR/DEST/ADS 7E NRR/DEST/ESB SD NRR/DEST/MEB 9H NRR/DEST/PSB SD NRR/DEST/SGB 8D NRR/DLPQ/QAB 10 NRR/DREP/RAB 10 RR/~IS/SIB 9A REG FXLE 02 ES/DSIR DEPY RGN1 FILE 01 EXTERNAL EG&G WILLIAMSI S H ST LOBBY WARD NRC PDR NSXC MAYS,G COPIES LTTR ENCL 1
1 1
1 1
1 1
1 2
2 1
1 1
0 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 4
4 1
1 1
1 1
1 RECXPIENT ID CODE/NAME PD1-3 PD ACRS MOELLER AEOD/DSP/NAS AEOD/DSP/TPAB DEDRO NRR/DEST/CEB SH NRR/DEST/ICSB 7
NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB ll NRR/DREP/RPB 10 NUDOCS-ABSTRACT RES TELFORD,J RES/DSIR/EIB FORD BLDG HOY,A LPDR NSIC HARRIS,J COPIES LTTR ENCL 1
1 2
2 1
1 1
1 1
1 1
1 1
1
'1 1
1 1
1 1
1 1
2 1
1 1
1 1
1 1
1 1
1 1
1 h'-=
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 45 ENCL 44
July 18, 1988 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Follow-up Summary of Close-out Unusual Event R.E.
Ginna Nuclear Power Plant Docket No. 50-244 of July 16, 1988 In accordance with NUREG 0654, FEMA-REP-1, Rev.
1 reporting requirements which requires a written summary of "Close-out or Class Reduction Conditions",
the attached close-out summary for the July 16, 1988 Unusual Event is hereby submitted.
This event has in no way affected the public's health and safety.
Very truly yours,
&7 Stanl y M. Spector Superintendent-Ginna Station Attachment xc:
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector gpss' 8807260357 880718 PDR ADOCK 05000244 S
Attachment to Close-out of Jul 16 1988 Unusual Event.
R.E.
Ginna Nuclear Power Plant Docket No. 50-244 On July 16, 1988 at approximately 1355 EDST with the reactor at 100% steady state power an electrical fault in the plant's main electrical substation caused five main breakers in the substation to trip open.
These five..main-breakers opening caused the loss of approximately one half of the transmission capability of the substation plus caused the loss of offsite power to the plant.
All safeguards.busses de-energized and were re-energized with the two station emergency diesel generators in approximately 30 seconds.
The plant was stabilized at approximately 754 power.
At approximately 1400 EDST the Security Department reported to the Control Room that they heard an explosion at the main electri-cal substation.
At 1409 EDST the Operations Shift Supervisor declared an Unusual Event in accordance with plant procedure SC-100, "Ginna Station Event Evaluation and Classification",
Emergency Action Level:
Hazards Being Experienced or Projected; Explosion Near or Onsite Reported to Operations Personnel.
All offsite notifications were made per plant procedure SC-601, "Unusual Event Notifications".
At approximately 1445 EDST after offsite power had been restored through a backup circuit, Rochester Gas and Electric Corporation's (RGGE)
Power Cont'rol Dispatcher requested a plant shutdown due to damage to the offsite power transmission equipment.
At 1539 EDST the turbine generator was taken off the line and at 1621 EDST the reactor trip breakers were opened.
The plant was stabilized in the hot shutdown condition.
At 1645 EDST the Operations Shift Supervisor, with approval and concurrence from the Superintendent of Ginna Station, the Opera-tions Supervisor, and the Duty Engineer declared'he Unusual Event terminated in accordance with plant procedure SC-110, "Ginna Station Event Evaluation for Reducing the Classification".
The rationale involved in the termination was:
o The cause of the explosion was known (i.e. circuit breaker 91102 had exploded) o The failed circuit breaker had been electrically isolated 0
o 0
There was no.longer a danger of fire at the substation The reactor was stable at hot shutdown Offsite power had been restored