ML20104B104

Monthly Operating Rept for Aug 1992 for Lasalle Nuclear Power Units 1 & 2

ML20104B104
Person / Time
Site:	LaSalle
Issue date:	08/31/1992
From:	Cialkowski M, Diederich G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9209140349
Download: ML20104B104 (26)

Text

C:mm nw;alth Edis n LaSalle County Nuclear Station 2601 N. 21st. Rd.

Marseilles, lilinois 61341 Telephone 815/357-6761 September 9, 1992 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Comission Mail Station P1-137 Hashington, D.C.

20555 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for August 1992.

Very truly yours, O

G. J. Diederich f)fStationManager LaSalle County Station GJD/HJC/dj f Enclosure xt:

A. B. Davis, NRC, Region III D. E. Hills, NRC Resident Inspector LaSalle J. L. Roman, IL Dept. of Nuclear Safety B. Siegel, NRR Project Manager D. P. Galle, CECO D. L. Farrar, CECO INP0 Records Center D. R. Eggett, NED P. D. Doverspike, GE. Resident T. J. Kovach, Hansger of Nuclear Licensing T. A. Rieck, Nuclear Fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor H. P. Pietryga, 0A/NS Off Site Review Station File I

92o9140349 920031 fv

^== oso a v

zCAD1S,5 goa

LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT AUGUST 1992-COMMONHEALTH EDISON COMPANY-NRC DOCKET-NO, 050-373 LICENSE NO. NPF-il J

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TABLE OF CONTENTS (UNIT 1)

I.

INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE B.

AMENDHENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C.

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPHENT D.

LICENSEE EVENT REPORTS E.

DATA TABULATIONS 1.

Operating Data Repert 2.

Average Daily Unit Power Level i

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.

Iidications of Failed Fuel Elements i.

L ZCADTS/5 l

1 I.

INTRODUCTION (Unit 1)

The LaSalle County Nuclear P'wer Station is a two-unit facility owned by Commonwealth Edison Company rd located near Marseilles, Illinois.

Each unit is a Boiling Hater Reactor with a designed net electrical output of 1078 Hegawatts.

Haste hwat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown.

The architect-engineer was Sargent and Lurdy and the primary construction contractor was Commorsealth Edison Company.

Unit One was issued operating license number NPF-il on April 17, 1982.

Initial criticall'y was achieved on June 21, 1982 and commercial power operation was commenced on January 1, 1984.

This report was compiled by Michael J.

Cialkowski, telephone number (815)357-6761, extension 2427.

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4

'. II. MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 1) f pm Time:

Ev_ent l

1 0000 Reactor critical, Generator on-line at 780 Mwe due to system load (Unit in coastdown).

1100 Increased power level to 1015 Hwe.

l 2000 Reduced power level to 780 Hwe due to system load.

2 1000 Increased power level to 1010 Mwe.

1 3

0200 Reduced ~ power level to 950 Mwe due to system load.

0600 Increased power level to 1010 Hwe.

l.

4 0000 Reduced power level to 740 Hwe due to system load.

~

1000' Increased power -level-to 1005 Mwe.

l-5 0130 Reduced power level to=740 Hwe due to-system load.

-0900 Increased power level to-1005 Mwe.

6 0200 Reduced power level to 740 Mwe due to system load.

l 0800 Increased power level to 1000 Hwe, 8

0000 Reduced power level - to -835.Mwe

.a'to system load, t

0900 Increased power level.to 920 Mwe.

l 2330 Reduced power level to 850 Mwe due -to' system'1 cad.

9 0930 Increased _ power level-to 980 Mwe..

l 2330 Reduced power level to 840 Mwe-due to system load.

11' 1000 Increased power 1ovel to 980 Mwe.

1930 Reduced power level.to 900 Mwe-due F stem load.

2300 Re'duced power level to 840 Mwe due to-system load.--

12 0730-Increased' power level to 980 Mwe.

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

13 0800--

Increased power. level to 975 Mwe; 14 2300 Reduced power level to 850 Mwe due to system load.

15 0700 Increased power level to 975 Hwe.

[

ZCADTS/S

,II. MONTHLY REPORT (CONTINUED)'

A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 1)

Dgy Ilm_1 Event 1900 Reduced power level to 880 Hwe'due to system load.

16 0000 Reduced power level to_850 Hwe due to system loads 0400 Reduced power level to 750 Hwe due to system load.

1000 Increased power level to 975 Hwe.

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

17 0700 Increased power level to 960 Hwa.

18-0100 Reduced power level to 850 Hwe due.to system load.

l 0900 Increased power-level to 950 Hwe.

I 19 2300 Reduced power level to 850 Hwe due to system. load.

20 0900 Increased power level to 950 Hwe.

1930 Reduced power level to 850 Hwe due to system load.

21 0800 Increased power level. to 945 Hwe, i

2330 Reduce 6 power level.to-850 Hwe due to system load.

23 0200 Reduced power level to 700 Hwe'due to system load.

1400 Increased. power level to 940 Hwe, 24 0030 Reduced power level to 800 Hwe.due to system load.

1000 Increased power level to 930 Hwe.

I 26 0230 Reduced power level to 740 Hwe due_ to system load.

a

1000 Increased power level to'930 Hwe.

2330

_ Reduced power level to 740 Hwe.due-to' system load.

i 27 1000

. Increased power-level to 930 Hwe.

28 0100:

Reduced-power level to 700 Hwe-due to system load.

-0800-Increased power level to 930:Hwe.

e

'1 l

29 0200

- Reduced power' level _ to 750 Hwe due to system load.

j 1

1000:

Increased power-level to 930 Hwe.

j

-~

l i

.i ZCADTS/5 2

1 II. HONTHLY REPORT (CGNTINUED)

A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 1)

D33 Time Event 30 0030 Reduced power level to 740 Hwe due to system load.

1200 Increased power level to 930 Hwe.

31 0100 Reduced power level to 800 Mwe due to system load.

0700 Increased power level to 930 Hwe.

2300 Reduced power level to 740 Hwe due to system load.

2400 Reactor critical, Generator on-line at 740 Hwe, continuing coastdown, t

ZCADTS/5 l

_J

I B.

AMENDMENTS TO THE FACILITY LICENSE OR TECHNICAL SPECIFICATION Revised reference from General Electric performing core operating limits analysis to Commonwealth Edison and General Llectric.

C.

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

(See Table 1)

D.

LICENSEE EVENT REPORTS (Unit 1)

(None.)

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)

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~

ari.

+

C.

TABLE 1 (Unit 1) i MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT-

-WORK REQUEST RESULTS AND EFFECTS NUMBER

. COMP 0"5NT.

CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION 1

Ll6302'

. Division II Post-LOCA Bottle regulator leakir.g.

None.

Replaced regulator.

' Containment Monitoring.

Reagent Gas Bottie-ICM12T Ll6591 Main' Control Room Alarm lamp.

Spurious alarms.

Replaced bulb..

Ammonia Detector O'(Y-VC1258

.L17068

. Local Power Range' LPRM card.

Inaccurate indication.

Replaced' diode on LPRM l

Monitor 24-25B card.

L17128-'

Standby Gas Treatment Chart drive motor.

Chart paper not advancing Replaced chart drive motor.

1 Hide Range Noble Gas properly.

Monitor Recorder-0018-R519

.(No SOR Failures this month.)'

i ZCADTS/5r n.

TABLE 2 E.1 OPERATIhG-DATA REPORT DOCEET NO. 050 373 UNIT LASALLE ONE DATE September 10, _1992-COMPLETED-BY M.J,CIALKOWSKI OPERATING STATUS TELEPHONE (815) 357-6761 1.

REPORTING PERIOD:

August 1992

~

";ROSS HOURS IN REPORTING PERIOD:

744 2.

CURRENTLY AUTHORIZED POWER LEVEL (MWt):

3,323 MAX DEPENDABLE CAPACITY (MWe-Net):

1,036 DESIGH ELECTRICAL RATING (MWe-Net):

1,078 3.

POWER LEVEL TO WHICH RESTRICTED (Ir ANY) (MWe-Net):

N/A-4.

REASON FOR RESTRICTION (IP ANY):

THis MONTH YEAR TO DATE CUMULATIVE 5.

REACTOR CRITICAL TIME (HOURS) 744.0 5,793.5--

53,150.0 6.

REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2 7.

GENERATOR Cti-LINE TIME - tKOURS) 744.0 5,760.8 52,139.1 8.

UNIT RESEP.Y/ SHUTDOWN TIME (HOURS) 0.0 0.0-1.0 1

9.

THERMAL ENERGY GENERATED (MWHt) 2,061,488 17,992,356 153,149,335

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 683,526 6,ts 5,619 51,155,391

11. ELECTRICi.I. ENERGY GENERATED (MWHe. Net) 656,988 5,865,824 49,060,969

12. Ri: ACTOR SERVICE TACTOR (%)

100.0 98.9 69.9 I

13. REACTOR AVAILABILITY FACTOR (%)

100.0 98.9:

72.1

14. - UNIT SERT' ICE FACTOR (M 100.0 98.4 68.6

15. UNIT AVAll.IBILITY (ACTOR (* i '

100.0 98.4 68.0

16. UNIT JTPAC%f FACTOR (USING MDC) (%)

85.2 96.7.

02.3

17. UNIT CAPACITY TACTOR (USING DESIGN MWe) 81.9 92.9 59.9 s

18. UNIY FOSCED 'ODTAGE TACTOR (%)

0.0' 1.6-

'7.0

19. SHUTDOWNS SCHEDULED OVER THE NEXT 6,s4VNTHS (TYPl.; DATE, AND DURATION OF EACH) ;

Refuel. Outage,-09/26/92, 13 Weeks

20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

. ~. -.

.. -. -. -.. -. - -. ~.

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

e TABLE 3 E.2 AVERAGE DAILY UNIT POWER LEVEL (MWe. Net)

DOCKET HO. 050 373 UNIT LASALLE ONE

{

DATE September 10, 1992 COMPLETED BY H.J.

CIALKOWSKI TELEPHONE (815)-357 6761 l

j i

REPORT PERIODI Augubt 1992 t

DAY POWER DAY PONER r

1 852 17 905 2

900 18 903 3

960 19 909

~

f 4

900 20 868 5

~B88-21 889 6

900 22 825 7

949 23 803 8

878 24 877 i

9 907 25 901-10 937 26 846 11 892 27 837 12 906 28 8M 13 914 29 833 14 915 30-825 15-897-31 853 16 874 k

a (r--m-y 4.-

.--s y e ve.-

e v,-.. o g w.-e. gr y t e --

ru e

• r w

~ en h v e w +

+,-*w s

ea e* w mg=v=e m+ny+w e

---++wweg re,-

+ m = a w e r - wm e % -*-r e - w rf e--

r

-4m*+-#-9-9--we---,*we w*

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

(Unit 1) l METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOHN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if DUMBER (YYMMDD) S: SCHEDULED (HOURS)

REASON REDUCING POWER appilcable)

(None.)

SUMMARY

OF OPERATION:

The unit remained on line at high power throughout the month. Several minor power reductions were required due to system loading and maintenance activities.

2CADTS/5

t F.

UNIQUE REPORTING REQUIREMENTS (Unit 1) 1.

Safety / Relief valve operations (None.)

2.

ECCS System Outages (See Table 5) 3.

Changes to the Off-Site Dose Calculation Manual (None.)

4.

Major changes to Radioactive Haste 'reatment Systems.

(None.)

5.

Indications of railed fuel Elements.

(None.)

I f

i l

ZCADTS/5

(Unit 1)

Table 5 f.2 ECCS System Outages Note:

The year and unit data has been removed from the outage number.

OUTAGE NO.

EOUIPHFNT PURPOSE (0-0) 0617 ODG08CA Repair the compressor discharge check valve.

(U-1) 0626 lE22-5001 Varmeter replacement and megger cooling water pump.

0629 lE22-5001 HACR relay inspection.

0631 IE22-S001 Change soakback oil filter.

0632 lE22-S001 Install cylinder test valves.

0642 IE12-F047B Refurbish limitorque.

0643 0644 0645 1E12-C002B Inspection and oil change.

0652 0646 lE12-C002C Inspection and oil change.

0647 1DG049A Check Valve inspection.

0651 1DG0498 Check valve inspection.

0689 1E12-C300A Hegger motors.

lE12-C3000 0690 lE21-C001 Hegger motor and change oil.

0691 lE12-C002A Hegger motor and change oil.

0713 1E12-C001 Relay calibrations.

0714 lE12-C002A Relay calibrations.

0741 lE12-f085A Admin control during alarm testing.

0755 1E51-C003 EQ test on water leg pump, replace 1E51-f025 solenoid coils on drain valves.

lE51-f026 0783 lE22-C003 Hater leg pump inspection.

0784 1E22-C003 Coupilng lubrication.

ZCADTS/5+

i 4'

]

1 1

LASALLE NUCLEAR POWER STATION j

UNIT 2 MONTHl.Y PERFORMANCE REPORT 1

AUGUST 1992 COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-374 i

j LICENSE NO. NPF-18 f

i 1

1 I

J ZCADTS/7

4 lABLE Of CON 1LNTS (Unit 2)

I.

INTRODUCTION II.

REPORT A.

SUMMARY

Of OPERATING EXPERIENCE B.

AMENDHENTS 'O FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C.

KAJOR CORRECTIVE HAINTENANCE TO SAFETY-RELATED EQUIPHEhi D.

LICENSEE EVtNI 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.

Safety / 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 4

ZCADTS/7 J

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 Hater Reactor with a designed not 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 Commonwealth Edison Company.

Unit Two was issued operating license number NPT-IS on December 16, 1983.

Initial criticality was achieved on March 10, 1984 and commercial power operation was commenced on October 19, 1984.

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

ZCADTS/7 i

., II. MONTHLY REPORT A.

SUMMARY

Of OPERATING EXPERii.NCE (Unit 2) 4 4

DU 11EQ EYInt l

1 0000 Reactor critical, Generator on-lii.e at 1080 Mwe (Power level held due to high Main Turbine vibrations).

0200 Reduced power-level to 840 Mwe due to system load.

1200 Increased power level to 1050 Mwe.

2230 Reduced power level to 850 Hwe due to system load.

2 1030 Increased power level to 1070 Hwe.

1600 Reduced power level to 1000 Mwe dce to system load.

3 0200

. Reduced power level to 950 Mwe due to system load..

1000 Increased power. level to.1050 Hwe.

4 0100 Reduced power level to 850 Mwe due to system load.

1100 Increased power level to 1100 Hwe.

1700 Reduced power level to 1000 Mwe due to APRM high alarms.

2300 Reduced powcr level to 800 Mwe'to perform scram timing i

and rod set.

5 1100 Increased power level to 1070 Mwe.

2330 Reduced power level to 830 Hwe due to system load.

6 1100 Increased power level to 1120 Hve.

8 0030 Reduced power level to 890 Mwe due to system load.

1600 Increased power level to 1115 Hwe.

9..

0130 Reduced power level to 940 Mwe due to system load.

1400-Increased power level to'1115 Mwe.

11 0030 Reduced power level to 850 Hve due to system load.

1300 Increased power level: to 1115 Hwe.

12 0230' Reduced power 1evel to'850 Hwe'due to system load.

~

1000 Increased power level to 1010 Hwe.

13 0200' Reduced power level. to _800 Mwe;due to system load.

1100 Increased power level to-1120 Hwe.

ZCADTS/7

II. HONTHLY REPORT i

A.

SUMMARY

Or OPERATING EXPERIENCE (Unit 2)

(CONTINUED)

{

Dity LLms Event 14 0130 Reduced power level to 840 Hwe due to system load.

1000 Increased power level to 1110 Hwe, 1830 Reduced power level to 940 Hwe due to system load.

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

15 0830 Increased power level to 1050 Hwe.

16 0030 Reduced power level to 850 Hwe due to system load.

1200 Increased power level to 1075 Hwe.

17 0400 Reduced power level to 900 Hwe due to system load.

1000 Increased power level to 1100 Hwe.

18 0130 Reduced power level to 1010 Hwe due to system load.

0600 Increased power level to 1085 Hwe.

19 0300 Reduced power level to 840 Hwe due to system load.

1000 Increased power level to 1100 Hwe.

27 0310 Reactor scram due to main turbine trip.

The turbine trip was caused by & thrust bearing wear detector.

31 2400 Reactor subtritical, Generator off-line, Eorced outage in progress.

ZCADTS/7

~

B.

AMENDMENTS TO Tile FACILITY LICENSE OR TECilNICAL SPECIFICATION Revised reference from General Electric performing core operating limits analysis to Com.onwealth Edison and General Electric.

C.

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

(See Table 1)

D.

LICENSEE EVENT REPORTS (Unit 2)

LER_lhtmhe.E DAlf Qftiflipilan 92-010-00 08/10/92 Failure of the Reactor Core Isolation Cooling steam line outboard isolation valve 2E51-f008 during performance of the steam line high flow calibration.

92-011-00 08/09/92 Spurious automatic start of the Control Room ventilation emergency makeup train due to a high radiation spike.

92-012-00 08/27/92 Main Turbine trip due to thrust bearing wear detector which resulted in a Reactor scram.

E.

DATA TABULATIONS (Unit 2) 1.

Operating Data Report.

(See Tabic 2) 2.

Average Daily Unit Power level.

(See Table 3)

?

(

3.

Unit Shutdowns and Significart Power Reductions.

1 (See Tcble 4) i ZCADTS/7 j

F

~

C.

TABLE 1 (Unit 2)

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT HCP.K REQUEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MAU UNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L15544 High Pressure Core Air receiver pressure None.

Replaced valve.

Spray Diesel Generator relief valve 2E22-F3698 "B" Air Receiver leaking.

Ll7093 Reactor Core Isolation Valve motor burned up due Valve breaker tripped on Replaced valve motor.

Cooling Turbine to the torque switch magnetics during surveillance Isolation Valve contacts and the valve testing.

2E51-F008 being closed prior to initiation of Isolation signal.

(No SOR Failures this month.)

ZCADTS/7

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

+

TABLE 2 o<

E.1 CPERATING DATA REPORT DOCKET NO. 050 373 UNIT LASALLE 'IMO DATE September 10, 1992 COMPl.ETED BY M.J.CIALKOWSKI OPERATING STATUS TELEPHONE (815) 357-6761 j

1.

REPORTING PERIOD August 1992

{

GROSS HOURS IN REPORTING PERIOD:

744 j

)

2.

CURRENTLY AUTHORIZED POWER LEVEL (MWt):

3,323

}

MAX DEPENDABLE CAPACITY (MWe-Net):

1,036 DESIGN ELECTRICAL RATING (MWe-Net):

1,078

}

}

3.

POWER LEVEL TO WHICil RESTRICTED (IF ANY) (MWe-Net):

N/A 4.

REASON FOR RESTRICTION (IF ANY)*

i T1115 MONTH YEAR.TO DATE CUMULATIVE

}

5.

REACTOR CRITICAL TIME. (110URS) 627.2 3,388.4 48,124.3-

)

6.

REACTOR RESERVE SilUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 7.

GENERATOR. ON-LINE TIME (!!OURS) 627.2 3,226.6-47,431.1 l

8 UNIT RESERVE SHUTDOWN TIME (HOURS) 0,0

- 0. 0 0.0 ij' 9.

THERMAL ENERGY GENERATED (MWilt)

-1,941,742 9,676,399' 141,918,798.

p 1

10. ELECTRICAL' ENERGY GENERATED -(MWile-Gross) 652,068 3,274,700 47,164,450'

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 627,160 3,129,740 45,261,244

12. REACTOR SERVICE FACTOR (%)

84.3 57.'9 70,0

13. REACTOR AVAILABILITY FACTOR-(%)

84.3-57.9 72.5

14. UNIT SERVICE FACTOR (%)

84.3 55.1 68.7

15. UNIT AVAILIBILITY FACTOR (%)

84.3 55.1 68.7

16. UNIT CAPACITY FACTOR =(USENG MDC) (%):

81.4 51.6 63.3

.17. UNIT CAPACITY FACTOR (USING DESIGN Minio) 76.2' 49.6l 60.9

-18. UNIT FORCED OUTAGE FACTOR.(%)

15.7.

-6.8 12.7

- 19. SNUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AN'i DURATION OF. EACH)

• 20.~IF SIIUTDOWN AT END OF REPORT PERIOD,-ESTIMATED DATE OF STARTUP:

09/10/92 f

3

h..- m, 9p g q w - r m p y.%s s, g e,

.y-,r-

-_em, m,,..r.

u.,.

y.w ww

,r -ian w w p. g,.

.g yg e ig.g y

,v%,,.

y

',y E. y 9.c a

a

.u--

m

1!.

t j

o TABLE 3 1 o E.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-tiet)

I DOCKET NO. 050-373 I

UNIT LASALLE *IHO f

DATE September 10, 1992 4

COMPLETED BY-M.J. CIALKOWSK1 l

TELEPHONE (815)-357-6761 1

4 1

i l

1 1

REl' ORT PERIOD: August 1992 I

j DAY POWER DAY PohER 1

I 1

916 17 1,018 2

937 18 1,026 3

979

.19 991 4

935-20-1,054 l

S 915 21 1,061 6

993 22 1,051 7

1,061 23 1,043 8

991 24 1,051 9

1,010 25 1,059-

)

j 10 1,054 26 1,053 l-11 982 27 117 l

12 1,004 28

-12' 13 1,009 29

-12 14 960 30 15 953 31

-12 16 953 l.

i

TABLE 4 E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS >20%

(UNIT 2) t METHOD OF CORRECTIVE

. YEARLY TYPE SHUTTING DoWN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR I if NUMBER LYp04DD1 S: SCHEDULED (HOURS)

REASON RELUCING POWER applicable) 07 920827 F

116.8 A

3 Main turbine trip due to turbine thrust bearing wear detector (LERf 92-012-00/

DVRf I-2-92-067).

SUMMARY

OF OPERATION:

The unit remained on line at high power throughout the month. Several minor power reductions were required due to systt.m loading and maintenance activities. The unit experienced a forced outage on 08/27/92 due to a main turbine thrust bearing wear detector. The unit is expected to return to service'on 09/10/92.

ZCADTS/7

F.

UNIQUE REPORTING REQUIREMENTS (Unit 2) 1.

Safety / Relief Valve Operations VALVES N0 & 1YPE PLANT DI SCRIPTION QAlf ACTUATED ACTUATIO6 CONDITIOS Of_DF __

08/27/92 2821-f013U Automatic 3

Scram (LER# 92-012-00) 08/27/92 2021-f013A Manual 3

Scram (LER# 92-012-00) 08/27/92 2021-f013B Hanual 3

Scram (LER# 92-012-00) 2.

ECCS System Outages (See Table S.)

3.

Changes to the Off-Site Dose Calculation Manual.

(None.)

4.

Major changes to Radioactive Naste Treatment Systems.

(None.)

5.

Indications of failed fuel Elements.

(None.)

t 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, ffUl&!Dil PURPOSE 1928 2E22-f3698 Reset relief valve setting.

l 1929 2E22-S001 HACR relay inspection 1931

?E22-S001 Change soakback oil filters.

I 1936 2051-f331 Lubricated turbine trip and throttle velve, repair flange on drain pot.

i 1938 2E51-f008 Breaker inspection and :alve i

1939

repair, i

1995 1999 2000 1950 2E12-C002A Lubrication.

4 1967 2E12-C002B Lubrication.

4 1974 2DG08CB Repair check valve.

1979 2E51-f091 Admin control.

1980 2E12-f024A Admin control during full flow test.

'd025 2E51-f066 Check valve repair.

I 2028 2E12-f0508 Valve repack.

2034 2DG08CB Repair compressor.

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ZCADTS/7 e

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