05000312/LER-1979-008, Forwards LER 79-008/03L-0

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Forwards LER 79-008/03L-0
ML20132A766
Person / Time
Site: Rancho Seco
Issue date: 08/09/1979
From: Mattimoe J
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
NUDOCS 7908200370
Download: ML20132A766 (1)


LER-2079-008, Forwards LER 79-008/03L-0
Event date:
Report date:
3122079008R00 - NRC Website

text

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SMUD 4' SACRAuENTO MUNICIPAL UTILITY OtSTR 95813. (916) 452 3211 August 9, 1979 sc.. ,.

Mr. R. H. Engelken '

C. S. Nuclear Regulatory Commission f [%?'..

s, g g\% 9 g Region V Of fice of Inspection & Enforcement =t"; p -j 1990 North California Boulevard M. '.,U.s~ ~/

Walnut Creek Plaza. Suite 202 M .; , . -

Walnut Creek, CA 94596 '

'.~',..

RE: Operating License DPR-54 Docket No. 50-312 Reportable Occurrence 79-08

Dear Mr. Engelken:

In accordance with Technical Specifications for Rancho Seco Nuclear Generating Station. Section 6.9.4.2d, and Regulatory Guide 1.16 Revision 4 Section C.2.b.4, the Sacramento Hunicipal Utility District is hereby submitting

.s thirty-day report of Reportable Occurrence 79-08.

On July 19, 1979, during the performance of SP 203.0$G !!onthly Decay llcat Remova1 Venting Surveillance, leakage was observed from the outboard seal of the B Decay Heat pump. The leakage was found to be in excess of the 0.63 gph

.allowaole per Technical Specifications Section 4.5.3.1. As a result, the B Decay liest System was dete:1 mined inoperable and removed from service. The redundant nystem was tested satisfactory per SP 203.05A, Quarterly Decay Heat Removal Pucip P-261A Surveillance and Inservice Test.

The seal was replaced and the system was tested per SP 203.09. Decav Heit Removal Leakage Surveillance, and SP 203.058, Quarterly Decay Heat Removal P c.; P- A1B Surveillance and Inservice Test. The results of these tests proved acceptable and the system was declared operable. The total time that the system un out of service was within the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> allowed by Technical Specifications sect ion 3. 3.2 for continued reactor operation.

The pump is a single stage, 3000 spa centrifugal pump manufactured bv Ba w a t. WilcoF, Canada. The seal is a " John Crane" type 13 4 1/2 Inch shaft

    • al manuf actured by Crane Packing Co., Ltd.

There were no plant traristents or power reductions asaociated with t m event.

Respectfully submitted, i , 6 \

t

/J.yMattiooer7Gm J. >

Auuistant General Manager and Chief Eingineer iV08200 g g