ML19325E592

LER 87-017-01:on 870805,Group IV Isolation Received Which Resulted in Closure of HPCI Steam Supply Valves.Caused by Failed HPCI Steamline Differential Pressure Transmitter Due to Loss of Oil in Sensing cell.W/891024 Ltr

ML19325E592
Person / Time
Site:	Quad Cities
Issue date:	10/24/1989
From:	Bax R, Pairitz J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-87-017-01, LER-87-17-1, RLB-89-239, NUDOCS 8911080067
Download: ML19325E592 (6)

Text

F.

l . Commonwealth Edison

. ouad Cites Nuclear Power Station ,

s. , 32710 206 Avenue fiorth

.t

.- Cordova, Illinois 61242 9740  :

. Telephone 309 654 2241 RLB-89-239

October 24. 1989 U. S Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Quad Cities Nuclear Power Station

-Docket' Number 50-254, DPR-29, Unit One Enclosed is Licensee Event Report (LER)87-017 Revision 01, for Quad Cities Nuclear Power Statlon.

This report is submitted in accordance with the requirements of the Code of Federal Regulations,. Title 10 Part 50.73(a)(2)(iv) and (a)(2)(v), which require the reporting of any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature, and 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 or mitigate the consequences of an accident, respectively.

Respectfully, COMMONWEALTH EDISON COMPANY

., QUAD CITIES NUCLEAR POWER STATION R.L.Nx Station Manager l RLB/MJB/eb i

Enclosure  !

cc: R. Stols R. Higgins INPO Records Center  ;

NRC Region III I 2287H ts 891108vo67 891024 )

PDR ADOCK 05000254 -

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b* LICENSEE EVENT REPORT (LER)

Fpcility Name (1) Docket Number (2) . Pace f31 OljAD-CITIL1_HMCLEAR POWER STATIDL UNIT DNE 01 El el el el fl il 4 1 of a E

' Title (4) HIGH PRESSURE COOLANT IN,)ECTION SYSTEM INOPERABLE DUE 70 INVALIO SYSTEM !s0LATION FROM FAILED DIflit[NTI AL PRES $yOMit$MITTER __

l ,,.,.Lynnt Date (El Lig_gumber (6) RengIt Date (7) Othgr Facilities Inyglygg,_(11 Month Day Year Year /// sequential //jj/ Revision Month Day Year _ Facilit y Namet QQgkg1_gignbggL11 j//,

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of a el 5 al 7 al 7 o11 17 oI i t Io 214 al 9 el si al of of I I OPERATING (Check one or more of the followinal (111 4 20.402(b) 20.40s(c) _X. 50.73(a)(2)(iv) _ 73.71(b)

POWER _ 20,405(a)(1)(1) __ 50. 36(r. ) ( 1 ) _X_ 50.73(a)(2)(v) _ 73.71(c)

LEVEL 20.405(a)(1)(ii) 50.36W)(2) so.73(a)(2)(v11) Other (specify i

,, 1.101 1 o o 20.405(a)(1)(111) _ 50.73(a)(2)(1) ,_. 50.73(a)(2)(vitt)(A) in Abstract below

/,/ /,/,//,/,///,/ /,/ / /,/ /,//,// /,/ /,/ / 20.405(a)(1)(iv) _ 50.73(a)(2)(ti) 50.73(a)(2)(v111)(B) and in Text)

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LICEks[E CONTACT FOR TMIS LER f121 Name TELEPHONE NUMBER AREA CODE

.301EPH P. PAIRIT2 TECHNLCAL STAFF ENQ1NEER EXT. - 2159 3 Iol9 61 E l 41 l 21 21 41 ]

COMPLETE ONE LINE FOR EACH COM FAILURE DESCRIE(0 IN THIS REPORT (131 CAusE SYSTEM COMPONENT MANUFAC- REPORTABLE CAUsE SYSTEM l COMPONENT MANUFAC- REPORTABLE TURER TO NPRDS TURER To NPRDS X Bl J Pl Dl fl Ri 31 61 9 YES l l l l l l l l I I1 1 1 l l 1 I I l 1 i SUPPLEMENTAL REPORT EXPECTED (141 Expected Month i Day i Year submission lYet fIf vet. complete EXPECTED SUBMISSIDg_ RATE) X l No l I l ABSTRACT (Limit to 1400 spaces, i.e, approximately fifteen single-space typewritten lines) (16)

On August 5, 1987. Unit One was operating in the RUN mode at 100 percent of rated core thermal power. At 1212 hours0.014 days <br />0.337 hours <br />0.002 weeks <br />4.61166e-4 months <br /> during the performance of the High Pressure Coolant Injection (HPCI) system monthly operability test, a Group IV isolation was received which resulted in closure of the HPCI steam supply valves. The HPCI system was declared inoperable and Technical Specification required surveillances were initiated. The isolation was the result of a failed HPCI steamline differential pressure transmitter that detects excessive flow in the steamline. The exact cause of the transmitter failure was a loss of oil in the transmitter's sensing cell. The transmitter was replaced with a like-for-like replacement. This report is submitted in accordance with 10CFR50.73(a)(2)(iv) and (a)(2)(v).

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PLANT AND SYSTEM IDENTIFICATION:

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

EVENT IDENTIFICATION: High pressure coolant injection system inoperable due to invalid system isolation from failed differential pressure transmitter A.. CONDIVIONS PRIOR TO EVENTJ k

Unit: One Event Date: August 5,1987 Event Time: 1212 Reactor Mode: 4 Mode Name: RUN Power Level: 100%

This report was initiated by Deviation Report D-4-1-87-076.

RUN Mode (4) - In this position the reactor system pressure is at or above 825 psig, l and the reactor protection system is energized, with APRM protection and RBM i

. interlocks in service (excluding the 15% high flux scram).  ;

3. DESCRIPTION Oi EVENT:

- On August 5, 1987, at 1212 hours0.014 days <br />0.337 hours <br />0.002 weeks <br />4.61166e-4 months <br />, Unit One was in the RUN mode at 100 percent of rated core thermal power. While Operating personnel were performing QOS 2300-2, High Pressure Coolant Injection System (HPCI) Pump Operability, the HPCI [BJ) steam supply isolation valves (ISV), 1-2301-4 and 1-2301-5, closed due to a Group IV Isolation as the HPCI turbine [TRB] was being warmed. The isolation was due to an invalid HPCI steamline high differential pressure signal which is used to detect a ,

steamline break. The HPCI subsystem was then declared inoperable, and outage report 00S.2300-01, HPCI Subsystem Outage Report 7 Day Limitation, was immediately '

initiated. The outage report is used to record immediate and subsequent operator actions as well as document the operability of redundant systems. Technical Specification 4.5.C.2 requires that the Low Pressure Coolant Injection (LPCI) mode

- of the Residual Heat Removal (RHR) system (BO), both Core Spray subsystems (BM], the Automatic Pressure Relief (APR) subsystem, and the Reactor Core Isolation Cooling (RCIC) system (BN] shall ba demonstrated to be operable when it is determined that the HPCI subsystem is inoperable. 0.oerability surveillances were begun on these systems in order to comply with the Technical Specification requirement. The  ;

Instrument Maintenance Department initiated an investigation of the isolation.

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r An investigation by the Instrument Maintenance Department revealed that a differential pressure transmitter (PDT) (EPN DPT 1-2352) used to detect excessive HPCI steam supply line flow had failed. This failure resulted in the Group IV Isciation, although no excessive HPCI steam supply line flow existed.

At 2005 hours0.0232 days <br />0.557 hours <br />0.00332 weeks <br />7.629025e-4 months <br />, QOS 2300-2, HPCI Pump Operability, was completed, and the HPCI e subsystem was declared operable. Outage report 005 2300-01 was then terminated.

Surveillances QOS 1000-3, LPCI Hotor Operated Valve Operability Test, QOS 1400-2, C re Spray System Motor Operated Valve Operability Check, and 00S 1300-3, RCIC Motor Operated Valve Operability Test, were completed before the outage report tas terminated. QOS 1000-3 and QOS 1000-2, Residual Heat Removal System Pump Operability, had previously been performed successfully at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br /> on August 4,1987, for the "A" loop of the RHR system. QOS 1400-2 and QOS 1400-4, Core Spray Valve and Pump Operability Tests, had been performed successfully at 2240 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.5232e-4 months <br /> on August 4, 1987, for the "A" Core Spray subsystem.

There were no systems'or components ~1noperable at the beginning of this event which.could have contributed to this event. ,

r C. APPARENT CAUSE OF EVENT:

This report is being submitted in accordance with Federal Regulations 10CFR50.73(a)(2)(lv), which requires the reporting of any event or condition that ';

resulted in the manual or automatic actuation of any Engineered Safety Feature (ESF), and 10CFR50.73(a)(2)(v), which requires the reporting of any event or L condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.

l The cause of this event was the failure of differential pressure transmitter DPT 1-2352 which is used to detect excessive flow in the HPCI steam supply line. The I

failed transmitter produced a Group IV Isolation signal.

The failed transmitter was returned to the manufacturer who determined the cause l lof the transmitter failure to be a loss of oil in the transmitter's sensing cell.

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- ol 1 17 - oi 1 014 QF of s l TEXT Energy Industry Identification system (E!!s) codes are identified in the text as (XX)

D.- SAFETY ANALYSIS OF EVENT:

Differential pressure transmitter DPT 1-2352 is used to detect excessive flow in the HPCI steam supply line. Excessive flow in this line would be indicative Gf a steam line break which would require immediate isolation. Thus, a signal from this transmitter initiates a Group IV isolation. When this transmitter failed, it produced the isolation signal which placed the HPCI subsystem in a censervatively safe configuration. With the HPCI system inoperable, the Technical Specifications allow continued operation for seven days provided the APR, RCIC, and low pressure core cooling systems are operable. The APR system in conjunction with the low pressure core cooling systems provide a backup to HPCI to depressurize and inject into the reactor vessel in the event of a small line break. If any of these systems had not been available, a reactor shutdown would have been initiated to reduce reactor pressure to less than 90 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Therefore, the safety consequences of this event were minimal. . j E. CORRECTIVE ACTIONS:

- Work Request 059291 was written to investigate and repair differential pressure transmitter DPT 1-2352. After it was determined that the transmitter could not i be repaired, it was replaced with a like-for-like replacement on August 5, 1937. l In February of 1989, Rosemount issued a Part 21 notification concerning the loss of oli problem in the sensing cells of some of their 1153 and 1154 transmitters. The main symptoms exhibited by transmitters that are  !

experiencing the loss of oil problem are sluggish or : low response time and a zero shift of more than 0.5 percent.

Actions are already in process at the station to cover this concern and are being tracked under NTS 2544578803300 for RIC SIL 33. Based upon this, no further corrective action is deemed necessary for this event.  ;

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l3 F. PREVIOUS EVENTS: j There have been'no previous similar events. .

F 'G. COMPONENT FAILURE DATA:

Manufacturer Nomenclature Model Number .

Rosemount Differential 1153DB5PA g Pressure Transmitter 1-2352-

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