05000272/LER-1980-062, Forwards LER 80-062/03L-0

Forwards LER 80-062/03L-0

ML18085A474
Person / Time
Site:	Salem
Issue date:	01/02/1981
From:	Underitz R Public Service Enterprise Group
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18085A475	List: 05000272/LER-1980-062, Forwards LER 80-062/03L-0 05000272/LER-1980-062-03, /03L-0:on 801204,during Refueling Outage,Leakage Rate of 15 Containment Isolation Valves Exceeded Tech Spec Limits.Caused by Inadequate Test Equipment.Valves Cleaned & Internals Replaced
References
NUDOCS 8101090698
Download: ML18085A474 (2)

LER-1980-062, Forwards LER 80-062/03L-0

Event date:
Report date:
2721980062R00 - NRC Website

text

.-:...

.i

• /

.._j /'

e PS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /430-7000 Mr. Boyce H. Grier Director of USNRC January 2, 1981 Off ice 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 80-62/03L

')

C..;:.

2 ce

• Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1, we are submittin0 Licensee Eyent Report for Reportable Occurrence 8U-62/03L.

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

Sincerely yours, A11t.1~*~ I' R. A. Uderitz General Manager -

Nuclear Production CC:

Director, Office of Inspection and Enforcement (30 copies)

Director, Office of Management Information and Program Control (3 copies) o<;.)001 (200M)

Repo;i::t Number:

Report Date:

so-903L Ol/02/Bl.

Occurrence Date:

12/04/80 Facility:

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

Initial Containment Type C Leak Rate Test Results Exceeded Technical Specification Requirement CONDITIONS PRIOR TO OCCURRENCE:

.Operational Modes 1 through 6 DESCRIPTION OF OCCURRENCE:

While conducting scheduled leak rate testing of Type C components, initial test results for fifteen containment isolation valves indicated a leakage rate greater than the maximum range (2000 seem) of the volumetric test equipment.

Since the actual leak rate could not be ascertained, it was not possible to verify that the total containment leakage volume did not exceed the value assumed in the accident analysis at the peak accident pressure.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

This occurrence resulted from the use of inadequate test equipment.

ANALYSIS OF OCCURRENCE:

.T.echnical Specification 3. 6.1. 2 requires the me.a sured combined leakage rate for all penetrations and valves subject to type B and C tests to be less than 0.60 La prior to increasing the Reactor Coolant System temperature above 200°F.

The measured overall leakage rate limit of 0.60 La during performance of periodic tests is an added conservatism to account for possible degradation of the containment leakage barriers between leakage rate tests.

Valves with excessive leak rates have been repaired with the plant in Modes 5 and 6.

CORRECTIVE ACTION

Initial test leakage for 1FP147, 1NT25, and 1NT26 was found to be through the test boundary valves, not the referenced isolation valves.

Cleaning the internals of valves 1WR81, lVCS and 1NT34 corrected their excessive leakage.

Valves 1CV284, 1CC113, 1CC215, 1SS10*7, 1SS49, 1NT32, 11GB4, 13GB4 and 14GB4 required the reworking of their internals to reduce their excessive leakage.

FAILURE DATA:

Not Applicable Manager ~ Sa.1.em Gnerating Station Prepared By W. J. Steele SORC Meeting No.

111-80

.1