ML19275A032

LER 79-011/01T-0 on 790809:during NRC Performance Appraisal Team Interview,Discovered That Pressurizer Safety Relief Valve PSV-1002 Was Not Properly Tested in Mar 1978.Valve Retested 790812 W/No Adjustments Required

ML19275A032
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/23/1979
From:	Shively C ARKANSAS POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19275A031	List: ML19275A030 ML19275A032
References
LER-79-011-01T, LER-79-11-1T, NUDOCS 7908300571
Download: ML19275A032 (4)

Text

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ei that Pressurizer Safety Relief Valve, PSV-1002, was not properly testeo 1o 1 1 i in March, 1978. Documentation revealed the acceptance criteria of pro- i uu.s.j i cedure 401.03, requiring two consecutive lifts at 2500 + 1% psi, was not i 10161 I met. The AN0 Plant Safety Committee (PSC) ruled the test was not per- i o , i formed satisfactorily. There have been no similar occurrences. This ,

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1. Reportable Occurrence Report No. 50-313/79-011

2. Report Datc: 08/23/79 3. Occurrence Date: 08/09/79 4 Facility: Arkansas Nuclear One - Unit One Russellville, Arkansas 72801

5. Identification of Occurrence:

Personnel error in procedure execution which could prevent the fulfillment of the functional requirement of the pressurizer relief system to cope with accidents analyzed in the FSAR.

6. Conditions Prior to Occurrence:

Steady-State Power Reactor Power MWth lio t Standby Net Output MWe Cold Shutdown Percent of Full Power S.

Refueling Shutdown Load Changes During Routine Power Operation Routine Startup Operation Routine Shutdown Operation Other (speci fy)

Routine power operation following incorrect testing of pressurizer relief valve.

7. Description of Occurren;c:

Upon investigation of an item discussed during the NRC Performance Appraisal Team exit interview on 8/3/79, it was discovered that Pressurizer Safety Relief Valve, PSV-1002, was not properly tested per procedure 1401.03, " Pressurizer Code Relief Valve Test", in March, 1978.

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Reportable Occurrence Peport No. 50-313/79-011

8. Designation of Apparent Cause of Occurrence: ,

Design Procedure bbnufacture Unusual Service Condition Including Environmental Installation /

Const ruction Component Failure (See Failure Data)

Operator Other (specify) Engineering personnel

9. Analysis of Occurrence:

Per T.S.4.L b , Table 4.1-2, Item 3, the pressurizer code safety valve setpoint must be tested on one of the relief valves every 18 months.

The documentation shows that valve, PSC-1002, was tested for lift pressure per procedure three times on March 18, 1978, with calculated lift pressures of 2499, 2530, and 2531 psi. The acceptance criteria of procedure 1401.03 requires two consecutive lifts at 2500 + 1% psi.

The data sheet on file with this test procedure contains a note written by the engineer supervising the test. He justified the acceptability of the test results. based on the fact that the pressure gage indicated higher than actual due to the exceedingly hot ambient temperature in the area. However, the test gage in question was not calibrated follow-ing the test, as it was not specifically required by the procedule.

The AN0 Plant Safety Committee (PSC) met on 8/9/79 and reviewed all documentation pertaining to the test in question. It was ruled that the justification for acceptability was not a valid argument, and the test results were not satisfactory.

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Reportable occurrence Report No. 50-313/79-011

10. Corrective Action:

Valve PSV-1002 was retested for lift pressure on 8/12/79. The setpoint was tested three times, with calculated lift pressures of 2518, 2493, and 2523 psi. This met the acceptance criteria of procedure 1401.03 for two consecutive lifts at 2500 + 1% psi. There were no adjustments necessa ry. It can therefore be concluded that the valve was operable during the period of March, 1978 to August, 1979.

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11. Failure Data:

N/A