ML13308B483

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RO 76-09:on 761101,remote Visual Exam of Reactor Internals Indicated Failure of Four Flexure Supports.Caused by Cycle Fatigue Related to Thermal Shield Dynamic Oscillations Due to Coolant Flow Induced Vibration
ML13308B483
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 11/08/1976
From: Ottoson H
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
RO-76-09, RO-76-9, NUDOCS 8103060504
Download: ML13308B483 (1)


Text

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  • LICENSEE EVENT REPORT CONTROL BLOCK:

(PLEASE PRINT ALL REQUIRED INFORMATION) 1 6

LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE

]L I clAI S1 01S I I 0

0

-1001 01 01 4 I 111111

[L Ii 789 14 1525 26 30 31 32 REPORT REPORT c

t fY TYPE IOURsE DOCKET NUMBER EVENT DfA 5

fpuRT 0

A 7(

~E ECONT DIPl LT LJ 1 5I 01-10121 01 6 LiLLP...L11 71 6 LU 0 7

8 57 58 59 60 61 (A8 69 74 75 80 EVENT DESCRIPTION During the refueling outage which began on September 30, 1976, remote Ivisual examinations of the reactor vessel internals were conducted d part of aroutinel 7 8 9inspection program. *The examinations were performed utilizing a standard underwater so Srlevision sstem wi al minations recorded on a video-tave to provide a Permanent

7.

9record of the inspections.

The results of the visual examinations indicate that four 80 M

f t ix fltxure suppor _ natpd at the top of the thermal shield have failed-.A1.

7 f

oqzutparae u

at 80 7 13 hrza lengthowof th lxres. oThe six1 exure oare4 ituated arundThef cr br-SO 80 7 9 12 X Reo Po X

7 89 t_'.INENT COMPONffNT COMPONENT CUE LSui DLIER MANUFACTURRYR VIOLATEN 07 IR JA I E I X-1 XI X I X I WjLN 11L 2j 0L2.

7 8 910 11 12 17 43 44 47 48 CAUSE DESCRIPTION

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The flexures failed because of cycle fatigue related to dynamic oscillations of the 7 8 9thermal shield causebc a

tiow induced vibration.

1ai2ure ot 13lex s

80 9Ihad no adverse effects on the thermal shield and the remainder of the reactor 7 8 9internal structures.

Therefore, the flexures will be left-in the reactor vesse-T so

[M1~ Ln their rwjrrpnt condition, 1

7 8I9 80 FAILITY METHOD OF SATUS POvER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTIN i

l 1010101 NA J

I S1 visual inspection 7 8 9

10 1213 44 45 46 80 FORM OF ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Do I A

I'INA I

L NA 7 8 9

10 11 44 45 8o PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION 1

ID 1

_j I NAI 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION 7

L'J 1 0e1 NA 7

9 9 1

1 so OFFSITE CONSEQUENCES Fn5]

NA 7 8 9 LOSS OR DAMAGE TO FACILITY PI PE DESCRIPTION 8

I II NoneI 7 8 9 10 80 PUBLICITY 1 I Event released to standard publicity list.

7 8 9 80 ADDITIONAL FACTORS (Event description-continued)

E0l at 210, c50 2050, and 3250, were found failed. Since the flexure failures had no

? 6 9adverse effects on the remainder of the reactor internals structures, the flexures 80 will be left in the reactor in their current condition. Licensee Event Report No.769 7 Us 80 NAME L L. Ottoson 714-492-7700 gi 6 PHONE:.7-49-70