ML20072H001

Forwards Response to IE Bulletin 83-03 Re Check Valve Failures in Raw Water Cooling Sys of Diesel Generators. Current Test Program Sufficient to Verify Integrity of Check Valves

ML20072H001
Person / Time
Site:	Browns Ferry
Issue date:	06/15/1983
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-SSINS-6820, REF-SSINS-SSINS-6 IEB-83-03, IEB-83-3, NUDOCS 8306290250
Download: ML20072H001 (3)

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TENNESSEE VALLEY AyJf; ipr {Tg Y ggg 3 CHATTANOOGA TENNESdb.3ddoi. . G EORGI A 400 Chestnut Street Tower II June 15,8ff 8pg l7 p 2 : 0 0 U.S. Nuclear Regulatory Commission Region II ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

IE BGLLETIN 83 CHECK VALVE FAILURES IN RAW WATER COOLING SYSTEMS OF DIESEL GENERATORS - BROWNS FERRY NUCLEAR FLANT Enclosed is our response to the subject bulletin for the Erowns Ferry Nuclear Plant. This submittal constitutes c'ur final response to the bulletin. If you have any questions, please call Jim Domer at FTS 858-2725.

To the but of my knowledgement, I declare the statements contained harsin aae complete ano true.

Very truly yours, ,

TENNESSEE VALLEY AUTHORITY i

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L. M. Mills, nager Nuclear Licensing Enclosure oc (Enclosure):

U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 8306290250 830615 PDR ADOCK 05000259 O PDR An Equal Opportunity Employer T

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ENCLOSURE RESPONSE TO IE BULLETIN 83-03 DATED MARCH 10, 1983 BROWNS FERRY NUCLEAR PLANT Item 1 The subject valves (see attached list) are included in the Browns Ferry Pump and Valve Inservice Testing (IST) program and are forward-flow tested in accordance with section XI of the ASME Boiler and Pressure Vessel Code.

Iter 2 The check valvs arrangement for the diere) generators (3/n),et Brewns j Ferry is quite diff erent from that found at Dresden and Quad Cities where the r6 ported failure occurred. Each D/G at Browns Ferry is supplied by two separate soorces of emergency eqaipaant ecoling water (EECF). Either

of these two sources of 2ECW is capable of supplying the 420-gpa flow required for diesel operability. With a single source of EECW capable of supp2yirg the necessary ficw rate, a dcuble passive failure (one check valve in each EFCW supply) cn a single D/G would be necessary to render the diesel inoperabls. The nigh imprabability of such an event indicates that the current test procedures-are sufficielt to maintain D/G operacility.

Item 3 The current test program is sufficient to verify the integrity of the check valves when one EECW source is capable of supplying the required flow rate.

Item 4 The subject valves are listed on the attachment. The valve integrity verification will be performed as stated above. Review of available i maintenance history records and discussions with sinformed maintenance personnel reveal tnat there have been no failures or significant problems l associated with these valves.

l Item 5 Because the current test program is sufficient to verify the integrity of the check valves, no additional testing will be done. Consequently, no additional report will be submitted.

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Attachment I

Listing of E=ergency Equipmen Coolir.g Wat$r (EECW) Check Valven to Diesel Generator (D/G) Coolers D/G 1A Cooler D/G 3A Cooler .67-528 67-693 67-529 67-694

.67-634 67-695 67-635 67-696 D/G 1B Cooler . D/G 33 Cooler

• 67 -52,1 67-703 - -

67-7C4 67-522 - 67-630 67-705 i GT-631 57-700 4

D.'31C CcoJ er D/3 3C Cooler 67-514 67-713 67-515 .67-714 67-6I4 67-715 67-(25 67-716 D/G 1L Coolee D/G 3D cooler

.67-507 67-723 67-508 67-724 67-637 ..67-725 67-628 - 67-726 .

Pmap Discharge Check Valves A3 23-588 B3 23-591 C3 23-594 D3 ~23-507

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