ML18283B340

Licensee Event Report Concerning an Outboard Main Steam Isolation Valve, Which Closed Faster than Allowed by Technical Specifications

ML18283B340
Person / Time
Site:	Browns Ferry
Issue date:	07/18/1978
From:	Fox H Tennessee Valley Authority
To:	O'Reilly J NRC/IE
References
Download: ML18283B340 (6)

Text

P 7/zs/~8 REGULATORY INFORMATION DISTRIBUTION SYSTEM < RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-296 REC: OREILLY J P ORG: FOX H S DOCDATE: 07/i 8/78 NRC TN VALI EY AUTH DATE RCVD: 07f2i/78 DOCTYPE: LETTER NOTARIZED: NO, COPIES RECEIVED

SUBJECT:

LTR i ENCL i LICENSEE EVENT REPT 178-0i4 ON 6/26/78 CONCERNING AN OUTBOARD MSIV FCV 3/i/38 CLOSED FA TLR THAN ALLOWED BY TECH PEC 3. 7. D. i.

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PLANT NAME:BROWNS FERRY - UNIT 3 REVIEWER INITIAL: XRS DISTRIBUTOR INITIAL:

4F<<F<<HHHHHHF4HF~4HHF DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS

<DISTRIBUTION CODE A002)

FOR ACTION: :ITIEF-QRB$3 BC<<FW/4 ENCL l

INTERNAL: EG FILE~~~ /ENCL NRC PDR<<FW/ENCL

.E+~L4/2 ENCL MIPC++W/3 ENCL I 8( C SYSTEMS BR<<FW/ENCL EMERGENCY PLAN BR~<W/ ENCL NOVAK/CHECK+4FW/ENCL EEB>>FW/ENCL AD FOR ENG~HFW/ ENCL PLANT SYSTEMS BR<~W/ ENCL I-IANAUER++W/ENCL AD FOR PLANT 'YSTEMS<<FW/ENCL AD FOR SYS h PROJ~F+W/ENCL REACTOR SAFETY BR<+W/ENCL ENGINEERING BR~F4FW/ENCL VQLLMER/BUNCH++W/ENCL l(RI:-GER/J. COLL INS4 4FW/ ENCL POWER SYS BR<<FWfENCL K SEYFRIT/IE>F+W/ENCL EXTERNAL: LPDR S ATHENSr AL<<FW/ENCL TIC LIZ CARTER4F4FW/ENCL NSIC<<FW/ ENCL ACRS CAT B~F+Wf i 6, ENCL DISTRIBUTION: LTR 45 FNCL 45 CONTROL NBR: 782060295 SIZE i P+i P

%%%% %%%<M 4 %%<<F4F%%% <<F%%%%%%%%0M'0M'%4'O'HE, END

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TENNESSEE VALLEY AUTHORITY CHATTAr(lOOGA. TEr(ir(iESSEE 37401 JL'L 1 8 ]97e h

Mr. James P. O'Reilly~ Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement tp Region XX 101 Marietta Street~ Suite 3100 Atlanta, Georgia 30303 C/p Deax Mr. O'Reilly:

TENNESSEE VALLEY AUTHORITY EHOWNS FERRY NUCLEAR PLQ7P UNIT, 3 - DOCKET NO. 50-2)6 - FACILITY OPERATING LICENSE DPR-68 - EEPORTAKE OCCURRIM REPORT 3PRO 50-296/7814 The enclosed report provides details concerning an outboard main steam isolation valve, FCV 3-1-38~ which closed fastex'han allo>red by technical specifications duxing pexiodic surveillance instruction while the unit a

sras in a shutdown condition. This xeport is submitted in accordance with Bzewns Ferry unit 3 technical specification 6.7.2.b.(2).

Very truly yours, TENNESSEE VALLEY AUTHORITY Hi ST Fox Director of Power Production Enclosure (3) cc (Enclosure):

Director (3)

Office of Ifanagement Information and Program. ontrol U.S. Nuclear, Regulato'ry Commission Mash ton ,D.C. 20555.

Director (IN)

Office of Inspection and. Enforcement U.S; Nuclear Regulatory Commission Qashington, D.C. 20555 An Equal Opportunity Employer

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NRC,FORM 386 U. CLEAR REGUlATORY COMMISSION 1777) P' ~ .-

, l4 CONTROL BLOCK:

,Q IPI.EASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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CON'T 8 9 A L B LICENSEE CODE H F I 1 3

14 Q20 15 0 0 0 0 0 LICENSE NUMBER 0 - O 25 26 LICENSE TYPE 30 0~Q 57 CAT 58,

~01 SOURCE L~JQB 7 75 80 09 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 4 REPORT DATE EVENT'DESCRIPTION AND PROBABLE CONSEQUENCES 010

'v7hile the unit was in a shutdown condition a eriodic survei'llance inst:r p" r formed on the MSIV ' . An out ooard MSIV FCV 3-1-38 closed faster the n a llowed bv 4 T.S.3. (.D,l, The resulting LCO was observed and MSIV FCV -I- "as closed There was no effect to the public health and. safety. Previous event was 50-296/ Bl

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~OB 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~CC Q11 ~EQ>2 ~EQn V A 0 V 0 P Q4 ~CQ>> ~Z Q+

7 8 9 10 11 12 13 18 i,19 20 SEQUENTIAL OCCURRENCE REPORT REVISION

'17 REI47 ACTION . FUTURE

/RO EVENT YEAR

~78 2'I 22 EFFECT

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23 SHUTDOWN

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24 REPORT NO.

A 26 Q+

27

~0 ATTACHMENT 28 CODE 29 NPRDR TYPE Qj, 30 PRIME CohIP.

Q 31 QC NO.

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~XQIB ~X Q19 ~ZQzo LJZQ21 O O O O ~X 4'I Q23 ~8 Q24 ~n Q26 A 8 Q26 I)3 34 "

35 36 37 40 42 43 44 47 BECAUSE DESCRIPTION AND CORRECTIVE ACTIONS &27 o Invcsti at,ion revealed an Atwood-Morrill valve's t.

Fluid was added. and the valve was s17cessf'ul r 3-5 sec. T.S. limit. Further action is to check the dash t f' week until next refuelin outa c. At that time the Rash nt. w E 1 e r 7 8 9 80 FACILITY METHOD OF STATUS '4 POWER OTHER STATUS QBO DISCOVERY DISCOVERY DESCRIPTION Q32 1 5 G 0 LLLJO 26 ACTIVITY CONTENT 0 0 0 29 HA LBJQ>>

45 46 Surveillance Performance 80 RELEASED OF RELEASE AMOUNT OF ACTIVITYQ36 LOCATION OF REI.EASE Q Cra 7 8 W

9 Q33 LJQ34 10 NA 44 45 NA 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 ~00 0 QÃ~ZQAA NA 7 8 9 11 12 13 80 PERSONNEL INJURIES 1 NUMBER DESCRIPTIONQ41 8 ~00 0 Q4o tJA 80 7 8 9 11 12 LOSS OF OR DAhIAGE TO FACILITY TYPE DESCRIPTION Q43 9 ~ZQ42 NA 8 9 10 80 PUBLICITY Q NRC USE ONLY "KZ WQ44

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ISSUED 9

DESCRIPTION 10 68 69 80 III O

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PHONE: a NAME OF PREPARER

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