ML18283B340
| 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
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DISTRIBUTION FOR INCOMING MATERIAL 50-296 REC:
OREILLY J P
NRC ORG:
FOX H S TN VALI EY AUTH DOCDATE: 07/i8/78 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:
INTERNAL:
EXTERNAL:
- ITIEF-QRB$3 BC<<FW/4 ENCL EG FILE~~~ /ENCL
.E+~L4/2 ENCL I
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C SYSTEMS BR<<FW/ENCL NOVAK/CHECK+4FW/ENCL AD FOR ENG~HFW/ENCL I-IANAUER++W/ENCL AD FOR SYS h PROJ~F+W/ENCL ENGINEERING BR~F4FW/ENCL l(RI:-GER/J.
COLLINS4 4FW/ENCL K SEYFRIT/IE>F+W/ENCL LPDR S ATHENSr AL<<FW/ENCL TIC LIZ CARTER4F4FW/ENCL NSIC<<FW/ENCL ACRS CAT B~F+Wfi6, ENCL l
NRC PDR<<FW/ENCL MIPC++W/3 ENCL EMERGENCY PLAN BR~<W/ENCL EEB>>FW/ENCL PLANT SYSTEMS BR<~W/ENCL AD FOR PLANT 'YSTEMS<<FW/ENCL REACTOR SAFETY BR<+W/ENCL VQLLMER/BUNCH++W/ENCL POWER SYS BR<<FWfENCL DISTRIBUTION:
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782060295
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JL'L 1 8 ]97e TENNESSEE VALLEYAUTHORITY CHATTAr(lOOGA. TEr(ir(iESSEE 37401 Mr. James P. O'Reilly~ Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region XX 101 Marietta Street~ Suite 3100 Atlanta, Georgia 30303 Deax Mr. O'Reilly:
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TENNESSEE VALLEYAUTHORITY EHOWNS FERRY NUCLEAR PLQ7P UNIT, 3 - DOCKET NO. 50-2)6 - FACILITY OPERATING LICENSE DPR 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 a pexiodic surveillance instruction while the unit 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 VALLEYAUTHORITY 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 1777) P'
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CLEAR REGUlATORYCOMMISSION
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,Q IPI.EASE PRINT OR TYPE ALLREQUIRED INFORMATION) 0 0
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LICENSE NUMBER 0~Q 25 26 LICENSE TYPE 30 57 CAT 58, EVENT DATE 80 09 SOURCE L~JQB 7
60 61 DOCKET NUMBER 68 69 4
75 REPORT DATE EVENT'DESCRIPTION AND PROBABLE CONSEQUENCES 010
'v7hile the unit was in a shutdown condition a
eriodic survei'llance inst:r p"rformed 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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80 SYSTEM CAUSE CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
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9 10 11 12 13 18 i,19 20 SEQUENTIAL OCCURRENCE REPORT REVISION
/RO EVENT YEAR REPORT NO.
CODE TYPE NO.
'17 REI47 ~78
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A Q+
~0 Qj, Q
QC 2'I 22 23 24 26 27 28 29 30 31 ACTION. FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDR PRIME CohIP.
COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.
SUPPLIER MANUFACTURER
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8 Q26 I)3 34 35 36 37 40 4'I 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.
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FACILITY STATUS
'4 POWER OTHER STATUS QBO 1
5 G
26 0
0 0
29 HA NAME OF PREPARER 0 LLLJO ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITYQ36 Cra W Q33 LJQ34 NA 7
8 9
10 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7
~00 0
QÃ~ZQAA NA 7
8 9
11 12 13 PERSONNEL INJURIES 1
NUMBER DESCRIPTIONQ41 8
~00 0
Q4o tJA 7
8 9
11 12 LOSS OF OR DAhIAGE TO FACILITYQ43 TYPE DESCRIPTION 9
~ZQ42 NA 8
9 10 PUBLICITY ISSUED DESCRIPTIONQ "KZ WQ44
'7 8
9 10 METHOD OF DISCOVERY LBJQ>>
45 46 45 80 80 80 80 80 PHONE:
68 69 80 NRC USE ONLY III O
V 80 0a DISCOVERY DESCRIPTION Q32 Surveillance Performance LOCATION OF REI.EASE Q NA
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