ML18093B482

LER 89-007-00:on 890206,reactor Tripped on Steam Generator Low Level Concurrent W/Steam Flow/Feed Flow Mismatch.Caused by Nuclear Control Operator Not Selecting Correct Channel During Performance of Procedure 1PD-2.6.060.W/890302 Ltr

ML18093B482
Person / Time
Site:	Salem
Issue date:	03/02/1989
From:	Miller L, Pollack M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-007, LER-89-7, NUDOCS 8903140533
Download: ML18093B482 (4)

Text

NRCP'otlftJ!lll U.S. NUCLEAR REGULA TORY C()MlillllllON i9-83l A""ROVED OMll NO. 31!0--410ol EXPIRES: 8/3111111 LICENSEE EVENT REPORT (LER)

FACILITY NAME 111 DOCKET NUMllER 121 I Pao~ 131 Salem Generating Station - Unit 1 o 15 Io Io Io I 217 12 1 loF o I3 TITLE 141 Rx. Trip - #14 S/G SF/FF Mismatch With Low S/G Level Due To Personnel '

Error

, EVENT DATE 151 LER NUMBER 1111 REPORT DATE 171 OTHER FACILITIES INVOLVED Ill MONTH DAY YEAR YEAR  :::;:;:::: SEQUENTIAL f::::::::: REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI

~~~~ NUMBER  !~~: NUMBER o j5!010101 I I o b o 16 s 9 s 19 - o lo I 1 - ob ob ol 2 s 19 THll REPORT II IUIMITTED PURIUANT TO THE REQUIREMENTS OF 10 CFR §: IC/Id OM or morw of Iii* following/. 1111 OPERATING

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- ll0.7311112)(11) ll0.731oll2J(lllJ ll0.731oH2llwl11Hll llD.7311)(211*1 LICENSEE CONTACT FOR THll LER 1121 NAME TELEPHONE NUMBER AREA CODE M. J. Pollack - LER Coordinator 6 I Of 9 3 I 319 1- I 410 12 12 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DEICRllED IN THll REP'ORT 1131 CAUSE SYSTEM COMPONENT MANUFAC* MANUFAC*

TUR ER TUR ER B SIB ZIIIS I NIO 10 17 N I I I I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY Y~AR EXPECTED

~NO SUBMISSION h YES (If yn, compl1to EXPECTED SUBMISSION DA TEI DATE 1151 I I I AllTRACT (Limlr to 1400 IPIJC*. i.1.* *pproxim*toly fiftHn 1ingl1*11>>~* rr1>>wrimn /inn) (HU On February 6, 1989 at 1055 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.014275e-4 months <br />, during routine power operation, the Unit experienced a Reactor Trip on No. 14 Steam Generator (S/G) Low Level concurrent with Steam Flow/Feed Flow mismatch. At the time of the event, No. 14 S/G steam pressure channel I functional surveillance was in progress. The root cause of this event has been attributed to personnel error. Post trip data indicates that the Nuclear Control Operator (NCO) did not sel~ct the correct channel during performance of I&C procedure lPD-2.6.060, "Channel Functional Test - lPT-544 #14 Steam Generator Steam. Pressure Protection Channel I". Pressure compensation for determining steam flow is eliminated when the channel test switch is placed in the test position as per procedure. This causes Steam Flow indication to drop radically causing a signal to initiate closure of the 14BF19 Feedwater Control Valve thereby decreasing feed flow. With the wrong channel apparently chosen as the controlling channel, the 14BF19 valve began closing. Once S/G level dropped to 25% the reactor trip occurred since the signal for Steam Flow/Feed Flow mismatch was proceduraly previously actuated. This event has been reviewed by Operations management. Appropriate corrective disciplinary action has been taken. This event will be reviewed by the Nuclear Training Center for incorporation into applicable training proarams. Operations Department will review this event with ap~licable Operations Department personnel.

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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generatinq Station DOCKET NUMBER LER NUMBER PAGE lJBLt. __ l _____________________________?_Q_Q_Q_~-7-~----- _______8_~_-::_Q_Q_?_=_Q_Q _____ ----~-12L_L_

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NT__ A_°f'.l_:Q_ ~ysr:gj'.l ____I_:Q_El'-JT~F_ICATION_:

Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xxl Reactor Trip - No. 14 S/G Steam Flow/Feed Flow Mismatch With Low Steam Generator Level Due To Personnel Error Event Date: 2/06/89 Report Date: 3/02/89 This report was initiated by Incident Report No.89-084.

C_O_r_f]2J_TIQ_l:i_~--~-~J~QJL __T_Q_ _OCCURRENCE:

Mode 1 Reactor Power 100% - Unit Loao 1155 MWe On February 6, 1989 at 1055 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.014275e-4 months <br />, during routine power operation, the Unit experienced a Reactor Trip on No. 14 Steam Generator (S/G) Low Level concurrent with Steam Flow/Feed Flow mismatch. At the time of the event, No. 14 S/G steam pressure channel I functional surveillance was in progress.

The Unit was stabilizEd in Mode 3 (Hot Standby) and at 1153 hours0.0133 days <br />0.32 hours <br />0.00191 weeks <br />4.387165e-4 months <br />, the same day, the Nuclear Regulatory Commission was notified of the automatic actuation of the Reactor Protection System [JCI in accordance with Code of Federal Regulations 10CFR 50. 7 2 (b) ( 2) (ii) .

APPARENT CAUSE OF OCCURRENCE:

The root cause of this event has been attributed to personnel error.

Post trip data indicates that the Nuclear Control Operator (NCO) did not select channel II as the No. 14 S/G Steam Flow "Record and Control channel as required by I&C procedure lPD-2.6.060, "Channel Functional Test - lPT-544 #14 Steam Generator Steam Pressure Protection Channel I", reference procedure step 7.1. Channel I appears to have been selected. Pressure compensation for determining steam flow is eliminated when the procedure step for placing the channel test switch in the test position is performed. This causes Steam Flow indication to drop radically causing a siqnal to initiate closure of the 14BF19 Feedwater Control Valve thereby decreasing feed flow. With the wrong channel apparently chosen as the controlling channel, the 14BF19 valve began closing. Once SIG level dropped to 25%, the reacto~ trjp occurred since the signal for Steam Flow/Feed Flow mismatch wa8 prcceduraly previously actuated.

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION*

Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1

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The Steam Flow/Feed Flow Mismatch coincident with Low S/G Level reactor trip is anticipatory. Its function is to prevent a loss of heat sink capability by sensing conditions which would eventually result in a dry steam generator. By tripping the reactor prior to reaching the Low-Low Level trip setpoint, the required starting time and capacity requirements for the Auxiliary Feedwater System {BA} are reduced; thereby, minimizing the thermal transient on the S/Gs and the Reactor Coolant System {AB}.

The Reactor Protection System functioned as designed. However, Control Room indication of closure of the 14MS167 valve (Main Steam Isolation Valve) was not immediately received. Post trip investigation revealed that it did close within the required time frame.

This occurrence did not affect the health or safety of the public.

Due to the automa~ic actuation of the Reactor Protection System, this event is reportable in accordance with Code of Federal Regulations 10 CFR 5 0 . 7 3 ( a ) ( 2 ) ( iv) .

CORRECTIVE

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ACTION:

This event has been reviewed by Operations management. Appropriate corrective disciplinary action has been taken.

This event will be reviewed by the Nuclear Training Center for incorporation into applicable training programs.

Operations Department will review this event with applicable Operations Department personnel.

Investigation of the 14MS167 Control Room indication problem has revealed that the "close" limit switch was not making proper contact. The switch was repaired and the valve was tested satisfactorily.

General Manager -

Salem Operations MJP:pc SORC Mtg.89-016

e PS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station March 2, 1989 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 89-007-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR 50.73(a) (2) (i~). This report is required within thirty (30) days of discovery.

Sincerely yours,

• ~.~- ?~

,;r L. K. Miller General Manager Salem Operations MJP:pc Distribution