05000311/LER-1982-148, Forwards LER 82-148/03L-0.Detailed Event Analysis Encl

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Forwards LER 82-148/03L-0.Detailed Event Analysis Encl
ML20064F261
Person / Time
Site: Salem 
Issue date: 12/30/1982
From: Midura H
Public Service Enterprise Group
To: Haynes R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20064F262 List:
References
NUDOCS 8301060292
Download: ML20064F261 (3)
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LER-1982-148, Forwards LER 82-148/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
3111982148R00 - NRC Website
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text

.

'O PSEG

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Public Service Electric and Gas Company P.O. Box E Har> cocks Bridge, New Jersey 08038 Salem Generating Station December 30, 1982 t

Mr.

R.

C.

Haynes Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Haynes:

LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 82-148/03L i

Pursuant to the requirements of Salem Generating Station Unit No.

2, Technical Specifications, Section 6.9.1.9.b, we are submitting Licensee Event Report for Reportable Occurrence 82-148/03L.

This report is required within thirty (30) days of the occurrence.

Sincerely yours, p

J. Midura General Manager -

Salem Operations RF:ks CC:

Distribution 8301060292 621230 PDR ADOCK 05000311 S

PDR The Energy People pW 95 2189 (20M) 1181

]

~

Report Number:

82-148/03L Report Date:

12-22-82 Occurrence Date:

12-08-82 Facility:

Salem Generating Station Unit 2 Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

I Reactor Trip and Engineered Safety Feature Actuation System Instrumentation - No. 21 Steam Generator Level Channel II -

Inoperable.

This report was initiated by Incident Report 82-508.

CONDITIONS PRIOR TO OCCURRENCE:

Mode.1 - RX Power 82 % - Unit Load 910 MWe.

DESCRIPTION OF OCCURRENCE:

At 1106 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.20833e-4 months <br />, December 8, 1982, during routine operation, the Control

. Room Operator observed a No. 21 Steam Generator Program Deviation i

alarm.

Inspection of the control indication revealed that No. 21 Steam Generator Level Channel II had failed and was reading off scale high.

The high indication caused an automatic decrease in feedwater flow, and actual steam generator level started to decrease.

Control l

was immediately shifted to the manual mode, and the level was restored to normal.

Channel II was declared inoperable, and Limiting i

(-

Conditions for Operation 3.3.1 Action 7 and 3.3.2 Action 14 were entered.

All bistables associated with the channel were placed in the l

tripped condition at 1145 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.356725e-4 months <br />, December 8, 1982.

The redundant

(

steam generator level channels were operable throughout the occurrence.

APPARENT CAUSE OF OCCURRENCE:

Investigation revealed that the failure of the channel was due to leakage past the packing of Instument Root Valve 21BF23.

The resulting decrease in sensing line pressure caused the indicated level i

to increase.

A previous, similar problem with the valve occurred on July 16, 1982 (See LER 82-061/03X-1).

ANALYSIS OF OCCURRENCE:

l The steam generator level. instruments are utilized in the Reactor Trip l

and Engineered Safety Feature Actuation Systems.

A reactor trip on f

low steam generator level insures a minimum DNBR of 1.30 during normal l

operation and anticipated transients.

Automatic initiation of auxiliary feedwater flow insures that the Reactor Coolant System can i

be cooled down to less than 350 F in the event of a total loss of offsite power.

l

LdR 82-148/93L '

ANALYSIS OF OCCURRENCE: (cont'd)

Due to the operability of the redundant channels, the event involved no risk to the health and safety of the public.

The occurrence constituted operation in a degraded mode permitted by a limiting condition for operation.

As such, the incident is reportable in accordance with Technical Specification 6.9.1.9b.

Limiting Conditions for Operation 3.3.1 Action 7 and 3.3.2 Action 14 require:

With the number of operable channels one less than the total number of channels, power operation may proceed until performance of the next required channel functional test, provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

1

CORRECTIVE ACTION

As noted, the bistables associated with the channel were placed in the tripped condition, in compliance with the action statements.

Control of steam generator level was restored to the automatic mode utilizing an alternate level channel.

The root valve was repacked and the leakage was stopped.

To provide an additional pressure boundary, the valve was placed on the backseat.

No. 21 Steam Generator Level Channel II was returned to service and satisfactorily tested.

The channel was declared operable, and at 1748 hours0.0202 days <br />0.486 hours <br />0.00289 weeks <br />6.65114e-4 months <br />, December 11, 1982,. Limiting Conditions for Operation 3.3.1 and 3.3.2 Actions 7 and 14 were terminated.

Due to the recurrence of the packing leakage, disassembly and inspection of the valve is scheduled for the next refueling outage.

Appropriate measures to correct any problems discovered will be implemented at that time.

FAILURE DATA:

Rockwell-International 3/4" Globe Valve Type 3624, Mark FA-99 H' h

/).l^~s,2 -

y.

/h Prepared By R.

Frahm l/

Genera'l Manager -

Salem Operations SORC Meeting No.82-113

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