ML20085G343

AO BFAO-7320W:on 731003-04:control Rod Drive 54-27 & 26-55 in Fully Withdrawn Insequence Condition.Strainer for Rod 26-55 Cleaned,Violation of Tech Spec Assumed & Occurrence Being Reviewed

ML20085G343
Person / Time
Site:	Browns Ferry
Issue date:	10/12/1973
From:	Eric Thomas TENNESSEE VALLEY AUTHORITY
To:	Oleary J US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20085G349	List: ML20085G343 ML20085G354
References
AO-BFAO-7320W, NUDOCS 8308240857
Download: ML20085G343 (2)

Text

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TENNESSEE CHATTANOOGA,VALLEY AUTHOFilTY M]s ' o TENNESSEE 37401 b' A 3 .J A/ u October 12, 1973 8 e

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'C&kY Mr. John F. O' Leary, Director p pou M M Directorate of Licensing gut 5" Office of Regulation U. S. Atomic Energy Commission

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Dear Mr. O' Leary:

TENNESSEE VALLEY AUTHORITY - BROWUS FERRY NUCLEAR PIAIiT UNIT 1 -

DOCKET NO. 50-259 - FACILITY OPEFATING LICENSE DPR ABNOT0:AL OCCURRENCE REPCRT BFAO-7320R The purpose of this report is to provide details concerning events involving unit 1 control rods 54-27 and 26-55 at Browns Ferry nuclear Plant on Octcber 3 and 4, 1973. This occurrence was reported by telegram on October 4,1973, to the Region II Directorate of Regulatory Operations, Atlanta, Georgia. -

l Descrittien of the Incident -

Control rod drive 54-27 was valved out to replace a scram outlet valve seat at 9:00 a.m. on October 3 in a fully withdrawn insequence conditicn. At 8:51 a.m. on October 4, it was fully inserted.

Throughout thn time, control rod drive 54-27 could have been valved in and inserted if required.

Control rod 26-55 was in a fully withdrawn insequence conditica at 5:15 a.m., on October 4, when it was determined the rod wculd I

not move with normal CRD pressure. After raising CRD pressure, it was inserted at 10:30 a.m. on October 4. The plant was operating

! at less than 8-percent power at less than or equal to rated

temperature and pressure.

Investigation and Corrective Action The occurrence was reviewed by the Startup Coordination Committee about 8:30 a.m. on October 4. In review of the situation with respect to technical specification 3 3/4.3.A, it was decided that control rod 54-27 should be valved in and fully inserted and that

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Mr. Jchn F. O' Leary October 12, 1973 TENITESSEE VALLEY AUTHORITY - BRGTIiS FERRY NUCLEAR PLUIT UNIT 1 -

DOCKET UO. 50-259 - FACILITY OPERATIEG LICENSE DPR AEHORMAL OCCURREHCE REPORT BFAO-732CW efforts should centinue to fully insert control rod 26-55 as soon as possible. After raising CRD pressure, control rod 26-55 was inserted.

Study of this occurrence is not ecmpleted. It is under centinuing review by members of the Plant Operations Review Cc=mittee, the manufacturer's representatives, and the Safety Review Board.

Until this study is ccmplete, a violation of technical specification 3 3.A.1 is assumed te have occurred; and written instructicna have been issued to require any incperable control rod to be fully inserted or the reactor placed in a shutdown condition unless it can be inmediately determined that technical specification 3 3.A.1 is satisfied.

The strainer for drive water to control red 26-55 was cleaned.

This rod was then tested and returned to normal service.

Very truly yours, TENNESSEE VALLEY AUTHORITY

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E. F. Ahemas c' Directcr of Pcwer Production i

CC: Mr. Norman C. Moseley, Director Region II Regulatory Operations Office, USAEC 230 Feachtree Street, IM.

Atlanta, Georgia 30303

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