ML20085M651
| ML20085M651 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/23/1973 |
| From: | Eric Thomas TENNESSEE VALLEY AUTHORITY |
| To: | Oleary J US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| AO-BFAO-7342W, NUDOCS 8311090137 | |
| Download: ML20085M651 (2) | |
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TENNESSEE VALLEY AUTHO*~llTY CHATTANOOGA, TENNESSEE i 4 3740'l L} ' !'i?~
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November 23, 1973 T.)
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^f Mr. John F. O' Leary, Director w'r t
Directorate of Licensing N4 i
Office of Regulatien U.S. Atomic Eneri;y Ccemission N:%..
Washington, DC 20545
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Dear Mr. O' Leary:
DOCKST NO. 50-259 - FACILITY OPER OCCURRENCE REPORT BFAO-7342W
- ABNORMAL.
to torus due to water-level functions in torus whic c on aligned' Ferry Nuclear Plant unit 1 on November 15 and 16 red'on Browns in accordance with Isppendix A to Regulatory Ouide 1.16, Revision October 1973.
Very truly yours, ENNESSEE VALLEY AUTHORITY
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h,.yE.'F. Thomas
'D'irector of Power hoduction
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Enclosure CC(Enclosure):
Mr. Norman C. Moseley, Director
. Region II Regulatory Operations Office,-USAEC
- 230 Peachtree Street, IM, Atlanta, Georgia 30303 i
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Q) v ABNORPAL OCCURRENCE REPORT Report No.--BFAo-7342W Report Date--Hovember 23, 2973 Occurrence Date--Hovember 15 and 16, 1973 Facility--Browns Ferry Nuclear Plant unit 1 Identification of Occurrence HPCI suction aligned to torus due to water-level functions in torus Conditic s Prior to Occurrence Reactor at approxirately 25-percent power during startup testing Descrintion of Cccurrence Following a planned scram from 25-percent power required by startup t relief valve operated to reduce reactor pressure.
esting, a valve reali'gned from the condensate storage tank to the torus.
At this time, the HPCI suction initiated relief valve actuations were followed by EPCI suction valvSubsequent m e transfer.
_ Designation of Amtsrent Cause of Occurrence the release of reactor steam frca the relief valves throug panying discharge pipes, which are submerged in the torus water e valve repeatable on subsequent relief valve tests.
This conditionTeas not water-level fluctuations, induced level sensor actuation.It is possible that torus vibra Analysis of Occurrence torus had no adverse safety implications.The transfer of the HPCI su o the r.aintains a minimum air volume above the torus water Section 3 7.A/L7.A bases).
, Appendix A, function without condensate supply (see BF FSAR, Section 6 2 11Since low level, there was no degradation of safety. Bases 11) and s
, Safety Design us on CST Corrective Action Although the transfer of the HICI suction to the torus does not hav cf injecting torus corrosion inhibitors into the reactor vessel.
e adverse y
climinating this problem is underway in the Division of Engineering Design Study for L -
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