ML20044B322

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Monthly Operating Repts for June 1990 for LaSalle County Nuclear Power Station,Units 1 & 2.W/900710 Ltr
ML20044B322
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 06/30/1990
From: Diederich G, Thunstedt J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9007180341
Download: ML20044B322 (25)
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  • Commonweahh Edison 3
  • . LaSalle County Nuclear Statiort Rural Route #1, Box 220 Marseilles,lillnois 61341 Telephone 815/357-6761 July 10, 1990 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C. 2'J555 ATTN Document Control Desk Gentlement Enclosed for your information is the monthly performance report c.aring LaSalle County Nuclear Power Station for June,1990.

i Very truly yours, kO gG. J. Diederich Station Manager LaSalle County Station n

GJD/JWT/jdp 97 Enclosure xes A. B. Davis, NRC, Region III NRC Resident Inspector LaSalle

-Ill. Dept. of Nuclear Safety R. Pulsifer, NRR Project Manager l b. 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 W. F. Naughton, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle Terry Novotney, INPO Coordinator, LaSalle Station i .T. A..Hammerich, Regulatory Assurance Supervisor J. W. Gieseker, Technical Staff Supervisor Central File I

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LASALLE NUCLEAR POWER STATION UNIT 1 MONTilLY PERFORMANCE REPORT JUNE 1990 COMMONWEALTil EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF ZCADTS/S

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TABLE OF CONTENTS l (UNIT 1) ,

r I. INTRODUCTION ,

l i

II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE i B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED NAINTENANCE r

1. Amendments to racility License or Technical Specifications  !

Changes to procedures which are described in the Safety 2.

Analysis Report [

3. Tests and Experiments not covered in the Safety Analysis Report '
4. Corrective Maintenance of Safety-Related Equipment
5. Completed Safety-Related Modifications '

C. LICENSEE EVENT REPORTS D. DATA TABULATIONS 1.- Operating Data Report

2. Average Daily Unit Power Level ,
3. Unit Shutdowns and Power Reductions i 1

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 Maste Treatment System ,
5. Indications of railed ruel Elements ,

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f 1. INTRODUCTION (Unit 1) {

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 not electrical output of  ;

1078 Megawatts. Waste heat is rejected to a man-made cooling pond using j 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 Ilcense number NPF-11 on April 17, 1982.- l Initial criticality was achieved on June 21, 1982 and commercial power l operation was' commenced on January 1, 1984. t This' report was complied by John W. Thunstedt, telephone number (815)357-6761, extension 2463. 'I i

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11. MON 7HLY REPORT A.

SUMMARY

OP OPERATING EXPERIENCE (Unit 1)

Day Tima gyar t _

1 0000 Reactor critical, generator on-line at 3110 MWT.  ;

5 0030 Reduced load to 3120 MWT for CRD exercising.

1000 Returned to full power.

12 0300 Reduced load to 3150 MWT for CRD exercising.

1000 Returned to full power, 19 0100 Reduced load to 2850 MWT for CRD exercising. '

1000 Returned to full power. ,

24 0000 Reduced load to 2915 MWT for System load.

25 1300 Returned to full power.

26 0500 Reactor trip, generator trip, during Turbine Control Valve testing.

30 2242 Reactor critical.

2400 Reactor critical, generator off-line, Unit startup in progress.

l-l 2CADTS/5

B. PLANT OR PROCEDURE CHANGESo TESTS, EXPERIMENTS AND SAFETY RELATED i MAINTENANCE.(Unit 1)  !

(

1. Amendments to the Facility License or Technical Specification.  !

(None)

^

2. Changes to procedures which are described in the Safety Analysis Report.
a. LaSalle Out-of-Service 60 *S-88 for the Control Room HVAC i System (VC), closed the Domestic Water System (WD) supply to the VC boilers to ensure that the malfunctioning boiler feedwater level controls will not result in the  ;

humidifiers dumping water instead of steam into the VC supply ductwork. The humidifiers, which are supplied with steam by the OVCO2SA/B, are non-safety related with seismic support per UFSAR 9.4.1.1.3.a. The operability of the Control Room HVAC system is unaffected by the boilers.

b. LaSalle Special Test, LST-90-079 " Evaluation of Control .i Room Pressurization." The purpose of this test is to .!

evaluate the ability of the VC system to pressurise the ,

Control Room with the Turbine Buildjug HVAC System (VT) in the normal line-up by adjusting balancing dampers.  !

c. LaSalle Temporary System Change 42-710-90 increased the portion of the Emergency Makeup Flow to the Control Room from 1500 cfm to 2650 cfm and decreased the flow to the Aux. Equipment Electric Room from 2500 cfm to 1350 cfm to provide additional airflow to the Control Room for pressurization (see LST-90-079). The maximum temperature will be less than the limit of 104'r per Tech Spec 4.7.7. P
3. Tests and Experiments not cescribed in the Safety Analysis Report.

(None)  ;

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4. Major corrective maintenance to Safety-Related Equipment, including any SOR switch failure reports.

(See Table 1)

5. Completed Safety-Related Modifications.

(See Table 2)

C. LICENSEE EVENT REPORTS (Unit 1) '

LER Humber Data Dager1ption 90-007-00 6/18/90 RCIC Trip on Mechanical Overspeed

, 90-010-00 6/26/90 Reactor Scram During MTSV Surv Testing ,

1 1.

q D. DATA TABULATIONS (Unit 1)  ;

1

1. Operating Data Report (See Table 3)
2. Average Daily Unit Power Level (See Table 4)
3. Unit Shutdowns und Significant Power Reductions (See Table 5)

ZCADTS/5

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a D.4 (TABLE I (Unit 1) ... .g.

' MAJOR CORRECTIVE MAINTENANCE TO ..-

SAFETY-RELATED EQUIP 9ENI .

NORK REQUEST RESULTS AND EFFECTS NUMBER.- COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION

' LOO 513 RCIC Turbine Rust particles Turbine tripped on Cleased governor oil in governor oil system overspeed during startup. .systeem.

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ZCADTS/S

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B.5 TABLE 2 (Unit 1)

COMPLETED SAFETY-RELATED MODIFICATI0HS HUMBER DESCRIPl]ON M01-1-86-0290 Reconfigure portions of the Unit 1 Division 1 and 2 instrume.A sensing lines such that the proper direction and degree of slope is provided to allow drainage of condensation. The proper sloping will be directed from the condensate pots towards the suppression pool penetration and at a minimum slope of one-half-inch per foot.

ECADTS/5

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ItM 3 D.1 DiUA114 MTA PUmi IOCKET NO. 050-371 lHli LASALLI Ott M TE July 10,1990 00ftITED l'Y J.W. TifJGTE01 TELD40E (015)-357-6761 OftRAllE STAitG

t. RFJtRilE FtRIOD: JJE 1999 GROSS KARS IN RUST 1% ftRIOD: 720
2. CtRRENTLY AUTIKRIZED POWER LEVEL (MWtb 3,323 hAX t(ftND CitACITY (He-Het): -1,036 t(SIGN ELECTRICAL RAT 14 (Mide-Het) (,078
3. IMR LEVEL 10 kHICH l'ESTRICTED (IF ANY) (MWe-Net): (N(me)
4. REASONS FOR RESTRICTION (If ANY): (N/A)

RD%il$ ITRIOD DATA THIS MONTH YEAR-10-MTE CLPiuLAi!VE

. _ - L. _ _ . - .

5. TIME REACTOR CRITICAL DRI@ 606.3 4,050.3 36,192.4
6. Tite REACTOR RESERVE GUllGM ORRS) 0.0 0.0 t,641.2
7. T!HE GDERATl* OH Lite 00VRS) 605.0 3,930.1 35,349.4
0. TIME LDDA10R REDERVE SfJllON (H0lRS) 0.0 0.0 1.0
9. TERMAL ENERGY GDGATED (M.Mt-Cross) t 991,472 12,501,609.4 100,335,177
10. ELECTRICAL ENERGY GENLRATED ( M ie-Gross) 673,298 4,270,277 33,339,018 it. ELECTRICAL DERGY GENEPATED (Miediet) 649,950 4,132,374 31,065,076
12. REACTOR SERVICE FACTOR (%) B4.2 93.4 63.5
13. REACTOR AVAILA1:lLITY FACTOR (%) B4.2 93.4 66.4
14. SERVICE FACTOR (1) 84.0 90.5 62.0
15. AVAILI!41LITY FACTOR (%) B4.0 90.5 62.0

'16. Ct(ACITY FACTOR (121% MDC) (%) 87.0 91.0 54.0

17. CAPACITY FACTOR (USING DESIGN MWe) (%) 83.6 00.3 51.9
18. FORCED OUTAGE FACTOR (%) 16.0 5.9 9.7
19. QUID 0l#E SCHEDULED DVER THE NEXT 6 MONTtG (TYFT, MTE. AND ItRATION OF EACH):

None

20. IF 9U11GN AT END OF REPORI PERIOD, ESilt)ATED MTE OF STARTtlP:

July 1, 1990

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i IG I O NO. 0 %-373 it,itt 4 lHli LKALLE ONE D.2 AVDK,E MILY LHli IMF, LEVEL (Ne-Net) MTE July 10,1990 00ftETED DY J.W. TUG 1E.D1 TELEFtDE (015F357-6761 REFORT FtKIOD; J kE 1990 MY FMR MY IMR i 1,096 17 i.h9 2 1,098 10 1,059 3 i,098 19 i.033 4 i,099 20 1.064 5 1,006 21 1,067 6 i,097 22 i,066 7 i.092 2 1,069 0 1,097 24 1,021 9 1,074 25 1,067 10 1,000 26 160 11 1,082 27 -12 12 1.071 28 -12 13 1,004 29 -12 14 1,001 30 -12 15 1,072 31 16 1,069

6

.- r TABLE 5 9

D.3 UNIT SHUTDONNS AND POWER REDUCTIOitS > 20C .

(Unit.1)

METHOD OF TEARLY TYPE SEUTTING DONN SEQUENTIAL F: FORCED DURATIN THE REACT 0tt OR CORRECTIVE NUMBER DATE S: SrWKT1ULED (BOURS) REASON REFJCING POWER ACTIONS /C0ge efts 16 6-26 F 115.0 A 3 LIF11, Turbine Stop i

valve-limit-switch failure, condenser tube P l #99 189-d I

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-e E. UNIQUE REPORTING REQUIREMENTS (Unit 1) i 1. Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIPTION DATE ACIVATED AC211ATL0ti CONDITI(Ri OF EVENT (None)

2. ECCS System Outages (See Table 6)
3. Changes to the Off-Site Dose Calculation Manual (None).
4. Major changes to Radioactive Waste Treatment Systems.

(None)

5. Indications of railed ruel Elements.

(None)

ZCADTS/5

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(Unit 1)

TLblo 6 ECCS System Outages Note: The year and unit data has been removed from the outage number.

DUIAGE NQ EQU1EMMI LTREQSE (U-0) 190 TSC D/G Replace battery Battery Charger (U-1) 270 IB D/G Calibrate 1PS-1E22-N508 271 RCIC Install motor brushes 272 RCIC Lubricate 273 RCIC Lubricate 285 1B D/G Calibrate crank-case pressure switch ZCADTS/5

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l LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERTORMANCE REPORT JUNE, 1990 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPP-18 ZCADTS/7 me. .. . . . . . _ . . . . . . , . . . . . . . . . . .. . . . . . . . _ . , . . . . . . . , .. . . . , .. . . . , . . ,

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TABLE OF CONTENTS (Unit 2)

I. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE B. PLNRT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SATETY RELATED MAINTENANCE

1. Amendments to facility License or Technical Specifications
2. Changes to procedures which are described in the Safety Analysis Report.
3. Tests and Experiments not covered in the Safety Analysis Report.
4. Corrective Maintenance of Safety-Related Equipment
5. Completed Safety Related Modifications 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. Safety / Relief Valve Operations
2. ECCS System Outages
3. Off-Site Dose Calculation Manual Changes
4. Major Changes to Radioactive Waste Treatment System
5. Indications of railed fuel Elements ZCADTS/7

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1. INTRODUCTION (Unit 2)

The LaSalle County Nuclear Power r;tation is a two-unit f acility owned by Commonwealth Edison Company and located near Marselliss, Illinois. Each unit is a Boiling Water Reector with a designed not eittetrical output of 1078 Megawatts. Waste beat is rejected to a man-made ling pond using the Illinois River for reake-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company.

Unit Two was issued operating license number NPT-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 John W. Thunstedt, telephone number (815)357-6761 extension 2463.

ZCADTS/7

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II. NGfTHLY itEPORT A. SUMHARY OP OPERATING EXPERIENCE (Unit 2)

Eny. Ilmt Event 1 0000 Reactor subcritical, generator off-line, refueling outage in progress.

9 1440 Reactor critical.

12 1445 Generator on-line at 100 MWE, L2R03 ends.

1615 Generator trip due to high MSR level (no Reactor trip due to low-power level) 2155 Generator on-line at 200 MWE.

15 1620 Turbine-Generator trip for over-speed testing.

16 0400 Generator on-line.

17 1000 Generator at 820 MWE.

19 0145 Reduced load to 655 MWE for rod-set.

1000 Increased power to 960 MWE.

21 2400 Reduced power to 200 MWE in preparation for Unit shutdown to repair hydraulic leak on "B" Reactor Recic flow control valve.

23 1725 Generator trip.

2340 Reactor subcritical (manual shutdown).

25 1959 Reactor critical.

26 1653 Generator on-line.

27 2015 Generator at 900 MWE.

29 0130 Reduced load to 580 MWE for rod-set.

0800 Increased power to 1000 MWE.

30 2400 Reactor critical, generator on-line at 985 MWE.

ZCADTS/7

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  • B. PLANT OR PROCEDURE CHAN ES, TESTS, EXPERIMENTS AND SATETY RELATED MAINTEN ANCE. (Unit 2)
1. Amendments to the racility License or Technical Specification.

_(None)

2. Changes to procedures which are described in the Safety Analysis Report.

(None)

3. Tests and Experiments not described in the Safety Analysis Report.

(None)

4. Major corrective maintenance to Safety-Related Equipment, including any SOR switch failures.

(See Table 1)

5. Completed Safety-Related Modifications.

(See Table 2)

C. LICENSEE EVEN" REPORTS (Unit 2)

LELLHumbtI Ditte Desctlp.tlon ,,,,,

(None)

D. DATA TABULATIONS (Unit 2)

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)

ZCADTS/7

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D.4- TABLE 1 (U?lt 2) .

_.. o-MAJOR CORRECTIVE MAINTENANCE "IO ,

SAFETT-RELATED EQUIPMENT .

.180RK ' REQUEST RESULTS AND EFFECTS NUMBERL ~ COMPONENT CAUSE Or 67 ION - :05 SAFE ~ PLANT OPERATION CORRECTIVE ACTION i.89347 2A RR Pusep. Excessive Wear- 52 Seal Pressure high -Replaced seal Seal #2 L99119 "A" SRV Vibration Loose hold-down stud Replaced and repinned stud, added Jockwire.

i (No SOR failures)

ZCADTS/7

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', e .. . B.5 TABLE 2 (U lt 2)

COMPLETED SATETY-RELATED MODITICATIONS liUMBER DEECRIEILON MC1-2-90-004 Install live-loading packing for valve 2E51-T006. This is a Minor Change safety related/ASME Section III Class 1 component. This will '

reduce the leakage problems associated with the valve.

M01-2-87-013 Install a new " Local-Remote" Transfer Switch and a new set of control circuit fuses to existing Generator and Engine control Panel 2DG02JB.

M01-2-87-029 Perform Human Tactors on the annunciator for the scram air header pressure alarms in the control room to assist the operator to determine whether the pressure is high or low without dispatching someone to the local station.

M01-2-87-030 Perform Human factors to reroute the present location of the .

control room Breathing Air Lines which have created a tripping har.ard for control room personnel.

M01-2-87-085 Replace the ECCS and RCIC reactor water level switches with an analog trip system consisting of Rosemount level transmitters for Division I, II, and III.

M01-2-88-013 Perform Human Tactors to correct panel mimic arrangement for the off gas system holdup line drain valves. Currently, it shows them in series, when they are actually in parallel. '

M01-2-89-006 Provide wiring installation for the Remote Recirculation Pump l

Vibration Monitoring Instrumentation Cables and will add the capability for continuous monitoring of the pumps..

I i

ZCADTS/7

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' t UNIT LASALLE TWO

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Y COMPLETED BY J.W.THUNSTEDT- -

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3 D IWil/ EEPORTING KRIOD; iJUE 1990 - ' GROSS H0lRS IN REPORTING PERIOD: < ' 720 ; "'

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MD3MPOER f yh LEVEL-TO WICH RESTRICTED..(If ANYL (MWe-Net):.~ (None)

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352.5: 2,101.2. 31,'784.3 -

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713,256- ,6,300,223.2; 92,620,271.2 er g Jm9.Va.- TERMAL ENER.GY GENERATED (MWHt-Gross).

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TABLE 5 '- . .

D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS >20% ,.

(UNIT 2)

METsoD Or TEARLY TYPE SHUTTING DOWN SEQUENTIAL F: FORCED DURATION THE REACTOR OR CORRECTIVE NUMBER DATE 3. SCHEDULED (HOURS) REASON CODE REDUCING POWER ACTIONS / COMMENTS 6 3-17-90 S 278.8 C 4 L2R03 7 6-12-90 F .5.7 A 6 L2F07, high MSR level.

(Reactor did not trip due to low power level)".

G 6-15-90 S 11.7 B 6 L2M05, overspeed testing.

(Reactor did not:. trip due to low power level) 9 6-23-90 F 71.5. A 1 L2F08, hydraulic oil-~

. leak on "B" Reactor Recirc flow control valve.

ZCADTS/7

- _ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ____ _ _ _ _ _ _ _ __ _. - __ - - - ~ . . . - . . ~ . . . -.

a, m

.. - d: :( i

.,, 'E... UNIQUE REPORTING REQUIREMENTS (Unit 2) i

.; . _; - .o; * ..

1. Safety / Relief Valve Operations VALVES NO & TYPE PLANT' DESCRIPTION, DATE. ACTUATID ACTUAT10 tis CCtiDIT10ti 0LJYIKI___.

(None) 2;. ECCS. System Outages l' (See Table 6)

3. Changes to the Off-Site Dose Calculation Manual.

(None).'

4. Major changes to Radioactive Waste Treatment Systems. -

(None)

5. Indications of railed Fuel Elements. '

(None) l-r k

s B

~

g i

.* Il 2 S '.

\\1 t i, .

1 ZCADTS/7 3 .

$t;'

i ,

^,

  • ~

.. t- (Unit ~ 2 )-

h!.! ' , ; C , -

iTablo 6-

.ECCS System' Outages Note: The year.and unit data has'been removed from the outage ' number.

DUIAGE_NA EQUIPMENT PURPOSE 1485 RCIC Repair Valve 2E51-F076 1

[

I 1

')

i t

.1

)

.t

.E ~

ZCADTS/7 1

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