ML19351A675

LER 89-027-00:on 891113,primary Containment Isolation Sys Group I Isolation Occurred While Performing Instrument Surveillance.Caused by Loss of Power to Leak Detection Sys Logic.Isolation reset.W/891213 Ltr

ML19351A675
Person / Time
Site:	LaSalle
Issue date:	12/12/1989
From:	Crowl D, Diederich G COMMONWEALTH EDISON CO.
To:	Office of Nuclear Reactor Regulation
References
LER-89-027-01, LER-89-27-1, NUDOCS 8912200432
Download: ML19351A675 (8)

Text

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a Commonweshh Edison W .- 'L[/,

LaSt11e County N;.c!nr Station

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~ Rura' Route #1, Box 220 Marseilles, Illinois 61341 ]

'x Telephone 615/357 6701

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4. g December 13, 1989 p

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Director of Nuclear Reactor Regulation

' U.S. Nuclear Regulatory Comunission . l Mail Station P1-137 Washington, D.C. 20555

Dear Sir:

1 Licensee avant Report #89-027-00, Docket #050-373 is being

- 4 submitted to your office in accordance with ,

10CFit50.73(a)(2)(iv) .

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ch h(G.J.Diede Station Manager t,aSalle County Station ,

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xc: Nuclear Licensing Administrator NRC Resident Inspector h NRC Region III Administrator P'@h INPo '- Records Center

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LICENSEE EVEN1 REPC31 (LER) , p Docket Nunt>cr (2) Pace (3)

F6cility me (1) 1loF!0l6 LaSalle County Station Unit 1 0]$101010131713 Title (4) Primary Containment Isolation During Surveillance Testing Due to Burned Out Annunciator Wii./e.i Licht Bulbs Other Facilities involved,_(8)

Eeent Date (5) LER_N atper (6? Reoort Date (7)

Sequential /// Revision Month Day Year Facility W mes Docket Nat>er(s) t Month Day Year Year ///

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THis RCMT 15 $USMITTED PURSUANT TO THE REQUIREMENTS OF 10CFR (Check one or is re of the followinn) til)

" 0 20.402(b) _ 20.405(c) .X,_ 50.73(a)(2)(lv) ,,,_,

73.7)(b) 20.40i(a)(1)(l) 50.36(c)(1) 50.73(a)(2)(v) ,,,,,_ 73.7t(c)

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20.40$(a)(1)(111) 50.73(a)(2)(l) 50.73(a)(2)(vill)(A) in Abstract (10) 01 01 0 ,,,,,,, _ __,,

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/// // / u ///,/,/,/,/// , / ,,,,,, 20.405(a)(1)(lv) ,,,,_

50.73(a)(2)(ll) __ 50.73(a)(2)(vill)(B)

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f f LICENSEE CONTACT FOR THis LER (12)

TELEPHONE NUSER Name AREA CODE Don Crowl. Reaulatory Assurance. extension 2860 8 l 1 15 31 Sl 71 -l 61 71 61 I werLETE ONE LINE FOR EACH wrivuiNT FAILURE DESCRIBED IN THis REPORT (13) 7 CAUSE SYSTEM C0fr0NENT MANUFAC- REPORTABLE CAUSE SYSTEM COPPOWENT MRNUFAC- REPORTABLE TURl!R TO NPRDS TURER TO NPRDS i i i N i l i l i l

• 0 l i I I l l l l l l l l l l I i l l Expected Month l Day l Year SUPPLEENTAL REPORT EXPECTED (14) ,,,_

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YlNO  ! ll ll ABSTRACT (Limit to 1400 spaces, i.e, approximately fifteen single-space typewritten lines) (16)

On Noventier 13, 1989 at 1823 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.936515e-4 months <br /> with Unit I defueled, a Primary Containment Isolation System (PCIS) Group 1 isolation occurred while perfoming LaSalle Instrument Surveillance LIS-MS-1078, " Unit 1 Reactor Vessel Low

• Water Level I and Level 2 1 solation Instrument channels 8 and D Refuel Calibration." A full PCIS Group 1 lsolation occurred because the other half of the isolation logic was tripped due to the loss of leak l

detection power from the AC electrical bus 135X and 135Y outage. No valve movement occurred because all the l

Main Steam system isolation valves were previourly deenergized due to other scheduled refuel outage work.

The alarm windows were extinguished and the light bulbs for alam windows F504, "CHAN Al/A2 MSIV ISOL TRIP,"

and E504, "CHAN 81/82 MSly ISOL TRIP." on the Control Room panel 1H13-P601 were later detemined to be burnt out when testing was done. This prevented both the Unit 1 Nuclear Station Operator (PSO, licensed Reactor Operator) and the Instrument Maintenance Technician from detecting that half of the isolation logic was initiated when the AC electrical bus 135X was deenergized.

A review of the guidance for what an alam window test requires will be performed.

This event is being submitted pursuant to the requirements of 10CFR50.73(ah2)tiv) due to the actuation of an l

Engineered Safety Feature System.

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tlCENSEE EVENT REPORT (LER) itXT COWilWuAtl0W _ Fom Rev 2.0

, LtR WuegER (6) Page (3)

.(p ' PACllllY NAME (1) 00CKLI NUagER (2)

Year fj// Sequential ///

/ Revision f fff

/// Nmber /// thster L W lle County Station unit 1 0 1 5 1 0 1 0 1 0 1 31 71 3 e19 - 012I7 - 0I o of 2 0F of 6 TEXT ' Energy Industry identification System (Elis) codes are identified in the text as [XX)

~ PLANT AIS $1 STEM IDENilflCATION

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General Electric - Dolling Water Reactor Energy Industry Identification System (Ells) codes are identified in the text as (XX).

p A. CONDITION PRIOR TO EVENT Event Date: 11/13/09 Event fles: 1823 Hours Unit (s):' 1 Reactor Mode (s): Defueled Mode (s) Name: Defueled Wr MO: 1 l l

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8. . OESCRiffl0N OF EVENT on llovember 13,1989 at 1823 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.936515e-4 months <br /> with Unit I defueled, a Primary Contalmuent Isolation System (PCis, PC) [JM) Group i isolation occurred while performing LaSalle lastrument Surveillance LIS 4tS-1078, " Unit i

- 1 Reactor vessel low Water Level 1 and Level 21 solation Instrement Channels 8 and 0 Refuel Calibration." Both Inboard'and Outboard Maln Steam Line Isolation valves (MS!V, MS) [$9] and Maln Steam les valve line drain valves were deenergized prior to the isolation due to planned refuel outage work.

motion took place during this event. The PCIS Group 1 isolation only resulted in relay and alam actions.

At 0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br /> on November 13,1989.the "A" channel calibration was completed in acconiance with LaSalle '

instrument Surveillance L15-4tS-107A, " Unit 1 Reactor Vessel Low Water Level I and Level 2 Isolation l Instrissent Channels A and C Refuel Calibration." .

L At 0725 hours0.00839 days <br />0.201 hours <br />0.0012 weeks <br />2.758625e-4 months <br /> "C" channel callbration was started in accordance with LIS-MS-107A.

i At 1305 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.965525e-4 months <br /> the Division 1 AC Electrical Olstribution Duses 135X and 135Y (AP) [ED) were deenergized J and taken out-of-service in accordance with LaSalle Aeninistrative Procedure LAP-900-4, " Equipment Out-of-Service Procedure," for scheduled refuel outage work. The bus 135X and 135Y outage deenergized the Olvision I Leak Detection logic (LD/E31) (lJ). (Relays.1E31A43A and IE31A43C doenergized.)

Relays' IE31A43A and IE31A43C cause relays 1821H47A and 1821H47C to deenergize on loss of powe

. area dublent temperature or high differential temperature signal. When relays 1821H47A and 1821H-47C This occurred during the day shift and doenergize, a channel Al and A2 MSIV isolation signa) occurs. +

caused no consequence to testing the Olvision I logic per LIS-MS-107A. (only half of the isolation logic was made up at this time.)

I At 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> the calibration of the "C" channel per LIS-StS.107A was stopped for the shift to allow s

shift turnovers (the exchange of day shift personns) with afternoon shift personnel) to take place.

- At 1540 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.8597e-4 months <br /> the calibration of the "C" channel was resisned per L15-MS-107A.

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- llCENSEE FVENT REPORT (LER) TEXT COWilNuATION Page (3)

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DOCKET NUMBER (2) LER WU9ER (6)

IACIL11Y NAME (1)

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01 0 01 3 01 6 LaSalle County Station unit 1 015101010131713 819 - 01217 - 0F TEXT Energy Industry Identification System (Ells) codes are identified in the text as [XX) ,

5. DESCRIPil0N OF EVENT (Continued)

At 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> the Instrument Maintenance (IM) personnel coupleted the calibration of the "C" channel per LIS-Jis-107A.

At 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> the calibration of *t" channel was started in accordance with LIS4tS-1078. The surveillance test was authorized by the Shift Engineer (SE, licensed Senior Reactor Operator), Shift Control Roam Engineer (SCRE, licensed Senior Reactor Operator) and Unit 1 Nuclear Station operator (WSO, licensed Reactor Operator) prior to beginning the surveillance test.

At the beginning of the surveillance test, the computer points (CX/C91) [LD) were verlfled to indicate as follows:

a. 0997, "LO L0 RX WTR LVL OlV 81 -N-LO"

b. C500. "VERY L0 RX WTR LVL DIV ll - N-LO"

c. C581, "RPS CH B1 INSTR GROSS Fall - AVAIL"

d. C582, "RPS CH S1 INSTR POER LOSS - AVAIL"

e. C564, "RPS CH B2 INSTR OROSS Fall - AVAIL"

f. C505, "RPS CH B2 INSTR POER LOSS - AVAIL" t At the Control Rown panel IH13-P603 the following alems (AN) (18) were verifled reset or clear (slow l

flash or extinguished):

a. B401, "DIV 1 RX VESSEL WIR LVL 2 LO"

b. 8412. "DIV 2 RX VESSEL WTR LVL 2 LO"

c. 6405, "CHAN A1/91 PRI CNMT PRESS HI"

d. 1)a09, "CHAN A2/82 PRI CNMT PRESS Hi*

e. A210. "CHAN A1/81 RX VESSEL WTR LYL 1 LO-LO-LO" At the Contro) Room panel 1Hl3-P601 alam E504, "CHAN B1/82 MSIV ISOL TRIP " was verified reset or clear (slow flash or extinguished).

LIS-MS-1078 did not require the IM's to check the Auxillary Electric Room panels 1H13-P622 and IH13-P623 The Malp Stem isolation Valve (MSIV, MS) solenold valve status lights if the MSIV's were closed. ,.

solenoid status lights are nonnally energized when no isolation signal is present.

The alam windows were extinguished and the light bulbs for alann windows F504, "CHAN A1/A2 MSIV ISOL TRIP." and E504, "CHAN 81/82 MSiv 150L TRIP," on the Control Room panel 1H13-P601 were later detem to be burnt out when testing was done, n#ien the test switch 1821-5208, "MSL DRN ISOL LOGIC," was turned to test in accordance with LIS-MS-1078 a full PCIS Group 1 isolation occurred because the other half of the isolation logic was tripped due to the loss of leak detection power from the AC electrical bus 135X and 135Y outage. No valve movement occurred because all the Main Stean system isolation valves were previously closed due to other scheduled refuel outage work. Both the Unit 1 NSO and the IM did not realize a full Group 1 1 solation had occurred at this time because the annunciator light bulbs were burnt out for alann windows- E504 --

and F504, and no valve motion took place.

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• LICENSEE [ VENT REPORT (LER) IIx1 CONTINUATION LER NUMBER (6) Pace (3)

FACllliY NAME (1) 00CKLI NUMBER (2)

Year #// Sequential M Revision ,

Eff Net >er fff Net >er 01217 01 o 01 4 0F 01 6 0 l S 1 0 1 0 1 0 1 31 71 1 81g

- - f LaSalle County Station Unit 1 TEK1 Energy Industry identification System (Ells) codes are identified in the text as (XX) l B. DESCRIPTION OF EVENT (Continued)

The Instr aent Maintenance personnel proceeded to the fleid and isolated 1821 4 4028 Division 11 reactor When level transmitter and attached the test equipment to simulate lowering reactor water vessel level.

the trip setpoint was reached, the Olvision 11 reactor water level trip unit opened contacts in the logic which deenergized the It21H-478 relay. The Olvision 11 reactor vessel water level trip indicator t unit trip light and alam window A210 "A1/81 LYL 2 LO LVL," lilminated. The alam window E504 did not 111 minate at this point. The IM's stopped testing to investigate why the alam window E504. "CHAN 81/82 MSly !$0L TRIP," did not 111uminate. The IM's r4 quested the NSO to make an annunciator check and it was discovered that both alam window E504 and F504 had no indication because the window light bulbs were burnt out. At this point the IM's notified the IM foreman of the probism. ,

The IM personnel were requested to return reactor level transmitter 1821-N4022 to service and the  ;

Division 11 isolation was reset. The light bulbs were replaced for alam windows E504 and f 504 and the operatingDepartmentrequestedtheIM'stojupertheIE31A-K3AandIE31A-K3CrelaysforOlvisionIto allow testing of Division 11 logic to continue. This was done in accordance with LaSalle Aeninistrative Procedure LAP-240-4, " Temporary System Change," and testing was completed without any further event.

this event is being submitted pursuant to the requirements of 10CFR50.73(a)(2)(lv) due to the actuation of an Engineered Safety Feature System.

C. APPARENT CAUSE OF EVENT l

l toth alam windows E504, "CHAN 81/82 MSIV ISOL TRIP " and F504, "CHAN A1/A2 MSIV ISOL TRIP " had no indication because the window light bulbs were burnt out. This caused both the Unit 1 NSO and th* IM to When the proceed with LIS-MS-1078 believing that no other isolation signal was present at this time.

test switch 1821-5208, "MSL DRN ISOL LOGIC," was turned to test in accordance with LIS-MS-1078, a full PCIS Group 1 Isolation occurred.

When AC electrical bus 135X was deenergized for planned outage work, a Division 1 PCIS Group 1 i signal resulted (only half of the isolation logic was made up at this time.) due to the loss of power to the Leak Detection system logic which inputs to the PCIS Cogic. This was done during the day shift (0700-1500 hours). After shift change the afternoon shift (1500-2300 hours) Unit 1 NSO checked Control Room panel alams per LaSalle Operating Surveillance LOS-AA-SI, "Shiftly Surveillance," and not notice any extinguished alam window light bulbs. The Unit 1 NSO demanded an alam suunary to out on the Sequential Event Recorder typer (alann typer, AN) [lQ). A detailed review of the printout wasn't perfomed due to the work load during the shift and the neerous amount of clanns Insted on the

typer. Many alanas were caused from the amount of work requiring systems to be in an off-nomal condition during a refueling outa08.

The LaSalle Instrument Surveillance procedure did not require verification of the alanns printed out by the Sequential Event Recorder suunary. This procedure also did not require the IM to verify the MSly The MSIV's solenoid status lights energized in the Auxiliary Electric Room if the MSIV's are closed. Checking were closed due to planned refuel outage work and were deenergized to allow work to continue.

the alann summary printout may have allowed the WSO or IM to identify that an isolation signal was present. Checking the solenoid status lights for the M51V's would not have helped in this event-because the MSIV's were out of service and the solenoids deenergized to support planned outage work.

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' , f om Rev 2.0_ i LICfW5it EVlWT REPORT (LtR) itXT CONilWUATI E k' age (3) 00CKli WUMBER (2) _ t[R WOMB (R (3)

F ACllliY NAML (1) Revision j/j/j/ Sequential Year //

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01217 01 0i015 0F 01 6 0 l $ 1 0 1 0 1 0 l 31 71 3 9l9 LaSalle County Station Unit 1 Energy industry identification System (Ell 5) codes are identified in the text as [XX) l 1 EXT I

C. APPARENT CAUSE OF EVENT (Contir9ed)

When AC electrical bus 135X was deenergized the Unit i N50 on the afternoon shift did not realize th power was also lost to the Olvision I Leak Detection system which inputs to the PC15 syste isolations. Mores 11y the M50 would be aware of the condition of the system by the indication of C Room alarus.

There are no specific procedures or lists (outside design drawings) which leentify every effect a bus outage has.

The SCRE who prepared and reviewed the AC electrical bus 135X and 135Y outage knew that the valv associated with the FC15 Group 1 Isolation logic were all out of service closed or in their isola Rd position. The SCRE felt that it would not be a concern during subsequent testing that would cause an The SCRE used isolation because no actual valve rovement would take place, only relay actuation.

LaSalle Emergency Plan laplementing procedure LIP-1310-1, " Notifications," as a reference for ma this interpretation. This evaluation was not connunicated to af ternoon shift personnel.

D. SAFETY ANALYSIS OF EVENT A loss of power to the Bus outages are performed for modification work during planned unit outages.

Leak Detection system provided a Olvision I primary containment isolation system actuatlon as des The safety significance of this event is mirilmal since the unit was defueled and the valves that w have isolated were already in the closed position due to planned outage work.

E. CORPICTIVE ACT3DNS At 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br /> the IH personnel wre requested to return reactor level transmitter 1821-N4028 to se and the Division 11 isolation was reset, f

1 The light bulbs were replaced for alarm windows E504, "CHAN 81/82 MSIV 150L TRIP," and F l M51V 15CL TRIP."

On Notenber ad,1989 at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> the IM's installed jumpers in accordance with LaSalle Acalnistl Procedure LAP-240-4, "Tauporary System Change," (TSC 1-983-89) to prevent Main Steem isolation l

(M51V) Group i PC15 lse sation frtun occurring while a half isolation signal is present due to AC '

electrical bus 135X/Y outage. This was done to a. low testing of Olvision 11 logic to contin 9e.

At 1240 hours0.0144 days <br />0.344 hours <br />0.00205 weeks <br />4.7182e-4 months <br /> on Novsaber 14, 1999, L15-MS-107B was conpletes satisfactorily without any further etent.

All alarm windows for both Unit I and 2 main Control Room have been checked to verify both light bul in each window are working properly.

1 The Operating Department will review the need to revise procedures to provide more guidance on wh alars window test regulres, such as checking each wladow to determine if both bulbs are working pro ,

when tested. Action item Record (AIR) 373-200-89-11201 will track this correct;ve action, ..

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' Forn Rev 2.0 l tlCtW5tE EVtWT REPOR? (tfR) ItXT 00NilWUA110W __

,__ Page (3) l F ACILITY WAME (1) 00CKEl NUMBER (2) _ llR WVMRtR (0)

Year // 5equential // Revision l j/j/j

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01 0 01 6 01 6 C l 5 1 0 1 0 1 0 l 31 71 3 8I9 -f01217

- 0F Le411e County Station Unit I

TEXT Energy industry identific?llon System (Ells) codes are identi(led in the text as (XX.]

, E. CORRf;.'TIVE ACTIONS (Continued) ,

AC electrical but outant procedures will be developed to assist the Operating personnel in identifying AIR potential probisms which will arise due to doenergizing equipment or logic system power supplies.

373-200-49-11202 will track these procedures.

The Trainir.g Department will review this event to determine if additional training is required to insure i

proper turntsver information that could effect Engineered safety Featured system actuation reportability is discussed. AIR 373-200-09-11203 will track the completion of this review.

A General Inforination Motificatloa (GIN) wl11 be developed to review inis event with Operating,

! Melntenance and Technical Staff personnrI asphasizing the luportance of verifying or reverifying the I

required initial conditions just prior to performing a test or surveillance to prevent inadvertent Engineer # Safety Featured System acts.ations. AIR 373-200-49-11204 will track the coupktion of this GIN..

F. PREVIOUS EVENTS LER Nunber Title 373/8444940 Secondary contaltunent isolation During Testing 373/84-074-00 Reactor Water Cleanup Isolation 373/07-009-00 Group IV isolation During Survrillance Test Due to Instrassent Maintenance Procedure inadequacy 373/8743040 Reactor Scram telle Shutdown During Surveillance Due to Casananication Error 374/98-U17-00 Reactor Water Cleanup Isolation During Modification Test Due to inadequate Reset 374/99-003 4 1 Engineered Safety Feature Actuation During Perforiaance of Instrument Maintenance Functloral Tests Due to Personnel Error 374/09-013 4 0 Primary Corn:sinment Isolation During Instrument Surveillance Testing of LIS-MS-401 G. COMPONEN1 fAlLURE DATA Not applicable, i

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.. QCf 45f E IVlWT REPORT (llR) itti COWilNUA110N Pagej3) .;

DOCKL1 WOMBfR (2) I(R WU8e(R (6)

' F ACitIIY NAME (1) Revision g/j/ Sequential j////jj/

Year / /

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0l217 01 0, 01 6 01 6 l 0 1.5 l 0 1 0.1 0 1 31 il 3 819 - - 0F LaSalleCountySuggnUnit1 1EX1 Energy Industry Identification System (Ells) codes are Identified in the text as (XX]

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L. CORRECTIVE ACil0NS (Continued)

AC electrical bus outage procedures will be developed to assist the Operatteg personnel in identifying AIR potential problems which will arise due to deenergizing equipment or logic system power supplies.  :

373-200-89-11202 will track these procedures. i The Training Department wlli review this event to dete mine if additional training is required to lasure proper turnover information that could effect Engineered Safety featured system actuation reportability is discussed. AIR 373-200-89-11203 will track the completion of this review.

A General Information Notification (ClN) will be developed to review this event with Operating, Maintenance and Techalcal Staff personnel suphasizing the leportance of verifying or reverifying the requiredinitialconditionsjustpriortoperformingatestorsurveillancetopreventinadvertent Engineered Safety featured System actuations. AIR 373-200-89-11204 will track the completion of this GIN.

4 F. PREVIOUS EVENTS LER Nuntper Title

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373/84 4 49-00 secondary Containment isolation During Testing 373/84-014-00 Reactor Eater Cleanup Isolation t

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373/87-009-00 Group IV isolation During Surveillance Test Due to Instrument Maintenance "

l Procedure Inadequacy 373/87-030-00 Reactor Scram While Shutdown During Surveillance Due to Connunication Error 374/98-017-00 Reactor Water Cleanup Isolation During Modification Test Due to inadequate Reset 374/09-003-01 Engineered Safety feature Actuation During Performance of Instrument Maintenance functional Tests Due to Personnel Error 374/09-013-00 Primary Containment isolation During Instrument Surveillance Testing of LIS-MS-401 j

1 O. COMPONENT FAILURE DATA Not applicable.

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