ML20045D750

LER 93-003-00:on 930524,Div 1 ECCS Initiation Signal Received & LPCS Pump,Lpci Pump 2A & EDG Unit 0 Automatically Started.Caused by Personnel Error.Pumps Secured & Event Documented in Personnel file.W/930623 Ltr

ML20045D750
Person / Time
Site:	LaSalle
Issue date:	06/23/1993
From:	Bejlovec W, Spedl G COMMONWEALTH EDISON CO.
To:	Office of Nuclear Reactor Regulation
References
LER-93-003-10, LER-93-3-10, NUDOCS 9306300020
Download: ML20045D750 (6)

Text

Commonwrith Edison

. LaSa!!e County Nuclear Station  !

2601 N. 21st. Rd.  :

Marseilles, Illinois 61341 l Telephone 815/357-6761 June 23, 1993 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Station Pl-137 Washington, D.C. 20555 Dear Sir Licensee Event Report #93-003-00, Docket #050-374 is being submitted to your office in accordance with 10CFR50.73(a)(2)(iv).

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'nC2f4 F.kedl Station Manager LaSalle County Station GFS/WB/tsh ,

Enclosure cc Nuclear Licensing Administrator NRC Resident Inspector NRC Region III Administrator INPO - Records Center IDNS Resident Inspector

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9306300020 930623 i PDR ADOCK 05000374 I S PDR l-

SHEET 7 EVENT SG MARY A N<, D "" =6" q,L_3,4"1-913 1

CAUSE CODES Lost generation Reactor trip i NRC violation, level __

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Cost > $25,000

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ESF actuation GSEP event, class ____.:

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Hazard or Spill NRC reportable Tech . Spec LCO l

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Personnel injury LER Potential or future loss l Component TaiMe ,S,Ede P SALP functional area __.

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LICENSEE EVENT REPORT (LER)

Facility Name (1) Docket Number (2) Pace (3)

LaSalle County Station Unit 2 0 15 10 10 10 13 17 14 1lof!0l4 >

Title (4)

Inadvertant ESF Actuations Due to Personnel Error During Performance of Instrument Surveillance Event Date (5) LER Number (6) Report Date (7) Other Facilities Involved (8)

Month Day Year Year fjj/

// Sequential / Revision Month Day Year Facilltv Names Docket Number (s)

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015 2 14 9 13 9l3 0 1 0 13 010 016 2 13 9l3 0 15 10 10 10 I l l OPERATING MODE (9) 1 20.402(b) _ 20.405(c) _L 50.73(a)(2)(iv) _ 73.71(b)

POWER ___ 20.405(a)(1)(i) _ 50.36(c)(1) _ 50.73(a)(2)(v) _ 73.71(c)

LEVEL 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) Other (Specify

!0 l (10) 1 0 __._ 20.405(a)(1)(iii) _ 50.73(a)(2)(i) _ 50.73(a)(2)(viii)(A) in Abstract

/, /, /, /,/, /, /, /,/,/ /,/, /,/, /,/,/ /, /,/, /, /,/ /, / /, _ 20.405(a)(1)(iv) _ 50.73(a)(2)(ii) _ 50.73(a)(2)(viii)(B) below and in fffff j ///j/' / j /'/jj{ /

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LICENSEE CONTACT FOR THIS LFR (12)

Name TELEPHONE NUMBER AREA CODE William Beilovec-Instrument Department Ert. 2673 811l5 3 15 17 I -16 17 16 i COMPLETE ONE LINE FOR EACH COM 0 NT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFAC- REPORTABLE CAUSE SYSTEM COMPONENT MANUFAC- REPORTABLE TURER TO NPRDS TURER TO NPRDS l 1 I I I I l N l l 1 l l l l 1 1 I I I i 1 't i I ! I I I I SUPPLEMENTAL REPORT EXPECTED (14) Expected !!g. nth ! Day l Year Submission lyes (If ves complete EXPECTED SUBMISSION DATE)

• X l NO I lI l ABSTRACT (Limit to 1400 spaces, i.e. approximately fif teen single-space typewritten lines) (16)

On May 24,1993 Unit 2 was in Operational Condition 1 (Run) at 100 percent power. At 0524 hours0.00606 days <br />0.146 hours <br />8.664021e-4 weeks <br />1.99382e-4 months <br /> a Division 1 Emergency Core Cooling System (ECCS) Initiation Signal was received.

At the time of the initiation the Instrument Maintenance Department (IMD) was performing LIS-NB-404A " Unit 2 Reactor Water Level 1 ECCS Division 1 Initiation and Level 2 RCIC Initiation Instrument Channels A & C Monthly Functional Test".

The Unit 2 Low Pressure Core Spray Pump, the 2A Low Pressure Core Injection Pump, and the Unit 0 Emergency Diesel Generator automatically started due to the initiation. Due to plant conditions at the time of the event, the Unit 0 Emergency Diesel Generator did not lead to the bus, nor did either the Unit 2 Low Pressure Core Spray Pump or 2A Low Pressure Core Injection Pump inject into the Reactor Vessel.

Immediate corrective actions were taken by the Operating Department to verify the initiation signal was invalid and to secure the involved plant equipment. An investigation was performed and the cause of this event was determined to be an inappropiate actien taken by the Instrument Technician performing the LIS-NB-404A surveillance.

This event is reported to the Nuclear Regulatory Commission as a Licensee Event Report in accordance with 10CFR50.73(a)(2)(iv) due to an actuation of an Engineered Safety Feature (ESF).

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f LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rev 2.0 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) Pace (3)

Year /jj/j/ Sequential /jj/

/ Revision f

/// Number /// Number LaSalle County Station 0 l 5 1 0 1 0 l 0 13 17 14 913 - 010l3 -

O l0 0 12 0F 0 14 TEXT Energy Industry Identification System (EIIS) codes are identified in the text as [XX)

PLANT AND SYSTEM IDENTIFICATION:

Gsneral Electric - Boiling Water Reactor Energy Industry Identification System (EIIS) codes are ' identified in the text as [XX).

A. CONDITION PRIOR TO EVENT Unit (s): 2 Event Date: 5/24/93 Event Time: 0524 Hours Reactor Mode (s): 1 Mode (s) Name: RUN Power Level (s): 1921 B. DESCRIPTION OF EVENT On May 24,1993 Unit 2 was in Operational Condition 1 (Run) at 100 percent power. At 0524 hours0.00606 days <br />0.146 hours <br />8.664021e-4 weeks <br />1.99382e-4 months <br /> a Division 1 Emergency Core Cooling System (ECCS) Full Initiation Signal was received.

At the time of the initiation the Instrument Maintenance Department (IMO) was performing Instrument Surveillance LIS-NB-404A " Unit 2 Reactor Water level 1 ECCS Division 1 Initiation and Level 2 RCIC Initiation Instrument Channels A & C Monthly Fuctional Test".

The Unit 2 Low Pressure Core Spray (LPCS, LP) (BM) Pump, the 2A Low Pressure Core Injection (LPCI.RH)

(BI) Pump and the Unit 0 Energency Diesel Generator (DG (EK) automatically started during the initiation. Due to plant conditions at the time of the event, the Unit 0 Emergency DG did not load to -

the bus (no undervoltage signal occurred), nor did either the Unit 2 LPCS Pump, or the 2A LPCI Pump inject into the Reactor Vessel. (Reactor pressure was greater than 500 psig).

The surveillance directs testing of the initiation channels one at a time such that an initiation will not occur. The procedure directs connecting Volt Ohm Meters (VOMs) to the logic circuits: VOM #1 to a test jack at panel 2H13-P628 (terminals B and C); VOM #2 to a test jack at panel 2H13-P629 (terminals A and B) , and VOM #3 at panel 2H13-P629 (terminals EE-17 and EE-16). The VOMs are then checked for any voltage present.

Since no voltage was present, the V0Ms were then set to measure resistance. The Master Trip Unit (MTU) is placed in test and varied until VOM #3 changes state. This step worked properly. The HTU is again-varied until VOMs #1 and #2 change state. Reportedly, VOM #2 changed state but VOM #1 did not. At this point the Instrument 'achnician verified the test connections. Upon being satisfied with the connections, VDM #1 was s. ken to a lower resistance scale in an attempt to verify contact closure.

During the ranging of the VOM, a Division 1 ECCS initiation took place.

This sequence of events is consistent with the annunciator alarm typer. There was an approximate span of 34 seconds from the time of receiving the intial expected alarm to the time of the ECCS initiation during which time the V0M connections were being verified. In order for the subsequent relay action to take place, it would have required an inappropiate action by the technician during the initial setup or the investigative steps. The surveillance was suspended at this time.

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LICENSEE EVENT REPORT (LER) TEXT CONTINUA 1 ION Form Rev 2.0 FACfLITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) Pace (3)

Year /// Sequential Revision fjj/

// Namber j//j/j/

// Number LaSalle County Station 0 l 5 l 0 1 0 1 0 13 17 14 9I3 - Ol013 - 0 10 0 13 0F 0 14 TEXT Energy Industry Identification System (EIIS) codes are identified in the text as [XX]

8. DESCRIPTION OF EVENT CONTINUED The Operator immediately verified that the initiation signal was invalid and operating personnel secured the Unit 2 LPCS Pump, the 2A LPCI Pump and the Unit 0 Emergency DG in a'ccordance with approved Station Procedures. An investigation was initiated to determine the cause of this event.

This event is reported to the Nuclear Regulatory Commission as a Licensee Event Report in accordance with 10CFRSO.73 (a)(2)(iv) due to an actuation of an Engineered Safety Feature (ESF).

C. APPARENT CAUSE OF EVENT The root cause of this event is personnel error. It is believed that during the performance of the surveillance an inappropiate action was taken by the Instrument Technician, such that VON #1 was connected to terminals B and C of the test jack in panel 2H13-P629 rather than 2H13-P628 as directed by the procedure. Upon not seeing the desired change of state, the VOM was ranged to the lowest ohm scale' which created a current path suitable to allow the initiating relay to energire.

The investigation determined that the surveillance procedure LIS-NR-404A has been performed over a dozen times in its present format with satisfactory results.

D. SAFETY ANALYSIS OF EVENT The Safety significance of this event was minimal due to plant conditions at the time of the event. The systems are designed to provide cooling to the reactor and responded per design af ter receiving an initiation signal. Operator actions were appropriate.

E. CORRECTIVE ACTIONS Immediate corrective actions taken by the Operating Department were to verify that the initiation signal-was invalid and to secure the Unit 2 LPCS Pump, the 2A LPCI Pump and the Unit 0 Emergency DG in accordance with approved Station procedures.

An inspection.of the test equipment used was performed and it was determined to be acceptable except one VOM found inoperable in a range not used during the surveillance. -

LIS-NB-404A was successfully performed by different personnel using all of the same test equipment without incident.

Personnel involved were counseled, and this event was documented in the individual's personnel file.

No further corrective actions are required.

LICENSEE EVENT REPORT (LER) TEXT CON 71NUATION Form Rev 2.0 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) , Paae (3)

/jj Year fjj/

// Sequential // Revision f

/// Number /// NumbeL LaSalle County Station 0 l $ 1 0 1 0 1 0 13 17 14 9l3 - 010l3 - 0 10 0 14 0F 0 14 TEXT Energy Industry Identification System (EIIS) codes are identified in the text as [XX)

F. ~ PREVIOUS EVENTS LER NUMBER TITLE 374/89-003-01 RHR SDC Isolation during Survalliance/ Inattention to Detail 374/90-013-00 MSIV Isolation Signal During Survelliance Test Due to Personnel Error / Attachment Used Without Procedure 373/89-001-00 Spurious Auto Start of 'O'.DG/IM Shorted While Removing Test Equipment G. COMPONENT FAILURE DATA None.

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