ML19329F915

LER 80-007/01T-0:on 800619,at Full Power,Test IT-04 Was Performed W/Emergency Diesel Generator 3D Out of Svc. Emergency Safeguards Train Equipment Would Have Been Inoperable on Loss of Ac Power.Caused by Personnel Error

ML19329F915
Person / Time
Site:	Point Beach
Issue date:	07/03/1980
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19329F914	List: ML19329F913 ML19329F915
References
LER-80-007-01T-01, LER-80-7-1T-1, NUDOCS 8007110357
Download: ML19329F915 (2)

Text

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U. S. NUCLE A3 KEIULATO*,Y COMMISSION CPC F&14 m a.m . .

LICENSEE EVENT REPORT CoNrRoL stoCx: } l l l l j@ PLEAsE PRINT c2 TYPE ALL CEQUIRED INF3KMATICN)

TO TT1 I w I II P l B l n i 2 j@l 0 l 01 - l 0101010101 - l 01025l@l26 411LICENSE l 1 { TYPE 111Jol@lS7 GAT l l@

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le it LICENSE NuwSER 7 8 9 UCENSEE CODE I CON'T E

7 8 E"R$ l L l@l 0 l 5 l 0 l 0 l 0 l 3 l 0 l1 )@l 0 l 6 l1 { 9 l 8 l 0 l@l0 l 7 l 80 61 DOCKET NUMS E R 68 69 EVENT OATg 7e 75 REPORT DATE 80 EVENT DESCRIPTION AND PROSA8tE CONSEQUENCES h l g lAt 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on 06-19-80 with Unit 2 at 100% power, test IT-04 was Emergency j done including stroking of "B" RHR pump suction valve. l FOTTl I j 1 g l safeguards train equipment would have been inoperable on a loss of AC l

pqT) l power because emergency Diesel generator, 3D, was OOS for maintenance.

d f l01611Both RHR systems were momentarily inoperable had a loss of AC occurre . j 1 Similar l l 1OI7IIReportable under Technical Specification 15.6.9.A.2.

1 g lLER 80-006. _

80 7 8 9 COMPONENT CODE SU8C00'E SU E DE CO E SU8C E l'O lT) lS lF j@ @@ y@ lP lU lM lP lX lX l@ @@ W @

12 83 18 19 20 7 8 9 to 11 REPORT REVISION SE DUE NT14 L OCCURRENCE CODE TYPE NO.

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33 34 JS CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l 1 101 l Personnel Error: Short-term action- orchibit oeriodic testina until I

i i lemeraency Diesel aenerator. 30, is returned to service. Leno-Perm i

, 2 1 action; additional administrative policies and procedure changes are

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g ibeing reviewed.

J 1 4 l 80 7 8 9 01 RY OfSCOVERY OESCRIPTION

% POWER OTHER STATUS ST S W @l Management observation j Q y @ l1l0l0j@l N/A l A TlVlTY CO TENT LOCATION OF RELEASE @

$ [Z_j @ l_Zj@l N/A AMOUNTOF** ACTIVITY @l RELEASEO OF RELEASE l l N/A "

PER$cuNEL ExPOSuAES Nuw,ER TYPE DESCRIPTION @ i j

[TT71 101010 l@LIJ@l " N/A PERSONNENEEEs NuwSER OESCRiPriON@ l i a 8 9 l 0 l 0 l -11 0 l@l 12 N/A 80 7

LOSS OF OR O AMAGE TO FACILITY TYPE OL$CRIPTION l

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7 9 to C. W. Fay "" "

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.o ATTACHMENT TO LICENSEE EVENT REPORT NO. 80-007/OlT-0 4

Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 2 Docket No. 50-301 Unit 2 was operating at 100% power at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on June 19, 1980 when inservice test IT-04 was performed.

IT-04 satisfies the residual heat removal (RHR) pump and valve operability assessment as required by ASME Code Section XI, IWP Section 1100. Step 3.2 of IT-04 calls for the stroking of motor-operated valve (MOV) 856B, suction valve from the refueling water storage tank to the "B" RHR pump.

Valve MOV-856B is a normally open valve requiring approximately 90 seconds to move from its full-open to full-closed position and. return to its full-open position. The valve operated satisfactorily during IT-04, b~ut during the time of cycling, "B" RHR pump suction from the refueling storage water tank could not have been assured. The pump would not have been 1 able to perform its intended function in its intended manner l with reduced suction; therefore, "B" RHR system was momentarily considered to be inoperable.

At about 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> on June 16, diesel generator 3D

, was removed from service for an annual inspection and was not available to supply power to engineered safeguards train "A" equipment on a loss of AC power on June 19. Had a loss of AC power occurred, "A" RHR pump would not have operated.

Had a loss of AC power occurred simultaneously with the cycling of MOV-856B, neither "A" nor "B" RHR train would have been fully functional for a short period of time (<90 seconds).

Valve 856B has manual override capability and is readily accessible to operations personnel. Valve position is indicated by limit switch lights located on the main control board.

A lapse of personnel attention to the details of plant conditions along with testing surveillance requirements caused this event.

The short, term corrective action was the postponement of any other periodic testing until diesel generator 3D was returned to service.

The Managers' Supervisory Staff has determined that if certain periodic tests fall within the time when a diesel generator is out-of-service, specific Staff approval.is required prior to performance of the test.

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