Text

Monthly Operating Repts for Feb 1986
	ML20138A028
Person / Time
Site:	LaSalle
Issue date:	02/28/1986
From:	Diederich G, Peters J; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM)
References
	NUDOCS 8603130399
	Download: ML20138A028 (36)
	v • d • e

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LASALLE NUCLEAR POWER STATION UNIT 1 !

l MONTHLY PERFORMANCE REPORT .

t FEBRUARY, 1986 i

COfMONWEALTH EDISON COMPANY ,

t NRC DOCKET NO. 050-373 ,

LICENSE NO. NPF-11 ,

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8603130399 840229 {

PDR ADOCM 05000373 -

R PDR Document 0043r/0005r h t l{ l

TA"LE OF CONTENTS I. INTRODUCTION II. MONTHLY REPORT FOR UNIT ONE A. Summary of Operating Experience B. PLANT OR PROCEDURE C{ANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

1. Amendments to Facility License or Technical Specifications

2. Facility or Procedure Changes Requiring NRC Approval

3. Tests and Experiments Requiring NRC Approval

4. Corrective Maintenance of Safety Related Equipment C. LICENSEE EVENT REPORTS D. DATA TABULATIONS

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS

1. Main Steam Relief Valve Operations

2. ECCS System Outages

3. Off-Site Dose Calculation Manual Changes

4. Major Changes to Radioactive Waste Treatment System Document 0043r/000$r

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, I. INTROlXICTION i I The LaSalle County Nuclear Power Station is a two-unit i i facility owned by Cn==nnwealth Edison Company and 1 located near Marseilles, Illinois. Each unit is a .

Boiling Water Reactor with a designed net electrical i

, output of 1078 Megawatts. Waste heat is rejected to a

? man-made cooling pond using the Illinois River for

} make-up and blowdown. The architect-engineer was ,

j Sargent and Lundy and the primary construction ,

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contractor was Cn==anwealth Edision Company.

t i Unit one was issued operating license number NPF-11 on

April 17, 1982. Initial criticality was achieved on i

} June 21, 1982 and commercial power operation was [

commenced on January 1, 1984. ,

f This report was compiled by James P. Peters, telephone

} number (815)357-6761 extension 325.

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II. MONTifLY REPORT FOR UNIT ONE A. SUPMARY OF OPERATING EXPERIE'!CE FOR UNIT ONE Pebruary 1-28 Feb.1, 0001 flours. The Unit entered February with the reactor subcritical and unit off-line in cold shutdown for first refuel outage.

Feb. 28, 2400 llours. Reactor in cold shutdown for first refueling outage.

Document 0043r/000$r

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,B. PLANT OE PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED

. PRINTENANCE.

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1. Amendments to facility license or Technical Specification. '

l Amendment 33- Amendment to the CRD Low Charging Water Header

-! Pressure Scram Setpoint; Surveillances and LCO. j T.;;a-t :at 34- Add Excess Flow Check Valve ICM102 to Table I 3.6.3-1. j 1

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2. Facility or procedure changes requiring NRC approval.

There were no Facility or Procedure Changes Requiring NRC 3 L

,l approval during this reporting period.

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3. Tests and Experiments requiring NRC approval. -

l There were no tests or experiments requiring NRC approval during j this reporting period.

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4. Corrective maintenance of safety related equipment, ;

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The fo!!owing table (Table 1) presents a summary of t i i f safety-related maintenance completed on Unit one during the {

I reporting period. The headings indicated in this summary l 1

includet Work Request number, component Name, cause of f 1

Malfunction, Results and Effects on Safe operation, and j

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j corrective Action. i i !

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7 TaaLE 1 00ERSCTIVE ORINTemMCE OF .

SAFETY RELATED MUIP9ENT CAUSE OF PELPUNCTION RESULTS AND EFFECTS CORRSCTIVE ACTION WORE RSQUEST 00BWOMENT ON SAFE PU WT OPERATION , ,j L20783 *lA* DG Prelube Pump Dry-starting of the Diesel Prelubrication of Diesel Engine. M-1-1-83-129.

IDG0lK Engine.

L20787 *lA* Diesel Generator Excessive vibration on Relocate controls and monitoring M-1-1-82-310.

1DG0lK floor area. Instrtamentation to a qualified location.

L43784 HPCS full flow test Packing leaks external Contamination problem Repacked valve.

valve to suppression to valve pool IE22-P023 L51706 Diesel cenerator Internal binding within valve was stuck open Rebuilt East E Nest Air air relay valve the valve. start relay valves with IDc0618 new software kit.

L53312 la DG Blocking Bad diode CR2 Failed LES-DG-102 Replaced diode CR2 diode CR2 L53595 shutdown cooling Limit switches were valve indicates open. Reset limit swtiches testable check misa11gned. edwn actually closed.

valve IE12-F050A L53936 RHR service water Packing leak etternal to No pottential effect. Repacked valve.

50[ outlet valve the valve.

IE12-F068E Dcnament 0043r/0005r

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TABLE 1 CORRECTIVE MAINTENANCE OF .

SAFETY REIATED EQUIPMENT CCMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION idCRK REQUEST ,

ON SAFE PLANT OPERATION L54765 Div-II CSCS Pump Bad bearings No pottential effect, just Installed new bearings.

room cooling fan sounded bad.

IvYC6C L55302 RMR "lB* Pump sw tion Loose packing Ccntamination problem Adjusted packing till leak valve IE12-F0048 stopped.

L55400 RHR "lA* HX vent Torque switch set too low Valve torque out going to Adjusted torque switch to valve IE12-F074A at I open position. 2. within FLI requirements.

L55402 APR?t *E* IC51-k605CS Excessive AC ripple on ARPM "E* in bypass Replaced capacitor C1 and SVDC Power Supply, bridge diode.

L55553 Pressure detector Bad mounting studs are Need to remove pressure Adjusted and replaced assembly IPS-DG047 either too stract or detector to fix. studs to appropriate stripped. length.

LS%73 HPCS injection valve Internal binding within Valve binds up in intermediate Cleaned valve stem and IE22-F004 valve. position, tripping breater. lubricated.

L55707 H2 Reccabiner Internal binding within Overloads trip while cycling Cleaned and lubricated cooling water valve the valve. valve. stem.

Erement C043r/00C5r W ____-_____ - - _ _ - -- - - - - ._______ _ _ - - _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _

7 TABLE 1 CORRECTIVE MINTENANCE OF SAFETY RELATED EQUIPMENT !

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WORK RECUEST CO NCWUfr CAUSE OF M LFthCTION RESULTS AND EFFECTS CORRECTIVE ACTION ~

ON SAFE PLANT OPERATION l

I L55783 *lA* IC Cooling Pump oil fil! line broken Pump inoperable Fix line and refilled with j water pump IDG0lP oil. !

1 L55849 Cbntrol Roon HVAC Bad optic light. Tripped during LIS-VC-053 Replaced Optic lights. I Ammonta detector and unable to reset.

cxY-VC165A i

1.55872 *lA* DG Differential Cut wire at connection Differential relay inoperable. Resoldered cut wire.

relay 1487-DG002 I

L55909 *lA* DG lube oil Thermal overload on Pump inoperable. Replaced thermal pump 10ColK breaker keeps tripping. overload.

L54% Bus 143 Relaying Loose connections and Relay Chatters cleaned and tightened 1AF07E dirty slide contacts appropriate contacts. !

for bus pot comparta nt.

l L560#1 RHR Shutdows cooling Bound up servo motor Recorder was inoperab!?. Replaced servo motor. I l temperature recorder l IE12-R6CI L56143 *1B* CC Fuel oil Breaker position set too Breaker trips en magnetics Adjusted to appropriate transfer pump IDOO2P high. with switch in any position. setpoint on breaker. i l

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C. LICENSEE EVENT REPORTS !

The following is a tabular su.mmary of all licensee event reports for LaSalle haclear Power Station, Unit One, 1;gged during the reporting period, February 1 through February 28, 19.,6. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFN 50.73.

kl.qef1see Event _ Report Number _ Qalq Illle_qlpqquff ef)qa j 86-001-00 01/10/86 "B" VC Ammonta Detector Trip, Due from loading gate j misa!!gned or dirty photo cel!

optic. l 86-002-00 01/20/86 SNV'S - S. K U failed to meet lift tolerance, due to seat

, leakage, i

l 86-003-00 01/25/86 Missed sample on Reactor Water pit, due to personnel error.

86-004-00 02/05/06 "A" VC Ammonia Detector trip, q due to broken chescannette tape.

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D. DATA TABULATIONS The following data tabulations are presented in this report:

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit shutdowns and Power Reductions l

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1.* OPENATING DATA NEIM]!!I

, DOCKNT NO. 050-373 UNIT lia'ialle One l DATE J/_10/86 [

00MPLETED BY Lames P. Peters .

TELEPHONE 1815)357-6761 l i

OPERATING STATUS

1. REPOhTING PENIOD:_ November 1985 GNOSS HOUNU IN REPONTING PENIOD:_672_ f

2. CUNNENTLY AUTHONIZED POWEN LEVEL (MWt) ))2] MAX DNPEND CAPACITY (MWe-Net): 1036 DESIGN NLECTMICAL NATING (MWe Net) 1078._

3. POWEN LEVEL TO WHICH NESTNICTED (IF ANY) (MWe-Net): N/A -

4. NKASONS PON NESTNICTION (1F ANY): N/A THIS MONTH YN TO DATM CUMULATIVE 5 NUM8EM OF HOUNS NKACTON WAS CRITICAL __, ,92_ 0 00 12Q)_9tQQ_ l

6. NEACTON NKSENVE SifUTDOW HOUNS ,_ _,_Q1Q _ 0.0 _L6.12t q0_ {

7. HOURS GENENATON ON LINE _,_0.Q __, QiQ 11)(2 QQ_

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8. UNIT NESERVN SifUTDOW HOUNS ... 0.0_ . . . ._ 0 . 0_,,_ ___Q10 Ot Q_ , {

9. GNOSS THRRMAL ENENGY GENENATHD (MWH) 0.0_ 22211429_

10. GNOSS RI.NC. ENKNGY GKNKNATKD (MWH) 01 Q_ 0.Q , LQi92)21. !

11. NNT MLEC. ENENGY GMNKNATED (MWH) _-A!.Q__ l_i12?_,_ 222Q921.__ !

12. NMACTON SERVICE FACTON _0 . 0 \_,,, _, Qt9L., _6]21% l

13. hKACTON AVAILABILITY FACTON 0.0L .,_,,920 % 72tl% j

14. UNIT SKRVICE FACTON ,__QM.__ __Q29L,, _612 ,_,,,,, p

15. UNIT AVAILABILITY FAC10N _Q t0 L __Q2Q) , _91tB l

16. UNIT CAPACITY FACTON (USING MDC) , _112L -0.9% .jlt0. 8% !

17. UNIT CAPACITY FACTOH(USING DMSIGN MWe) _- 12RL . -0. 9L_ _18A __

18. UNIT FONCND OUTA05 NATE .0.0%_ .__QtQ L._ _l.2t4% ;

19. SHUTDOWS SCHEDULRD OVMN NKXT 6 MONTifS (TYPK, DATK, AND DUNATION OF RACH) l The First Refueling, Maintenance, Su:veillance and Modif1 cat ton Outage i.

began October 18, 1985 and will last 30 weeks.

20. IF SifUT DOW AT END OF NKPONT PMNIOD, NUTIMATMD DATE OF STANTUPt ,f4y1 (

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 '2'., AVERAGE. DAILY _ UNIT _ POWER LEYWI.

DocNET No: 050-371 UNIT! byJALLK_0NE DATK! J/10/66 CONLNTED BY t denets_ P.. Petera __ TELNPHONE 1815)..357-676[ ENTH1,RMUMY _l986, DAY AVENAGE DAILY POWER LEVEL DAY AVENAGN DAILY POWEN LEVNL (MWe-Net) (MWe-Wet)

1. -13 17. -13

2. -13 18. -12 3 -13 19. -12

4. -13 20. -12 S. -13 21. -13

6. -13 22. -14

7. - -13 23. -14

8. -13 24. 9. -13 25. -14

10. -13 26. - l_4

11. -14 27. -1)

12. -14 2d - 1,4_ _

13. - 13_,_ 29. N/JL

14. -13 30._ N/A-15 . _ - L]_ __ 31. - N/A

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3. tasIT StarrDnnan Amp Pondet asDUCTIces ~

DOCERT 880. 050-373 LBf!T MhfE Le5elle One - DATE 3/10/06 .

RarostT DIDerni Ps3SUARY 1996 COfWLETED BY James P. Peters TELarssoses (415)357-6761 , 1 mne00 OF TYPE SHUTTIafG D0taf I F: FOSCID DURATIOef THE RSACTOR OR N ECTIVE 3s0. DATE S: SOEIDULED (HOURS) REASOpf RsDUClafG POnduR ACTIOefS/C0f9WBfTS There wre no Unit shutdones or penser reductions during this reporting period due to the refuel outage in progress.

Docament 0043r/COOSr

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e I E. UNIQUE RKPONTING NEQUIREMMNTS

1. Safety / Relief valve operations for Unit one. !

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VALVK3 NO & TYPH PLANT DESCNIPTION I [%TE ACTUATKQ 8CElgl.QN CONpJTION QE,l0(MNT ; l There were no Safety Nelief Valves Operated t<.: Unit One during this reporting period. i l l ) 1 I [ 4 1 I 1 1 1 j I t l il I l I l l tx>cissent 0043r/000$r

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2. BCCS Sy tems Outcges (

l [ l The following outages were taken on RCCU Systems during the reporting period. l t 9EMK % NEEfMNI EVPJE!K_9f'_@!TN]H , t Reference Attached Pages 1-2, 1 i l l l i i i I i i I i 1 f L i I t I i j l l } J l 1 Doctament 0043r/000$t

WTAGE.E2.4. BQVIE!!MNJ PUNfQyK OF (EAGM l-217-83 HilN Uhutdown Cooling InstcIl new Temparcture system Inst itme ntat ion. 1-218-86 1831-F005C1 Hepair Sealtite i 1-220-86 IE51-F076 Repalt Leaking Deat 1-221-86 1E12-F094 f.KU - hy- 112 1-228-86 "l A" DG Coollnq ptmp Repalt pump Ollet 1-229-86 IH12-F0740 L83-EO-!!2 1-230-86 IH12-F0478 Clean Worm Shaft Annembly 1-231-86 IE51-F045 LEU-RQ-l!2 1-233-86 IE12-F016a LEU-RQ-l!2 1-240-86 lip-OY Upool piece Install Upool piece 1-241-86 "A" and "B" Wu pumps Liu-kO-l!2 1-242-86 IE22-C003 Lubrication 1-243-86 lH12-F018A LEU-hV-ll2 1-246-86 IH22-F010 Isolate 1.ine 1-251-86 IK12-FO!!b Chan9e Motor Grease i 1-252-86 "lu" DG Motor AC Troubleshoot and Hep 41t 1-253-86 "lA" DG New 011 ptmp Test Breaker l 1-254-86 IN12-F064A Nep41t Valve , 1-256-86 IE51-F010 LEU KQ-ll2 l l-257-86 1H51-F019 LNU NQ-112 1-258-86 IE51-F022 LEU - EQ- 112 , 1-259-86 1851-F031 Lku-EQ-ll2 i 1-260-86 IH51-F046 f.HU-EQ-112 l l-261-86 lH51-F059 1.H3-E0-112

1-265-86 "lA" IxJ Turbo's Repolt/Neplace Thermal ; A/C pimp. Overload. ; l-267 86 "D* HitN W.L. pump Hep!4ce Check Valve I check Valve Flange bolts ! l 1-268-86 lH12-F0600/758 Repatt Valves [ 1-274-86 IM12-F040A 1.ubt icat ton ' l-277-86 1N12-F068A Neplace Unaltite. f I-280-86 NCIC Lubtledtton Thiuttle Valve. 1-285-86 "H" NifM U4mple V4lve Nep4lt Valves 1-287-86 IH21-F001 f.KU -l?Q -I l 2 1-288-86 11x1035 f.H3 80-182 i 1-302 86 kCic Throttle Valve Asnist. Marh. Maint. l l-311-86 "lA" 1/3 Water Tight Add Time Delay l Door 1-319-86 IMl2 F090ti Clone Valve Till Tenting C(aplete , 1-333-86 1033-F102 Neytedse Limitorque ; l-334 86 IN51-F061 Hepack V4lve ! l-337-86 IH22 F012 Nep4tt Witor i 1-339-86 LK'u Upool piece Nemove uloel ; l-340 86 IM12 C100A 1,ubtleatton ; f r I loc uent 0043t/0005t

QUTAGE Wo< HELIIERMI Et!M1XiH OF OVMGM

l-343-83 lH12-F049A LEU-EQ-ll2 1-344-86 "l A" HilN Pump Recouple 1-347-86 lH21-c001 Lubrication 1-349-86 IH21-F057 close closed Till System Nestarted 1-352-86 lH12-F040A Peplace Unap Ning.

1-382-86 lH12-F041 Replace Packing 1-387-86 "lA" HilN Pump 011 Gample 1-389-86 "10" HilN WU Nad Relocate Probe Monitor 1-405-86 DIV-1 Water Leg Pump Repalt Pump 1-408-86 lH12-F0928 Keep Closed 1-409-06 1812 F010A open for Dr41ntrig 1-413-86 "lA" DG Malnt. Uwltch cooling Water Pump out of Service. 1-415-06 NHH Uystem Pressure Install New Low Pressure Uwitchen Switchen. l l ' l l l 1 l l l fxecument 0043r/0005r ? - __-

            ' 3. off-sito Doso Calculction Manuel I

There were no changes to the ODCM during this reporting perlod.

4. Radioactive waste Treatment Systems.

There were no significant changes to the radioactive waste treatment system during this reporting period.

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LASALLE NUCLEAR POWEN STATION UNIT 2 MONTifLY PERFORMANCE HFJORT FKBNUARY 1986 COfmONWMALTil EDISON COMPANY NHC DOCXKT NO. 050-374 LICENUM NO. NPF-18 DOCUMENT 1D 0036r/000$r

    .                             TABLE OF CONTENTS I. INTRODUCTION II. MONTliLY REPORT FOR UNIT TWO A. Summary of Operating Experience B. PLANT OR PROCEDURE Cl{ANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

1. Amendments to Facility License or Technical Spec 1fications l 2. Facility or Procedure Changes Requiring NRC Approval

3. Tests and Experiments Requiring NRC Approval

4. Corrective Maintenance of Safety Related Equipment C. LICENSEE EVENT RFSORTS D. DATA TABUI.ATIONS

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations

2. ECCS System Outages

3. Off-Site Dose Calculation Manual Changes

4. Major Changes to Radioactive Waste Treatment System l

l t I DOCUMENT ID 0036r/0005r

I. INTRODUCTION 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 Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste heat is rejected 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 Commonwealth Edison Company. Unit two was issued operating licenne number NPF-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and commercial power operation was commenced on June 19, 1984. This report was compiled by James P. Peters, telephone number (815)357-6761 extension 325. l i l l IX)CUMENT ID 0036r/000$r

II. . MONTHLY REPORT FO JNIT '190 A.' SUFORRY OF OPERATING EXPERIENCE FC UNIT TWO February 1-28 Feb. 1, 0001 Hours. The Unit entered February with the Reactor critical at 100% power and Generator on line at 1118 MWE. Feb. 6, 1155 Hours. Reactor power reduced to 91% (1000 MWE) for Control Rod Manipulations. Feb. 7. 0400 Hours. Reactor power restored to 100% (1117 MWE). Feb. 8, 1210 Hours. Commenced power to drop to 64% (700 MWE) due to BPV #1 failing l surveillance. Feb. 8, 1445 Hours. BPV #1 repaired and began ramping up in power.

Feb. 9, 1500 Hours. Reactor power restored 99% (1100 l MWE).

Feb. 10, 1500 Hours. Commenced power to drop of 250 : MWE/Hr. due to RPV #1 failing l surveillance. Feb. 10, 2110 Hours. Generator taken off-line. Feb. II, 0125 Hours. Reactor shutdown (subcritical). j Feb. 11, 2050 Hours. Reactor went critical. Feb. 12, 0300 Hours. Generator on-line and reactor ramping up in power. Feb. 12, 2300 Hours. Reactor power at 72% (840 MWE). Feb. 13, 0455 Hours. Reactor power reduced to 53% (596 MWE) due to control Rod Manipulations. ( Feb. 13, 2300 Hours. Reactor power restored to 91% (1005 WME). Feb. 14, 0200 Hours. Reactor power reduced to 65% (725 l' MWE) due to control Rod Manipulations. Feb. 16, 2300 Hours. Reactor power restored to 99% (1106 MWE). l DOCUMF#1' ID 0036r/0005r

II. MONTHLY REPORT FOR UNIT TWO (Continued)

                   .         A.                     SUfegutY OF OPERATING EXPERIENCE FO UNIT TWO Eebruary 1-28 Feb. 16, 1503 Hours. Reactor scram on load reject.

Feb. 17, 1906 Hours. Reactor went critical. Feb. 18, 0355 Hours. Generator on-line. Feb. 20, 0700 Hours. Reactor power restored to 84% (945 MWE) limited by rod pattern. Feb. 20, 2100 Hours. Reactor power reduced to 51% (586 MWE) due to Control Rod Manipulations. Feb. 23, 2000 Hours. Reactor power restored to 100% (1114 MWE). Feb. 25, 0505 Hours. Reactor power decreased to 85% (966 MWE) due to Control Rod Manipulations and held for preconditioning ramps and LIS-NR-216. Feb. 26, 1500 Hours. Reactor power restored to 100% (1116 MWE). Feb. 28, 2400 Hours. Reactor power at 99% (1100 MWE). } I 'l 1 t 2 l i l ! DOCUMENT ID 0036r/0005r L___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _

B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.

1. Amendments to facility license or Technical Specification.

There were no Ammendments to facility license or Technical Specifications during this reporting period.

2. Facility or procedure changes requiring NRC approval.

There were no facility or procedure change requiring NRC approval during the reporting period.

3. Tests and experiments requiring NRC approval.

i There were no tests or experiments requiring NRC approval during l the reporting period. 4 1

4. Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a summary of l safety-related maintenance completed on Unit Two during the i reporting period. The headings indicalitd in this summary l ' include: Work Request number, Component Name, cause of , malfunction, results and effects on safe operation, and I i corrective action. i i 4 l l l l 1 i DOCUMENT ID 0036r/0005r

TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION i L49202 "A" SBLC Pump Bad packing and Piston Water leaks about 20 Gal / Min Installed new packing

2C41-C001A Shaft. into drain barrell. and piston shafts.

i L49982 HPCS Pump Suction Incorrect valves on Reading 25 psig with HPCS Recalibrated pressure i Pressure Indicating Data Sheet. System off, when should switch. Switch 2822-N015. read 10 psig. L54030 RCIC Pump Suction Need torque switch Improper valve. indication Installed limiter plate. from CY 2E51-F010 < L54832 HCU-22-27 Bad cartridge intervals Valve leaks by when opening Repaired cartridge valve. 2C11-D001-111 and closing. 1 L54833 HCU-14-39 Bad cartridge intervals Valve leaks by when opening Repaired cartridge valve. 2Cll-D001-Ill and closing. L54834 HCU-14-27 Bad cartridge intervals Valve leaks by when opening Repaired cartridge valve. 1 2Cll-D001-lll and closing. L54837 HCU-54-35 Bad cartridge intervals Valve leaks by when opening Repaired cartridge valve. 2Cl1-D001-111 and closing. { L54838 HCU-42-15 Bad cartridge intervals Valve leaks by when opening Repaired cartridge valve. 2C11-D001-111 and closing. i i 1 1 DCIUMENT ID 0036r/0005r

TABLE 1 1 CCRECTIVE MAINTENANCE OF . SAFETY RELATED BQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION l ON SAFE PLANT OPERATION L55510 Blown fuse resulting from Valves has no light indication Replaced wire and lugs. I H2 Recombiner j Cross-tie valve pinched wire causing a l 2HG009 short. L55627 Main Steam Line valve Bad torque switch Seal-in the close direction does Installed new torque ' switch. 2B21-F067C not work. L55629 #1 Bypass valve Loose packing bolts. Valve packing leaks. Tightened packing bolts. 2B21-MSBPV-1 L55677 APRM-A 2C51-K6056M Bad meter Panel indication sticks at 6S% Replaced meter and l calibrated.

,             L55708                 "C" RHR Pump Min.         2E12-N010CA Setpoint         Valve does not open when should Recalibrated to

! Flow valve 2E12-F064C was too low. appropriate setpoint. I

;             L55871                 RCIC Outboard Steam       Improper packin3             Steam leak around stem.          Added I ring of packing
!                                    Isolation 2E51-F008                                                                     and adjusted till leak
!                                                                                                                            stopped.

L55890 RCIC Outboard Steam Unidentified Jumpers Valve failed to close Replaced unidentifiable ] ! Isolation 2E51-F008 and loose screw on limits intermittently. jumpers, tighten loose screw and limits. I l i i

1 I l 1 ! DOCUMENT ID 0036r/0005r

_ - _ _ . ___ _ _ _ _ . _ . _ _ _ _ _ . _ _ _ . _ _ . . . _ _ _ . . _ _ _ m. , . ___ _ ._. _ . _ . . _ _ , _ _ _ __ __ _ _ . TABLF 1 i CORRECTIVE MAINTENANCE OF . , i SAFETY RELATED EQUIPMENT l; l. WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION , L55910 ADS System "B" Bad Agastat GPI Time During LES-NB-102, setpoint Calibrated new agastat to 2B21-K35B Delay Relay. was determined to be 101 seconds. 3 inconsistent.

L56109 MSIV-LCS temperature Bad meter Failed down scale, 30 day time Temporary system change: indicator 2832-R602J clock. 1-345-86 to install meter from Unit #1.

l L56143 RCIC Outboard Steam Defective contacts on Valve failed to close from Replaced contact blocks on Line Isolation valve Control switch, control switch. switch. ! 2E51-F008. i j L56234 MSIV-LCS Heater Temperature indicator Improper temperature indication. Recalibrated temperature j Temperature indicator out of tolerance indicator. j (N) TY-2E32-R60lN l l

l l

l l 4 1 l i 1 a i d DOCUMENT ID 0036r/0005r

C. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, February 1 through February 28, 1986. This information is provided pursuant to the reportable occurrence reporting requirements as j set forth in 10CFR 50.73. Licensee Event Report Number Date Title of Occurrence 86-001-00 01/14/86 Failure of ACB 2413 to close, due to faulty relay contacts. l l l { 1. l l DOCUMENT ID 0036r/0005r i L

i D. DATA TABULATIONS The following data tabulations are presented in this report:

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions DOCUMENT ID 0036r/0005r

    .           1.' OPERATING DATA REPORT

DOCKET NO. 050-374 UNIT LaSalle Two

;                                                                                                                                                                                      DATE 3/10/86 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS

'l

l. REPORTING PERIOD: February, 1986 GROSS HOURS IN REPORTING PERIOD: 672

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY l (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net):1078

!              3.                       POWER LEVEL TO WHICH RESTRICTED (IP ANY) (MWe-Net):                                                                                                         N/A

4. REASONS FOR RESTRICTION (IP ANY): N/A THIS MONTH YH TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 624.54 1368.54 6757.94

6. REACTOR RESERVE SHUTDOWN HOURS 29.83 29.83 1716.93

7. HOURS GENERATOR ON LINE 605.3 1349.3 6585.6

8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 t

9. GROSS THERMAL ENERGY GENERATED (MWH) 1798080 3964104 19472656

10. GROSS ELEC. ENERGY GENERATED (MWH) 601090 1325871 6435940

11. NET ELEC. ENERGY GENERATED (MWH) 582879 1289889 6113104

12. REACTOR SERVICE FACTOR 92.9% 96.6% 56.4%

13. REACTOR AVAILABILITY FACTOR 97.4% 98.8% 70.8%

14. UNIT SERVICE FACTOR 90.1% 95.3% 54.9%

l 15. UNIT AVAILABILITY FACTOR 90.1% 95.3% 54.9% i 16. UNIT CAPACITY FACTOR (USING MDC) 8's.7% 87.9% 31.1%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 80.5% 84.5% 29.8%

18. UNIT FORCED OUTAGE RATE 9.9% 4.7% 23.2%

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

There are no shutdowns scheduled over the next 6 months.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A I

i l DOCUMENT ID 0036r/0005r i

  ,   .-.__..._,._--,-,..-.-..-.,_....n.                                                               . . - - , _ _ _ _ _ _ _ _ _ _ , - - . - . , , - - - - - - - - , - .                                                         _ . - , _ = _ . - , . - -

2 AVERAGE DAILY UNIT POWER LEvgt DOCKET No: 050-374 UNIT: LASALLE TWO DATE: 3/10/86 COMPLETED BY: James P. Peters TELEPHONE: (315) 357-6761 MONTil: February 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWEN LEVEL (MWe-Net) (MWe-Net)

1. 1073 17. -12 j

2. 1078 18. 408 3 1074 19, 835

4. 1072 20. 872

5. 1067 21. 757

6. 1032 22. 916

7. 1076 23. 1030

8. 986 24. 1055

9. 1047 25. 981

10. 763 26. 1070

11. -13 27. 1075

12. 503 28. 1069

13. 853 29. N/A

14. 918 30. N/A

15. 1040 31. N/A

16. 667 1

DOCUMENT ID 0036r/0005r

 - .-. - - --..       - - - - . -      . - - - . - . . ..... - - -. - -.              - - . - . - . - _ . . . - - _ _ . ~   . . - - . _ _
                                                                                                                                          - .-           . - - ~ .     ..   . - - . ~ -

ATTAC39ENT E

3. UNIT SHUTDOWNS AND POWER REDUCTIONS , ,

DOCKET NO. 050-373 UNIT NAME LaSalle One i DATE 3/10/86 . REPORT MONTH FEBRUARY 1986 00ffLETED BY James P. Peters TELEPHONE (815)357-6761 , ! METIK)D OF TYPE SHUTTING DONN ; F: FORCED DURATION THE REAC1M OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING PONER ACTIONS /COFMENTS 15 2/10/86 F 29.83 A 5 Failure of #1 Bypass Valve. 16 2/16/86 F 36.87 A 3 Reactor scram on load i reject due to a phase [ to phase fault on a transmission line. The A phase OCB l-9 failed to trip (out of tolerance on trip coils) resulting in the I 2 East Main Transformer. ; i t t I I I DOCUMENT ID 0036r/0005r , l f

r l ]. 8. UNIQUE REPORTING REQUIREMENTS f l '

l. Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE PLANT DESCRIPTION , i ACTUATED ACTUATIONS CONDITION OF EVENT 02/16/86 2B21-P013U l. Automatic 98% power The unit scramed on 2821-P013K 1, Automatic load reject, and SRV's l 2B21-F013D 1 Automatic 2821-F013U,K.D,S.E and l 2B21-P013S 1. Automatic C. All immediately 2821-F013E 1, Automatic opened to relieve

!                            2B21-F013C       1. Automatic                    reactor pressure.         !

These actuations were automatic due I to reactor over pressurization. The valves were open for U(52 ) sec.), K(15 sec.), D(12 sec.), S(15

>                                                            sec.), E(12 sec.), and C(12 sec.)          l respectively. The suppression pool         ;

heated up 7.l*F as a result of i ! these actuations. All SRV's which opened appeared to properly reseat i by tailpipe temperature indications. i t i I i i I ! } i i I , I - 1 i i i i i l l l I 1 DOCUMENT ID 0036r/0005r { -

2. ECCS Systems Outages The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO. BOUIPMENT PURPOSE OF OUTAGE 2-59-86 2851-F008 Inspect Wiring 2-64-86 2E51-F008 Isolate RCIC System 2-72-86 RCIC Vacuum Pump Troubleshoot. 2-74-86 "2A" DG Air Compressor Replace second stage discharge Cap Gasket. 2-76-86 2851-F008 Wiring Inspectlon. I I ! l , t )

DOCUMENT ID 0036r/0005r

 --r e~n-,e~                    .nm y                 em en e w- w-,r-          .,.---r-m.,-ve-,--,--e

              ', 3. Off-Sito Dose Calculction Manual There were no changes to the ODcM during this reporting period.

4. Radioactive Waste Treatment Systems.

There were no changes to the radioactive waste treatment system during this reporting period. DOCUMENT ID 0036r/0005r

Commonwealth Edison LaSade County Nuclear Station Rural Route 01, box 220 Marsemes. Illinois 61341 Telephone 815/357-6761 March 10, 1986 Director, Office of Management Information and Program Control United States Nuclear Regulatory Ccmmission Washington, D.C. 20555 ATTN: Document Control Desk Gentlemen: Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for the period February 1, through February 28, 1986. Very truly yours, f/ /,jfa G/J. Diederich Itation Manager LaSalle County Station GJD/RJR/cth Enclosure xc: J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center L. J. Anastasia, PIP Coordinator SNED J. E. Ellis, GE Resident H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle , f I } Document 0043r/0005r}}

ML20138A028

Text

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