ML19269E578

LER 79-037/01T-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

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: ML19269E569 ML19269E578
References
LER-79-037-01T, LER-79-37-1T, NUDOCS 7906290306
Download: ML19269E578 (3)

Text

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4 l tion valves B21-F022 A. B. C, and D did not have a comolete temoerature and radiation I s 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 7 Iworst case failure of these limit switches would only result in a loss of valve positiop lindication on the failed valve or the tricoing of the main steam isolation valves (cont)i  !

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JI l010l0IUl 40 lY lg 41 lN [g lN lg lN l0 l0 l7 jg 42 43 44 47 CAUSE CESCRIPTICN AND CCRPECTIVE ACTIONS h o l At the time of installation, the NAMC0 Model SL3-E2W limit switches were not reauired i  ;

i I to have environmentally cualified test report documents. The later imolemented IEB i  ;

17 l 79-01 requires that all IE equipment in the drywell meet test. qualifications for  ;

3 l accident conditions. A new NAMC0 Model EA-740-8000 limit switch has been ordered and 4 t i t will be installed at the first scheduled cold shutdown upon receipt of the new (cont)i 8 9 80

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- 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. .

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. I 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. d 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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