05000321/LER-1980-076-01, /01T-0:on 800701,while Reactor Was at Hot Standby for Hpci/Reactor Core Isolation Cooling Testing,Site Notified by Ae That Listed RHR Supports Would Not Adequately Support All Design Based Loads

/01T-0:on 800701,while Reactor Was at Hot Standby for Hpci/Reactor Core Isolation Cooling Testing,Site Notified by Ae That Listed RHR Supports Would Not Adequately Support All Design Based Loads

ML19320D440
Person / Time
Site:	Hatch
Issue date:	07/14/1980
From:	Coggin C GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19320D439	List: 05000321/LER-1980-076, Forwards LER 80-076/01T-0 05000321/LER-1980-076-01, /01T-0:on 800701,while Reactor Was at Hot Standby for Hpci/Reactor Core Isolation Cooling Testing,Site Notified by Ae That Listed RHR Supports Would Not Adequately Support All Design Based Loads
References
LER-80-076-01T, LER-80-76-1T, NUDOCS 8007210371
Download: ML19320D440 (2)

LER-1980-076, /01T-0:on 800701,while Reactor Was at Hot Standby for Hpci/Reactor Core Isolation Cooling Testing,Site Notified by Ae That Listed RHR Supports Would Not Adequately Support All Design Based Loads

Event date:
Report date:
3211980076R01 - NRC Website

text

F ORM 366 L77)

LICENSEE EVENT REPORT NTROL BLOCK:

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l 8 9 LICENSEE CODE 14 15 LICENSE NUMUEH 25 26 LICENSE TYPE JO bl CAI $8 [ON'T

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8 50 61 DOCKET NUMBER 63 63 EVENT DATE 74 75 REPOHT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h

,o 121 lWhile the Un it 1 Reactor was at hot standby for HPCI/RCIC testing, the I

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that RilR supports 1 E 11 -RH R11-19 6, 313, 262, l

l site was notified by the AE

,g,3, l,o,,,gend 274 would not adequately support all of their design based loads.

l l

This is a repetitive occurrence for inadequate RHR supports, see LER # _j lo,3, g

l 50-321/1979-089.

There were no effects upon public health and safety duq 01611 o l 7 [ lto this event.

The RHR system was available and operable during the l

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event, O la l l 80 DE CODE S BC E COMPONENT CODE SUBCOdE S

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10 11 12 83 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION

_ EVENT YEAR R EPORT NO.

CODE TYPE NO.

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22 23 24 26 27 28 29 30 31 32 AK N A O PL NT ME HOURS SB IT D FOR1 B.

SUPPL 1 MAN FAC URER

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3b 36 31 40 41 42 43 44 47 33 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l The problem with hangers 1E11-RHRH-196 and 313 was due to the use of in-1

,,,, gcorrect valve weights during the original design, and the problem with l hangers 1E11-RHRH-262 and 274 was due to welds being inadvertently leftl gg installation.

DCR # 80-222 and MR's 1-80-3532, 3526, and l

l g off during 3527'were implemented to correct the support problems.

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80 7

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% POWER OTHER STATUS IS O RY DISCOVERY DESCHIPTION l

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lDl@l A/E Notification i s 80 17 8 re to 12 11 44 45 46 LOCATION OF RELE ASE AMOUNT OF ACTIVITY l

AELEASE@D OF RELE ASE@l NA l

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• 7' 8 9 10 11 44 45 PERSONNEL f MPOSURES NUMBEH TYPE DE SCH1PTION l

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,EnSONd'imu','l[S oEstniPriO~@

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~uMnt n l 0 l 0 l 0 l@l NA t a 80 7

8 9 11 12 LOSS OF OH DAMAGE TO FACillTY l

TYPE DE SCRIPitON [Z_j@l NA i 9 80 7

8 9 to NRC USE ONLY PuntlCITY DESCH6 piton 'r 800721037/

l lIlllllllIII!I ISSUI D LN_jhl N

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.I cW 10 fT2IUrmPAn2n C. L. Connin - Supt-T> 1,-

r,g g erv. PRONE: 912-367-7781 f,

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LER-1:.-50-321/1980-076 Licensee:

Georgia' Power Company

' Facility:Name:

.Edwin I.

Hatch Docket #:

50-321

~

Narrative

Report for LER 50-321/1980-076

, With' the Unit 'l reactor _at hot' standby for HPCI/RCIC testing andt adjustment the. site was notified that the. axial supports

'.(RHRH-196 -and - RHRH-313) _ f or the 2D"-suction lines between the lEll-F006A-D. valves were inadequate.

Later that day, the site

~

- notified _ that two.other RHR supports were. inadequate.

was Both a r'e on.4 inch lines; RHRH-262 is -around the IEll-F090 check ' valve ~ and RHRH-274 is-around the-lEll-F026B valve.

While reviewing the as-builts submitted for the I.E.

Bulletin 79-14 program.the Architect Engineer. discovered ' that hangers lEll-RHRH-196, lEll-RHRH-313, IEll-RHRH-262, and IEll-RHRH-274 Twould not. adequately support all.of their design based loads.

^This' situation constituted a-degradation of part of the Unit 1 RHR sys tem. pip.ing,

but the LPCI piping remained adequately supported ~through out-the event.

This is a

repetitive occurrence for inadequate RHR supports, reference R.O.

Number 50-321/1979-089.-

There were no effects upon public health and

-. safety due to-this - event.

The RHR system was not inoperable

. during this event _and the- ' core -spray,

ADS, LPCI, and RCIC systems. were.also~ available and operable.

The apparent cause of -the event as

'it

- relates to hangers lE11-RHRH-196 and

.lEll-RHRH-313 was a. design. deficiency in which incorrect valve

weights were_ use'd in-the original. analysis.

The problems relating to' hanger lEll-RHRH-262 and lEll-RHRH-274 were caused

by~ improper- -field installation, some ' welds were left off.

Design Change Request. number 80-222 and Maintenance Request numbers 1-80-3532', :1-80-3526, and 1-80-3527 were written and implemented';to correct the -problems mentioned.-above.

The review - of I. E '.Bulletin no. 79-14 as builts for the similar-supports

. are now- 'in - full compliance with the design specifications so, no further reporting is r e q u'i r e d.

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