05000259/LER-1981-001-03, /03L-0:on 810105,core Spray Sparger to Reactor Pressure Vessel D/P Switch 1-PDIS-75-28 Found Set Above Tech Spec Limit.Caused by Barton Model 288 Setpoint Drift.Switch Replaced W/New Switch on 810115

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/03L-0:on 810105,core Spray Sparger to Reactor Pressure Vessel D/P Switch 1-PDIS-75-28 Found Set Above Tech Spec Limit.Caused by Barton Model 288 Setpoint Drift.Switch Replaced W/New Switch on 810115
ML20003A358
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 01/28/1981
From:
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20003A355 List:
References
LER-81-001-03L-01, LER-81-1-3L-1, NUDOCS 8102030556
Download: ML20003A358 (2)


LER-1981-001, /03L-0:on 810105,core Spray Sparger to Reactor Pressure Vessel D/P Switch 1-PDIS-75-28 Found Set Above Tech Spec Limit.Caused by Barton Model 288 Setpoint Drift.Switch Replaced W/New Switch on 810115
Event date:
Report date:
2591981001R03 - NRC Website

text

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4RC PORM 366 U. S. NUCLE A3 CEGULATORY COMMISSION (7 77) ~

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60 61 DOCK E T NUV9 g R 68 69 EVENT D ATE 14 75 RE PORT D A TE 80 EVENT CESCRIPTION AND PROB ABLE CONSEQUENCES h I O I 21 l During normal operation, while performine SI 4.2.B-24. core surny sparzer to I

t o t a l I RPV d/p switch 1-PDIS-75-28 was found set at 1.4 osid.

T.S. 3.2.B limit is Q l 2 +/- 0.4 psid. Redundant switch 1-PDIS-75-56 was operable. There was no effect i

I l o I s l I on the health or safety of the public. Previous event: 259/8087.

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l i l o l l The Barton model 288 setpoint had drif ted.

The switch was recalibrated and I

m i functionally tested for repeatability. The switch was reolaced with a neu switch I

Lt_j u lon January 15, 1981. No further action is planned.

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Tennessee Valley Authority Form BF417 Browns Ferry Nuclear Plant BF 15.2 1/10/79 LER SUPPLEMENTAL INFORMATION BFRO 259 / 8101 Technical Specification Involved 3.2.B Reported Under Technical Specifir ation 6.7.2.b(1)

Date of Occurrence 1/5/81 Time of Occurrence 1300 Unit 1

Identification and Description of Occurrence:

While performing S1 4.2.B-24, core spray sparger to reactor pressure vessel differential pressure switch 1-PDIS-75-28 was found set at 1.4 psid.

.T.S.

limit is 2 +/- 0.4 psid.

Conditions" Prior to Occurrence:

Unit 1 at 1001 Unit 2 at 75%

~

.. Unit 3 refueling 4

Action specified in the Technical Specification Surveillance Requirements met due to inoperable equipment. Descrioe.

None Apparent Cause of Occurrence:

Instrument drift Analysis of Occurrence:

There was no danger to the health or safety of the public, no release of activity, no damage to plant or equipment and no resulting significant chain of events.

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Corrective Action

Recalibration functionally tested and returned to service. The switch was replaced on January 15, 1981.

Failure Data:

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259/8087

  • Retention:

eriod - Lifetime; Responsibility - Administrative Supervisor

  • Revision :

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