05000272/LER-1981-069, Forwards LER 81-069/03L-0.Detailed Event Analysis Encl

From kanterella
(Redirected from ML20010A583)
Jump to navigation Jump to search
Forwards LER 81-069/03L-0.Detailed Event Analysis Encl
ML20010A583
Person / Time
Site: Salem PSEG icon.png
Issue date: 07/31/1981
From: Uderitz R
Public Service Enterprise Group
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20010A584 List:
References
NUDOCS 8108110574
Download: ML20010A583 (3)
v • d • e


LER-1981-069, Forwards LER 81-069/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
2721981069R00 - NRC Website
v • d • e

text

\\

LEA

.O PSEG Public Service Electric anri Gas Company 80 Park Plaza Newark, N.J. 07101 Phone 201/ '0-7000 July 31, 1981 M 'I/t.o

(>\\,' ' f M

Mr. Boyce H. Grier

)g g\\

Director of USNRC b[.UL,1.

J office of Inspection and Enforcemen?

/

Region 1 631 Park Atenue (9

,'iUG 101981 > g King of Prussia, Pennsylvania 19406 u.s.tu ata,, g s k' &

/

Dear Mr. Grier:

4 %

to W

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 81-69/03L Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Sectioh 6.9<l.9.b, we are submitting Licensee Event Report for Reportable Occurrence 81-69/03L.

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

Sincerely yours, C

/

ff R.

A.

Uderit2 General Manager -

Nuclear Production CC:

Director, Office of Inspection and Enforcement (30 copier:)

Director, Office of Management Information and Program Control (3 copies 8108110574 810731 PDR ADOc% 05000272 S

PDR The Energy People 95 2001 (400M1181

~

Report Number:

81-69/03L Report Date:

July 31, 1981 Occurrence Date:

7-3-81 F;:cility:

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

Flow Control Valve, Component Cooling Water Heat Exchanger - Inoperable.

This report was initiated by Incident Report 81-231.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 - Rx Power 97% - Unit Load 1040 MWe DESCRIPTION OF OCCURRENCE:

On July 3, 1981, while trying to adjust service water flow through No. 12 component cooling water heat exchanger (CCW Hx), the operator noticed that flow control valve 12SW127 would not open.

The valve was declared inoperable, and action statements 3.7.3.1 and 3.5.2.a were entered at 0420 hours0.00486 days <br />0.117 hours <br />6.944444e-4 weeks <br />1.5981e-4 months <br />, July 3, 1981.

This occurrence constituted operation in a degraded mode in accord-ance with technical specification 6.9.1.9.b.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

The flow control valve is a Fisher Vee-Ball valve, which utilizes a hollow ball sealing against the open end of a tube bundle with a smooth, curved sealing surface.

This sealing surface was marred, restricting movement of the valve.

ANALYSIS OF OCCURRENCE.

Technical specification 3.5.2.a requires:

With one ECCS Subsystem inoperable, restore the inoperable subsystem to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Technical specification 3.7.3.1 requires:

With only one component cooling water loop operable, restore at leact two loops to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 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 />.

LER 81-69/03L 7/31/81

CORRECTIVE ACTION

No. 11 CCW Hx was placed in service, and No. 12 CCW Ux removed from service.

Valve 12SW127 was dLsassembled, and the tube bundle was cut back to remove the marred surface, and allow free operation.

The valve was reassembled, tested satisfactorily, and returned to service.

Action statements 3.7.3.1 and 3.5.2.a were terminated at 0250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br />, July 4, 1981.

The valve manufacturer is being contacted for further evaluation.

A supplemental report will be issued.

F_AILURE DATA:

Ficher Controls Co.

Fisher Control Valve - 16" Type 478-6-16-U-CAV5 lblffb

'l Prepared By F.

Dickey 4 +tA$L -

Man 6 der - Salem Generating Station SORC Meeting No.

81-69

Retrieved from "https://kanterella.com/w/index.php?title=05000272/LER-1981-069,_Forwards_LER_81-069/03L-0.Detailed_Event_Analysis_Encl&oldid=4650062"