ML20084U535

Updated Interim Deficiency Repts DDR-222,223 & 225 Re Demineralized Water Sys Piping,Steam Lines & Standby Liquid Control Pump Discharge Relief Valve Drawings,Respectively. Rept Supersedes 760122 Rept

ML20084U535
Person / Time
Site:	Browns Ferry
Issue date:	01/23/1976
From:	Eric Thomas TENNESSEE VALLEY AUTHORITY
To:	Rusche B Office of Nuclear Reactor Regulation
Shared Package
ML20084U538	List: ML20084U535 ML20084U563
References
10CFR-050.55E, 10CFR-50.55E, DDR-222, DDR-223, DDR-225, NUDOCS 8306290108
Download: ML20084U535 (2)

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January 23, 1976 i O.+ --

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' /A" I_c. t Mr. Benard C. Rusche

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Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Rusche:

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLAllT IETITS 1 AND 2 -

DOCKET NO. 50-260 - FACILITY OPERATING LICENSE DPR-33 AND DPR ABNORMALOCCURRENCEREPORTBFAO-50-260/761W This letter will supersede my letter on this subject dated January 22, 1976.

The enclosed interim report is to provide details concerning three design deficiencies on Browns Ferry unit 3 which also apply to units 1 and 2 and is submitted in accordance with Appendix A to Regulatory Guide 1.16, Revision 1, October 1973 Very truly yours, TENNESSEE VALLEY AUTHORITY

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r. 2 5 s rector of Power Production Enclosure ,

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Mr. Nor:nnn C. Moseley, Director U.S. Nuclear Regulatory Commission Regional Office 230 Peachtree Street, IM., Suite 818 Atlanta, Georgia 30303 8306290100 760123 WO DR ADOCK 0500

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AL JAL OCCURRE! ICE REPORT V[ -

Report Number: BFAO-50-260/761W , ..

Report Date: January 22, 1976 ,

. ' Occurrence Date: Reported to Browns Ferry Nuclear Plant on January 12, 1976 l

- ' Facility: Browns Ferry Nuclear Plant units 1 and 2 l l

'Three design deficiencies on unit 3 were discovered by the Division of Engineering Design; and Design Deficiency Report Kos. 222, 223, and.225 will be issued in accordance with 10 CFR 50.55(e). These deficiencies, which also apply to units 1 and 2, were reported to Browns Ferry Nuclear Plant on January 12, 1976. Following is a suery of each deficiency and the corrective action to be taken.

1. DDR-222 - The demineralized water syste". siping to the drywell was found to have Class M inboard isolation vaba several feet frem the dr/vell penetration. Eeing Class M, the valves cannot be considered containment ,

isolation valves as required in the FSAR Sectica 5 2 3.5 A Class D hand I valve that is seismically qualified will be added immediately cutboard of

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the present outboard check valve.

2. DDR-223 - During an analysis of the unit 3 stea= lines in the deter =ination of the effects of substituting two Crosby relief valves for two Targe , Rcck

. main steam relief valves, it was found that, during relief valve cperatien, sections of the discharge lines underwent stresses which exceed the stress level stated in the FSAR. Snubbers will be added to each main steam relief valve discharge line to correct this problem.

3 DDR-225 - The drawing revision necessitated by design change ECI! m40 which modifies the standby liquid centrol p=p discharge relief valve piping inadvertently specified schedule 40 pipe instead of schedule 60 pipe.

The SIC pu=p discharge piping modification will be changed to schedule 80 pipe.

~; g-This repcrt serves as an interim repert. T?re final repcrt for each c:currence will be included in the respective design deficiency reports.

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