ML20084U563

Interim Deficiency Repts DDR-222,223 & 225 Re Demineralized Water Sys Piping,Steam Lines & Standby Liquid Control Pump Discharge Relief Valve Drawings.Initially Reported on 760112

ML20084U563
Person / Time
Site:	Browns Ferry
Issue date:	01/22/1976
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 8306290118
Download: ML20084U563 (2)

Text

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, TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 e /,

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e January 22, 1976 *

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'est ~j Mr. Benard C. Rusche ]d Director of Nuclear Reactor Regulation u.5

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. U.S. Nuclear Regulatory Commission Q Washington, DC 20555 '

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Dear Mr. Rusche:

TENNESSEE VALLEY AUTHORITY - BR0lfNS FERRY NUCLEAR PIANT UNIT 1 -

DOCKET NO.50-26G - FACILITY OPERATING LICENSE DPR ABNORFAL OCCURRENCE REPORT EFAO-50-260/761W .

The enclosed report is to provide details concerning 1A and 1B SRM's

• which were made inoperable and is submitted in accordance with

. Appendix A to Regulatory Guide 1.16, Revision 1, October 1973 This event occurred on Browns Ferry Nuclear Plant units 1 and 2.

Very truly yours,

- TENNESSEE VALLEY AUTHORITY dk E. F. Thomas

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Director of Power Production l Enclosure CC(Enclosure):

Mr. Norman C. Moseley, Director U.S. Nuclear Regulatory Commission Rc61 onal Office 230 Peachtree Street, Mi., Suite 818 Atlanta, GeorCia 30303 DR PDR /

, g COPY SENT REGION C, 771 .

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. 6 ABNORMAL OCCURRENCE REPORT O.

Report Number: BEAO-50-260/761W -

Report Date: January 22, 1976 r

Occurrence Date: Reported to Browns Ferry Nuclear Plant on January 12, 1976 Facility: Browns Ferry Nuclear Plant units 1 and 2 Three design deficiencies on unit 3 were discovered by the Division of Engineering Design; and Design Deficiency Report Hos. 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 Januar. 12, 1976. Following is a summary of each deficiency and the corrective action to be taken.

1. DDR-222 - The demineralized water system piping to the.drywell was found to have Class M inboard isolation valves several feet from the drywell penetration. Being Class M, the valves cannot ce considered containment isolation valves as required in the FSAR Section 5.2 3 5 A Class D hand valve that is seismically qualified will be added immediately outboard of the present outboard check valve.

2. DDR-223 - During an analysis of the unit 3 stea= lines in the determination of the effects of substituting two Crosby relief valves for two Target Rock

, main steam relief valves, it was found that, during relief valve operation, 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.

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3 DDR-225 - The drawing revision necessitated by design change ECN Lll40 which modifies the standby liquid control pump discharge' relief valve piping inadvertently specified schedule 40 pipe instead of schedule 80 pipe. -

P ' _ _ ,- - The SLC pump discharge piping modification will be changed to schedule 80 pipe.

This report serves as an interim repert. The final repcrt for each occurrence will bo inwiuded in the respective design deficiency reports.

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