05000272/LER-1979-059-03, /03L-0:on 790424 & 0508,during Refueling Outage, Public Svc Relay Dept Was Performing Relay Tests & de-energized Vital Bus Supplying Operating RHR Pump.Caused by Inadequate Work Procedures.Low Level Limit Raised

/03L-0:on 790424 & 0508,during Refueling Outage, Public Svc Relay Dept Was Performing Relay Tests & de-energized Vital Bus Supplying Operating RHR Pump.Caused by Inadequate Work Procedures.Low Level Limit Raised

ML18081B274
Person / Time
Site:	Salem
Issue date:	03/27/1980
From:	Kapple A Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18081B273	List: 05000272/LER-1979-059, Forwards LER 79-059/03L-0 05000272/LER-1979-059-03, /03L-0:on 790424 & 0508,during Refueling Outage, Public Svc Relay Dept Was Performing Relay Tests & de-energized Vital Bus Supplying Operating RHR Pump.Caused by Inadequate Work Procedures.Low Level Limit Raised
References
LER-79-059-03L, LER-79-59-3L, NUDOCS 8004010370
Download: ML18081B274 (1)

LER-1979-059, /03L-0:on 790424 & 0508,during Refueling Outage, Public Svc Relay Dept Was Performing Relay Tests & de-energized Vital Bus Supplying Operating RHR Pump.Caused by Inadequate Work Procedures.Low Level Limit Raised

Event date:
Report date:
2721979059R03 - NRC Website

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NRC FORM 366 (7-77)

U.S. NUCLEAR REGULATORY COMMISSION 91cENSEE EVENT REPORT e

CONTROL BLOCK: !--_._ _

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LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T 02]

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~~~~~~ ~©I oi s I o I o I o I 2 I 7 12 101 o I 4 I 214 I 7 60 61 DOCKET NUMBER 68 69 EVENT DATE 91@1ol3I217 1 s lo 10 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

[QJ]J I During the refueling outage, on April 24 and May 8, 1979, Public Service Relay Department was performing relay tests and de-energized the vital bus supplying the operating RHR Pump.

The operations shift was aware of the work being conducted and in each case restored RHR within 4 minutes.

On June 30, 1979, the level in the reactor vessel was lowered to 1 inch above the low level limit to support plant

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I maintenance.

The RHR Pump started to lose suction and was secured.

The level was [2JIJ I raised 6 inches and RHR flow was restored.

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SYSTEM CODE I c IF I@

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LE R 'RO LVENT YEJl.R

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REPORT I 7 J 9 J NUMBER 21 22

CAUSE

CAUSE CODE SU8CODE COMPONENT CODE lEJ@ ~@ I zl zl zl zj zj z I~

11 12 13 18 SEQUENTIAL OCCURRENCE REPORT NO.

CODE I 0 I 5 I 9 1 I......-1 I 0 I 3 I 23 24 26 27 28 29 COMP.

SUBCODE LI@

19 REPORT TYPE

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30 VALVE SUBCODE

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20 REVISION NC.

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32 80 ACTION FUTURE EFFECT SHUTDOWN

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ATTACHMENT NPRD-4 TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM ::,UB.

31 PRIME COMP.

SUPPL I ER COMPONENT MANUFACTURER

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

43 44 47 I The cause of the April 24 and May 8, 1979 occurrences was inadequate work procedures which have been corrected.

The low level limit which caused the RHR Pump to lose III1:J suction on June 30, 1979, has been raised 5 inches above the previous low level.

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I The new low level provides sufficient suction to the RHR Pump.

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FACILITY f30\\

STATUS

% POWER OTHER STATUS ~

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N_/A __

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ACTIVITY CONTENT Q\\

RELEASED OF RELEASE AMOUNT OF ACTIVITY l2:liJ w@ ~@I N/A 7

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10 11 80 7

METHOD OF t::::,..

DISCOVERY DISCOVERY DESCRIPTION

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N/A 44 45 80 PERSONNEL EXPOSURES

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NUMBER f-::;\\ TYPE

DESCRIPTION

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9 11 12 13 80 PERSONNEL INJURIES Q

NUMBER DESCRIPTION6

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9 11 12 80 LOSS OF OR DAMAGE TO FACILITY f'43\\

TYPE

DESCRIPTION

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N/A [2EJ ~

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PUBLICITY

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ISSUEDQDESCRIPTION ~

NRC USE ONLY ITTIJ W6 N A I I I I I I I I I I I I I ~

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