ML20042B975

Slide Presentation Entitled LER Info & Data Flow Process

ML20042B975
Person / Time
Issue date:	03/16/1982
From:	NRC COMMISSION (OCM)
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ML20042B973	List: ML20042B972 ML20042B974 ML20042B975
References
REF-10CFR9.7 NUDOCS 8203290068
Download: ML20042B975 (1)

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LER INFORMATION A_ND DATA _F_L_0W PROCESS _

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Southern California Ea'ison Cornpany

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>I 400 2244 W AL NUT G ROV E AV[agy(

R051utAD C ALIFORNea 9 8 ? ?0 Parch 24, 1980

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U. S. Nuclear Regulaterf C=nnission Region V Office of Inspection and Enforcerrent Walnut Creek Plaza, Suite 202 1990 North California Boulevard Walnut Creek, California 94596 Attention: Pr. R. R. Engelken, Direc*ar

Dear Sir:

Cocket No. 50-206 San Onofre - Unit 1

'Ihis letter. describes a reportable occurrence involving cer*ain carpenents in the salt water ecoling system which are required to be cpale under San Cncfre Unit 1 Technical Specification 3.3.1.

Subrittal is in accordance with the reporting requirements of Technical Specificatien 6.9.2.a.

At 2Q5, hours en March 10, 1980 with the unit operating at 100 percent pcwer and with the south salt water eccling ptrno (G-13B) in operaticn, salt water c= cling pt::p lcv ficw and icw discharge pressure alarns were received en the main centrol recm auxiliary teard annt-sciator panel. Concurrently, the north salt water ecoling pu:ip (G-13A) autcratically started due to lcw pressure in the discharge line of scuth ptr:p G-13E and ptr:p G-13B rretcr a::perage was observed to be indicating icw.

Cperatcrs were then dispatched to the salt water ecoling pr:p ar'ea and repcrted that both ptr:ps were r.rming with discharge pressures of 0 and 40 psig indicated at the south (G-13B) and ncrth (C-13A) p',r:ps, respectively.

' he'eperatcrs further repcrted that the pnetreatically operated discharge j

valves (IOV's 5 and 6) cf each pu::p were in.the 'clcsed position. Under the

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ccnditiens cbserved, IW-5 (discharge of ncrt.h ptrrp C-13A) should have been-cpen while FOV-6 (dischaIge of scuth pu::p C-13B) should have been c1 sed.

9 Efforts were then initiated to open 50V-5.

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U. S. Nuclear Pegulatcry Ccmrission Page 2 At 2120 hours0.0245 days <br />0.589 hours <br />0.00351 weeks <br />8.0666e-4 months <br />, the auxiliary salt water ccoling pt=p, G-13C, sus manually started frcm the control recm. Ebwever, a 1cw ficw condition as indicated by

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,1cw pu p noter awge was observed. Investigation of the auxilia.mf purp and

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piping system iMicated that the icw ficw conditicn was due to apparent insuf-ficient pt=p priring and the auxilia:'/ pung was then stopped. In crder to re-establish salt water cooling ficw, the screen wash pt=ps were started frem the local panel and valves nanually aligned to discharge to the tettcm mget.

ccoling water heat exchanger, E-203, ncrually served by the north salt water punp, G-13A. At 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />, salt water cooling ficw to E-203 was observed to be alcut 2000 gpn and wu.@nent ecoling water te=perature exiting E-203 was f_,

decreasing, having reached a peak value of 82*F.

At 2156 h::urs, adequate priming was restored to the auxilia.mf salt. water pt=p, G-13C, and the pt.p was placed in service.

During the pericd described above, a limiting ccnditicn for cperaticn of Technical Specification 3.3.1.A was not ret. Consistent with the require:ent of the specification that the reactor shall not be raintained critical unless the specified limiting ceniitiens are net, preparatiens were rade tc cc=rence an crderly shutdcun of the init. Ek: wever, at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> with the aM14mmf salt water pt=p restored to opention and cc:.sistent with the previsicn of Technical' Specification 3.3.1.B, the trtit shutdcwn was te=inatal after,a slight load reduction ard full pcwer cperation was restrned while raintenana efforts to egen POV-5 continued. At 0005 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> en March 11, 1980, POV-5.was opened and the north salt water pt=p C-13A placed in service. At 0010 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, with the ncrth salt water pt=p and the auxiliary 5x..:p dete=rined to be operable, the am414ary pt=p was stopped and imit cpentien proceeded in acco:Mance with the limiting conditions for operation of Technical Specificatica 3.3.1.A.

2rotz;hout the above incident, adequate c= cling was naintained to equipnent nc= rally served by the w.waent ecoling water system during power cperation.

ne peak uuwent ecoling water heat exchanger exit ter:=erature of 82*F was well belcw the alarm conditien setpoint of 97'F.

Te peratures of pt=p bearings eccled by the uu.gaent ecoling water system were ronitored during the incident and no significant changes observed.

Investigations conducted to date have revealed that the south salt water c= cling pt=p, G-13B, shaft failed due to apparent excessive vibratica resulting fron worn tearings. n e pu p shaft and bearings have since been repaired and the pt=p returned to service. ne failure of P:N-5 to open autcratically and the problem of insufficient priring of auxiliary salt water pr:p G-13C are presently under investigation.

Pending the results of these investigations and.inplementation cf am.iate long te=n corrective actions to prevent recurrence, the follcuing measures are being taken to assure availability of required salt water cooling:

(1) POV-5 is being naintained cpen with the i

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U. S. Ibclear Regulatory Cotrission Page 3 north salt water pt=p rir:ning, and (2) the auxiliary salt water pc:p surveillance testing will be increased frczn cace per week te once daily during

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Icv tide conditions.

It is planned that 1cag te=n corrective acticn to prevent re<.urrence will be identified and inplemented ddring the forthconing Cycle 8 refueling cutage prier to returning San onefre Unit 1 to service.

It was concluded that acticns taken during this incident wera consistent with the recuirements of the San Cnefre thit 1 hchnical Specifications ard that plant cenditions were maintained such that there was ne effect en the public health ard safety.

An investigation is being carried i:ut to review the adequacy of precedures govermng cperatica of the salt water ccoling systen.-

If you have any questions, please centact me.

Sincerely, b

H. L. Otteson-Manager,1bclear Genera'ticn -

Attachnent:

Licensee Event Report 80-006 becter,1bclear Reacter Regulaticn (40)

Director, Office of Panagement Inic= ration & F.w.cen Centrol (3)

Direc*cr, ibclear Safety Analysis Center O

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64 69 OOCKETNuutta 64 49 tvtNT DATE 74 76 mtPQmTQATE SQ EVENT DESCRIPTION AND PRC8 ABLE CONSEQUENCES h Ioi21i Durino nc=al operation, the south salt water ecolig p;;p (SFCP) discharge

.t.o ! 2 i l pressure d-W sharply. ne north salt water.ecoling p::p (NS'<P) autmatically Io ea! I started en icw pressure. Ib ever, its discharge POV failed to cpen. We '

l Io is1 [ auxiliary salt water ecoling pt = 75CP) was then started but flew could not be Io is ] l es*c.blished. There was no effect og jdic health er safety.

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< ACCESSION NO.> OOZO155475

< TITLE >.ALL SALT WATER COOLING PUMPS FAIL AT SAN ONFORE 1

<CORPAUTH > SOUTHERN CALIFORNIA EDISON CO.

<DATE> 1980

< TYPE > Q

< MEMO > LTR W/LER 80-006 TO O.S. NRC, REOION 5,' MAR 24, 1990, DOCKET 50-206',

TYPE--PWR. MFG--WEST, AE--BECH

< AVAIL > AVAILABILITY - NRC PUBLIC DOCUMENT ROOM, 1717 H STREET, WASHINGTON, D.

C.

'20555 (08 CENTS /PAGE -- MINIMUM CHARGE

$2.00)

< CATEGORY.> 1700001050000

< EDITION > 0109

< CORP CODE > SCE

< COUNTRY > A

< ABSTRACT > DATE OF EVENT - 031080.

POWER LEVEL - 100%.

'CAUSE - VIBRATION, VALVE FAILURE, AND INADEQUATE PRIME.

DURING NORMAL OPERATION, THE SOUTH SALT WATER. COOLING PUMP (SSWCP) DISCHARGE PRESSURE DROPPED SHARPLY.

THE NORTH SALT WATER COOLINO PUMP (NSWCP) AUTOMATICALLY STARTED ON LOW PRESSURE.

HOWEVER, ITS DISCHARGE POV FAILED TO OPEN.

THE AUXILIARY SALT WATER COOLING

' PUMP-(ASWCP) WAS THEN STARTED BUT FLOW COULD NOT BE ESTABLISHED.

AS A RESULT OF ~(1) EXCESSIVE VIBRATION, THE SHAFT OF THE (SSWCP) SHEAREDi (2) MECHANICAL FAILURE, THE (NSWCP) POV GIO NOT OPEN; (3) APPARENT INADEQUATE PRIME, THE (ASWCP) LOST SUCTION.

THE POV ON THE (NSWCP) WAS MANUALLY OPENED AND THE (ASWCP) REGAINED SUCTION.

DESIGN OF THE.POV AND (ASWCP) IS UNDER INVESTIGATION.

SHAFT OF (SSWCP) BEING REPLACED.

< COMPONENT CODE > PUMPXX-PUMPS

< SYSTEM CODE > WB-COOL SYS FOR REAC AUX & CONT l

< KEYWORDS > FAILUREIREACTOR,'PWRISAN ONOFRE 1 (PWR)iFAILURE, EQUIPMENTIFAILURE, INHERENT; SERVICE WATER SYSTEMiPUMPSIREDUNDANCE;VIBRATIONiVALVESiCMASP; FAILURE. SEQUENTIALIFAILURE, LATENT l

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