05000272/LER-1980-068-03, /03L-0:on 801220,leak Rate on 100-foot Containment Air Lock Exceeded Tech Spec Limit.Caused by Failure of Inner Door Seals to Maintain Pressure.Seals Adjusted & Tested

/03L-0:on 801220,leak Rate on 100-foot Containment Air Lock Exceeded Tech Spec Limit.Caused by Failure of Inner Door Seals to Maintain Pressure.Seals Adjusted & Tested

ML18085A527
Person / Time
Site:	Salem
Issue date:	01/14/1981
From:	Steele W Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18085A528	List: 05000272/LER-1980-068, Forwards LER 80-068/03L-0 05000272/LER-1980-068-03, /03L-0:on 801220,leak Rate on 100-foot Containment Air Lock Exceeded Tech Spec Limit.Caused by Failure of Inner Door Seals to Maintain Pressure.Seals Adjusted & Tested
References
LER-80-068-03L, LER-80-68-3L, NUDOCS 8101200391
Download: ML18085A527 (4)

LER-1980-068, /03L-0:on 801220,leak Rate on 100-foot Containment Air Lock Exceeded Tech Spec Limit.Caused by Failure of Inner Door Seals to Maintain Pressure.Seals Adjusted & Tested

Event date:
Report date:
2721980068R03 - NRC Website

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PS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /430-7000 January 14, 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 80-68/03L

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Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1, we are submitting Licensee Event Report for Reportable Occurrence 80-68/03L.

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

Sincerely yours,

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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) mo:J-rn1s r:l 11':\\RSOI' St:ll\\lCE 95-2001 (200M) 2-78

Repo~t Number:

80-68/03L

• ~eport Date:

Jinuary 14, 1981 Occurrence Date:

12/20/80 Facility:

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

Containment Air Lock Inoperable CONDITIONS PRIOR TO OCCURRENCE:

Mode 3 DESCRIPTION OF OCCURRENCE:

While performing a routine surveillance SP(O) 4.6.1.3 of the 100' Containment Air Lock, it was determined the leak rate exceeded its Technical Specification limit of 0.05 La at a design pressure of 47.0 psig.

At 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br />, Action Statement 3.6.1.3 was entered which requires with an air lock inoperable, restore the air lock to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

The inner door seal would not hold pressure.

ANALYSIS OF OCCURRENCE:

Upon investigation, it was determined the inner door seal had popped out of its channel and so could not maintain pressure.

CORRECTIVE ACTION

The seals on the inner door were adjusted and tested satisfactorily.

Action Statement 3.6.1.3 was terminated at 0537 hours0.00622 days <br />0.149 hours <br />8.878968e-4 weeks <br />2.043285e-4 months <br /> on December 20, 1980.

FAILURE DATA:

Containment Personnel Air Lock Chicago Bridge and Iron Company Prepared By W. J. Steele SORC Meeting No.

81-01 Manager -

Salem Cenertiilg Station

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NRC FORM 366 17-77) u. s. NUCLEAR REGULATORY COMMISSION

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LICENSEE EVENT REPORT

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LICENSEf. CODE 14 15 LICENSE NUMBER 25 2b I i I i I i I i 101 I 10 LICENSE TY~ 30 57 CAT 58 CON'T

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~;~~~~ UJ© I o I s I o I o I o I 2 I 1 I 2 10)11 12 12 Io I a I o 101 o 11 I 1 I 4 I s I i I G) 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

!While performing Surveillance Procedure SP(O) 4.6.1.3 on the 100' Containment

[£J:I) jAir Lock, it was determined that the appropriate Technical Specification limits had

((II] jbeen exceeded.

Action Statement 3.6.1.3 was entered at 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br />.

This is the [Q))J 1eighth occurrence of this type (75-57, 78-80, 79-02, 79-31, 79-75, 80-11, 80-32).

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SYSTEM CODE Is I Al@

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LER/RO CV ENT YEAR

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REPORT I 8 I 0 I NUMBER 21 22

CAUSE

CAUSE CODE SUBCODE COMPONENT CODE ill..J@. w@ I p I E I N I E I T I R I@

11 12 13 18 SEQUENTIAL OCCUR REN CE REPORT NO.

CODE I I I o I 6 I a I I /I Io I 3 I 23 24 26 27 28 29 COMP.

SUB CODE

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20 l.=1 31 ACTION FUTURE EFFECT SHUTDOWN

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ATTACHMENT NPRD-4 PRIME COMP.

SUPPLIER REVISION NO.

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- COMPONENT MANUFACTURER 80 TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM SUB.

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS@

43 44 47 n::m IThe inner door seals would not maintain pressure.

The seals were adjusted and o:IIJ jtested satisfactorily and Action Statement 3.6.1.3 was terminated at 0537 hours0.00622 days <br />0.149 hours <br />8.878968e-4 weeks <br />2.043285e-4 months <br />.

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BO FACILITY STATUS

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• OTHER STATUS METHOD OF DISCOVERY DESCRIPTION @

DISCOVERY

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9 10 12 1'.l ACTIVITY CONTENT

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RELEASED OF RELEASE AMOUNT OF ACTIVITY ~

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10 11 44 45 46 BO LOCATION OF RELEASE @

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PERSONNEL EXPOSURES

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NUMBER A

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9 10 80 PUBLICITY G\\

NRC USE ONLY ISSUEDt,;:;\\ DESCRIPTION~

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w. J. Steele NAME OF PREPARER~~~~~~~~~~~~~~~~~-

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