05000361/LER-1982-013, Forwards LER 82-013/011-0.Detailed Event Analysis Submitted

Forwards LER 82-013/011-0.Detailed Event Analysis Submitted

ML20053D779
Person / Time
Site:	San Onofre
Issue date:	05/28/1982
From:	Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20053D780	List: 05000361/LER-1982-013, Forwards LER 82-013/011-0.Detailed Event Analysis Submitted 05000361/LER-1982-013-11, /011-0:on 820428,RCS Water Inventory Test Indicated Total Leakage Rate in Excess of 1 Gpm.Caused by Concurrent Testing of Valves.Surveillance Procedure 3023-3-3.37 Will Be Improved
References
NUDOCS 8206070315
Download: ML20053D779 (2)

LER-1982-013, Forwards LER 82-013/011-0.Detailed Event Analysis Submitted

Event date:
Report date:
3611982013R00 - NRC Website

text

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MEIVE3 VM Southern California Edison Company UR n',' - j p~, I, 21SCB S AN ONOFRE NUCLE AR GENER ATING STA TION P.O. B O X 124 [I), j ('

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S A N C LEMENTE. C A LIFORNI A 92672 2

H. B. R A Y

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U. S. Nuclear Pegulatory Commi ssion Office of Inspection and Enforcement l

Region V i

1450 Maria Lane, Suite 210 Walnut Creek. Cclifornia 94596 - 536?

j Attention:

fir. R. d. Engel ken, Regione.1 Admin i strator C=ar Sir:

1 1

SUBJCCI:

Docket.'lo.

50-301 j

LER No.32-013 San Onofre Nuclear Generating Station, Unit 2 l

In at:ord uce ith Technical Specification 6.9.1.13.6 of Appendix A to Operating License NPF-10 for San Onofre Nuclear Generating Station Unit 2, this letar is submitted as a 30 day report concerning a circumstance which f

was daclued as an bousual Event and report ed by telephona to the NRC en April 28, 1932.

/r completed copy of :ne LER E2-013 is enclosed.

On April 28,19E2 the Reactor Coclant Systern (RCS) was in Moca 4 at a i

temparature of approximately 225 F and a pressure'of 2250 psia.

RCS isolation j

valve leak rate testing 1.at in progress'pursuar.: to Technical Specification 5

Surveillcoce Requirement 4.4.5.2.2.d using Encincering Procedure 5023-V-3.5.2.

A Charg'ng/ Letdown fic.v niematch was cbrerved by control rocm operators and an RCS Water Inventory Balance, in accordance with Surveillance Procedura 5023-3-3.37, was ccamenced.

The results of this test indicated total leak l

rate in eress of Techniccl Specificc"ian 3.4.5.2.. with indications of unidentified leakage in excess of I gpn.

Unidentified leakade could not be 1

reduced below 1 gpm, in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> p uaitted by Technical Specification 3.4.5.2 Acticn b.

This caused the declaration of an Unusual. Event in accordance with our Emergency Plan.

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TC A 4

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I 8206070315 820528 PDR ADOCK 05000361 l

5 PDR i

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Mr. R. H. Engelken Unidentified leakage was reduced below 1 gpm in about 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> through a combination of actions including:

a.

More accurate measurement by Station Engineering of identified leakage using a revised Surveillance Procedure 5023-3-3.37 with improved correlation of RC Drain Tank Level versus quantity.

b.

Tightening numerous RCS and CVCS boundary salves.

c.

Suspending all parallel activities such as chemistry sampling, surveillance testing of RCS Isolation Valves in accordance aith Technical Specification 4.4.S.2.2.d and carefully maintaining RCS temperature constant.

Corrective action to prevent recurrence is to improve Surveillance Procedure 5023-3-3.37 to facilitate more accurate determination of identified and unidentified leakage and to provide additional manpower when raising RCS pressure following an extended shutdown in order to promptly take any action required to reduce unidentified leakage below 1 gpm.

If there are any questions regarding the above or the attached, please contact me.

Sincerely, l'N5

&{hrga-fQ i

Enclosure:

Licensee Event Report 82-013 cc:

U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Of fice of Management Information & Program Control (MIPC)

Institute of Nuclear Power Operations (INPO)

A. E. Chaffee (USNRC Resident Inspector San Onofre Unit 2) l

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