ML20085G984
| 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) | |
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October 9, 1974 ANNIVE R.:; A CY W
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lir. Edson G. Case t
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Acting Director of Licensing
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Office of Regulation i
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Dear !!r. Case:
z TENNESSEE VALLEY AUTHORITY - BROUNS FERRY NUCLEAR PLANT'
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UNITS 1 AND 2 - DOCKET NOS. 50-259, 50-260 - FACILITY H
OPERATING LICENSE DPR-33, DPR-52
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e The enclosed report, submitted as required by Browns Ferry Nuclear Plant Technical Specification 6.7.2.B(3), is to i
1 provide details concerning Reactor Building crane modifi-cations described in the Browns Ferry Nuclear Plant Final i
Safety Analysis Report but still not incorporated at the plant. The discrepancy between existing design and the FSAR i
was discovered on September 9, 1974.
4 Very truly yours, l
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' J. E. Gilleland
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Assistant to the 11anager of Power 4
Enclosure CC (Enclosure):
t lir. Norman C. !!oseley, Director
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I Directorate of Regulatory Operations U.S. Atomic Energy-Commission Region II - Suite 818 i
fi 230 Peachtree Street,.NW.
Atlanta, Georgia 30303 8
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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.
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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
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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 lt casks have been handled at the Browns Ferry Nuclear Plant to date.
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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