ML20085G984

Ro:On 740909:mods to Reactor Bldg Crane Discovered Described in FSAR But Not Yet Implemented.Crane Does Not Pass Single Failure Protection for Refueling Cask Handling.Mods Will Be Performed

ML20085G984
Person / Time
Site:	Browns Ferry
Issue date:	10/09/1974
From:	Gilleland J TENNESSEE VALLEY AUTHORITY
To:	Case E US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8308300025
Download: ML20085G984 (2)

Text

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O Temmasses CHATTANOOGA, vAuOnursoni TsNNsSSEs v r m cz e i

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r-October 9, 1974 {/2-~  : i ? '~f>

ANNIVE R.:; A CY W i

OF PE'CP;O IN c-PARTNHASHIA

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lir. Edson G. Case 1

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Office of Regulation ((,y *l

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Washington, DC 20545 \<5.'s s

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Dear !!r. Case:

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..j TENNESSEE VALLEY AUTHORITY - BROUNS FERRY NUCLEAR PLANT' '

UNITS 1 AND 2 - DOCKET NOS. 50-259, 50-260 - FACILITY ]

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! OPERATING LICENSE DPR-33, DPR-52 e '[

The enclosed report, submitted as required by Browns Ferry i 1

Nuclear Plant Technical Specification 6.7.2.B(3), is to "

provide details concerning Reactor Building crane modifi-cations described in the Browns Ferry Nuclear Plant Final Safety Analysis Report but still not incorporated at the i plant. The discrepancy between existing design and the FSAR 4

i was discovered on September 9, 1974. .

Very truly yours, l

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' J. E. Gilleland ~ ~~

4 Assistant to the 11anager of Power Enclosure t

CC (Enclosure):

I lir. Norman C. !!oseley, Director ].

Directorate of Regulatory Operations -

U.S. Atomic Energy-Commission Region II - Suite 818 i

230 Peachtree Street,.NW. fi Atlanta, Georgia 30303 8 e.

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1bM 83045300025 741009 PDR S ADOCK 05000259 PDR

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ENCLOSURE

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?i NON-ROUTINE 30-DAY REPORT ff i

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Report Date: October 8, 197h I Occurrence Date: September 9, 197h

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A Facility: Browns Ferry Nuclear Plant Units 1 and 2

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Description of Occurrence '

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t While making an unreviewed safety question determination of the plant 4 modifications covered by TVA Enc.ineering Change Notice (ECN) C9, it was determined that the modifications .to the. Reactor Building Crane . created a potentially. reportable condition under Technical Specifications 6.7.2.B(2) and~6.7.2.B(3). On September 9, 1974, e.fter further investigation, it-was determined that these modifications did constitute a reportable I condition. 'I a

Causes of Deficiency s

TVA ECN-C9 was issued.on November 15, 1972, prior to the issuance of the Brovns Ferry- Nuclear Plant Unit 1 operating license; and these modifica-L*4 tions were added to the discussion in FSAR section 12.2.2.5.2 under Amendment No. 2h. The =odifications have not been accomplished to date as a result of late materials shipments. The last raterials. ship =ent-arrived at BFNP on August 20, 197h. The deficiency arises'in the fact that the FEAR states that the 125-ton Reactor Building Crane passes single failure protection for refueling cask handling which in reality has not [")

been added due to later materials shipment. '

1 Safety Implications ')

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The only safety implications involved are those associated with the 125-ton <

Reactor Building Crane during handling of the refueling cask. No refueling -

casks have been handled at the Browns Ferry Nuclear Plant to date. lt t

Corrective Measures s

The modifications covered by TVA-ECN-C9 vill be performed on the .125-ton  !

Reactor Building Crane prior to the handling of a spent fuel cash containing spent fuel. '

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