05000272/LER-1982-071, Forwards LER 82-071/04L-0.Detailed Event Analysis Encl

Forwards LER 82-071/04L-0.Detailed Event Analysis Encl

ML20063N945
Person / Time
Site:	Salem
Issue date:	09/22/1982
From:	Midura H Public Service Enterprise Group
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20063N946	List: 05000272/LER-1982-071, Forwards LER 82-071/04L-0.Detailed Event Analysis Encl 05000272/LER-1982-071-04, /04L-0:on 820827,control Operator Discovered Increasing Level on Plant Vent Radioactivity Monitor & Issued Significant Event Notifications for Unplanned Releases.Caused by Primary Coolant Leakage from RCS Filter
References
NUDOCS 8210070380
Download: ML20063N945 (3)

LER-1982-071, Forwards LER 82-071/04L-0.Detailed Event Analysis Encl

Event date:
Report date:
2721982071R00 - NRC Website

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' Pu'blic Service Electric and Cas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station September 22, 1982 Mr.

R. C. Hayncs Regional Administrator US N'/.C Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Haynes:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 82-071/04L Pursuant to the requirements of Salem Generating Station Unit No.

1, Environmental Technical Specifications, Section 5.6.2.3.3, we are submitting Licensee Event Report for Reportable Occurrence 82-071/04L.

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

Sincerely yours, H.

J. Midura General Manager -

Salem Operations RF:ks d%

CC:

Distribution e' 8210070380 820922

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l PDR ADUCK 05000272 8

PDR x

The Energy People 6

E2189 (20M) 11-81

V Report Number:

32-071/04L Report Date:

09-22-82 Occurrence Date:

08-27-82 Facility:

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

Unplanned Gaseous Release Due To Reactor Coolant System Filter Leak.

This report was initiated by Incident Report 82-268.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 - Rx Power 50% - Unit Load 530 MWe.

DESCRIPTION OF OCCURRENCE:

At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, August 27, 1982, during routine operation, the Control Room Operator discovered an increasing level on the Plant Vent Radioactivity Monitor 1R16.

Activity continued to increase and significant event notifications for an un-planned release were made in accordance with Emergency Procedure EPI-l Attachment 3.

A leak on the gas space of the Volume Control Tank (VCT) was suspected.

VCT pressure was lowered by decreasing the hydrogen pressure, in order to reduce the leakage; radioactivity levels on Monitor 1R16 decreased from 100k CPM to 60k CPM.

An attempt to identify the source of leakage on the VCT using a hydrogen detector failed, however.

The Reactor Coolant System (RCS) leak rate was determined to be within specification.

While changing the VCT valve lineup to further reduce tank pressure, leakage was discovered emanating from the RCS filter.

The filter was bypassed, and radioactivity levels decreased, confirming that the leak was the source of the activity.

The total amount of the release was calculated to be 46.8 Ci of noble gas, which is within the limits of the Environmental Technical Specifications (ETS).

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

The RCS filter had recently been changed.

Due to a combination of procedural inadequacy and personnel error, the filter cover was not properly reinstalled, resulting in primary coolant leakage and the unplanned release.

LER 82-071/04L.

ANALYSIS OF OCCURRENCE:

The ETS limits for the discharge of gaseous radioactive effluents-insure that the concentrations and doses to individuals in un-restricted areas-are within the limits of 10CFR20.

As noted, these limits were not exceeded, and the incident consequently involved no risk to the health of the public or adverse environ-mental impact.

Since the release was unplanned and in excess of 5 Ci, however, the occurrence is reportable in accordance with ETS Section 5.6.2.3.3.

CORRECTIVE ACTION

As noted, the release was terminated by isolating the RCS Filter.

The cover on the filter was reinstalled properly and the leakage was stopped.

Personnel who had changed the filter were counseled concerning the incident and proper installation of the filter cover.

The procedure for plant filter replacements has been separated into more detailed, separate procedures for each filter.

Torque values for filter cover nuts are specified in the individual procedures;. the procedures are presently in the review process.

FAILURE DATA:

Not Applicable.

i Prepared By R. Frahm 4

'l Gederal Manager -

Salem Operations SORC Meeting No.

82-85 l

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