05000321/LER-1979-037-01, /01T-0 on 790612:GE Review of Class IE Drywell Equipment Per IE Bulletin 79-01 Found Incomplete Documentation of Limit Switches on MSIV B21-F022 A,B,C & D. Caused by Changed Requirements.New Switch Ordered

/01T-0 on 790612:GE Review of Class IE Drywell Equipment Per IE Bulletin 79-01 Found Incomplete Documentation of Limit Switches on MSIV B21-F022 A,B,C & D. Caused by Changed Requirements.New Switch Ordered

ML19269E578
Person / Time
Site:	Hatch
Issue date:	06/18/1979
From:	Thomas Greene GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19269E570	List: 05000321/LER-1979-037, Forwards LER 79-037/01T-0 05000321/LER-1979-037-01, /01T-0 on 790612:GE Review of Class IE Drywell Equipment Per IE Bulletin 79-01 Found Incomplete Documentation of Limit Switches on MSIV B21-F022 A,B,C & D. Caused by Changed Requirements.New Switch Ordered
References
LER-79-037-01T, LER-79-37-1T, NUDOCS 7906290306
Download: ML19269E578 (3)

LER-1979-037, /01T-0 on 790612:GE Review of Class IE Drywell Equipment Per IE Bulletin 79-01 Found Incomplete Documentation of Limit Switches on MSIV B21-F022 A,B,C & D. Caused by Changed Requirements.New Switch Ordered

Event date:
Report date:
3211979037R01 - NRC Website

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8 60 61 COCK ET NUM6ER bd b3 EVENT OATE J4 75 HEPORT OATE 80 EVENT oESCRIPT3oN AND PROBABLE CONSEGUENCES h i2 l Ouring the 1979 refueling outage a General Electric review of Class IE drvwell equio-J I ment in response to IEB 79-01, indicated that the limit switches on main -steam isola- [

is l tion valves B21-F022 A. B. C, and D did not have a comolete temoerature and radiation I 4

I oualification test report document to aualify it to perform under an accident con-I s

I dition. There was no significant effect on olant safety from this event since the' j

s Iworst case failure of these limit switches would only result in a loss of valve positiop 7

lindication on the failed valve or the tricoing of the main steam isolation valves (cont) i a

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JI 40 41 42 43 44 47 CAUSE CESCRIPTICN AND CCRPECTIVE ACTIONS h l At the time of installation, the NAMC0 Model SL3-E2W limit switches were not reauired i o

I to have environmentally cualified test report documents.

The later imolemented IEB i

i l 79-01 requires that all IE equipment in the drywell meet test. qualifications for 17 l accident conditions. A new NAMC0 Model EA-740-8000 limit switch has been ordered and 3

t t will be installed at the first scheduled cold shutdown upon receipt of the new (cont) i i

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NAME OF PREPARER

Georgia Power Company E. I. Hatch' Nuclear Plant Baxley, Georgia 31513 Reportable Occurrence No.

50-321-1979-37 Event Description And Probable Consequences Cont.

to the failed closed or safe condition on the failed valve.

Since the outboard MSIVs would still have valve position indication and function normally out of the accident environment,.there would still be a re-i dundant main steam isolation valve' with valve position indication.

This is a non-repetitive occurrence.

Cause Description And Corrective Actions Cont.

limit switches.

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NARRATIVE

REPORT 0

LER 79-037-01-T-0 F

On June 12, 1979, during the 1979 refueling outage a General Electric Company review of Class IE electrical equipment in' the drywell, in response to IE Bulletin 79-01, indicated that the limit switches on main steam isolation valves 821-F022 A, B, C, and D did not have a complete temperature and radiation qualification test report to qual-y ify it to perform under an accident condition.

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There was no significant effect on plant safety from this event since the worst case failure of these limit switches would only result in a j

loss of valve position indication on the failed valve or the tripping of the main steam isolation valves to the failed closed or safe condi-U tion on the failed valve.

Since the outboard MSIVs would still have valve position indication and function normally out of the accident en-E vironment there would still be a redundant main steam isolation valve with valve position indication that would function normally.

At the time of the installation, the NAMCO Model SL3-82W limit switches were not required to have environmentally qualified test report docu-ments.

The later implemented NRC IES 79-01 requires that all IE equipment j

in the drywell meet test qualifications for accident conditions.

A new NAMCO model EA-740-8000 limit switches has been ordered and it will be installed at the first scheduled cold shutdown upon receipt of the new limit switches.

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