05000272/LER-1980-008-03, /03L-0:on 800129,maint Was Performed on Inboard Containment pressure-vacuum Relief Valve lVC6 Using nonsafety-related Procedures & Nonqualified Parts.Caused by Omission on List of safety-related Control Valves

/03L-0:on 800129,maint Was Performed on Inboard Containment pressure-vacuum Relief Valve lVC6 Using nonsafety-related Procedures & Nonqualified Parts.Caused by Omission on List of safety-related Control Valves

ML18081B074
Person / Time
Site:	Salem
Issue date:	02/15/1980
From:	Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18081B070	List: 05000272/LER-1980-008, Forwards LER 80-008/03L-0 05000272/LER-1980-008-03, /03L-0:on 800129,maint Was Performed on Inboard Containment pressure-vacuum Relief Valve lVC6 Using nonsafety-related Procedures & Nonqualified Parts.Caused by Omission on List of safety-related Control Valves
References
LER-80-008-03L, LER-80-8-3L, NUDOCS 8002200568
Download: ML18081B074 (3)

LER-1980-008, /03L-0:on 800129,maint Was Performed on Inboard Containment pressure-vacuum Relief Valve lVC6 Using nonsafety-related Procedures & Nonqualified Parts.Caused by Omission on List of safety-related Control Valves

Event date:
Report date:
2721980008R03 - NRC Website

text

v Report Number:

Report Date:

Occurrence Date:

80-08/03L 2/15/80 1/29/80

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Facility:*

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

Non-Safety Related Procedures Applied to Safety Related Equipment CONDITIONS PRIOR TO OCCURRENCE:

Modes 1, 2, 3, 4, 5 and 6 DESCRIPTION OF OCCURRENCE:

During January 1979, maintenance was performed on 1VC6, inboard 10" containment pressure-vacuum relief valve, using non-safety related procedures and non-qualified parts.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

An investigation indicates that 1VC6 was incorrectly classified as a non-safety related control valve on the safety related equipment list (our Reference Project Directive 7).

ANALYSIS OF OCCURRENCE:

Valve 1VC6 was designated as a safety related component during the design and construction phas.e of Salem Unit No. 1.

There is proper documentation that the valve was purchased and installed as safety related equipment.

The engineering disciplines in subsequently compiling the list of control valves, in an apparent oversight, did not classify 1VC6 as a safety related control valve.

During January 1979, maintenance was performed on the valve using non-safety related parts and procedures.

Subseqeunt testing of the valve, after the maintenance, verified that the valve performed its intended function as required.

During the recent refueling outage, the valve was damaged while attempting to block it in the open position during performance of the integrated leak rate test.

The valve was removed and subse-quently sent to the manufacturer.

In examining the valve, the manufacturer identified the extent of damage done during the integrated leak rate test and discovered that the parts used in our maintenance work, presumably during January 1979, were not the same as those originally furnished.

They then notified Publip Service.

An investigation was initiated to determine the cause of the incorrect parts being used.

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• LER 80-08/03L CORRECTIVE ACTION:

Due to the work being done by the manufacturer on the Unit No. 1 valve, the Unit No. 2 valve was put in its place.

The Unit No. 2 valve has had no corrective maintenance performed on it and, there-fore, remains a fully qualified safety related valve.

The original Unit No. 1 valve is being restored to a fully qualified condition by the manufacturer and will be placed in Unit No. 2.

As corrective action for the oversight in incorrectly classifying the valve, the Engineering Department is currently reviewing all safety related control valves to confirm the accuracy of their classification.

If any discrepancies materialize, the station personnel will review maintenance records and take the necessary corrective action to ensure that all components are fully qualified.

The Salem Master Equipment List will be revised to indicate the correct classification of equipment.

FAILURE DATA:

Not Applicable Prepared By P. Moeller Manager 2 Salem Generating Station SORC Meeting No.

12-80

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NRC£._c;>RM_~6 e LICENSEE EVENT REPORT U.S. NUCLEAR REGULATORY COMMISSION (7-i'71

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(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) lTI!] INIJISIGlsl 110101 01010 Iola Iola lol ololG)l411l1l 1l1l©I I 10 7

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LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T filTI 7

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[)))) I The inboard 10" containment pressure-vacuum relief valve, 1VC6, was repaired in January 1979, maintenance was performed using non-safety related procedures and [QJ1] I non-qualified parts.

During the recent refueling outage, the valve was damaged and sent to the manufacturer for repairs.

During the manufacturer's repairs, he

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identified parts were used that were not the same as those originally furnished.

[£]1J I Between our repairs and the manufactuer's, the valve had been tested satisfactorily.f

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CAUSE

CAUSE CODE SUBCODE COMPONENT CODE

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

42 43 44 47 DJ)) I The valve, 1VC6, due to an apparent oversight was not listed as a safety related control valve.

During January 1979, it was repaired with non-safety related parts and procedures.

The Unit 2 valve was used as a replacement and it has not had o:r::IJ I corrective maintenance, therefore, maintaining its qualification.

Engineering is [III] I reviewing all systems for proper valve classification and any discrepancies will be 1

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