05000259/LER-1980-043-03, /03L-0:on 800411,during Test Instruction 36A, W/Unit at 85% power,1A RHR Heat Exchanger Was Found Leaking. Caused by Six Loosened Lock Nuts.Gasket Replaced & Tested Per Mechanical Maint Instruction 49

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/03L-0:on 800411,during Test Instruction 36A, W/Unit at 85% power,1A RHR Heat Exchanger Was Found Leaking. Caused by Six Loosened Lock Nuts.Gasket Replaced & Tested Per Mechanical Maint Instruction 49
ML19323G078
Person / Time
Site: Browns Ferry 
Issue date: 05/23/1980
From:
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19323G076 List:
References
LER-80-043-03L, LER-80-43-3L, NUDOCS 8005300346
Download: ML19323G078 (2)


LER-1980-043, /03L-0:on 800411,during Test Instruction 36A, W/Unit at 85% power,1A RHR Heat Exchanger Was Found Leaking. Caused by Six Loosened Lock Nuts.Gasket Replaced & Tested Per Mechanical Maint Instruction 49
Event date:
Report date:
2591980043R03 - NRC Website

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l o l 2 l l With unit at 85 percent power in steady state operation, it was found during TI-36A l

,o;3y; that 1A RHR heat exchanger was leaking.

Redundant systems B and D RHR, LPCI, gny,,l and core spray were operable.

There was no danger to health or safety of the public j

IoIsl l and no resulting significant chain of events.

See Technical Specification 3.5.B.3.

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CAUSE DESCRIPTION AND COHHECTIVE ACTIONS I i l o l l Six of the fif ty-two lock nuts were found to have loosened causing a gasket leak.

l lil } l The gasket was replaced and tested per Mechanical Maintenance Instruction 49.

j m l Lock nuts were installed on an earlier modification, and due to this failure

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Tennessee Valley Authority Form BF-17

...~ - Browns Ferry Nuclear Plant BF 15.2 1/10/79 LER SUPPLEMENTAL INFORMATION BFRO-M-259 / 8043 Technical Specification involved 3.5.B.3 and 5 Reported Under Technical Specification 6.7.2.b(2)

Date of Occurrence 4/11/80 Time of Occurrence Ud 1600 1

Identification and Description of Occurrence:

While performing TI-36A it was discovered that 1A RHR heat exchanger was leaking.

Conditions Prior to Occurrence:

Unit 1 0 85% steady state power.

Unit 2 @ 97% steady state power.

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Unit 3 @ 100% steady state power.

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

Describe.

B&D RHR, LPCI, and core spray all operable.

Apparent Cause of Occurrence:

Six of fifty-two lock nuts had loosened allowing gasket to leak.

Analysis of Occurrence:

WrFwas no dattger tu health or safety of the public, no release of activity, no damage to plant or equipment, and no significant resulting chain of events.

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Corrective Action

Gasket was replaced and MMI-49 run.

Failure Data:

BFRO-50-259-78 23

  • Retention :

eriod - Lifetime; Responsibility - Administrative Supervisor

  • Revision :

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