05000321/LER-1980-087-01, /01T-0:on 800724 W/Unit Shut Down During IE Bulletin 79-14 Review,Ae Found Anchor Inadequately Supported.Caused by Inadequate Design of Original Support. Design Modified & Anchor Replaced

/01T-0:on 800724 W/Unit Shut Down During IE Bulletin 79-14 Review,Ae Found Anchor Inadequately Supported.Caused by Inadequate Design of Original Support. Design Modified & Anchor Replaced

ML19330C392
Person / Time
Site:	Hatch
Issue date:	08/05/1980
From:	Coggin C GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19330C380	List: 05000321/LER-1980-087, Forwards LER 80-087/01T-0 05000321/LER-1980-087-01, /01T-0:on 800724 W/Unit Shut Down During IE Bulletin 79-14 Review,Ae Found Anchor Inadequately Supported.Caused by Inadequate Design of Original Support. Design Modified & Anchor Replaced
References
IEB-79-14, LER-80-087-01T, LER-80-87-1T, NUDOCS 8008080317
Download: ML19330C392 (2)

LER-1980-087, /01T-0:on 800724 W/Unit Shut Down During IE Bulletin 79-14 Review,Ae Found Anchor Inadequately Supported.Caused by Inadequate Design of Original Support. Design Modified & Anchor Replaced

Event date:
Report date:
3211980087R01 - NRC Website

text

U.S. NUCLEAR RE!ULATcRY COMMISSION

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60 61 DOCK ET NUMBER 68 63 EVEN T DATE 74 75 REPORT D ATE 80 EVENT DESCRIPTloN AND PROBA3LE CONSEQUENCES h 10121 I Wi th the unit shutdown, the AE was reviewina as-built suoco}ts Der IEB I

l o la l 179-14.

The AE notified the site that an anchor on the RCIC pump dis-I 1 charge line was inadequately supported.

No significant occurrence took l o 4 Io lsi Iplace as a result of this event.

Hatch Unit 2 was not affected by this I o o levent.

A similar event was reported by report #50-321/1980-086.

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33 34 35 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS lThe cause of this event was inadequate design of the original support.

I i O lThe AE transmitted a proposed design modification to the site.

This I

i i l change was made prior to unit startup.

No backup supports exist for i

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This event caused no threat to public health or I

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LER #:

50-321/1980-087 Liccnsee:

Georgia Power Company Facility Name:

Edwin I.

Hatch Docket #:

50-321

Narrative

Report for LER 50-321/1980-087 With the unit shutdown, the AE was reviewing as-built piping and. supports per the requirements of IEB 79-14.

The AE notified the site that RCIC pump discharge line

nchor

. E51-RCICH-23 was unacceptably flexible for seismic loaos.

Computer analysis indicated that stresses in this section of pipe exceeded code allowable stresses for operating and design basis earthquake' conditions.

Yield stresses would be exceeded

~only under DBE conditions.

This anchor is on the RCIC pump discharge -line.

No significant occurrence took place as a

result of this event.

Hatch Unit 2 was not affected by this event.

A similar event was reported by report #50-321/1980-086.

The cause of this event can be attributed to i. adequate design preposed design of the original support.

The AE transmitted i modification to the plant site.

This modif ica' ion provided 1

acceptable support for this section of pipe.

Th.s change was implemented prior to unit startup.

No backup supports exist for this section of pipe.

However, all backup ECCS systems were operable.

This event caused no threat to public health or safety.

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