ML19325E597

LER 88-003-01:on 880301,while Performing RCIC Monthly Test, RCIC Pump Could Only Achieve 400 Gpm Against Discharge Pressure of 500 Psig.Caused by Failed Hydraulic Actuator on Turbine Governor Valve.Actuator replaced.W/891024 Ltr

ML19325E597
Person / Time
Site:	Quad Cities
Issue date:	10/24/1989
From:	Bax R, Hill K COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-88-003-03, LER-88-3-3, RLB-89-223, NUDOCS 8911080074
Download: ML19325E597 (4)

Text

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/,,NJ: Commonwealth Edison  :

) ouad Cit:cs Nuclear Power Station

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. i, g lj 22710 206 Avenue North '

,' -% Cordova. Illinois 61242 9740

' \ Telephone 309/654 2241

'RLB-89-223 -

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October 24, 1989 {

U. $.. Nuclear Regulatory Commission Document, Control Desk ,

. Washington, DC .20555 <

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Reference:

Quad Cities Nuclear Power Station Docket Number 50-265, DPR-30, Unit Two Enclosed is Licensee Event Report (LER)88-003, Revision 01, for-Quad Cities Nuclear Power Station.

This report.is submitted in accordance with the requirements of the Code of Federal Regulations, Title 10, Part 50.73(a)(2)(v), which requires the i reporting of any event or condition that alone could have prevented the

' fulfillment of the safety function of structures or systems that are needed to

. remove residual heat. -

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Respectfully, l.

COMMONWEALTH EDISON COMPANY QgAD CITIES UC POWER STATION .

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l. R. L. x t

. Station Manager L.

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.RLB/MJBlad

l. Enclosure E

-cc: R. Stols R. Higgins INPO Records Center NRC Region III

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2318H/0683Z 8911080074 891024 PDR->cADOCK.05000265

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[ LICENSEE EVENT REPORT (LER)

Facility,Name (1) Docket Number (2) Ploe (1) 6 Quad Eities Unit Two 01 El ol of ol 21 61 5 1 of al3 l Tit.le (4)

Elf Inanarable Due to Failed Governor Actuator

,_ Event Data fE1 LE W er (6) Reoort Date (71 Othe* Facilitiet Involved (B)

Month Day Year Year /// Sequential / Revision Month Day Year Facility Names Docket Numby ft) l j/j,/

/ h ar //j/j j/

/ Number l

of El of of of I l

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of 3 01 1 al a al a oIo13 o11 1 Io 214 al 9 ofElol01of I I I THIS REPORT !$ SUBMITTED PUR$UANT TO THE REQUIREMENTS OF 10CFR OPEUN fCheck one or more of the followinal f11) 4 20.402(b) ,, 20.405(c) ,_ 50.73(a)(2)(iv) ___ 73.71(b)

POWER 20.405(a)(1)(1) 50.36(c)(1) _X_ 50.73(a)(2)(v) _._ 73.71(c)

LIVEL ___. 20.405(a)(1)(11) __ 50.36(c)(2) _ 50.73(a)(2)(v11) _ Other (Specify (101 ol9l6 _._ 20.405(a)(1)(iii) 50.73(a)(2)(1) 50.73(a)(2)(viii)(A) in Abstract

/////////////u/////////// _ 20.405(a)(1)(iv) _ 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) below and in

/////////////'/////////////

j _ 20.405(a)(1)(v) _ 50.73(a)(2)(itt) _._. 50.73(a)(2)(x) Text)

LICENSEE CONTACT FOR THIS LER f12)

Came TELEPHONE NUMBER AREA CODE K. J. Hill. Technical staff Enoineer. Fxt. 2150 1loI9 61 El al -l 21 21 41 COMPLETE ONE LINE FOR EACH COM FAILURE DESCRIBED IN THIS REPORT f131

• CAUSE SYSTEM COMPONFNT MANUFAC- REPORTABLE CAUSE SYSTEM COMPONENT MANUFAC- REPORTABLE TURER TO NPRDS TURER 70 WPRDS X aiN I il El wl 21 91 o 1 I 1 1 I I I I l l l l l l l 1 1 I I I I t SUPPLEMENTAL REPORT EXPECTED (141 Expected Mor.th l Day l Ygg Submission lyes (If ves. conclete EXPECTED SUBMISSION DATEl X l No I I l ABSTRACT (Limit to 1400 spaces, i.e. approximately fif teen single-space typewritten lines) (16)

ABSTRACT:

On March 1, 1988, Unit Two was in the RUN mode at approximately 96 percent power.

At 1005 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.824025e-4 months <br />, while performing QOS 300-1, " Reactor Core Isolation Cooling (RCIC)

Monthly Test," it was found that the RCIC pump [P) could only achieve 400 gpm (rated) against a discharge pressure of 500 psig with a turbine speed of 3,000 rpm. Normal pressure and speed is 1,250 psig at 4,500 rpm. RCIC was declared inoperable and NRC notification of this event was completed at 1155 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.394775e-4 months <br /> per 10CFR50.72. Work Request Q64717 was written to investigate the problem and to make repairs. ,

It was determined that the cause of this event was due to a failed hydraulic actuator [15] on the turbine [TRB] governor [65] valve (V). The actuator was replaced on March 2, 1988, and RCIC was successfully tested at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />. The failed actuator was sent to the manufacturer who determined that the problem was an electronic failure. This report is provided per 10CFR50.73(a)(2)(v)(B).

2317H/06832

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rev 2.0 FACILITY NAME-(1) DOCKET NUMBER (2) LER NUMBER f61 Pace (3) s Year seguential Revisicn g//

/ Number g//

/ Num*1t_

W Citlet Unit Two oIE!Ol0lol21615 Bl8 . Ol013 - 0i 1 012 0F 013 TEXT Energy Industry Identification SystNn (E!!S) codes are identified in the text as (Xx)  ;

PLANT AND SYSTEM IDENTIFICATION: ,

General Electric - Bolling Water Reactor - 2511 MWt rated core thermal power.

EV_ENT 10ENTIFICATION: RCIC Inoperable Due to Failed Governor Actuator A.. CONDITIONS PRIOR TO EVENT:

Unit: Two Event Date: March 1, 1988 Event Time: 1100 Reactor Mode: 4 Mode Name: RUN Power Level: 96%

This report was initiated by Deviation Report 0-4-2-88-009.

RUN Mode (4) - In this position the reactor system pressure is at or above 825 psig, and the reactor protection system is energized, with APRM protection and RBM interlocks in service (excluding the 15% high flux scram).

8. DESCRIPTION OF EVENT:

At 1005 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.824025e-4 months <br /> on March 1, 1988 Unit Two was operating in the RUN mode at approximately 96 percent of rated core thermal power. The Unit Two Nuclear. Station Operator (NS0) was in the process of performing QOS 1300-1, Reactor Core Isolation Cooling (RCIC)[BN] Monthly Test. This test employs a " fast start" testing method as described in General Electric Service Information Letter (GE SIL) 336. During this test, the RCIC system normally achieves full pump [P) flow of 400 gallons per 01nute (gpm) against a pump discharge pressure of 1,250 psig with turbine [TRB]

speed at approximately 4,500 rpm. However, in this event, the RCIC system was only able to achieve a pump flow of 400 gpm against a discharge pressure of 500 psig at I

a turbine speed of 3,000 rpm. Operating personnel in the RCIC room during turbine operation noted that the turbine governor-[65) valve [V) which is normally full open during standby operation, was closing satisfactorily upon turbine initiation but failed to open after the initial speed transient to increase turbine speed. At 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, RCIC was declared inoperable due to the inability of the RCIC pump to deliver at least 400 gpm against a system head corresponding to a reactor vessel l [RPV) pressure of 1,150 psig as required by Technical Specification Section 4.5.E.1. RCIC Outage Report, QOS 1300-01, was immediately initiated. NRC notification of the event via the Emergency Notification System (ENS) phone system was completed at 1155 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.394775e-4 months <br /> to comply with the requirements of 10CFR50.72. Work l

Request Q64717 was written to investigate the problem and make repairs. The test was repeated at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> and at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> on March 1, 1988. IM personnel were L in attendance to check operation of the flow controller [FC] in the control room L and the turbine governor valve and governor actuator in the RCIC room. IM l personnel determined that the cause of the turbine failing to increase speed was 1 due to a failed hydraulic actuator on the turbine governor valve.

1 The actuator was replaced on March 2, 1988, and QOS 1300-1 was successfully completed at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on March 2, 1988. The RCIC system was declared operable and the outage survelliances terminated.

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L 2317H/06832 l

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,, LICENSEE EVENT REPORT fLER) TEXT CQRTINUATION Form Rev 2.0 i DOCKET hupetR (2) LER NUMBER f6) L Paae (3)

FACILIJY NAME (1)t

,/pj $equential

// RevistGn

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• Year // j

/// Number j///jj/ Number h j-Guad cities unit Two 0lEl010 1 0 1 21 61 E aia - O l013 - 0l1 013 0F 013.

TEXT Energy Industry Identification system (E!!s) codes are identified in the text as (XX] t C. APPARENT CAUSE OF EVENT:

This event is being reported according to 10CFR50.73(a)(2)(v)(B), which requires the reporting of any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to remove residual heat.

The cause of this event is component failure. The hydraulic actuator on the RCIC turbine governor closed satisfactorily but failed to open to increase turbine speed. The actuator was sent to the manufacturer, who determined that the problem was due to an electronic failure.

D. SAFETY ANALYSIS OF EVENT:

The safety of the plant and public was not affected during this event. The RCIC .

system is a standby safety system used to pump make-up water to the reactor vessel in the event of a reactor isolation accompanied by a loss of flow from the reactor feedwater system [S)). The RCIC system supplies sufficient make-up water to replace the water lost by steam generation as a product of core fission decay

< heat. The RCIC system will automatically initiate upon receipt of a reactor vessel low-low water level (-59 inches)[JE). If a low-low water level had occurred, all other Emergency Core Cooling Systems (ECCS) were available to bring the reactor to a safe shutdown condition.

E. CORRECTIVE ACTIONS:

The actuator was replaced line-for-like under Work Request Q64717. No problems were found with either the governor valve or the remote hydraulic servo which is

! hydraulically connected to the actuator and positions the governor valve. Since there are no previous reported fallures of this component, it is considered to be y an isolated incident. .No further corrective action is necessary.

l~ F.- PREVIOUS EVENTS There are no previous events similar to this one at Quad Cities Station. A search of the Nuclear Product Reliability Data System found no similar occurrences of failure of the hydraulic actuator on a turbine governor, u

G. COMPONENT FAILURE DATA:

, The hydraulic actuator is manufactured by Woodwaro Governor Company. It is a 1 Hoodward EG-R actuator and is supplied as an accessory for the GS Model Terry 1: Turbines.

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