05000272/LER-2077-033-01, Inoperability of Containment Isolation Valve

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Inoperability of Containment Isolation Valve
ML19031A825
Person / Time
Site: Salem  PSEG icon.png
Issue date: 05/20/1977
From: Schneider F
Public Service Electric & Gas Co
To: O'Reilly J
NRC/IE, NRC Region 1
References
LER 1977-033-01
Download: ML19031A825 (5)


LER-2077-033, Inoperability of Containment Isolation Valve
Event date:
Report date:
2722077033R01 - NRC Website

text

Frederick W. Schneider Vice President Public Service Electric and Gas Company 80 Park Place Newark. N.J. 07101 201/622-7000 Production fJ.i~gulatory Docket File.

Mr. James P. O'Reilly D~rector of USNRC May 20, 1977 Off ice of Inspections and Enforcements Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. O'Reilly:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 77-33/03L 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 77-33/03L.

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

CC:

Director, Office of Inspection and Enforcement (30 copies)

Director, Office of Management Information and Program Control

( 3 copies)

  • Report Number:

Report Date:

Occurrence Date:

Facility:

~33/03L 5/10/77 4/29/77 Salem Generating Station Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Inoperable Containment Isolation Valve 1CV68 (CVCS - Charging Line Isolation Valve).

CONDITIONS PRIOR TO OCCURRENCE:

Operational Mode 3 DESCRIPTION OF OCCURRENCE:

At 1625 hours0.0188 days <br />0.451 hours <br />0.00269 weeks <br />6.183125e-4 months <br /> on 4/29/77, valve 1CV68 was declared inoperable due to it being stuck in the shut position.

Action Statement 3.6.3.l(b) was imple-mented and 1CV69 (Series eves - Isolation) was shut and de-activated.

Investigation by Maintenance personnel revealed that the motor operator was burned up.

Investigation into the operator failure revealed that the stern and wedge appeared to be jammed into the valve. The packing was removed and the stern and wedge stroked by hand.

The stern and wedge would not operate smoothly.

A new stern and wedge were installed and stroked by hand.

The valve operation was satisfactory.

A new motor operator was installed and valve stroked electrically.

The testing was satisfactory.

At 0410 on 4/30/77, Action Statement was terminated.

At 0829, the reactor was taken critical and at 0929, the unit entered Mode

1.

At 1300 after reviewing maintenance performed on 1CV68, Station QA informed the Shift Supervisor that a leak rate test had not been per-formed after valve disassembly, as required by Surveillance 4.6.l.2(d).

At 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />, the Shift Supervisor again implemented Action Statement 3.6.3.l(b) and 1CV69 was shut and de-activated.

A leak rate test was performed with unsatisfactory results.

1CV68 was disassembled and the seat to wedge mating surfaces were checked.

Checks showed uneven surface contact.

The wedge that had been previously removed was retrieved for re-installation.

Inspection showed evidence of cracks in the stellite seating surface.

The valve seats appeared to be distorted.

The valve seats were ground and polished.

A second new wedge was obtained from spares and beca~se of seat grinding, was too small. fbr valve se~ts.

A Technical Rep. from Velan Corporation was called to site.

After taking dimensional checks Technical Rep.

ret~rned to home office with valve wedge for rework.

On 5/5/77, Technical Rep. returned to site and in-stalled reworked wedge.

The valve was re-assembled and a leak rate test performed.

The leak rate test was satisfactory.

Action Statement 3.6.3.l(b) was terminated.

Report No. 77-33/03L --

  • 5/10/77 DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

The cause of the motor operator failure was over current.

valve wedge jammed in the closed position, the attempt to valve caused the motor to draw excessive current damaging windings.

With the open the the motor Failure to perform the required leak rate test was caused by failure of maintenance personnel to follow the requirements of procedure Ml6E (Containment Isolation Type B and C Test).

Procedure Ml6E states that "the Maintenance Department is responsible for identifying leak retest requirements for work orders involving maintenance action on items and valves listed in Figures 3 and 4".

Valve 1CV68 is listed on page 1 of Figure 4.

Contrary to this requirement, no retest requirement was placed on the work order and the leak rate test was not performed.

This is a licensee identified item of non-compliance.

ANALYSIS OF OCCURRENCE:

Technical Specification 3.6.3.l(b) requires that in the event of an inoperable containment isolation valve, the affected penetration be isolated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one de-activated automatic isolation valve secured in the isolation position.

1CV69 was shut and de-activated for the term of the Action Statement.

The non-compliance arose when maintenance personnel released 1CV6B to the operations department without performing a leak rate test.

Operations was not aware of this requirement and returned the valve to service.

The unit was taken from Mode 3 to Mode 1 before the non-compliance was identified.

This item is a violation of the Technical Specifications and Maintenance Procedure Ml6E.

CORRECTIVE ACTION

The failed motor operator was replaced from spares.

A new valve stem and wedge were installed.

The valve was leak tested and stroked.

All testing was satisfactory.

Corrective action for failing to perform the leak test is being handled by a series of procedure revisions.

Maintenance Procedure Ml4A, General Instructions for Disassembly, Inspection and Reassembly of Valves, is being revised to include a specific precaution addressing leak testing of valves after reassembly.

A list of valves requiring leak testing is also being included.

Maintenance Procedure M3L, Motor Operated Valve Testing, is being revised to include a similar precaution and list.

Also, Ml4A is being changed to include a specific Shift Supervisor sign off, prior to valve disassebmly.

When procedure revisions are complete, a meeting will be held with all Maintenance Department Supervision to discuss this event and explain

~eport No. 77-33/03L ~

  • 5/10/77 the deiails and reasons for all revisions.

Corrective action should be completed by 5/30/77.

FAILURE DATA:

Valve Motor Operator Manufacturer:

Limitorque SMB-00 Model:

Prepared by~~-T_.~L~*~S~p_e_n_c_e_r~~~

SORC Meeting No.

51-77

~~~~~~~~~

Manager -

Sa i

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1 CONTROL BLOCK L.ICENSEE NAME LICENSEE EVENT REPORT 6

L.IC£NSE NUMBER L.ICENSE TYPE EVENT TYPE REPORT REPORT CATEGORV TYl'E SOURCE OOCKET NUMBER EVENT CATE REPORT CATE ram CON"TlRJ..Qj LlJ l1:!.J I 0 I 5 I 0 I -"I 0 I 2 I 7 l 2 I I 0 I 4 I 2 I 9 17 17 I I 0 15 I 1 l 0 I 7 I ~

57 sa se so 61 sa es 74 15

EVENT DESCRIPTION

@]JI. During Mode 3. 1CV68 (CVCS - Containment Isolation Vlv) was declared in-1 7

89 80

~ o erable.

lCV69, series isolation valve was o erable.

Valve 1CV68 was 7

8 9

@El* returned to service after repairs without required leak rate test. Pro-7 8

@Jill cedures have been revised to include requirement for leak rate test.

7 8 9 (ill]

(77-33/03L) 7 8 9 SYSTEM COCE

@TIJ!SIDI 1

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CAUSE

coce:

l£:.l 11 CAUSE DESCRIPTION COMPONENT COOE I VI Al LIV I E.Jl:U 12 17 P1'11ME COMPONENT SUPPl..IER Lbl 43 COMPONENT MANUFACTURER ILi Z 10 10 I 44 47 VIOLATION LXJ 48 I

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~I Valve being.jammed in shut position caused motor to draw excessive l *

@Jfil' 1 9 current.

Personnel error caused non-compliance to leak rate requirement 1 1

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OFFSITE CONScOUENCES

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