05000321/LER-1981-016-03, /03L-0:on 810306,review of Data Sheets from 810304 LLRT of Inboard MSIVs B21-F022A,B & C Determined That Valves Were Leaking in Excess of Tech Spec.Cause Unknown. Investigation Underway.Valves Will Be Repaired & Retested

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/03L-0:on 810306,review of Data Sheets from 810304 LLRT of Inboard MSIVs B21-F022A,B & C Determined That Valves Were Leaking in Excess of Tech Spec.Cause Unknown. Investigation Underway.Valves Will Be Repaired & Retested
ML20003E244
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 03/26/1981
From: Coggin C
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20003E243 List:
References
LER-81-016-03L, LER-81-16-3L, NUDOCS 8104020594
Download: ML20003E244 (2)


LER-1981-016, /03L-0:on 810306,review of Data Sheets from 810304 LLRT of Inboard MSIVs B21-F022A,B & C Determined That Valves Were Leaking in Excess of Tech Spec.Cause Unknown. Investigation Underway.Valves Will Be Repaired & Retested
Event date:
Report date:
3211981016R03 - NRC Website

text

u=v LICENSEE EVENT REPORT CoNTnol OLoCK: l l

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(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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te0 61 COC A ET NUY6E H iA b3 EVENT DATE 14 15 HEPOHT DATE do EVENT DESCRl TION AND PROBADLE CONSECUENCES h 2 10n 3-4-81, with Unit I shutdown for a refueling / torus modification out-l 10 la) I age. LLRTs of inboa rd MSIVs B21-F022A, B, and C were performed.

On 3-l

{ O-l 4 l l 6-81, the data sheets were reviewed by the LLRT coordinator, and it was l

~

IO isi l determined that the valves were leaking in excess of t'he 11.5 scfh per 1

0 6 Ivalve limit of Tech Specs 4.7.A.2.h (test volume would not pressurize). 1 0 7 lThis is a repetitive occurrence - refer to LER 50-366/1981-001.

There 1

Iwere no effects on public health or safety due to this event.

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8 9 60 C DE CODE SUDCO E CO*,iPONENT CODE SUSC dE S

E I C l D l@ [E._j@ l X l@ l V I A l L l V I E l X I@ l F l@ [D_j @

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10 11 12 13 Id 19 23 SEQUENTIAL OCCURRENCE REPORT REVislON LER EVENT YE AR NEPORT NO.

CODE TYPE NO.

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_ 24 22 23 24 26 27 28 23 30 31 32 Kf AC O ON PLANT

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33 34 3d 36 3/

40 44 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS lilOl l The cause of the valves' leakino is unknown at the present time; an in-I i i Ivestication is underway.

The valves will be repaired and successfully I

l refeMed prior to startup following the outape.

An update report will I

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lTTTl I b e s u b mi t t e d.

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% POWER OTHER STATUS dtS O RY Oi!COVERY DESCRIPTION [f.j @ l Ol ol 01 @ l f1A l

l B l@l Performed LLRT l

i 5 ACTivtTY CO TENT RELE ASED OF RE LE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE [2] @ [JJ @ l fiA l

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DESCRIPTION

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8 9 11 12 LOSS OF OR DAYAGE TO FACILITY

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DE SCHIF TION 7

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50-321/1981-016 Licensce:

Georgia Power Company Facility Name:

Edwin I. Ilatch Docket #:

50-321

Narrative

Report for LER 50-321/1981-016 On 3-4-81, with Unit 1 shutdown for a refueling / torus modific-ation outage, LLRTs of inboard main steam isolation valves

.B21-F022A, B,

and C were performed per procedure llNP-1-3952,

" Primary Containment Periodic Type B

and Type C

Leakage Tests".

On 3-6-81, the LLRT coordinator reviewed the data sheets, and it was determined that the valves were leaking in excess of the 11.5 scfh per valve limit of Tech Specs 4.7.A.2.

h (test volumes would not pressurize).

This is a repetitive occurrence refer to LER 50-366/1981-001.

There were no effects on public health or safety.

The cause of the valves' icaking i s unknown at the present time; an investigation is underway.

The valves will be

_.f) repaired and successfully rctosted prior to startup following the outage.

An update report will be submitted.

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