ML19326C048
| ML19326C048 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/18/1976 |
| From: | Cook R ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19326C040 | List: |
| References | |
| NUDOCS 8004180726 | |
| Download: ML19326C048 (4) | |
Text
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UCENSEE EVENT REPORT CONTAOL BLOCK:l l
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l (PLEASE PRINT ALL REQUIRED INFORMATION]
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8 NAME LCENSE NUMBER YPE TY i
lAIRIAIRIKill 10101-10101010101-10101 141 IIIIIIII 1 013 I
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7 89 14 15 25 28 30 31 32 CATEGORY T
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DOCKET NUMBEA EVENT DAT REPOAT DATE
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I LL_J LLJ 101510l-1o13l l 131 1o1512lGi716J lolGil 1817161 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCAfPTION DE I Leak was discovered in rocket weld upstreavvi of DM-l'iot A. Leak occumd al l
7 89 80 V,,.
EE I i pipe lo valve weld. TL crack was circumferewl.ial around approximately V3 l
7 89 80
@l leh kbe W9Id. CAu5e Ene f.o eXCetsiVe Vibration or impropey hitup. Tipe and l
7 89 80 EE li/dkVf W6fe V"6VHoved and & MetO pipe AMd \\jakUR i%$k1Ildd.
O 315/T4>-10) l 7 89 80 DE I I
7 89 p%g 80 E
CODE COMPONENT CODE SUP5MA M
A VIDI.ATON mE IC l Fl LBJ lZlIlZlIlElEl
{Z.J lE la la la l (N_J 7 89 10 11 12 17 43 44 47 48 CAUSE DESCAtPTION DG lCause of Grack was due do excessive vibraUen or immoev Oduo Tioe and I
7 89 80 lvalue were rmoved and wew 3;pe and valve indalleL I
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- V rAca.iTY METH00 OF p
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% PCW E A OTHER STATUS DISCOVEMY DISCOVERY CISCRIPTON LHj 1010101 I NA Lbj l
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7 8 9
10 T2 13 44 45 48 80 AEL2'I0 0FilJ l N EOUNT OF ACTMTV l
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ASE LOCATON OF AELEASE l
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7 8 9
10 11 44 45 80 PEA 50NNEL EXPOSURES Ni tMBE R TYPE DESCRIPTdt N
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7 89 11 12 13 80 PERSONNEL INJURtES 3
A cEsCArpfoN 7 89 11 12 80 OFFSITE CONSEQUENCES 5
BE I NA I
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LOSS OR OAMAGE TO FAC;LITY TYPE I
DE LEJ lDESCRfPT'OlA f
7 89 10 l
j 80 P IBUCITY
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7 89 80 (9 ADD'ilONAL FACTORS
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i 7 89 80 NAME 00 9
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', d I-Reportable Occurrence I:eport No.
50-313/76-10 2.
, Report Date: June l'8, 1976 3.
Unurrence Da_ty: May 26,1976 4
I:ac ility:
Arkansas Nuclear One-Unit 1 Russellville, Arkansas 5.
Identification of Occurrenec:
l Leak in socket weld in decay iteat flow element instrument tap.
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6 Conditions Prior to Occurrence:
Steady-State Power ;_
Reactor Power n
Wth llot Standby Not Output n
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'5 Cold Shutdown Porcent of Full Power n
Refueling. Shutdown X'
Load Changes During Routinc 3
Powrr Operation
}. 'j Routine Startup Operation i
Routine Shutdown Operation
.fI Other (specify)
Defueled i
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7.
Description of Occurrence:
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A leak was discovered at 1400 hrs, on 5/26/76 in a socket weld up-l stream of valve Dil-1401-A which is a root v11ve for the flow in-
,i strument for flow element FE-1401. The leak occurred at the 1/2" pipe to valve weld. The_ crack is circumferential around approxi-mately 1/3 of the weld.
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Attachuent."C" l
!! arch 23, 1976 N5hMO, Rev. 4 Page 2 of 1
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!!cportable Occurrence l:cport No.
50-313/76-10
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Des i gna t io n o f Appa ren t Caus.e...o.f..O..cc..u.r..rence.:
j Design Procedurc flanufacture IJnusual Service Condition I
including Environmental Installation /
1, Construction Component Failure Operator Other (specify)
X The cause is due to excessive vibration or. improper fit-up causing a_ crack.
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9.
Analysis of Occurrence:
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Since the Reactor was defueled and the decay heat system was not i
- I required to be operable, there was no hasard to the health and l
safety of the public.
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Att:chment "C"
itirch 23, 1976 NSI'- 10, Itev..I l' age 3Of4 w,,
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4 Itcp0rtable Occurrence !!cport do.
50-313/76-10
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Corrective Action:
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'ihe defective weld was removed by cutting out the pipe and valve and a new valve and pipe were installed. Tle excessive vibration will be resolved by replacing the present flow control valves (CV-1428,1429),
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'I which are cavitating, with'more suitable control valves or by adding l,
orifices downstream of the present control valves with full flow Lypass lines containing ES Activated MOV's.
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Failure. Data:
None.
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5-4 g.
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,I At ta cionent "C"
March 23, 1976 NSP-10, llev. 4 Page 4 of.1 i
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