05000311/LER-1981-042, Forwards LER 81-042/03L-0.Detailed Event Analysis Encl

Forwards LER 81-042/03L-0.Detailed Event Analysis Encl

ML20009G119
Person / Time
Site:	Salem
Issue date:	07/09/1981
From:	Uderitz R Public Service Enterprise Group
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20009G120	List: 05000311/LER-1981-042, Forwards LER 81-042/03L-0.Detailed Event Analysis Encl 05000311/LER-1981-042-03, /03L-0:on 810609,RCS Allowed to Decrease to Less than 541 F.Caused by Overfeeding Steam Generators & Inserting Control Rods.Control Rods Withdrawn & Personnel Counseled on Plant Procedures & Practices
References
NUDOCS 8108030345
Download: ML20009G119 (3)

LER-1981-042, Forwards LER 81-042/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
3111981042R00 - NRC Website

text

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O PSEG Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 Phone 201/430-7000 i

July 9, 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-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 81-42/03L 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 81-42/03L.

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

Sincerely yours,

,ff,

R.

A.

der.itt j

Generel Manager -

Nuclear Production CC:

Director, Office of Inspection hh and Enforcement (30 copies)

Director, Office of Management Information and Program Control l

(3 copies)

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8108030345 810709 i

PDR ADOCK 05000311 S

PDR The Energy People 95 2001 (400M) 181

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l Report Number:

81-42/03L Report Date:

July 9, 1981 Occurrence Date:

6-9-81

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Facility:

Salem Generating Station, Unit 2 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 I

IDENTIFICATION OF OCCURRENCE:

)

Reactor Coolant Temperature Less Than Minimum Required For Power Operation.

This report was initiated by Incident Report 81-183.-

CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 - Rx Power 6% - Unit Load 0 MWe DESCRIPTION OF OCCURRENCE:

1 j

During a turbine generator startup, at 1223 hours0.0142 days <br />0.34 hours <br />0.00202 weeks <br />4.653515e-4 months <br />, June 9,

1981, Reactor Coolant system temperature was allowed to decrease to less than 541*F.

The decrease in temperature was due to the overfeeding of the steam generators while attempting to restore them to the normal operating level.

In order to restore temperature, control rods were withdrawn and the Reactor Coolant System temperature was restored to greater than 541*F at 1236 nours.

Action Statement 3.1.1.4 was entered at 1223 hours0.0142 days <br />0.34 hours <br />0.00202 weeks <br />4.653515e-4 months <br /> and terminated at 1236 hours0.0143 days <br />0.343 hours <br />0.00204 weeks <br />4.70298e-4 months <br />.

This occurrence constituted operation in a degraded mode in accordance with Technical Specification 6.9.1.9.b.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

l Personnel error.

While performing the turbine start-up, the steam generator levels were inadvertently allowed to decrease to the low level set point.

The operator then started to increase steam generator levels to restore them to normal.

The restoration of steam generator levels caused Reactor Coolant System temperature to decrease to less than 541*F.

ANALYSIS OF OCCURRENCE:

With a Reactor Coolant System operating loop temperature (Tavg) less j

than 541 F, restore Tavg to within it's limit within 15 minutes or be

{

in Hot Standby within the next 15 minutes.

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'd July 9, 1981 LER 81-42/03L

CORRECTIVE ACTION

Reactor Coolant system temperature was restored by withdrawing control rods.

The personnel involved in the startup were counseled on plant operating procedures and practices.

FAILURE DATA:

None Prepared By J.

J.

Espey I. (

2' c c. oW Manager'- Sdlem Generating Station SORC Meeting No.

81-59