ML20085M651

AO BFAO-7342W:on 731115 & 16,during Startup Testing,Hpci Suction Valve Aligned to Torus Due to Water Level Functions in Torus.Caused by Release of Reactor Steam from Relief Valves Through Discharge Pipes.Investigation Continuing

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 CHATTANOOGA, VALLEY TENNESSEE AUTHO*~llTY i4 '

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November 23, 1973 g~.?yfC T.)

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$$3 9;g ^f Mr. John F. O' Leary, Director w'r t Directorate of Licensing N4 i

Office of Regulatien U.S. Atomic Eneri;y Ccemission '

Washington, DC 20545 '4 N:%.. -

Dear Mr. O' Leary:

DOCKST OCCURRENCE REPORTNO. 50-259 - FACILITY OPER BFAO-7342W - ABNORMAL.

to torus due to water-level functionsc in torus which on aligned' Ferry Nuclear Plant unit 1 on November 15 and 16 red'on Browns in accordance October 1973. with Isppendix A to Regulatory Ouide 1.16, Revision ,

Very truly yours,

( ENNESSEE .-VALLEY AUTHORITY -

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P h,.yE.'F. Thomas n

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'D'irector of Power hoduction Enclosure CC(Enclosure):

Mr. Norman C. Moseley, Director

. Region II Regulatory Operations Office,-USAEC

230 Peachtree Street, IM, Atlanta, Georgia 30303 -

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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 relief valve operated to reduce reactor pressure.

by startup t esting, a valve reali'gned from the condensate storage tank At tothis thetime, the HPCI suction torus.

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 discharge pipes, which are submerged in the torus water the reliefe valves throug panying 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 transferoof thethe HPCI su r.aintains a minimum air volume above, Appendix Section 3 7.A/L7.A bases).

the torus A, water (

function without condensate supply (see BF FSAR, Section 6 2 11Since

. . , Safety Design low level, there was no degradation of safety.usBases on CST 11) and s Corrective Action .

Although the transfer of the HICI suction to the torus does not hav e adverse -

cf injecting torus corrosion inhibitors into the reactor vessel.

Study for y

climinating this problem is underway in the Division of Engineering Design L - _ - J