ML19326C020
| ML19326C020 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/08/1977 |
| From: | David Williams ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19326C016 | List: |
| References | |
| NUDOCS 8004180707 | |
| Download: ML19326C020 (4) | |
Text
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UCENSEE EVENT REPC T
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CONTROL BLOCK:l l
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l (PLEASE PRINT ALL REQUIRED INFORMATION) 1 8
uE uCENSE NUMBER TY TY l A l a l Al Rl Kl 1l l0 l 0 l-l 0l 0l O! 0l0 l-l 0 l 0 l l 4l 1l 1l 1l 1!
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7 89 14 15 25 28 30 31 32 CATEGORY TYP SC 00CKET NUMBER EVENT CATE REPORT DATE l
OiCONil i
I LIJ LIJ 101 s l 01-101 sl~ 11 sl 101 s t,I s l 71 sl 1014lolalvisi 7 8 57 58 59 60 61 68 89 74 75 80 EVENT DESCRIPTION 95 l Ilhile making preparation for~ removing surveillance specimens for inspection of holder l 7 89 80 Ql tubes due to wear at other BSif plants, it was found that spring cartridge was missing l 7 89 80 gg l from 2 tubes and one of those two tubes was partially missing along with push rod l
7 89 80
@l and journal bearing. Search for missing oieces initiated.(50-313/76-3) l 7 89 80 61rs l l
7 89 80
- pau, 00E CE COMPONENT CODE VIOLATON E I cl Al Lp_1 lxl xi xi xix ixi Isi i si 01 11 51 In l 7 89 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION ilfi l NA l
7 89 80 s
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% POWER OTHER STATUS OtS VE CISCOVERY DESCRIPTON Le]
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s 7 8 9
10 12 13 44 45 48 80 PELE S 0 DF E ASE AMOUNT OF ACTMTV LOCATON OF RELEASE E
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7 8 9
10 11 44 45 80 PERSONNEL EXPOSURES i
NUMBER TYPE DESCRIPTION n I ni nIn i LJ l
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7 89 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTON lE l0l0l0l l
NA l
7 89 11 12 80 OFFSITE CONSEQUENCES
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7 89 80 LOSS OR OAMAGE TO FAC:LITY TYPE CESCRIPTON n LLJ l Extension of shutdown acoroximately 2 nonths to defuel. insueet. and refuel' l
7 89 10 80 PUBUCITY
$l Press release made on 4/8/76 I
9 80 ADDITIONAL FACTORS I
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7 89 80 8 0041809 h) 19 l l
7 89 80 NAME. Daniel 11. Ililliams-PHCNE: (501) 371-4192
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Reportable occurrenec Report 3>.
50-313/76-I 2.
Report 1)a te : 4/8/76
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O_a urrence Date:
3/2S/76 4.
Facility:
Arkansas Nuclear One-Unit 1 Russellville, Arkansas 72801 5.
Identification of Occurrenec:
Reactor surveillance specimen holder tube failure.'
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Conditibus Prior to Occurrence:
Steady-State Power Reaetor Power 0
MhIh llot Standby Net Outpui.
O Mh'e Cold Shutdown X
Percent of Fut 1 Power 0
"6 Refueling Shutdown Load Changes During Routinc
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Power Operation (j
Routins Startup Opera tion Routine Shutdown Operation Other (specify) 5 8
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licscriptien of Occurrence:
At approximately 2200 hour0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> while making preparation 'for removing the sur-veillance specimens.for t' e inspection of the specimen holder tubes due to voar problems at two other BGW plants, it became apparent that the spring
-l cartridge was missing from 2 of 3 specimen tubes. In addition one of those j
tubes, identified as tube no. 3,had clie push rod missing and detached from the, specimen, the journal bearing missing, and part, if not all, of the holiter tube missing from the top of the shroud to the upper hinge of the specimen, tube.
Tube no. 2 is in the same condition as tube no. 3 except that part, if
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not all, of the push rod is attached to the specimen and part, if not l
(~,j) all, of the holder tube is still around the push rod. All of tube no.1 was intact and the specimen has been removed. A 612 foot section of holder tube came out when the specimen was removed. The specimens for tubes no. 2 and 3 appear to be in their proper location.
Attachuent "C"
!! arch 23, 1976 NSP.lu, Rev. 4 Page 2 of 4
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I!cportable Occurrence I:cport No.
50-313/76-3 I
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Designat_lon o f Appa rent Cause_,ol, Oc,t;.nrrence:
[
Design y
l'rocedu rc Flanufac turc Unusual Service Condition including linvi ronmental Installation /
i Const ruction Component ' Failure Operato r Other (specify) i i
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Analysis of Occterrenec:
There is no evidence of failed fuel due to what appears to be loose parts in the reactor, thus no lut:ard to the health and safety of the public.
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Attachment "C" l
Ftirch 23, 1976 flSI'- 10, Rev. 1 l'a ge 3of4
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3 Reportable Occurrence Report ilo. 50-313/76-3 7
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Corrective Action:
i The reactor will be defueled, the internals removed, loose parts retrieved, and necessary modifications and inspect' ions made to prevent reoccurrence.
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Failure Data:
llo prior failures of this type at ANO.
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Mtac!unent "C"
-Fbreh 23, 1976 NSP-10, Rev. 4 Page,1 of.1 f
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