05000272/LER-1981-055, Forwards LER 81-055/03L-0.Detailed Event Analysis Encl

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Forwards LER 81-055/03L-0.Detailed Event Analysis Encl
ML20005B074
Person / Time
Site: Salem PSEG icon.png
Issue date: 06/19/1981
From: Uderitz R
Public Service Enterprise Group
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20005B075 List:
References
NUDOCS 8107060287
Download: ML20005B074 (3)
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LER-1981-055, Forwards LER 81-055/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
2721981055R00 - NRC Website
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text

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PSEG Pubhc Service Electric and Gas Company 80 Park Plaza Newar k, N.J. 07101 Phone 201/430-7000 June 19, 1981 Mr. Boyce H. Grier Director of USNRC Office of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 81-55/03L Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1, we are submitting Licensee Event Report for Reportable Occurrence 81-55/03L.

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

Sincerely yours, cs

/

R. A. Uderi-t$

General Manager -

Nuclear Production CC:

Director, Office of Inspection and Enforcement (30 copies)

Director, Office of Management Information and Program Control (3 copies) j s. t t

8107060287 810619 PDR ADOCK 05000272 S

PDR

~. :

a R port Nu:.ber:

81-55/03L R: port Date:

June 19, 1981 Occurrence Date:

5/21/81 Fccility:

Salem Generating Station, Unit 1 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Loss of #12 & 22 Station Power Transformers CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 - Reactor Power 28% - Unit Load 300 MW DESCRIPTION OF OCCURRENCE:

Action Statement 3.8.1.la was entered at 0836 on May 21, 1981 when the No. 3 Unit Generator Breaker was manually closed while in the test position.

The closure of this breaker in the test position caused the inadvertent breaker closure relay protection to trip the No. 12 and No. 22 Station Power Transformers.

The loss of the Transformers resulted in less than the minimum offsite A.C. electrical power sources required by the Technical Specifications.

The reactor was tripped automatically as a result of loss of flow in No. 13 and No. 14 Reactor Coolant Icop.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

Design deficiency.

Operation of the No. 3 Unf.t Generator Breaker for mnintenance testing while the breaker was in the test position caused the loss of Nu. 12 and No. 22 Station Power Transformers.

The inadvertent breaker closure circuit for No. 3 Unit was designed to allow testing of the relay protection with the generator in the test position.

(

ANALYSIS OF OCCURRENCE:

l l

Technical Specification 3.8.1.1 requires that with either an offsite circuit or diesel generator of the required A.C. electrical power sources inoperable, demonstrate the operability of the remaining A.C. sources by performing Surveillance Requirements 4. 8.1.1.1.a and 4. 8.1.1. 2.a. 2 within i

one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, restore at least two l

offsite circuits and three diesel generators to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

e 6/19/81 LER 81-55/03L.

CORRECTIVE ACTION

The power was restored to No. 12 and No. 22 Station Power Transformer at 0918 on May 21, 1981 and Action Statement 3.8.1.la was terminated at this time.

A Design Change Request (lSC-0577) has been initiated to modify the breaker protection scheme to prevent recurrence of this incident.

A caution tag hna also been affixed to the breaker to instruct the operator not to manually close, the No. 3 Unit Generator Breaker in the test position.

In addition, Operating Memo OM-5 was revised to explain the above precaution.

FAILURE DATA:

Not Applicable Prepared By J. J.

Espey

/ %-

'M ager'- Salem' Generating Station SORC Meeting No.

81-50 l

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