ML20085F042
| ML20085F042 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/15/1975 |
| From: | Eric Thomas TENNESSEE VALLEY AUTHORITY |
| To: | Case E US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20085F041 | List: |
| References | |
| NUDOCS 8308180247 | |
| Download: ML20085F042 (2) | |
Text
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TENNESSEE VALLEY AUTHORITY
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,U Mr. Edson G. Case
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Acting Director of Licensing N( *
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Washington, DC 20545
Dear Mr. Case:
TEmIESSEE VALLEY AUTHORITY - BROWIIS FERRY ITUCLEAR PLAUT UNIT 1 -
DOCKET NO. 50-259 - FACILITY OPERATING LICENSE DPR ABNORMAL OCCURRENCEREPORTBFAO-50-259/752W r
The enclosed report is to provide details concerning a crack in a 3/4-inchcarbon-steeltestlineonthecoresprayloopIIfull-flow pump test loop and is submitted in accordance with Appendix A to Regulatory Guide 1.16, Revision 1, October 1973. This event occurred on Browns Ferry nuclear Plant unit 1 on February 5, 1975.
Very truly yours, TENUESSEE VALLEY AUTHORITY E. F. Thomas Director of Power Production
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Enclosure j
CC (Enclosure):
Mr. Norman C. Moseley, Director U.S. Nuclear Regulatory Commission i
Regional Office 230 Peachtree Street, NW., Suite 818 l
Atlanta, Georgia 30303 PDRADOCK05000{g
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ABNOPPAL OCCURRENCE REPORT i
EFAO-50-259{752W Report No.:
Report Date:
February 1, 1975 Occurrence Date: February 5, 1975 Facility: Browns Ferry Nuclear Plant unit 1 Identification of Occurrence g
Acrackina3/4-inchcarbon-steeltestlineonthecoresprayloopIIfull-flow pump test loop.
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Conditions Prior to Occurrence The unit was in the cold ahutdown condition.
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Description of Occurrence a functional leak test of the core spray piping, a leak was discovered During/4-inch carbon-steel test connecticn on the pu=p flow test loop piping in a 3 outside the containment boundary. The leak resulted from a crack in a socket veld to test valve No.75-591.
4 Designation of Antarent Cause of _ Occurrence The apparent cause of the crack was metal fatigue due to vibration of the test connection line, Analysis of Occurrence No damage to systems, co=ponents, or structures was experienced; no personnel injuries or exposures were involved; no radioactive materials were released; and there were no adverse effects to the public health and safety as a result of this occurrence. The core spray loop was capable of performing its k
intended function with this small leak.
Corrective Action The crack was ground out and repaired by velding. Additional support for the test connection was provided to irtibit vibration. After the repair was completed, a functional leak '. cst was satisfactorily performed. A surveillcnce test was perfor=ed to ensure that the core sprey loop II was operable, Failure Datt BFAO-50-260/7419W (crack in a 2-inch bypass line)
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