05000260/LER-1980-040-01, /01T-0:on 800929,five Main Steam Relief Valves Failed to Actuate within Required 1% of Set Pressure During Bench Test.Cause Unknown.Set Pressure Was Reset & Proper Operation Verified

/01T-0:on 800929,five Main Steam Relief Valves Failed to Actuate within Required 1% of Set Pressure During Bench Test.Cause Unknown.Set Pressure Was Reset & Proper Operation Verified

ML18025B148
Person / Time
Site:	Browns Ferry
Issue date:	10/14/1980
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18025B146	List: 05000260/LER-1980-040, Forwards LER 80-040/01T-0 05000260/LER-1980-040-01, /01T-0:on 800929,five Main Steam Relief Valves Failed to Actuate within Required 1% of Set Pressure During Bench Test.Cause Unknown.Set Pressure Was Reset & Proper Operation Verified
References
LER-80-040-01T-01, LER-80-40-1T-1, NUDOCS 8010210663
Download: ML18025B148 (4)

LER-1980-040, /01T-0:on 800929,five Main Steam Relief Valves Failed to Actuate within Required 1% of Set Pressure During Bench Test.Cause Unknown.Set Pressure Was Reset & Proper Operation Verified

Event date:
Report date:
2601980040R01 - NRC Website

text

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QB 80 61 DOCKET NUMBER GS 69 EVENT OATf.

74 75 REPORT DATE 80 FVENT OESCRIPTION ANO PROBABLE CONSEQUENCEs Qo With the unit in cold shutdown durin a scheduled refuelin outa e

five of the main

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= ~06 steam relief valves failed to actuate within the required 1% of set pressure during a bench test.

There was no danger to the health or safety of the public, and no I significant resulting chain of events.

See Technical Specification 4.6.0.1.

There

~OB hive been no previous similar occurrences.

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32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPADX PRIME COMP.

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13 34 35 36 37 40 41 42 43 44 CAUSE DESCRIPT(ON ANO CORRECTIVE ACTIONS Q27 o

} The cause of the event is not known.

The set ressure was reset and the proper o eration verified b certified tests.

Tar et Rock mdl. 7567F-100-21 CS 1500 lb 6 x 10, valve serial numbers

1020, 1022,

1026, 1029 and 1031.

The cause is being 3

investigated with the manufacturer.

A followup report will be issued when the investigation is complete.

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10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITYQ 6

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F AC I LITY METHOD OF STATUS Oh POWER OTHER STATUS PQ DISCOVERY DISCOVERY DESCRIPTION Q32 Observed during bench test.

LOCATION OF AELEASEQ NA 80 80 80 80 7

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11 12 LOSS OF QA DAMAGETo FACILITYQ43 TYPE

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Ten'nessee Valley AuthorJty Browns Ferry Nuclear Plant Form BF-:.17 BF 15. 2 1/10/79 LER SUPPLEMENTAL INFORMATION BFRO 260 /

8040 Technical Specification Involved A.6.Del Reported Under Technical Specification Dote o/ Occurrence S/>S/S~

Time ot Occurrence Unit Identification and Descri tion'of Occurrence:

During a bench test with unit in a scheduled refueling outage, 5 main steam relief valves failed to actuate within the required 1% of set pressure.

They are as follows:

Valve SN s

1020 1105 1040 1029 1115 1140

,1031 1105 1184 1022 1105 1123 1026 1125 1177 Conditions Prior to Occurrence:

Unit 1 80% steady state power Unit 2 - scheduled refueling outage Unit 3 98% steady state power

.Action specified in the Technical Specification Surveillance Requirements met D

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ro Unknown'nal sis of Occurtence; There was no danger to the health or safety of the public, no re ease of activity, no damage to plant or equipment, and no resulting significant chain of events.

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A The set pressures were reset and the correct valve op'eration verified by certified test.

Failure Data:

None (10CFR21 evaluation will be made on follow-up report after completion of the investigation) sRetention:

eriod - Lifetime; Responsibility - Administrative Supervisor

• Revision:

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