05000296/LER-1981-008-03, /03L-0:on 810202,RHR Pump Found Inoperable.Caused by Loose Pump 3D Breaker Trip Adjustment Nut & Adjustment Change,Causing Breaker to Trip Free on Attempting to Close. Breaker Replaced.Adjustment Locknut Tightness Checks Add

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/03L-0:on 810202,RHR Pump Found Inoperable.Caused by Loose Pump 3D Breaker Trip Adjustment Nut & Adjustment Change,Causing Breaker to Trip Free on Attempting to Close. Breaker Replaced.Adjustment Locknut Tightness Checks Added
ML19341C247
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 02/24/1981
From:
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19341C246 List:
References
LER-81-008-03L-01, LER-81-8-3L-1, NUDOCS 8103020528
Download: ML19341C247 (2)


LER-1981-008, /03L-0:on 810202,RHR Pump Found Inoperable.Caused by Loose Pump 3D Breaker Trip Adjustment Nut & Adjustment Change,Causing Breaker to Trip Free on Attempting to Close. Breaker Replaced.Adjustment Locknut Tightness Checks Added
Event date:
Report date:
2961981008R03 - NRC Website

text

U. S. NUCLEAR REGULATORY COMMISSICN NRC10RM 366 (N7)N L'

LICENSEE EVENT REPORT

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8 60 61 DOCKET NUV8ER 68 69 EVENT DA TE 74 75 REPORT OATE 80 EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h l During normal operation, while performing SI 4.5.B.l.B, RHR pump was found to l

I o 12 l go g3; ; be inoperable. Reference T.S. 3.5.B.3. and 5.

Redundant systems were operable.

g There were no effects on public health l

g a ;4l l There were no significant resulting events.

l o I s i i r safety. No previous occurrences.

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I N [g l A lg l G l0 l 8 l0 lg 34 35 06 33 40 41 42 43 44 47 33 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l i 101 1 RHR pumo 3D breaker trip adjustment nut was loose and adjustment changed causing l

1i 1i l l brk to be trip free. Replaced brk with spare and successfully tested. Adj usted l

2 I brk that was tripping free. Adjustment locknut tightness checks will be added to

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GE, 1200A, AMH-4.76-250-10, Magne-Blast Brk.

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'Tenn sseo Valley Authority Form BF-17 Browns Ferry Nuclear Plant BF 15.2 1/10/79 LER SUPPLEMENTAL INFORMATION BFRO 296 / 81008 Technical Specification Involved 3.5.B.3 and 5 Reported Under Technical Specification 6.7.2.b(2)

Date of Occurrence 2/2/81 Time of Occurrence 0345 Unit 3

  • 6 Identification and Description of Occurrence:

While performing SI 4.5.B.l.b, RHR pump 3D was found to be inoperable.

Conditions-Trior to Occurrence:

Unit 1 at 93%

Unit 2 at 89%

dnit 3 at 88%

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

Technical Surveillance Requirements 4.5.B.3 and 5 were' met.

Apparent Cause of Occurrence:

RHR pump 3D breaker trip adjustment nut was loose and adjustment changed. This caused the breaker to trip free when attempting to close.

Analysis of Occurrence:

There was no damage to-plant equipment. There was no activity release, no personnel exposure or injury and no danger to the health or safety of the public.

Corrective Action

The breaker was replaced with another breaker and successfully tested. Adjusted the breaker that was tripping free. Adj us tment locknut tightness checks will be added to the breaker inspection procedure.

Failure Data:

NA

  • Retention:

eriod - Lifetime; Responsibility - Administrative Supervisor

  • Revision: (p