ML20092F173

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Monthly Operating Repts for Jan 1992 for LaSalle County Nuclear Power Station Units 1 & 2
ML20092F173
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 01/31/1992
From: Cialkowski M, Diederich G
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9202190125
Download: ML20092F173 (24)
v • d • e


Text

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Cornmonwealth Edison

. LaSalle County Nuclear Station 2001 N. 21st. Rd.

Marseilles, Illinois 61341 Telephone B16/357 6701 February 10, 1992 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mail Station PI-137 Hashington, D.C. 20555 ATIN: Document Control Desk Gentlemen:

Enclosed for your information is the monthly performaned report covering 4

LaSalle County Nuclear Power Station for January, 1992.

{ Very truly yours, Y 9, 7 e G. J. Dieder ch V Station Hanager LaSalle County Station GJD/HJC/djf Enclosure xt: A. B. Davis, NRC Region III D. E. Hills, NRC Resident Inspector LaSalle J. L. Roman, IL Dept. of Nuclear Safety J. B. Hickman, NRR Project Manager D. P. Galle, CECO D. L. Farrar. CECO INPO Records Center D. R. Eggett, NED J. E. Kuskey, GE Resident T. J. Kovach, Manager of Nuclear Licensing

  • H. F. Naughton, Nuclear fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor J. H. Gieseker, Technical Staff Supervisor H. H. Servoss. QA/NS Off Site Review Station File ZCADTS/S 9202190125 920131 PDR

" ADOCK'05000373

"*" ) i

LASALLE NUCLEAR POWER STATION UNIT 1 HONTHLY PERFORMANCE REPORT JANUARY 1992 CO M WEALTH EDISON COMPANY NRC DOCKET NO. 050-373 l.ICENSE NO. NPF-11 i

ZCADTS/5

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TABLE Of CONTENTS (UNIT 1)

1. INTRODUCTION II. REPORT A.

SUMMARY

Of OPERATING EXPERIENCE B. AMENDHENTS TO FACILITY LICENSE OR TECilNICAL SPECIFICATIONS C. KAJOR CORRECTIVE HAINTENANCE TO SAFETY-RELATED EQUIPMENT D. LICENSEE EVENT REPORTS E. DATA TABULATIONS

1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions F. 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 Haste Treatment System
5. Indications of failed fuel Elements l

1 ZCADTS/5

I. INTH000CTION (Unit 1)

The LaSalle County Nuclear Power Station is a two-unit facility owned by Co monwealth Edison Company and located near Marseilles. Illinois. Each unit is a Bolling Water Reactor with a designed net electrical output of 1078 Megawatts. Haste 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 One was_ issued operating license number NPF-11 on April 17, 1982.

Initial criticality was achieved on June 21, 1982-and commercial power operation was comenced on January 1,1984.

This report was complied by Michael J. Cialkowski,-telephone number (815)357-6761, extension 2427.

ZCADTS/S

II. MONTHLY REPORT A. SLMMRY Of OPERATING EXPERIENCE (Unit 1)

Day llEg Event  ;

I 0000 Reactor critical, Generator on-line at 930 Hve.

0500 Increased power level to 1090 Mwe.

2300 Reduced power level to 850 Mwe due to system load.

2 0520 Increased power level to 1090 Hwe.

2200 Reduced power level to 850 Mwe due to system load.

3 0500 Increased power level to 1100 Mwe.

7 0200 Reduced power level to 1070 Mwe for CRD exercising.

8 0000 Increased power level to 1130 Mwe.-

12 2300 Reduced power level to 900 Hve due to system load.

13 0330 Increased power level to 1080 Mwe.

2300 Reduced power level to 920 Mwe for CR0 exercising.

14 0500 Increased power level to 1080 Mwe.

2200 Reduced power level to 750 Hwe to perform weekly and monthly surveillances.

15 0630 Increased power level to 1000 Mwe.

16 0530 Increased power level to-1130 Mwe.

2330 Reduced power level to 850 Mwe due to system load.

17 0430 Increased power IcVel to 1070 Mwe.

1430 Increased power level to 1130 Mwe.

21 0000 Reduced power level to 950 Mwe for performance of Main Turbine testing.

0410 Increased power level to 1100 Mwe..

0900 Increased power level to 1130 Mwe.

24 0100 Reduced power level to 1000 Mwe.due to system load.

0430 Increased power level to 1100 Mwe.

0730- Increased power level to 1130'Mwe.

l l- ZCADTS/5 L

II. MONIHLY REPORT (CONTINUED)

A. SLMMRY Of OPERATING EXPERIENCE (Unit 1)

Day Ilse Event 26 2300 Reduced power level to 1060 Mwe due to system load.

27 1000 Increased power level to 1130 Mwe.

2200 Reduced power level to 850 Mwe due to system load and cycling of the Turbine Control Valves. ,

28 0500 Increased power leve' to 1100 Mwe, 1100 Increased power level to 1130 Mwe.

2330 Reduced power level to 1000 Mwe due to problems- with the Heater Drain Pump forward valve (power level held due to system load).

29 0730 Increased power level to-1130 Mwe. - -

30 2230 Reduced power level to 850 Mwe to perform maintenance on the Heater Drain Pump forward valve.

31 0630 Increased power level to 1100 Mwe; 2400 Reactor critical, Generator on-line at 1130 Mwe.

ZCADTS/5

B. AMENDHENTS TO THE FACILITY LICENSE OR TEGINICAL SPECIFICATION (None.)

C. HAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT (including SOR differential pressure switch failure reports).

(See Tabie 1)

._ D. LICENSEE EVENT REPORTS (Unit 1)

~

LER Number QAlg Descriotion 92-001-00 01/07/92 Average Power Range Mor.itors gain adjustment factors set nonconservatively due to a connunication error during performance of Average Power Range Monitor Gain Adjustment surveillance.

E. DATA TABULATIONS (Unit 1)

1. Operating Data Report (See Table 2)
2. Average Daily Unit Power Level (See Table 3)
3. Unit Shutdowns and Significant Power Reductions (See Table 4)

ZCADTS/S

C. YABLE 1 (Unit 1)

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPHENT RESULTS AND EFFECTS HORK RE00ES' CORRECTIVE ACTION NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION Reactor Core Isolation Valve packing leak. None. Adjusted valve packing.

L12795 Cooling Turbine l Suctica Isolation Valve IE51-F045 Temperature switch meter Degraded operation. Replaced meter module.

L13102 Main Steam Line Differential module.

Temperature Switch 1E31-N615A (Ko SOR Failures this month.)

l l

{

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ZCADTS/5+

TABLE 2 E.1 0FEFATIN3 IATA EPORT 10CtET 90 050-37.,

UN11 LA5ALLE CNE I4TE February 10, 1 92 CO*PLE;El If M.J. CI ALKDLR1 TELEPHONE 1815)-355-6761 OPEEATIN3 STAit!3

1. KPDFilNG rERIDB January 1992 69055 H0135 IN REFORTIN3 PERIOD: 744 2, CUMENTLY AUTH0FIZED P0GER LEVEL (MJth 3,323 MAX DEPEND CAPACITY We-Neth 1,036 DESIGN ELECTRICAL RATlhG NrNet): 1,079
3. POWER LEVEL 10 WHICH K51RICIED (If ANY) (WrNeth N/A
4. REASONS FOR RE51RICT10N hf ANTh FEPCRTINS PERICD I41A

~~

THIS MONiH YEAR-TO-DATE cut!LATIVE

5. FEACTOR (RITICAL IInt (HOURS) 744.0 744.0 48,100.5 6-. REAC10E ESERLE SHUTIru ilhE (HOURS) 0.0 0.0 1,641.2
7. EaE' '0? ON-LINE T!nE (HOURS) 744,0 744.0 47,122.4
8. UNIT RESERVE 5HUTIOWN TINE (kSURS) 0.0 0.0 1.0
9. THEMAL ENERBY GENERATED (huHt) 2,409,175 2,409,175 137,566,154
10. ELECTRICAL ENER5Y SENERATED (MWHeBross) 825,074 8:5,674 45,914,846
11. ELECTPICAL ENERGY COERATED (NHe-Net) - ',S30 800,830 43,975,975
12. REACICR SER'ilCE FACTOR (%) 100.0 160.0 67.8
13. REACTOR AVAILABillTY F ACTOR (%) If;0.0 103.0 70.2
14. l' NIT SERVICE FACIDR (%) 103.0 100.0 66 3
15. UNIT AVAILIEILITY FACTOR (%) 100.0 100.0 66.5
16. UNIT CAPACITY FACT 0li (LSING elC) (%) 103.9 103.9 59.9
17. UNIT CAPACITY FACTOR (USING IES15N Ne) (%) 99.9 97.9 57J
18. UNii FORCED DUTA3E F AEIGR (%) 0.0 0.6 7.5

!?. SHUTiULNS SCHEDULED 0"EE THE NEXT 6 hDNTHS (!(PE, IATE AG ItMATILN UF EACHH

20. IF SHUTIOWN AT END OF REPORT PERIOD, E5TIMATED IwiE OF STARTUP:

10CKET NO. 0 9-373 1ABLE 3 UNIT LA%LLE ANE E.2 AVf MGE IAILY UNIT POWEP LEVEL (Ne-Net) EATE february 10, 1992 COMETED EY M.J. CIAlkDGI TELETRWE (E!D-r?-6761 EFCPT *EF10D; J ouary 1992 F0di

-]

I.AY POWEk IAY i 1,029 17 1,037 2 1,006 18 1,103 3 1,023 19 1,106 4 1,096 20 1,102 5 1,090 21 1.078 6 1,097 22 1,110 7 1,088 23 1,108 6 1,0?? 24 1,0N 9 1,098 25 1,116 16 1,079 26 1,103 11 1,102 27 1,079 12 1,097 28 1,029 13 1 055 2 27 1,037 14 1,052 20 1,099 15 957 31 1,041 16 1,NS 1

1

~

TABLE 4 E.3 UNIT SHUTDONNS AND POWER REDUCTIONS > 207. .

' (Unit 1) 1 I

METHOD OF CORRECTIVE SHUTT'% DONN -ACTIONS /COMENTS YEARLY TYPE F: FORCED DURATION THE REACTOR OR (LER/DVR # if SEQUENTIAL DATE applicable)

(HOURS) REASON REDUCING PONER

j. NUMBER (YYmDO) S:' SCHEDULED (None.)

L SUMARY OF OPERATION:

The Unit. remained on-line at high powe'r throughout the month. Several minor power reductions were required due to system

. Ioadng, maintenance activtties and routine survelliances.

ZCADTS/5

F. UNIQUE REPORTING REQUIREMENTS (Unit 1)

1. Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIPTION DALE &CTUATED ACRJATIO3 CONDITION Of EVENT (None)
2. ECCS System Outages (See Table 5)
3. Changes to the Off-Site Dose Calculation Manual (None.)
4. Major changes to Radioactive Haste Treatment Systems.

(None.)

5. Indications of Failed Fuel Elements.

(None.)

W h

5 b

ZCADTS/5 l

(Unit 1)

Table 5 F.2 ECCS System Outages Note: The year and unit data has been removed from the outage number.

QUJAGL_(L E00lPHENT PURPOSE (U-0) 0013 ODG01K Replace cooling water pump.

0026 00G08CA Starting air compressor inspection.

0027 ODG08CB Starting air compressor inspection.

(U-1) 0022 1E51-C003 Replace water leg pump.

0033 1E51-C001 Lubrication.

0038 lE51-F019 Hotor inspection.

0047 IE22-C302B Perform inspection, a

O' a2 1DG08CA Starting air compressor inspection.

0053 ZCADTS/5+

. I t

LASALLE NUCLEAR POWER STATION .,,

UNIT 2 HONTHLY PERFORMANCE REPORT JANUARY 1992 COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE N0. NPF-18 ZCADTS/7 1

TABLE OF CONTENTS (Unit 2)

1. INTRODUCTION II. REPORT A. SUHKARY OF OPERATING EXPERIENCE B. AMENDHENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. HA30R CORRECTIVE HAINTENANCE TO SAFETY-RELATED EQU1PHENT D. LICENSEE EVENT REPORTS E. DATA TABULATIONS
1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions F. UNIQUE REPORTING REQUIREHENTS

.. Safety / Relief Valve Operations

2. ECCS System Outages
3. Off-Site Dose Calculation Manual Changes
4. Major Changes to Radioactive Harte Treatment System.
5. Indications of Failed Fuel Elements ZCADTS/7

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 Boiling Hater Reactor with a designed net electrical output of 1078 Hegawatts. Haste 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 Commohwealth 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 power operation was commenced on June 19, 1984.

This report was compiled by Michael J. Cialkowski, telephone number (815)357-6761 extension 2427.

ZCADTS/7

II. MONTHLY REPORT A' . StH4ARY OF OPERATING EXPERIENCE (Unit 2)

Day LLeg Event 1 0000 Reactor critical, Generator on-line Lt 995 Mwe Unit in coastdown.

2 1900 Power level at 980 Mwe, continuing coastdown.

3 1330 Power level at 850 Mwe, control rods being inserted per rod sequence.

1420 Power level' at 683 Mwe.

1700 Power level at=535 Mwe.

1800 Power level at 295 Mwe.

2100 Power level at 116 Mwe.

4 0000 Power level at 63 Mwe, control rod insertions held.-

0105 Reduced power level to 10 Mwe via load set.

0155 Generator offline, refueling outage (L2R04) began.'

1200 Reactor subtritical.

31 2400 . Reactor.subcritical, , Generator off line, L2R04 in progress.

1 ZCADTS/7

B. AMENDHENTS TO THE FACILITY LICENSE OR TECilHICAL SPECIFICATION (None.)

C. HAJOR CORRECTIVE MAINTENANCE TO SAFETY RELATED EQUIPHENT (including

  • SOR differential pressure switch failure reports).

(See Table 1)

D. 1ICENSEE EVENT REPORTS (Unit 2)

.LER Number Djtta DisIrlp_t.iQn 92-001-00 01/17/92 Inadvertant occurrence of a Primary Cor.tainment Group II isolation during performance of Reactor Vessel Low Hater Level 1 & 2 Isolation Channels B & D Refuel Calibration surveillance. >

E. DATA TABULATIONS (Unit 2)

1. Operating Data Report.

(See Table 2)

. 2. Average Daily Unit Power Lavel.

-;. (See Table 3) 6 i 3. linit Shutdowns and Significant Power Reductions.

(See Table 4) e

'J

)

ZCADTS/7 ,

1ABLE 2 E.1 GPERATING IATA EEPCRT N G ET ND. 05b 374 UNIT LAEALLE ILO I4TE f abruary 10,1992 CChFLEIED 11 n J. CIALK0WD]

TELEPHONE (E15) 357-6761 GPERATING ETAiUS

1. REFORTING FERIOD: January 1972 EROS 5 HOURS lh FEP0FilNii PEFIDD: 744 7 EUFRENTLT AUiHORIZED POWER LEVil (M;th 3,323 W 11EPEND CAPACITY (Ne-Ntth 1,036 EE515n ELECTRIC AL RAl!NS (hWe-Nct): 1J78 3, FMF LEVEL 10 WHICH PESTRICTED (If ANY) (Ne45 t h N/A
4. PEASONS FOR RE51kICTION (if AN1h REF0ETING FER10D TA1A Th15 h0 NTH TEAE-TO-IATE CUCLATIVE O REACTOR CRITICAL Tine (HOURS) B4.0 84.0 45,019.8
6. REACIOR RESERVE SHUTICLN 11hE (H093) 0.0 0.0 1,716.9

/. otNERATOR 04-LINE ilhE (HOURS) 73.9 73.9 4 4,2'/ b . 5 ,

6 UNil RESERVE SHUIDO W TIhE (H30PS) 0.0 0.0 0.0

9. THEihAt ECUY BEKRATED (NHt) 150,906 180,936 132,423,385
10. ELECTRICAL ENER5Y 6?ERATED (t%miros0 64,274 64,274 43,754,024 11 ELECTRICAL ENER3Y COEEATED (HWHe-Net) 54,161 54,161 42,105,665
12. REAC10d SEGVlt:.: FACTOR (t) 11.3 11,3 70.5
13. REAC10R NAILAD:llTY FACTOR (1) 11.3 11.3 73.2
14. tJNIT bERVICE FACTOR t%) 9.9 9.9 69.3
15. UNIT AVAILIEllliY FAC10R (1) 9.9 9.9 69,3 16 UNIT CAFACITY FACTOR (USINS tiEC) (%) 7.0 7.0 63.7
17. UNIT CAFACITY f ACTOR (USIN3 IESIGN Ne) (1) 6.8 6.8 61.3 18, ilhli CCRCED 09TA5E FACTOR (1) 0.0 0.0 13.1

. . . . . . . . . ~ . . . - -__.... -

17. StiUi10WN3 SCHEDULED DVER THE 1016 FCrdih5 (iYPE, DATE, AND TURATION OF EACH):

GEFUELIN3 (L2R04) 01/04/92 11 UEEK5

20. If SWIDOWN AT END OF REPORT FERIOD, ESTIhATED I! ATE Of STARfUP:

IOCFET NO. 050-??4 1AILE 3 0811 LASALLE TWO E.2 NEFAEE IeILY tw1T F3LER LEVEL owe-Neu I41E february 10,1972 COMPLETED PT n.J. LI Alr%Y1

!ELEf K*E (E!! h 257-Dil IEFORI PElilED: J avary 1992 Ist POWER IM POWER 1 961 17 -12 2 53 10 -12 3 653 19 -12 4 -5 20 -11 5 -12 21 -11 4 -12 22 -11 7 -11 23 -11 8 -11 24 -11 9 -11 25 -11 10 -11 ;6 -11 11 -11 27 -11 12 -11 28 11 13 -11 29 -11 14 -12 39 -11 15 -12 31 -11 16 -12

/

C. TABLE 1 (Unit 2)

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT RESULTS AND EFFECTS HORK REQUEST CORRECTIVE ACTION COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION NUMBER ___

Voltmeter found defective Inaccurate voltage readings. Replaced voltmeter.

L12684 Livision I 125 Volt Battery Volt Meter during surveillance.

2EI-DC057 Test switch contrci. None. Replaced test switch L12952 Unit 2 'O' Diesel control.

Generator Output Breaker ACB 2413 (No SOR Failures this month.)

i ZCADTS/7

_J

.i TABLE 4

~

E.3- UNIT SHUTDONNS AND POWER REDUCTIONS 220%

(UNIT 2) .

METHOD OF CORRECTIVE SHUTTING DONN ACTIONS / cop 04ENTS YEARLY TYPE SEQUENTIAL DATE F: FORCED DURATION THE REACTOR O2 (LER/IsVR # If (YYMMDD) S: SCHEDULED (HOURS)_ REASON REDUCING PONER Poolicable)

JtUMBER 01 920104- S 670.1 C 1 Refueling outage L2R04.

I l

SUMMARY

OF OPERATION:'-

L .

'The unit entered the' month.in coastdOwn in preparat10n fOr the upcoming' refuel Outage. The generator was .taken Off line -

i

! 01/04/92 and the unit entered a' scheduled refuel' Outage.

l I #

ZCADTS/7 c _

r.. . UNIQUE REPORTING REQUIREMENTS (Unit 2)

1. Safety / Relief Valve Operations VALVES NO & TYPE PLANT DESCRIPT10ti DAIE ACTUATED ACTUATIONS CQMDJ.ILQN OF EVENT (None.)
2. ECCS System Outages (See Table 5.)
3. Changes to the Off-Site Dose Calculation Manual.

(None.)

4. Major changes to Radioactive Haste Treatment Systems.

(None.)

5. Indications of Failed fuel Elements.

(None.)

a s

ZCADTS/7

(Unit 2)

Table 5 F.2 ECCS System Outages Note: The year and unit data has been removed from the outage number.

OUTAGE NO. E0UIPMENT PURPOSE 223 2E21-C001 Perform inspection.

244 2E22-F012 Perform votes testing.

245 2E22-F023 Perform inspection.

246 2F22-F015 Perform votes testing.

249 2E22-F004 Perform votes testing.

553 2E22-S001 Replace battery charger.

554 856 2E12-F042A Repair valve motor.

ZCADTS/7

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