ML20115C118

Monthly Operating Repts for Sept 1992 for LaSalle County Nuclear Power Station Units 1 & 2

ML20115C118
Person / Time
Site:	LaSalle
Issue date:	09/30/1992
From:	Cialkowski M, Diederich G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9210190161
Download: ML20115C118 (25)

Text

l' t

_.> C:mm:nw:alth Edis n LaSalle County Nuclear Station O' 2601 N.21st. Rd.

l-l_ Marseilles, Illinois 61341 l Telephone 815/357-6761 October 9, 1992 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Connission Mail Station Pl-137 Mashington, D.C. 20555 ATTN: Document Control Desk Gentlemen:

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

Very truly yours, f $c E<: G. J. Diederich Station Manager LaSalle County Station GJD/MJC/djf Enclosure xc: 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 INPO Records Center D. R. Eggett, NED

P. D. Doverspike, GE Resident T. J. Kovach, Manager of Nuclear Licensing l T. A. Rieck, Nuclear Fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor H. P._Pietryga, QA/NS Off Site Review Station File ZCADTS/S suvunu a h,

. . _ , _. . _ . . . _ . . . . ,~

4 se

.4g 6

d k'

l i-4

.t

.'b a

i

. LASALLE NUCLEAR POWER STATION +

l 4-

-UNIT 1 .

j . MONTHLY PERFORMANCE REPORT. -

. SEPTEMBER 1992 ,

COM* WEALTH EDISON COMPANY '

i.

f 1

NRC' DOCKET N0'. 050-373.

LICENSE NO. NPF l_

I e

i-i'.

l i

b n

f l:

r-1-

.i

[.- ~ZCADTS/5 b - . -

, , ~ . . . - . . . . . ..- -- -. . - . . . .

1 TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION II. REPORT A. St# NARY OF OPERATING EXPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. MAJOR CORRECTIVE MAINTENANCE 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

! ZCADTS/S

~

.8 .

]

i ---

I. INTRODUCTION (Unit 1) l The LaSalle County Nuclear Power Station is.a two-unit _ facility owned by-i Commonwealth Edison Company and. located near Marseilles, Illinois. Each c unit is a Boiling Hater 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-ll on April 17, 1982.

Initial criticality was achieved on June 21,.1982 and commercial power

!- operation was connenced on January 1,1984.

This report was compiled by Michael J. Cialkowski, telephone number j (815)357-6761, extension 242/.

l d'

i h

5 i

<ZCADTS/5

i.

.x II MONTHLY REPORT r ,

A. SlMMRY OF OPERATING EXPERIENCE (Unit 1)

Day llag Event 1 0000 Reactor critical Generator on-line at 740 Mwe due to

ystem load (Unit in coastdown).

0800 Increased power level to 930 Mwe.-

2 0000 Reduced power level to 745 Mwe due to system load.

0600 Increase) power level to 900 Mwe.

3 0000 Reduced power level to 745 Mwe due to system load.

1000 Increased power level to 925 Mwe.

4 0000 Reduced power level to 745 W e due to systes load.

0900 Increased power level to 915 Mwo.

2200 Reduced power level to 745 Mwe due to system load.

1 5 1000 Increased power level to 925 Mw.. '

6 0100 Reduced power level to 745 Mwe due to system load.

0900 Increased power level to 900 Mwe.

7- 0200 Reduced power level to 745 Mwe due to system load.

1100 Increased power level to 910 Mwe.

8 0100 Reduced power level to 740 Mwe due to systes load.

0700 Increased power level to 890 Mwo.

9 0000 Reduced power level to 745 Mwe due to system load.

0630 Increased power level to 880 Mwe.

13 0030 Reduced power level to 740 Mwe due to system load.

1300 Tacreased power level to 855 Mwe.

2330 Reduced power level to 740 Mwe due to systes load.

14 0700 Increased power level to 890 Mwe.

15 0200 Reduced power level to 750 Mwe due to ;ysten load.-

0600 Increased power level to 860 Mwe.

16 07.30 Reduced power level to 715 Mwe due to system load, 0630 Increased power level to 860 W e.

ZCADTS/5

.' II MONTHLY REPORT (CONTINUED)-

,) .

A.

SUMMARY

OF OPERATING ~ EXPERIENCE (Unit 1)

Day Ilma Event 19 0130 Reduced power level _ to 740 Mwe due to system load.

1 0900 Increased power level to 850 Hve.

Reduced power level to 740 Mwe due to system load.

20 0100 l 1000 Increased power level to 845 Mwe. _

21 0030 Reduced power _ level to 740 Mwe due to system load.

0630 Increased power level to 860 Mwe. j

22 004u Reduced pcwer level to 740 Mwe due to system load. l

! l 0500 Increased _ power level to 860 Mwe.

t ,

i 25 0100 Reduced power level to 740 Mwe due to system load.

i  !

~

i 0700 Increased power level to 840 Mwe.

b T7 0300 Reduced power level to 745 Mwe due to system load.

l 1000 Increased power level to 835 Mwe.

28 0000 Reduced power level to 740 Mwe due to system load.

j 0500 Increased power level to 815 Mwe, 1

29 2330 Reduced power level to 740 Mwe due cu system load.

30 0900 Increased power level to 810 Mwe.-

1 2400 Reactor critical,. Generator on-line at 800 Mwe, continuing coastdown.

4 4

i e

l i

i 2

ZCADTS/5

4

~

,f 8. AMENDMENTS TO'THE FACILITY LICENSE 0RLTECHN' %L SPECIFICATION L Relocation ofs the Radioactivity Effluent Technical Specifications to

the Offsite Dose Calculation Manual or the Process Control Program.

Change to the Technical Specification Administrative Section for the Onsite Review and Investigative Functicn.

Removal of the Primary Containment penetration conductor overcurrent protective devices component list.

- C. MAJOR 00RRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT (including '

SOR differential pressure switch failure reports).

(See Table 1) l l D. LICENSEE EVENT REPORTS (Unit 1)

LER Number D3.tg Descrio. tion i .

i 92-009-00 09/23/92 Spurious trip of the 'B' Control Room HVAC System 'B' Radiation Detector.

E. DATA TABULATIONS (Unit 1)

1. Operating Data Report (See Table 2)

2. Average Daily Unit Power Level (See Table 3) j 3. Unit Shutdowns and Significant Power Reductions (See Table 4) i 4

j ..

l l

t-ZCADTS/5

C. TABLE 1 (Unit 1)

MAJOR 00RRECTIVE MAINTENANCE TO .,

~

SAFETY-RELATED EQUIPMENT HORK REQUEST RESULTS AND EFFECTS ~

NUMBER 00MPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION LO1914 Control Room HVAC Actuator linkage. Damper actuator failure. Replaced linkage.

Control Damper OVC19YB L01915 Control Room HVAC . Actuator linkage. Damper actuator failure. Replaced linkage.

Control. Damper OVC16YE L15093 Auxiliary Electric Pressure switch freon leak. None. Replaced freon tubing.

Equipment Room HVAC Compressor OVE-04CB L15784 Auxiliary Electric Hot Gas Bypass Valve None. Replaced valve.

Equipment Room HVAC ORG0768.

L16923 High Pressure Core Deteriorating fuel level None. Replaced switches.

Spray Diesel Fuel switches.

Storage Tank L17328 Coantrol Rod Drive Instrument block >; top valve None. Replaced valve.

Hydraulic Control leaking.

Unit 22-59 L17870 Reactor Protection Logic card. Calibration failed. Replaced logic card.

System Electrical Protection Assembly IC71-S003E (No SOR Failures this month.)

ZCf;DTS/5+

TABLE-2

- E.I' OPERATING DATA REPORT

,3 ,

DOCKET NO. 050-373

. UNIT LASALLE ONE DATE OCTOBER 9,1992 COMPLETED BY M.J.CIALKOWSKI OPERATING STATUS TELEPHONE (815)357-6761 J

1. -REPORTING PERIOD: September:1992 GROSS HOURS IN REPORTING PERIOD: '720-

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 WHICH RESTRICTED (IF ANY) (MWe-Net): N/A

4. REASON FOR RE5IRICTION (IF ANY) t -

Ti!IS ' MONTH YEAR TO DATE CUMULATIVE

_____ _____ __ ____ .. --s ...... ._ ,

5. REACTOR CRITICAL TIME (HOURS) 720.0 6,513.5- 53,870.0

6. REACTOR RESERVE FFUTDOWN TIME (HOURS)- 0.0 0.0 1,641.2

7. GENERATOR ON-LINE TIME (HOURS) 720.0. 6,480.8- 52,859.1

8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0- 0.0 1.0

9. THERMAL' ENERGY GENERATED (HWHt) 1,816,757 19,809,113- - 154,966,092 10._ ELF.CTRICAL ENERGY GENERATED (MWHe-Gross). 606,174. 6,671,793 51,761;565

11. ELECTRICAL ENERGY GENERATED (MWHo-Net) 581,934 6,447,758 49,642,903

12. REACTOR SERVICE FACTOR (%) 100.0 '99.1 70.2 4-

13. REACTOR AVAILAB'ILITY FACTOR (%) 100.0 99.1 7 2.'3 '

14. UNIT SERVICE FACTOR (%) 100.0 98.6 68.9' l

15. UNIT AVAILIBILITY FACTOR (%) 100.0. - 9 8_ . 6 68.9

, '16. UNIT CAPACITY FACTOR-(USIhG'MDC) (%)- 78.0L 94.7' 62.5 4

17. UNIT CAPACITY FACTOR.(USING DESIGN MWe) 75.0. 191.0 6 0 . 0 -.

.18. UNIT FORCED OUTAGE FACTOR (%) 0.0 '1;4 6.9

19. SHUTDOWNS ' SCHEDULED OVER THE NEXT 6 MONTHS ' (TYPE, DATE, AND DURATION OF EACH)t.-

.Retuel Outage,- - 10/03/92, 13 Weeks L 20.~IF SHUTDOWN'AT.END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

l-I_______.'_lm'm___ I... ~E, g.Ew. ,-,,w-y,, -,

.m ,y,._,#wg_,,_, ,,9 ,m

-., , ,,w., .,,,._,y.-, ,-

. . . . ._. _ . . . . . . ..m . _ _ _ .. _ . _ . - .... _ . . . . _ __ . .. _ . _ _ _ - - ._ __

} .'-

I TABLE 3  !

a 's j.. . , ;- E.2- AVERAGE DAILY UNIT POWER LEVFL'(MWe-Net)

DOCKET.NO. 050 373 4- ~

i UNIT LASALLE ONE-4

-DATE OCTOBER 9,1992-

j. COMPLETED BY M.J. CIALKOWSKI:

. - -TELEPHONE (815).357-6761) ,

i. '

i.

)

a 1.

I REPORT PERIOD: September 1992 l'

DAY POWER DAY POWER

f. .--.. ... ________. .__..... . __....

1 835 17 :827 l

2 835 18 815 1-t- 3 835 19 780

[ 4 808 20 .774 k- 5 836 21 806-i' i 6 822 22 803 i

7 821 23 811 i

! 8 830 24 806 a

. 9 807 25- 780 10 823 26 795 f.

! 11 827' 27 786 12 825 28 771 j- 13 772 29- 781 i i

j- 14- 822 30 766

15 823 31 j-

i. 16 825

1

i i

i

,_ . , ..4,... . , . , , . -,,m.,, , , , , . - , , _ . , . .-,m..,.,,,.,-,.7,,_..y,my,,.,-

- ,m.,,.gm

~~

TABLE 4-E.3 UNIT SHUTDOHNS AND POWER REDUCTIONS > 201 ..,.

(Unit 1) -

METHOD OF CORRECTIVE .

IYEARLY TYPE- SHUTTING DOHN ACTIONS /COMENTS -

SEQUENTIAL DATE. :F: FORCED- DURATION THE REACTOR OR (LER/DVR # if NUMBER _ '(YYM4DD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable).- i 4

'(None.)

l

. SUMARY OF- 9PERATION:

~ The ' unit' remained. on '11ne at high power' throughout the month. Several minor power reductions were required due toLsystem

. loading and maintenance activities.

9 1

b +

i i

i ZCADTS/5

i i

F. UNIW E REFORTING RE@ IREMENTS (Unit ?)

1. Safety / Relief valve operations (None.)

2. ECCS System Outages (See Table 5)

3. Changes to the Off-Sif e Dose Calculation Manual (None.)

4. Major changes to Radioactive Maste Treatment Systems.

(None.)

5. Indications of failtd fuel Elements.

(None.)

1 T

3 f

1 l

I w

w 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. EOUIPMENT PURPOSE (U-0) .

0689 ODG0lK Replaced frequency meter.

0692 ODG0lK Replaced fuel sensing line and inspected pressure switch.

(U-1) 0854 1E22-F011 Reroute HPCS-CY Iines.

0859 0882 1E12-F094 Inspection, refurbishment and VOTES testing.

0903 1DG01K Removed and replaced cylinder test valves.

0904 1DG01K Replaced pressure switches.

0908 1E12-F093 Inspection, refurbishment and 0909 VOTES testing.

0912 1DG0lP Heggar motor and inspect control switch.

0925 1E12-C300C Lubrication.

IE12-C3000 1071 1DG08CA Troubleshoot and repair breaker.

1073 1077 1E12-F049A Replaced motor and VOTES test.

1078 1184 1E51-F059 Replaced motor and VOTES test.

1185 I 1217 1E51-F022 Administrative control.

1329 1E22-C302A Inspection.

1330 1E22-C302B Inspection.

ZCADTS/5+ .

e

'. ASALLE NUCLEAR PCHER STATION UNIT 2 MONTHLY PERFORW "CE REPORT SEPTEMBER 1992 COHHONHEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICEkSE NO. NPF-18 4

ZCADTS/7

?

TABLE OF 00R!ENTS 1

(Unit 2) i I. INTRODUCTION l

II. RE00RT l i'

A. SUNKARY OF OPERATING EXPERIEHCE B. AMENDHENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. HAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT D. LICENSEE EVENT REPORTS l

E. VATA TACULATIONS

1. Operating Data Report l

2. Average Daily Unit Power Level 4

3. Unit Shutdowns and Power Reductions i 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 ZCADTS/7

d

. I 1

l i

I. INTRODUCTION (Unit 2)  ;

i The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Ediso Company and located near Marsellies, Illinois. Each unit is a Boiling Water 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 Comonwealth 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 October 19, 1984.

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

4 1

ZCADTS/7 J

. - . _ -. =. . - -. ---- .- - -- - - - . .

e I II. KMTHLY REPORT ,

. SLM4ARY OF OPERATING EXPERIENCE (Unit 2)

PAY IjM Event ,_

1 0000 Reactor subtritical, Generator off-line, forced outage in progress.

9 2020 Reactor critical.

10 2047 Generator on-line at 80 Mwe, 0500 Increased power level to 200 Mwe.

11 1800 Increased power level to 245 Mwe.

14 0200 Increased power level to 280 Hve.

1000 Increased power level to 550 Hve, upshifted the Reactor Recirculation Pumps.

15 0200 Increased power level to 1065 Mwe.

16 0100 Reduced power lovel to 750 Mwe to perform rod set 17 1030 Increased power level to 1115 Mwe.

0230 Reduced power _ level to 90^ Hve due to system load.-

0900 Increased power level to 1115 Mwe.

19 0100 Reduced power level to 850 Mwe due to system load.

! 1100 Increased power level to 1000 Mwe.

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

20 1000 Increased power level-to 1000 Hve.

21- 0200 Reduced power level to 850 Mwe due to system load.

1000 Increased power level to 1115 Mwe.

l 22 1900 Reduced power level to 1000 Mwe to Turbine testing.

2130 Increased power level to 1126 Mwe for Turbine performance testing.

23 0130 Reduced power level to 1000 Mwe for Turbine performance testing.

0300 Increased power level to 1125 Mwe.

26 0100 Reduced power level to 900 Mwe, placed the Turbine Driven Reactor Feed Pump off-line.

ZCADTS/7

II. HONTHLY REPORT A.

SUMMARY

Of OPERATING EXPERIENCE (Unit 2) (CONTINUED)

QAy Ilme Event 10C0 Increased power level to 1000 Mwe.

2300 Reduced power level to 870 Hwe due to systen load.

28 1400 Increased power level to 1120 Hwe.

29 0200 Reduced power level to 880 Hwe due to systen load.

0700 Increased power level to 1110 Hve.

30 2400 Reactor critical, Generator on-line at 1110 Hwo. -

ZCADTS/7

• / .B. AMENDMENTS TO THE FACILITY LICENSE OR TECHNICAL SPECIFICATION Relocation of the Radioactivity Effluent Technical Specifications to  !

the Offsite Dose Calculation Manual or the Process Control Program. j Change to the Technical Specification Administrative T'ction for the Onsice' Review and Investigative function.

Removal of the Primary Containment penetration conductor overcurrent protective devices component list.

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 Number Dait (lescription 92-013-00 09/17/92 Spurious initiation of the Reactor Core Isolation Cooling System during surveillance performance.

E. DATA TABULATIONS (Unit 2)

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/7

C. TABLE 1 (Unit 2)

^

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT HORK REQUEST RESULTS AND EFFECTS ,

NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE AQis5L Ll6556 Containment Monitoring Valve degradation. Valve failed to cycle. Replaced valve internals.

Inboard Isolation Valve 2CM025A L17396 Safety Relief Valve Linear variable Indication failed to show valve Replaced iincar variable 2821-F0138 differential transformer. In full closed position. differential transformer.

L17397 Safety Relief Valve Linear variable Indication failed to show valve Replaced linear variable 2821-F013A differential transformer. in full closed position. differential transformer.

L17451 Reactor Core Isolation Hear of the indicator hinge Improper valve position Replaced pressure seal ring Cooling Inboard pin bearing surface. Indication. and repacked valve.

Testable Check Valve 2E51-F066 L17460 Reactor Core Isolation Indication cams out of ImprE;ir valve position Repositioned indication Cooling Inboard position. indication. cans.

Testable Check Valve 2E51-F065 Ll7640 Core Standby Cooling Actuator leaking oil. Damper failed closed. Replaced actuator.

System Damper 2VYO5Y (No SOR Failures this month.)

ZCADTS/7

TABLE 2

• * . E.1 OPERATING DATA REPORT-DOCKET NO. 050-373 UNIT LASALLE TWO DATE OCTOBER 9,1992 .i COMPLETED BY M.J.CIALKOWSKI J OPERATitlG STATUS TELEPHONE (815) 357-6761 i i

1. REPORTING PERIOD: September 1992 GROSS IlOURS IN REPORTING PERIOD: 720 >

1 5

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 .

MAX DEPENDABLE CAPACITY (MWe-Net): 1,036 DESIGN ELECTRICAL RATING (MWe-Het): -1,078

3. POWER LEVEL TO WHICl! RESTRICTED (IT ANY) (MWe_ Net): N/A i

4 REASON FOR RESTRICTION (IT ANY):

i TilIS MONTil YEAR TO DATE CUMULATIVE.

5. REACTOR CRITICAL TIME (HOURS) 507.7 3,896.1 48,831.9 l

6. REACTOR RESERVE S!!UTDOWN TIME (HOURS) ~ 0.0 0.0 1,716.9

7. GENERATOR ON-LINE TIME (HOURS) 483.2 3,709.8 47,914.4.

~

6. UNIT RESERVE SlfUTDOWN TIME (HOURS) 0.0 0.0 0.0-9.

THERMAL ENERGY GENERATED (MWilt)- 1,304,671 10,981,070 143,223,469

10. ELECTRICAL ENERGY GENERATED (MWHe. Gross) 430,106 3,704,806 47,594,556 II. ELECTRICAL ENERGY GENERATED (MWHe-Net) 410,766- 3,540,506 45,672,010 I2. REACTOR SERVICE FACTOR (%) 70.5 -59.3 70.0

13. REACTOR AVAILABILITY FACTOR'(%) 70.5 59.3 72.5

14. UNIT SERVICE FACTOR (%) 67.1 56.4 68.7 l

j 15 UNIT AVAILIDILITY TACTOR (%) 67.1 56.4 68.7

i. . .

,' 16. UNIT CAPACITY FACTOR (USING MDC) (%) 55.1 52.0. 63.2 1  !

{ 17. UNIT CAPACITY' FACTOR (USING DESIGN MWe) 52.9 50.0 60.8 h 18. UNIT FORCED OUTAGE TACTOR (%) 32.9 11.3- ,13.0 l=

19. SHUTDOWNS -SCHEDULED OVER THE NEXT 6 MONTHS. (TYPE, DATE, AND DURATION OT EACil) - .

t l

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

1 -i

[

I

,- .c. . ,,,.44__,_.,-.,_.;u.;_..,_,,_,. . . _ _ _ . . . . - _ . . . . , ..a.u,,,,;,,-.._,_,,_w.-...,._..

. 7ADLE 3 a

.* E.2 AVERADE DAILY UNIT POWER LEVEk (HWQ.!;4t)

DOCKET NO. 050-373 UNIT LASALLC TWO DATE OCTOBER 9,1992 COMPLETED DY M.J. CIALKUWSKI TELEPHONE (815).357 6761 REPORT PERIOD September 1992 DAY POWER DAY POWER 1 12 17 1,034 2 12 la 1,039 3 12 19 890 4 12 20 887 5 12 21 1,015-6 -12 22 1,074 7 -12 23 1,074 8 12 -24 1,080 9 12 25 1,075 10 6 26 942

! 11 174 27 872 i

12 199 28 1,001 f-

! '13 203 29 1,027 i

14 539 30 1,052 l

15 1,036- 31 l

.36 1,006' i

t I

L t

l-

TABLE 4 e

E.3 UNIT SHUTDONNS AID PONER REDUCTICNS->20%

(UNIT 2)

METHOD or CORRECTIVE YEARLT. ' TYPE SHUTTING DONW ACTIONS /CODGEDITS SEQUENTIAL DATE 'F: FORCED DURATION THE REACTOR OR (LER/DTR f if NUMBER (TTleeD) S: SCHEDULED (BOURS) REASON REDUCING PoNER applicable) 07- 920827 r 236.8 A 3 Main turbine trip due to turbine thrust bearing wear detector (LERf 92-012-00/

DTRf I-2-92-o67).

SunesARr or orERATION:

The unit started the month shutdown due to a main turbine trip. The unit was returned to service on 09/10/92. For the remainder of the month the unit remained on line at high power. Several. minor power reductions were required due to system loading.

ZCADTS/7 i' = _ _ _ _ - _ _ _ - - _ _ _ _ . . _ _ - - _

'I F. UNIQUE REPORTING REQUIREMENTS (Unit 2)

1. Safety / Relief Valve Operations (None.)

i 2. ECCS System Outages (See Table 5.)

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

(None.)

f 4. Major changes to Radioactive Maste Treatment Systems.

4 (None.)

5. Indications of Failed fuel Elements.

(None.)

A 4

i i

I 4

I I

4

~

j 'ZCADTS/7~

i

l

~

c.

(Unit 2) f l: Table 5 l i

1 F.2 ECCS System Outages  :

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

QQTAGE NO. E0VIPMENT PURPOSE l 2052 2E12-F0508 Repair wiring.

2064 2E12-F0248 Admin. control. >

1 l

2070 2DG08CB Repair compressor.

2072 2E51-C005 Motor inspection.

2077 2E12-F053B Admin. control.  ;

2079 2DG011 Admin, control.

4 j 2120 2E22-C302A Inspection.

2122 2E22-C3028 Inspection.

1.

1 a

4 i

+

1 i

i-i i-l- ZCADTS/7 i

2

-g ,,p-,y1,., m --,y-,, ,--,-y-.r- y -

3 -..,,- , ,r, y ,,_, , , , raw,- , 9 ..,-.,r. v ir y.-.,.m-a w- n .yy g vp w s, . .,4,r.- ..-w- ,-.e- + ,. , v-