05000259/LER-1980-049-03, /03L-0:on 800620,during Surveillance Check,Ti 36A, Pressure Increase Detected on Shell Side of 1-C RHR Heat Exchanger.Caused by Loosened Nuts Due to Thermal Cycling & Vibration.Heat Exchanger Reassembled & Tested

/03L-0:on 800620,during Surveillance Check,Ti 36A, Pressure Increase Detected on Shell Side of 1-C RHR Heat Exchanger.Caused by Loosened Nuts Due to Thermal Cycling & Vibration.Heat Exchanger Reassembled & Tested

ML19326D864
Person / Time
Site:	Browns Ferry
Issue date:	07/15/1980
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19326D863	List:
References
LER-80-049-03L, LER-80-49-3L, NUDOCS 8007230474
Download: ML19326D864 (2)

LER-1980-049, /03L-0:on 800620,during Surveillance Check,Ti 36A, Pressure Increase Detected on Shell Side of 1-C RHR Heat Exchanger.Caused by Loosened Nuts Due to Thermal Cycling & Vibration.Heat Exchanger Reassembled & Tested

Event date:
Report date:
2591980049R03 - NRC Website

text

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t.ICENSEE EVENT REPORT

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60 61 DOCKET NUMBER 68 69 EVENT OATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l 0 J 2 l l With Unit 1 at 92 percent steady state power TI 36A was beine run when an increase l

lTj q l in pressure was detected on the shell side of 1-C RHR heat exchanger.

There was no l

l0 i A i l danger to the health or safety of the public, and no resulting significant chain of I

l0IslIevents. B and D RHR loops were operable.

See tech. spec.3.5.B.S.

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33 34 35 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Disassembly and inspection of the eat exchanger revealed that about 30 percent of

, g y the locking and full nuts on the floating head had loosened due to thermal cycling and vibration.

There were no tube leaks. The exchanger was reassembled and tested per 21-49.

A determination of recurrence control measures to be taken is being g

made.

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Form BF.17 Browns Ferry Nuclear Plant BF 15.2 1/10/79 LER SUPPLEMENTAL INFORMATION BFRO 259 / 8049 Technical Specification Involved 3.5.B.5 Reported Under Technical Specification

6. 7. 2.b (2)

Date of Occurrence 6/20/80 Time of Occurrence _1230p.m. Unit _1 Identification and Description of Occurrence:

RHR heat exchanger 1-C was discovered to have loosened lock nuts -during routine

~

test TI-36A.

Conditions" Prior to Occurrence:

Unit 10 92% steady state power Unit 2 in routine shut-down condition Unit' 3 0100% steady state power 9

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

B & D RHR loops were operable Apparent Cauce of Occurrence:

Nuts had loosened d~ue to thermal cycling and vibration.

Analysis of Occurrence:

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

Corrective Action

Heat exchanger was reassembled and tested per MMI-49.

Recurrence control is being determined by Engineering Design and Outage Management Group.

Fai. lure Data:

'LER BFRO-50-259-80043, LER BFRO-50-259-78023, LER BFRO-50-259-77003.

• Retention:

criod - Lifetime; Responsibility - Administrative Supervisor

• Revision:

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