05000280/LER-1979-041-21, /21X-0:on 791219,low Reactor Coolant Flow in Loop a Caused Reactor Trip & Safety Injection.Caused by Ground Fault within Reactor Coolant Pump Motor 1A.Motor Replaced

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/21X-0:on 791219,low Reactor Coolant Flow in Loop a Caused Reactor Trip & Safety Injection.Caused by Ground Fault within Reactor Coolant Pump Motor 1A.Motor Replaced
ML18136A358
Person / Time
Site: Surry Dominion icon.png
Issue date: 01/02/1980
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18136A357 List:
References
LER-79-041-21X, LER-79-41-21X, NUDOCS 8001070435
Download: ML18136A358 (2)


LER-1979-041, /21X-0:on 791219,low Reactor Coolant Flow in Loop a Caused Reactor Trip & Safety Injection.Caused by Ground Fault within Reactor Coolant Pump Motor 1A.Motor Replaced
Event date:
Report date:
2801979041R21 - NRC Website

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-- NRC FORM 366--

U.S. NUCLEAR REGULATORY COMMISSION (7-77) t

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  • 74 75 REPORT DATE 80 EVENT DESCR_IPTION AND PROBABLE CONSEQUENCES@

I D.lring power operation, a reactor trip, followed by safety injection, occurred as a

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result of low reactor coolant flow in loop "A 11

  • All systans responded as designed and f IT:m the heal th am safety of the general public were not affected.

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30 VALVE SUBCODE*

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42 43 44 47 [IIfil I The reactor trip occurred as a result of a groun:l fault within 111A" Reactor Coolant Purnb ITIIJ I Motor.

Toe failure of the rrntor win:lirg' s insulation resulted in the groun:ling of I 1-RC-P-lA' s imtor.

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Toe rrotor has been replaced.

All emergency procedures were per-ITITI I fonned as required.

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FACILITY STATUS

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9 11 12 13 80 NU~BER DESCRIPTION 41 PERSONNEL INJURIES

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e (ATTACHMENT, PAGE 1 OF 1)

SURRY POWER STATION, UNIT 1 DOCKET NO:

050-0280 REPORT NO:

79-041/21X-0 EVENT DATE:

12/19/79 e

TITLE OF EVENT:

Reactor Coolant Pump, 1-RC-P-lA, Malfunction

1.

DESCRIPTION OF EVENT

During full power operation, a reactor trip occurred as a result of a grounded motor winding on reactor coolant pump.

At approximately~

minutes after the trip, a safety injection was initiated automatically by a low steam line header pressure differential on Loop "A".

2.

PROBABLE CONSEQUENCES OF EVENT:

The reactor trip and subsequent safety injection had no effect upon the health or safety of the general public because all systems, automatic and manual, responded in a manner consistent *with design.

3.

CAUSE OF EVENT

The reactor trip was caused by loss of Reactor Coolant flow, as a result of a ground fault in Reactor Coolant Pump Motor "IA".

The safety in-jection was due to a low steamline to header pressure differential on Loop "A".

4.

IMMEDIATE CORRECTIVE ACTION

The immediate corrective action taken following the reactor trip was to complete the appropriate emergency procedures.

All systems responded as designed.

5.

SCHEDULED CORRECTIVE ACTION:

The Reactor Coolant Pump motor has been replaced.

6.

ACTION TAKEN TO PREVENT RECURRENCE:

The same as scheduled corrective actions.

7.

GENERIC IMPLICATIONS None