ML20043A469

LER 90-008-00:on 900417,discovered That Testing of LPCI Pumps & Core Spray Subsystems Not Performed When LPCI Pump D Declared Inoperable on 900414.Caused by Personnel Error. Procedures Declaring Pump Inoperable revised.W/900516 Ltr

ML20043A469
Person / Time
Site:	Peach Bottom
Issue date:	05/16/1990
From:	Fulvio A PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-008, NUDOCS 9005220107
Download: ML20043A469 (4)

Text

s CCN-90-14094' PHILADELPHIA ELECTRIC COMPANY

. PEACll BUTIUM A1DMIC POWER STATION R. D.1, Ikix 208 'I Delta, Pennsylvania 17314

, . PEEN banUtl. tnt POWER OF R ECEL11Nca (717)456-7014 ~

. May 16,'1990 Docket No.' 50-277

. Document Control Desk U. S.. Nuclear Regulatory Commission Washington, DC 20555  ;

SUBJECT:

Licensee: Event-Report .

i Peach Bottom Atomic-Power-Station - Unit 2 1

This LER' concerns a violation of Technical Specifications because of a. ~

missed-surveillance'due to a personnel error' i

Reference:

Docket No. 50-277 Report Number: 2-90-008 Revision Number: 00 Event Date:- 04/14/90 Discovery Date: 4/17/90 Report Dath 05/16/90 1

Facilit a {

Peach Bottom Atomic Power Station '

RD 1. Box 208,-Delta,-PA 17314 r This LER is being submitted pursuant to the-requirements of 10 CFR' '

50.73(a)(2)(1)(B). i

. Since' rely.

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1 ant Manager cc: J. J. Lyash, USNRC Senior Resident inspector '!

T. T. Martin, USNRC, Region I '

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ADOCK 05000277 PDC

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LICENSEE EVENT REPORT (LER)

DOCKEY NUMSIR (28 P AGI '3' F ACILITY NAME III Peach Bottom Atomic Power Station - Unit 2 0 l5 l 0 [0 l 0121717 1 lOFl 0 l3

'" Technical Specification Violation Caused By Personnel Error Results In Missed Low Preneure core coolino System S'Irveillances EVENT DAf t (St LE R NUMSER (G) REPORT DATE til OTHER F ACILITIEE INVOLVED (8)

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NAME TE LEPHONE NUMBE R A84t A CQDE A. A. Fulvio, Regulatory Encjineer 711 l7 4l 5 l 6 l -l71 of 114 COMPLif t ONE LINE FOR E ACH COMPONE AT F AILURE Of 8CRitfD IN THl3 REPORT 1131 COMPONENT "Yo %,R0" * "'s' ' CAust sy STEM COvPONENT a OnT Astt CAUSE Sv 81 E M X'g*C M(NNC pq $

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On 4/17/90, 0850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br />. Operations personnel discovered that testing of Low Pressure Coolant injection (LPCI) pumps and Core Spray subsystems were not performed as I required by Technical Specification 4.5.A.4. This testing was required because the D LPCI pump was inoperable.when the Unit 2 Reactor mode was changed from shutdown to i

' refuel on 4/14/90, 2218 hours0.0257 days <br />0.616 hours <br />0.00367 weeks <br />8.43949e-4 months <br />. On 4/17/90, 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br />, a shift permit applied to the  !

D LPCI pump was cleared and the pump declared operable. The cause of this event was personnel error in not recognizing the inoperable status of the D LPCI pump when  ;

changing the reactor mode from shutdown to refuel. The D LPCI pump was declared I inoperable due to a unique design condition on Unit 2. No actual safety consequences ..,

l occurred as a result of this event. Appropriate Operations personnel will be  ;

I informed of this event. Procedural controls that involve declaring the D LPCI pump l

inoperable for the unique design condition requirement will be revised to require the

! mode switch be included within the blocking permit for the D LPCI pump. There were no previous similar LERs.

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Requirements'for the: Report'

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y This report =is required per'10 CFR 50.73(a)(2)(1)(B) because of?a condition.

prohibited;by' Technical Specifications-(Tech Specs).

l 'Un'it' Status at Time of Discovery Unit 2 was-in the Refuel Mode '

The-20 Residual-Heat Removal (RHR) (EIIS:B0) pump (EIIS:P) was tagged-out as part of a shift permit (i e.t pump declared. inoperable)-

lThe.2C-RHRpumpwas11nserviceintheshutdowncooling(SDC)modeof_RHR.'

l Description of Event- ,

.On 4/17/90, 0850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br />, Operations personnel discovered that testing of Low Pressure.

Coolant Injection (LPCI) pumps.and Core Spray (EIIS:BM)csubsystens.were _not performed as required by Tech Spec 4.5.A.4. : Tech Spec 4.5.A.4. requires that.with one LPCI pump

~ inoperable, the remaining 1LPCI pumps an6 associated flowpaths and both . core spray-subsystems be demonstrated to be operable by' testing within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sTand at;least once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />'.thereaf ter until. the LPCI pump is restored'to an operable status.-

-If this! testing cannot be performed, Tech. Spec 3.5 A.7-requires the initiation'of an orderly shutdown and to be:in the cold shutdown condition within 48' hours' This .

testing was required because the 20 RHR pump (.i.e..lLPCI' pump) was inoperable when ,

the Unit 2' Reactor (EIIS:RCT) mode-was changed from shutdown to refuel on'4/14/90, 2218. hours. Previous to this time, Unit 2 had been in the cold shutdown coridition and LPCI was not required to be operable. The 20 RHR pump was inoperable.because of' a unique design condition on Unit 2Lwhich necessitates the.2D RHR pump to be declared:

inoperable and blocked from service whenever the-2A,-2B or 2C RHR pumps are used;for SDC. .This unique design condition exists because the minimum flow valve'(Ells:V) for-the 2D RHR pump is.a normally open. valve to meet the requirements ofL10 CFR 50 ~

Appendix:R. As a result, to prevent inadvertent Reactor drain down events during SDC'  ?

operation, the minimum flow valveihas to be closed-(thereby rendering the 20.RHR pump.

• 1.noperable).

1 On 4/17/90, 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br />, a shift' permit applied to the 20 RHR pump was-clearedLand the pump was declared operable. The 2C RHR pump was secured from the SDC mode of operation prior to clearing the permit on the 2D RHR: pump.

Analysis of the Event No actua'l safety consequences occurred as a result of this event.

Subsequent testing proved that the other RHR pumps and the Core Spray System were 'i l operable 'during the time the mode switch was placed in refuel until the 20 RHR pump -

was declared operable. Because the other RHR pumps and' Core Spray System were  ;

operable through this time, this equipment would be available to provide low pressure core cooling if,needed.

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Additionally, lech Specs allow' 7 days of continued reactor operation with 1 RHR. pump inoperable. Ine 2D RHR pump was made-operable within this 7 day: Limiting Condition i

for Operation (i.e ~2D RHR pump was inoperable in the refuel mode for approximately 2 1 1/2' days).

~

Cause of the Event

The cause of this event was personnel error in not recognizing S e-inoperable, status a of the 20 RHR pump when-changing from the shutdown mode to the refuel mode of i operation. General-Plant' Procedure GP-11C, " Reactor Protection System Refuel Mode

. Operation'.' requires that prior to changing the plant mode tearefuel, LPCI be operable.

as specified in Tech Specs.. This step was signed:off-as satisfactory by Operations  !

personnel (Utility, Licensed) '

Corrective Actions .J 1

The 20 RHR pump was returned to an operable status on.4/17/90, 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br />, thereby.

complyingw'ith Tech Specs. Appropriate Operations personnel will be informed of this event. To provide an additional. barrier to prevent' recurrence of this event, .

procedural controls that involve declaring the 20 RHR pump inoperable when using the L2A, 28 or 2C RHR pumps for SDC will be revised to require the mode switch (EIIS:JS) be included within the blocking permit for the 20 pump.

Previous Similar Events ,

There have been no previous similar LERs caused by personnel error involving the non-- '

performance of surveillances that are required as a result of a mode switch change. '

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