ML18283B411

LER 1978-003-00 for Browns Ferry Nuclear Plant, Unit 3, Valve FCV 3-74-52 Was Found Inoperable During Performance of Surveillance Instruction 4.5.B.1.C

ML18283B411
Person / Time
Site:	Browns Ferry
Issue date:	03/10/1978
From:	Fox H Tennessee Valley Authority
To:	O'Reilly J NRC/IE, NRC/RGN-II
References
LER 1978-003-00
Download: ML18283B411 (8)

Text

~ P py (i>/'9 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS >

DISTRIBUTION FOR INCOMING MATERIAL 50-29b REC: OREILLY J P ORG: FOX H S DOCDATE: 03/10/78 NRC TN VALLEY AUTH DATE RCVD: 03/14/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 LICENSEE EVENT REPT (RO 50-296/78-03> ON 02/13/78 CONCERNING DURING PERFORMANCE OF SI 4. 5. B. i. Ci VALVE FCV 3-74-52 WAS FOUND INOPERABLE.

PLANT NAME:BROWNS FERRY UNIT 3 REVIEWER INITIAL: XJM DISTRIBUTOR INITIAL:Q4r DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002>

FOR ACTION: BR CHIEF LEAR++W/4 ENCL INTERNAL: r E~~W/ENCL NRC PDR++W/ENCL E%% MIPC+4W/3 ENCL SCHROEDER/IPPOL ITO++W/ENCL HOUSTON++W/ENCL NOVAK/CHECK44W/ENCL GR IMES+4 W/ENCL KNIGHT++M/ENCL BUTLER++W/ENCL HANAUER4+W/ENCL TEDESCO+4W/ENCL E I SENHUT4 +W/ENCL BAER++W/ENCL SHAO++W/ENCL VOLLMER/BUNCH++M/ENCL KREGER/J. COLLINS++W/ENCL ROSA++W/ENCL K SEYFR IT/IE++W/ENCL EXTERNAL: LPDR S ATHENS) AL+%W/ENCL T I C++W/ENCL I

NS C++W/ENCL ACRS CAT B++W/ib ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 780740018 SIZE: iP+iP+iP THE END

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TENNESSEE VALLEY ALITHOAITY cHATTANooGA.'ENNEssEE 37401 MAR 10 I978 j))

Mr. James P.

U.S, Nuclear 0'lly, .Director latory Commission 4if"j-'~ctq 4roptr

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Office of Ins ection and Enforcement Region II e Street, NW., Suite 1217 230 Peacht Atlanta, orgia 30303 ,(4%'ear Mr. 'Reilly:

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TENNESSEE VALLEY AUTHORITY BROWNS PERRY NUCLEAR PLANT UNIT 3 DOCKET NO. 50>>296 - FACILITY OPERATING LICENSE DPR&8 - REPORTABLE OCCURRENCE REPORT BPRO-50-296/783 The enclosed report provides details concerning valve PCV 3-74-52 which was found inopexable during the performance of Surveillance Instruction 4'.5.B.l.c'. This report is submitted in accordance with Browns Perry unit 3 Technical Specification 6.7.2.b.(2),.

Very truly yours, TENNESSEE VALLEY AUTHORITY H '. Pox Dixector of Power Production Enclosure cc (Enclosure)s Director (3)

Office of Management Informatio and Program Control

.U.S. Nuclear Regulatory Commiss n Washington, DC 20555 Director (40)

Office of Inspection and Enforcement U.S. Nucleax Regulatory Commission Washington, DC 20555 ab I

t An Equal Opportunity Employer

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BFA85 10/5/77 NRC FORM 366 LL S NUCLEAR REGULATORY COMMISSION IT.2 2 I

'I UCENSEE EVENT REPORT EXHIBITA peer6 1

CON'T 9

CONTR OL B LOCK:

LICENSEE COOK

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QI LICENSE NVMBEH

'reo~o~o (PLEASE PRINT OR TYPE ALLREOUIRED INFORMATION) 26 LICENSE 'IYPE 40 61 CA1 SB

~or "o",rLZZQep3 p 0 02 96 r~02 f YfN'1 69 1 37 DATf 8

14 e 0 16 REPOR'1 DATE 80 DOCKET NUMBfR IrB

,EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO

~Q2 Durin the erformance of SI 4.5.B.l.c, valve FCV 3-74-52 was found

~Q3 inoperable. This is reported under Technical Specification .6 . 7. 2 .b. 2 .

~o 4 Re air work was be un immediatel and the valve was restored to o erabilit within 4 days. Redundant systems were operable during this period. Similar

~o 6 oc ur ences have been reviousl e orted on BFAO-50-260 7435 and

~o 2 BFRO-50-259/7711. There were no effects upon public health or safety.

~QB 6 9 1

SYSTf M CAUSE CAUSE COMP, VALV f s>>rs>>'Js o>>>>e>>sos SUBCQDK COMPONENT CODE SUBCQOE

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COOK CODE

~OB 2 6 9 10 11 12 ll 16 Bus 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LfR/RO EVENT YEAR

~ ~00 REPORT NQ.

~03 CODE TYPE

~ NO.

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~S Qo erroor 3 ~W ~I ~0 21 22 21 24 26 21 26 29 lp ll l2 ACTION FVTURK EFFECT SHUTDOWN ATTACHLIE'CT IrSAD4 PRIME COMP. COMPONE NT TAKEN ACTION ONPLANT hlETHOD HQVRS Q22 SUBMITTED FOAM EUB. SUPPLIE R ereAIeUFACTVAKR roS>>'JS ooS SS LJS 26 31 Sp

>>oo ooS LJS 41 43 44 41 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS 021 o The valve is a 24" Walworth Co. ressure sea an le valve with a Limitor ue SMB-5T o erator. The valve.was disassembled and found that the u er bearin locknut h its normal o t r

dana ed the oke bearin s and 4 scorin n The dana ed machinin ITYdone on the yoke.

STATUS N POWER OTHER STATVS QSO OISCQ~VERY DISCOVERY OESCRIPTIQN Q32 e ~EQre ~10 0 Qre N A ~BQel N A 2 6 9 ACTIVITY CONTf NT IP I'2 Il 46 RELEASFD OF RELfASK AMOUNTOF ACTIVITY N/A Q N/A LOCATION OF RELEASE QB o ~Z 03 ~Z034 1 6 9 10 II 44 46

~ ERSQNNf 1 EXPOSURES NUMBER TYPE OKSCRIPTIONQ39 2 6

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o 11 Q>>

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~ ERSONNEL INJURIES 2 6 9 11 12 LOSS OF QR OAMAG'E TO FACILITY TYPE Of SCRIPTION Q43

~Z042 N/A 2 6 9 10 PUB LIC I T Y I~SUE 0 DfSCReP TION Q N A NRC USE ONLY

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. NAME OF PREPARER PHONE:

• Revi sion.

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.Attachment BFRO-50-296/783.

CAUSE DESCRIPTION AND CORRECTIVE ACTION (Continued)

Th'e valve was a 24" Walworth Co. pressure seal angle valve with a Limitorque SHB-5T operator. The valve was disassembled,and it was found that the upper bearing locknut had been 'stripped from its normal position with the upper bearing locknut, set screws still in place. This also damaged the yoke nut, the, upper and lower bearings, and caused some scoring on the yoke. As a result of this damage there was binding causing the valve stem to become 4

immovable. All the damaged parts were replaced, a small amount of machining work was done on the yoke, and the valve was reassembled. It is not known r

what exerted the excessive force on the upper bearing locknut.. Two probable causes of failure t

are that the valve at some time was stuck in'he closed position and was damaged when an attempt was made to open it or that it traveled past the backseated position.

HLA:SGS 3/8/78

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