05000321/LER-1981-010-01, /01T-0:on 810211,AE Reported That Diesel Generator 1A,1C,2A,2B & 1B Outlet Svc Water Piping & Associated Seismic Supports Exceeded Tech Spec.Caused by Design Omission.Design Mods Made

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/01T-0:on 810211,AE Reported That Diesel Generator 1A,1C,2A,2B & 1B Outlet Svc Water Piping & Associated Seismic Supports Exceeded Tech Spec.Caused by Design Omission.Design Mods Made
ML19341C652
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 02/24/1981
From: Coggin C
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19341C646 List:
References
LER-81-010-01T, LER-81-10-1T, NUDOCS 8103030877
Download: ML19341C652 (2)


LER-1981-010, /01T-0:on 810211,AE Reported That Diesel Generator 1A,1C,2A,2B & 1B Outlet Svc Water Piping & Associated Seismic Supports Exceeded Tech Spec.Caused by Design Omission.Design Mods Made
Event date:
Report date:
3211981010R01 - NRC Website

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t,0 t,3 DOCKL T NUMUEH 84 t=9 EVLN1 (JAI E 74 7b HEPOn1 DA10 80 EVENT DESCnlPTION AND PHoBA8tE CONSEoVENCES h 10121 During normal power operation the site was notified by the AE that the i

ULLa_j I /G 1A and 1C outlet service water piping and associated seis.nic supports!

D 10121 [ exceeded code limi ts.

Similar but not as serious deficiencies were also1 10151 lr_eported on pipe supports associated wi th D/Gs 2A, 2B, and IB service l

IO lc i kater nioing.

There were no effects upon nalblic health and safety due i

O 7 lto this event.

This is a r(petitive occurrence as last reported by i

I O 18 I LL E R # s 50-366/1980-136 and 50-321/1980-100.

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3J J4 35 36 31 40 41 42 43 44 47 CAUSE DESCnlPTION AND CORRECTIVE ACTIONS h 1i1011 It was discovered that an axial force wa s inadvertently omitted from I

li111 I the pipe stress analyses and support de' sign loads for the outlet PSU 1

i iil7; Ipiping attached to D/G 1A & IC.

Upon discovery the D/Gs were declared 1

l inoperable and the Rx was brought to cold S/D per T.S.

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LER #:

50-321/1981-010 Licensec:

Georgia Power Company Facility Name:

Edwin I.

llatch Docket #:

50-321

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Narrative

Report for LER 50-321/1981-010 During normal power operation the site was notified by the AE of a condition where the outlet plant service water piping attached to D/Gs 1A and 1C and the associated pipe supports exceeded code limits and FSAR commitments.

Upon discovery of this fact the associated emergency dicsc1 generators 1A and 1C were declared inoperable, and the reactor was brought to cold shutdown per Tech Specs section 3,9.B.

The review icading to the determination of these deficiencies was precipitated by a syster walkdown performed in response to IEB 79-14.

The evaluation,1crformed by the AE revealed that an axial force inherent only to piping designs c wenining bel-lows. cxpansion joints in the pressure boundary was inadver-tently omitted from the pipe stress analyses and support des-ign loads for the subject piping.

Subsequently, all other safety related piping systems containing'bcllows were reviewed for cach unit.

Similar, but not as serious deficiencies were found on D/Gs 2A, 2B, and 1B.

During cold shutdo':a of IINP-1 and prior to startup from the existing refueling cutage of IIN P-2, recommended design modifications were received from the AE and incorporated satisfactorily in the field.

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