05000272/LER-1980-007, Forwards LER 80-007/03X-2.Detailed Event Analysis Encl

Forwards LER 80-007/03X-2.Detailed Event Analysis Encl

ML18086A513
Person / Time
Site:	Salem
Issue date:	05/04/1981
From:	Uderitz R Public Service Enterprise Group
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18086A514	List: 05000272/LER-1980-007, Forwards LER 80-007/03X-2.Detailed Event Analysis Encl 05000272/LER-1981-007-03, /03X-2:on 800128,during Review of Sys Diagrams, Demineralized Water Supply Check Valve to Auxiliary Feedwater Storage Tank 1DR7 Found to Be Not Seismically Qualified.Caused by Design Deficiency.Valve Qualified
References
NUDOCS 8105190181
Download: ML18086A513 (3)

LER-1980-007, Forwards LER 80-007/03X-2.Detailed Event Analysis Encl

Event date:
Report date:
2721980007R00 - NRC Website

text

J

-. PS~G Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 Phone 201/430-7000 May 4, 1981 Mr. Boyce H. Grier Director of USNRC 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 80-07/03X-2 SUPPLEMENTAL REPORT Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1, we are submitting supple-mental Licensee Event Report for Reportable Occurrence 80-07/03X-2.

Sincerely yours,

. /

/f ~~f R. A. Uderid General Manager -

Nuclear Production CC:

Director, Office of Inspection and Enforcement (30 copies)

Director, Office of Management Information and Program Control

( 3 copies)

*-.-*,. -*. ;

• ::* (: -:- :--, : =-

Report Number:

80-07/03X-2 Report Date:

May 4, 1981 Occurrence Date:

1/28/80 Facility:

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

Check Valve 1DR7 Failure to Meet Intended Design CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 Reactor Power 98%

DESCRIPTION OF OCCURRENCE:

On January 28, 1980, Public Service Engineering Department identified 1DR7, Demineralized Water Supply Check Valve to the Auxiliary Feed-water Storage Tank (AFST) as not being seismically qualified.

The AFST was declared inoperable at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> (TS 3.7.1.3) and the Demineralized Water Storage Tank was verified as a backup water supply.

A seismic test of 2DR7, an identical valve, was performed by the Franklin Institute Research Laboratory in Philadelphia, Pennsylvania, to IEEE Standard 344-1975.

No physical failure was observed to have occurred to the valve due to the seismic test.

In order to duplicate test conditions, a pipe brace was added to the system.

The Action Statement was terminated at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on February 1, 1980.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

During an engineering review of the system diagrams, it was discovered that 1DR7 was not seismically qualified.

This valve. had been changed in 1970 from an auxiliary feedwater valve to a demineralized water supply valve placing it outside the boundary of seismic piping.

It was determined this was an error and resulted in a design deficiency.

ANALYSIS OF OCCURRENCE:

The design deficiency could have resulted in draining the AFST in the event of a seismic occurrence if the non-safety related valve boundary was breached.

CORRECTIVE ACTION

A valve of the same design was seismically tested and was able to withstand seismic levels which enveloped the Required Respo~se Spectrum as required for biaxial testing by IEEE Standard 344-1975.

LER 80-07/03X-2 2 -

5/4/81 A pipe brace was installed because test conditions could not duplicate actual plant conditions.

The added brace, therefore, allowed in-plant and test conditions to be equivalent.

Further review by the Engineering Department determined that the shake test of the valve type and the additional support that was seismically analyzed provide the necessary assurance that the situation was acceptably resolved.

A safety evaluation to review each plant system for a possible design deficiency similar to this was completed on January 26, 1981.

No other similar design deficiency was found.

Hence, no further corrective action is required.

FAILURE DATA:

Not Applicable Manager -

Salei1lGenerating Station Prepared By W. J. Steele SORC Meeting No.

81-30