ML20062D777
| ML20062D777 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/31/1990 |
| From: | Cialkowski M, Diederich G COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9011160133 | |
| Download: ML20062D777 (26) | |
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,. . Commonwealth Edison LaSalle County Nuclear Station RuralRoute e1 Box 220 Marseilles,Ittinois 61341 Telephone B15/357 6761 November 10, 1990 Director of Nuclear Iteactor Regulation United States Nuclear Regulatory Commission Hall Gtation P1-13*/
Washington, D.C. 20555 ATnt Document Control Desk Gentlement Enclosed for your information is the monthly performance report covering 1.aHalle County Nuclear Powet Station for October, 1990. Very truly yours, G. J. Diederich Station Manager LaSalle County St.ation
- UJU/MJC/bkw tr Enclosute.
xc1 A. D.-Davis, NRC, Iteglon III IIRC Resident inspector LaSalle 111. Dept. of Nuclear Safety R. Pulsifer, NRR Project Manager D. P. Galle, CE('o is, t. . Parrar, CECO IllPO Records Center D. 11 . Eggett, NED J. E. liuskey, GE Resident T. J. Kovach, Manager of Nuclent Licensing N. T. Naught.on, Nuclear Fuel Services Manager C. T. Dillon, Senior Financin1' Coordinator, LaSalle T. R. Novotney, INPO Coordinator, LaSalle Station T. A. llammerich, Regulatory Assurance Sul ervisor J. W. Gleseker, Technical Stali Supervisor Central file
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I l TABLE OF CONTENTS j (UNIT 1) I. INTRODUCTION
- 11. REPORT ,
A.'
SUMMARY
Or OPERATING EXPERIF TE B. PLANT OR PROCEDURE CHANGES, TESTS, EXPEPIMENTS, AND SAFETY RELATED i MAINTENANCE (50.59)
- 1. hwendments to racility License or Technical Specifications
- 2. Changes to procedures which are described in the Safety Analysis Report
- 3. Changes to facility which are described in the Safety Analysis .
Report. ;
-n 4. Tests and Experiments not covered in the Safety Analysis Report ,
C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT 4 D. COMPLETED'SATETY-RELATED MODirICATIONS t E.- LICENSEE EVENT' REPORTS { T .' DATA TABULATIONS
- 1. Operating Data Report j
- 2. Average Dally Unit Power Level
- 3. Unit Shutdowns and Power Reductions .
G. UNIQUE REPORTING REQUIREMENTS l
- 1. Main Steam Relief Valve Operations -,
- 2. . ECCS System Outages .
- 3. Off-Site Dose' Calculation Manual Changes
- 4. Major Changes to Radioactiva Waste Treatment System !
- 5. Indications of Falled Tuol-Elements i i 4
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- 1. INTRODUCTION (Unit 1)
The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marsellies, Illinois.' Each L unit is a Boiling Water Reactor,with a designed not electrical output of 1078 Megawatts. Waste heat is tejected to a man-made cooling pond using the. Illinois River for make-up and blowdown. The architect-engineer was , Sargent and Lundy and the primary construction contractor was f Commonwealth Edison Coinpany. Unit One was lesued operating license number NPF-11 on April 17, 1982. -]. Initial-criticality.was achieved on June 21, 1982 and commercial power ,f operation was commenced on January 1, 1984. L- . . . i This report was complied by Michael J. Clalkowski, telephone number
- (815)357 6761, extension 2427.
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- 11. H0H11tLY REPORT A.
SUMMARY
OF OPERATING EXPERIpNCE (Unit 1) Day 21mn Ernnt 1 0000 Reactor critical, generator on-line at 1100 MWE 2 0030 Reduced power to 1000 MWE for CRD exercising 1100 Increased power to 1110 MWE 9 0000 Reduced power to 1040 MWE for CRD exercising 1000 Increased power to 1110 MWE 14 0200 Reduced power to 950 MWE for system load 1400 Increased power to 1110 MWE 10 0200 Feduced power to 750 MWE for personnel access hatch work 2400 increased power to 1120 MWE 23 0130 Reduced power to 850 MWE for system load 1200 Increased power to 1120 MWE 25 -0300 Reduced power to 979 MWE due to feedwater transient 0900 Increased power to 1115 MWE 30 2200 Reduced power to 1020 MWE for CRD exerclsing 31 0700 Increased power to 1120 MWE 240. Reactor critical, generator on line at 1120 MWE ZCADTS/5
. B. PLANT OR PROCEDUk* CHANGES, TESTS, OR EXPERIMENTS (50.59) (Unit 1)
- 1. Amendments to the racility License or Technical Specification.
(Hone)
- 2. Changes to procedures which are described in the Safety As.dlysis Report.
a) LaSalle Operating Procedure LOP-WX-04, " Establishing A Concentrated Waste Tank Transfer Loop" was approved to include an option to drain the Concentrated Waste to the Ultrasonic Resin Cleaner Sludge Tank. A safety evaluation was performed and determined the change was beyond the literal statements of the UFSAR and the UFSAR will be revised to include this. The radwaste' sludge systems are deffned as not important to safety per UFSAR 11.2.1.1 and are not the basis for any Technical Specifications. This procedure change does not affect the Process Control Program b) LaSalle Special Test LST-90-054, " Control Room / Auxillary Electric Equipment Room HVAC System flow Adjustment", was apt royed to reposition the balancing dampers on Control Room / Aux 111ery Electric Equipment Room HVAC System. The purpose of this test is to provide a methodology for ensuring that the 'A' ('B') train Control Room / Aux 111ary Electric Equipment Room HVAC Systems are operable during the Initial adjustment of balancing dampers. The Intent of the dmnper adjustment is to increase the flowrote through the systems and still ensure the control room meets the requirements of Technical Specification 4.7.2.d. The safety evaluation concluded that the temperature in the control room will be maintained between 55'r and 104'r to ensure that the equipment is maintained operable. c) LaSalle Special Test LST-90-105, " Residual Heat Removal
'tRHR) Service Water Pressure Transient Monitoring During System Startup" was approved to record and document pressure transients in the 'D' loop of the RHR Service Water system during RHR Service Water operations. This test will be conducted with a temporary crosstle'to the Service Water System in place to evaluate the usefulness of a permanent Service Water keep-fill crosstle to prevent waterhammer in the 'D' loop of RHR Service Water during system startup. The safety evaluation prepared for this
, test stated that the connection between the RHR Service Water system and the Service Water system is protected by two check valves which would prevent RHR Service Water backflow and even in a worst case situation where the hose fall off at the heat exchanger low point drains, the RHR Service Water pumps could still maintain adequate flow through the heat exchanger to assure system operability, i
l ECADTS/S I
. ]
Changes to facility which are described in the Safety Analysis j 3. Report. a) LaSalle Temporary System Change (TSC) 1-715-90 installed jumpers for Unit 1 Reactor Water Cleanup (RWCU) Non-Regenitive heat exchanger tube outlet hi tempera +ure trip on November 19, 1990 due to a failed temperature switch. This enange wi13 prevent RWCU from isolating due to high outlet temperature until replacement par ts arrive or a component replacement is performed. Although the trip function is bypassed, a separate instrument for alarm and temperature ludication are still available. The basis for the isolation is to protect the resin beds end is not a safety function. The current actions specified to prevent degradation / resin intrusion are adequate (special log created to monitor temperature and manual isolation if required). b) LaSalle Temporary System Change (TSC) 1-689-90 installed floor drain plug at the lake screen house to prevent hypochlorite from getting into the floor drain system while draining and flushing the underground tank. The floor drain plugs will be installed in the basement of the lake screen house where the existing hypochlorite system is locMted. The floor drains are located near non-safety relate equipment and'in the event of a flood, the floor drain plugs can be removed. Also there are ample amounts of uncovered floor drains to further reduce-the possibility of flooding in the building. The safety evaluation determined the possibility of an accident or malfunction different than previously evaluated in the FSAR is not created'by the temporary covering of these floor drains.
- 4. Tests and Experiments not described in the Safety Analysis Report.
(None) C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMr.HT (including SOR differential pressure swltch failure reports). (See Table 1) D. COMPLETED SAFETY-RELATED MODIFICATIONS. (None) l ZCADTS/5
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.RESULTS AND-r.z:e. u NUMBER COMPONENT; -
CAUSE OF MALFUNCTIt25 ON SAFE PLANT OPERATION- CORRECTIVE ACTION. LOO 637 RHE Shutdown valve motor' failure- . Valve inoperable Replaced valve. motor-Cooling valve ~ _ _ and contactor _
.LO2550 -SBGT Flowi ~ Actuator' None - Replaced actuator Control Dasaper - .LO3119 RPS Area Love controller' ' Improper operation : Replaced controller-Air: Temp -L98209 LPCS Water, ~ Pump seals leaking None Replaced pump Leg Pump.
(No SOR failures:.this; month)- 2" m /5-w- q.
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e E. LICENSEE EVENT REPORTS.(Unit 1) LER Number Date Descrip11pn 90-012-00. 10/16/90 30 day-inadvertent auto start of a VC/VE , emergency makeup. F. . DATA TABULATIONS (Unit 1)
- 1. ' Operating Data Report (See Table 3).
2 '. Average Daily Unit Power Level (See Table 4) 3.. Unit Shutdowns.and Significant Power Reductions (See Table 5) d 4 z'{ p,' 1 v s
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SUMMARY
OF OPERATION: .
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The Unit-remained on'line atJhigh'r: power. throughout!: the emnth.. - Severa12 mino'r po or reductions were ' required due ' to low :
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m a h G.. UNIQUE REPORTING REQUIREMENTS (Unit 1)
- 1. Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIPTICt1 DATE ACEIATED- ACIVAIIDtI CWDlT1011 Of_.EYD1T (Hone)
.. ECCS System Outages (See Table 6).
- 3. ' Changes to the Off-Site Dose Calculation Manual (Hone) l il 4. Major changes to Radioactive Haste Treatment Systems.
(None)-
- 5. Indications of ralled Fuel Elements.
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2- , Table 0
,_ ' G.2 ECCS System Outages Hote* The year _and unit, data hat, been removed f rom the outage ntunber.
DUIAGEJ!h E.QUlrHRII P11Rf0SZ (U-0)'- s 329 0 DG Locktite screws on local trannfor switch and breaker inspection 1 (11- 1 ) - iL 533. '1DG00CH Lubr]cate air compressor motor
-537 1E12-C002C 1C RilR pump breaker luspection 5 3 t> 1E12-C002C Motor bearing oil change 542- IE12-C003H Lubilcate water leg pump
, 3 543 1E12-C0030 Changn motor 013
' tie 544 .1E124C002B 1B RilR pump breaker inspection 1554 1E12 4 003h , Perform.survol11ance-LES-EO-112
. '555'
.1E12-F003A ' Rebuild limitorque 4 556:
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.557: 1E12-T000A- Perform surveillance LES-EO-112.
?;c 558:
" , 505 1E21-C002_ Rep 1mco pump 566f c1E21LC0021 Performtbreaker inspoetlorr l+1 ,: '
, 1571L 1E 51-l'04 5 : perform surveillance LES-EO-112 l, ' i 1E51-F046
- 1 -:.
-583 1E22-8001 -Replace oil filtern i
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. LASALLE NUCLEAR POWER. STATION m.,.
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;; UNIT 2-1' MONTHLY PERTORMANCE .LPORTI
,. +..' .. 4) OCTOBER 1990 i 4 i
. COMMONWEALTH EDISON COMPANY-I i
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.i NRC DOCKET:NO.~050-374-
-L LICENSE NO. NPF-18. .
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S. 9 a TABLE OF CONTENTS (Unit 2) I. INTRODUCTION t
)
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EI I . REPORT r I A' . -
SUMMARY
OF OPERATING EXPERIENCE li D. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED .i
, MAINTENANCE :50.59) l
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~
1.o Amendments lto Facility License or Technical Specifications 2. Changes to procedures which are described in the Safety' Analysis = Report. J 3.: LChanges to- f acility which are described in the Safety Analysis- , Gl.- . Report. . .
- 4. Tests and Experiments not covered:in the Safety Analysis Report.
~
4 i " i C .L MAJOR CORRECTIVE ' MAINTENANCE TO. SAFETY-RELATED EQUIPMENT' Ej Ub ,' :D. -
?COMPLETUD SAFETY-RELATED MODIFICATIONS 4 1; Q: .
?", M' E.. -LICENSEE EVENT = REPORTS i W,;
d-F." DATA TABULATIONS : l.- Operating Data 1 Report- d i f 2.. Average Daily. Unit Power Level J'M .3. Unit Shutdowns-and Power = Reductions n'; ; ' '
- G; . . UNIQUE REPORTING REQUIREMENTS' j ,
1.- ' Safety / Relief Valve! Operations. i .E '2.- ECCS' System Outages c ll (p 3. Off-Site' Dose Calculation Manual' Changes- '
? 4 '. ' Major Changes lLo Radioactive Waste: Treatment -System a, b ,, s 5. 1Indic' ons of Failed Fuel Elemeats: l 1
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.l t I. INTRODUCTION (Unit 2)
The LaSalle. County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois.. Each
!- unit is.a-Bolling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste heat is rejected to a man-made cooling pond using *
'the1 Illinois River for'make-up and' blowdown. The architect-engineer was Sargent and Lundy'and tho' primary construction contractor was 7" Commonwealth Edison Company.
Unit Two was issued operating license number NPF-18 on December 16, 1983.. Initial-criticality was achieved on March 10, 1984.and commercial'
- l. power operation was~ commenced on June 19, 1984.'
This report was1 comp 21ed by Michael-J. Cialkowski, telephone number i.f (815)357-6761 extension-2427.
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111. MONTHLY REPORT: 3, , A ~, -
SUMMARY
Or OPERATING EXPERIENCE (Unit 2) Day, Ilmt ED At _ 1, 0000 Reactor critical, generator on-line at 1127 MWE 0200 3 educed power to 1070 MWE for condensate pump transfer 0900 Increased power to 1130 MWE 3 0100 Reduced-power to 850 MWE for turbine valve
. surveillance testing
'1400 Increased power to 1130 MWE:
10 0200 Reduced power to 1080 MWE to cycle
. ,;.. condensate / condensate booster pumps [ '- '1000 Increase power to 1130 MWE 23 0400 - Reduced power to 10.0 MWE for system load
[ 1000 Inc teased power to 1130 MWE ;
, 24' 0200 Reduced' power'to 850 MWE for heater bay inspection.
, '; 1400 : Increased power.to~1130 MWE n w.
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, 30 . --
?2300 Reduced power to 830'MWE for heater bay: work hi ;31' 1700~ Increased power to 1130,MWE-
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.2400 Reactor critical, generator on line at 1130 MWE *
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R. PROCEDURE
CHANGES, TESTS OR EXPERIMENTS (50.59) (Unit 2) ,
- 1. Amendments to the Facility License or. Technical Specif1 >. tion.
(None)
-2.- Changes to procedures which are described in the Safety Analysis Report. ,
a) LaSalle Special Procedure LLP-90-062, "Instrun.pnt Nitrogen
.(IN) Regulator AdjusLnent" was performed for Unit 2 to connect an additional IN pressure bottle to allow ,
regulator adjustments while preventing the loss of Automatic Depressurization System'(ADS) pressure. The connection was through a test tap valve which changed a . Primary Containment boundary and required Technical n Specification Action Statement 3.6.1 to be entered.1 The . use of personnel to enforce Primary Containment integrity
# "" was utilized during the regulator adjustments.- The safety evaluation concluded that no change in the probability of
~ ;b an accident initiated and the consequences are' mitigated
/U by prearranged neasures.taken.
- 3. Changes to facility which are described in the Safety Analysis
- Report.- ,
.(Hone): * ;p 4 .1 . Tests and Experiments not described in the Safety Analysis. ,
T = Report.
<(None)
C. MAJOR' CORRECTIVE' MAINTENANCE TO SAFETY RELATED EQUIPMENT (including q[ g: w: ;SOR; differential pressure switch failure reports). 1(See . Table il): b5 D'.l COMPLETED SAFETY RELATED MODIFICATIONS. 1 U '
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's LICENSEE l EVENT: REPORTS (Unit' 2) +
q,. , -(None)
- + s M- ( F.. = DATA TABULATIONSD(Unit 2) h .mu ' ' ,
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- 1. Operating Data Report. O (See' Table 3): 'I
. Sc4'1 s "f -2. : Average. Daily Unit Power Level.
5 "L (See TableJ4)J ; RT 3. ' Unit Ghutdowns and Significant Power Reductions. I :p -(See-Table 5) ' m,
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- -SAFETI-RTLA N EQUIPMENT
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RESULTS AND EFFECTS ON SAFE PLANT OPERATION
~
' NUMBER ~ CCMPONENT-' -.CAUSE OF.. MALFUNCTION -
CORRECTIVE ACTION' ~ x_:. _
"LO2045- Suppression Pool- -RTD Input Board Improper Temperectre- Replaced RTD Input Board Temperature Element. ' Indication LO2884- 1APRM "C'- -5 VDC. Power Supply TImproper Voltage to - Replaced S VDC Power to APRM. Supply L03153 RHR Pump. Minimum:. -
' Minimum Flow Switch Switch Out'of. Calibration Replaced. switch Flow ~
Tolerance i l I L L 1 i I l. i' 1 (See al.tached SOR: failure report) i ~' ~ -ZCADTS'/7 i-r { g ^g .-
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t; - SDR dp Switch Failure Data Sheet Equipment Piece Number: 2E12-N010BA Model Number: 103-AS-B202-NX-JJTT6 Serial Number. 85-6-3587R Application: Egaldual_.Reat Eemo.vgl_111aimum Flow Switch Date and Time of: Discovery:. 10/25/9.Q 113.Q hours Reactor Mode Run Power Level: 100% Calibration Tolerance: 23.6-22.4"WC Nominal:Setpoint: 23.0"WC {af
. Action Limits: ' <2 4. 7 or >2L a"WC Reject' Limits: <17.7 or >28.3"WC Technical Specification Limit 5.90"WC As Found Setpoint: * "WC Date and Time of Return to Service: 10/25/9Q hours Model Number of Replacement Switch: ~ '10 3 AS -B2 0 2'-NX-JJTT 6 '
- l TSerial. Number of Replacement Switch: .B.9-2-3874
-DVR Number: 01-2-90-072 2
pn
- Causo's 'Durino routine calibration.=oressure_ differential switch 2E12-N010BA-g ,. setpoint was found to be erratic and not:reggatable. The cause of the switch
'i -Lailure has not been determined pendino switch disassambly and' inspection.
i Corrective'Acthn: The switch was left isolated'and work recuest was written E3 j if t,Q replace it. The switch'was replaced _an.LLLRaiting_diaggasmbly and ~
't , , :ingpection. This failure data sheet will be undated and included in next E EQnthi _' LEO _ERE10.IMARCf _ Report . _
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~- + 2- 1 -
(F.3 i TUNIT SHUTDOWNS AND.PCWER' REDUCTIONS >200
~
c- .
- (UNIT ' 2 )
L. . METHOD OF. ' CORRECTIVE-
~ YEARLY:- .
. TYPE,.. -
SHUTTING DOWN .. ACTIONS /COpeENTS
- SEQUENTIAL DATE F:~ FORCED:- DURATION (_ THE REACTOR OR (LER/DVR S if' NUMBER '(YYMMDD) S : StN (BOURS); REASON -REDUCING' POWER' applicable'
~
(None) .;.
SUMMARY
OF OPERATION: -- The unit remained on51ine at'hightpower throughout the month. Several' minor power reductions were required due to low grid demand,: routine'surveillances.and heater bay' work. ZCADTS/7
; A. . ,, _ ,_ ;' . . - u~ . .,4 ;_ec ,n.,c ,v, - #c : _. a._ ,.e:w ;;; -a ,, , _ . , , _ . , _ . . . ; . . _ . .- - - . . . . . . _ _
4 .>
". * .G. UNIQUE REPORTING REQUIREMENTS (Unit 2)
- 1. Safety / Relief Valve Operations VALVES NO & TYPE PLANT DESCRIPTION DATE ACIMATED ACTUATIONS CONDITION QF EVENT
,g s (None).
- 2. ECCS System Outages (See Table 6)
- 3. Changes.to the Off-Site Dose Calculation Manual.
(None) 4 .' .M'ajor' changes to Radioactive Waste Treatment Systems. p, (None) [ r; '
- 5. ~ Indications of railed fuel Elements.
(None) kb
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_sk, ZCADTS/7-3
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3 (Unit 2) Tablo 6
- G.2 ECCS System Outages >
Note: The year and unft data has been removed from the outage number. DUIAGEJf02 EQUlfMI21T EHRE0SE - 1718 2E51-C005 Replace 74 relay , 1734 2E12-C002A Litbricate pump 1739 2A D/G Repalt crankcase pressure switch E I 1742 2E12-F085C Repair valve
'1745- 2E12-F064B Troubleshoot valve ;
,1751; 2B D/G- Replace atarting air compressor
,E . circuit breaker
.n ,
'1753 2B D/G Instal 1~ fuel manifold check _ valves 't
;1755 2B D/G- Disconnect patter diesel exhaust ..
,, lines
- n
- 1756- 2B D/G LRepair_ immersion heater temperature u .c switch 4
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