05000311/LER-1981-018, Forwards LER 81-018/03L-0.Detailed Event Analysis Encl

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Forwards LER 81-018/03L-0.Detailed Event Analysis Encl
ML19350E849
Person / Time
Site: Salem PSEG icon.png
Issue date: 06/12/1981
From: Uderitz R
Public Service Enterprise Group
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19350E850 List:
References
NUDOCS 8106230582
Download: ML19350E849 (3)


LER-1981-018, Forwards LER 81-018/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
3111981018R00 - NRC Website

text

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  • PSIEG Pubhc Service Electric and Gas Company 80 Park Plaza Newar k, N.J. 07101 Phone 201/430 7000 June 12, 1981

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Mr. Boyce !!. Grier Director of USNRC

'E u.s, emp2 '*# 7 Office of Inspection and Enforcement S/

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Region 1 A'Qgy p

631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

LTCENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 81-18/03L Pursuant to the requirements of Salem Generating Station Unit No. 2 Technical Specifications, Section 6.9.1, we are submitting Licensee Event Report for Reportable Occurrence 81-18/03L.

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

Sincerely yours, R.

A.

deritz' General Manager -

Nuclear Production CC:

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

Director, Office of Management Information and Program Control (3 copies) 8r106230 %

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Rcoort Nwnoer:

81-18/03L Report Date:

June 12, 1981 Occurrence Date:

5/15/81 Facility:

Salem Generating Station, Unit 2 Public' Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IpENTIFICA22ON 07 OCCURRENCE:

Overpressure Protection System - Channel 2 Activation

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CONDITIONS PRIOR TO OCCURRENCE:

Mode 5 - Rx Power 0% - Unit Load OMW DESCRIPTION OF OCCURRENCE:

While technicians were zeroing the E/P controllers fcr pressurizer spray valves, 2PS1 and 2PS3, pressure in the Reactor Coolant System (RCS) increased from 330 psig to 360 psig.

This occurrence initiated POPS Channel 2 while RCS temperature was at 175'F and a bubble in the pressurizer.

Action Statement 3.4. 9.3c was entered at 14 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> on May 15, 1981 for the activation of the POPS.

This occurrence constituted a special report IAW Technical Specifi-cation 6.9.2.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

Personnel error.

The technicians' supervisor informed them that he would notify the Shift Supervisoc, this was not done prior to commence-

't. tent of the work.

ANALYSIS OF OCCURRENCE:

Work Order #934960 was issued for the calibration of the E/P controllers for valves 2PS1 and 2PS3.

Following normal calibration procedures, these valves were closed, which in turn caused an increase in the Reactor Coolant System pressure.

The pressure increase from 330 psig to 360 psig, initiated the POPS Channel 2 reducing RCS pressure within 45 seconds.

The operation of the POPS within its design parameter prevented the pressure transient from exceeding pressure temperature limitations.

l Technical Specification 3.4. 9.3c requires that in the event the POPS is used to mitigate a RCS pressure transient, a Special Report shall j

be prepared and submitted to the Commission purtuant to Specification 6.9.2 within 30 days.

e LE R "' 81-18/03L 6/12/81

CORRECTIVE ACTION

The Supervisor _was instructed in the proper method of implementing work orders.

Action Statement 3.4. 9.3c was terminiated at 1431 hours0.0166 days <br />0.398 hours <br />0.00237 weeks <br />5.444955e-4 months <br /> on May 15, 1981.

. FAILURE DATA:

Not Applicable Prepared By J.

J. Espey 64un-SORC Meeting No'.

81-47