Text

Monthly Operating Repts for Sept 1988 for LaSalle Units 1 & 2
	ML20207N612
Person / Time
Site:	LaSalle
Issue date:	09/30/1988
From:	Diederich G, Thunstedt J; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
References
	NUDOCS 8810190254
	Download: ML20207N612 (30)
	v • d • e

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

e e

o*

LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT SEPTEMBER 1988 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 i LICENSE NO. NPT-11 e

f I

l t

l i

8810190254 880770 PDR ADOCK 0S000373 PDC R

DOCUMENT ID 0043r/0031r fll

e s

TABLE OF CONTENTS

-l I. INTRODUCTION II. MONTHLY REPORT FOR UNIT ONE A. Summary of Operating Experience

8. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY 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 Emperiments 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 j 2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions f E. UNIQUE REPORTING REQUIREMENTS 1

1. Main Steam Relief Valve Operations j 2. ECCS System Outages

3. Off-Site Dose Calculation Manual Changes l 4. Majtr Changes to Radioactive Waste Treatment System j 5. Indications of Failed Fuel Elements j

i e

ij j

1 l

l DOCUMENT ID 0043r/0031r 1

1 I

e I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marsellies, Illinois.

Each unit is a Boiling Water Reactor with a designed not 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 Commonwealtb Edison Company.

Unit one was issued operating license number NPT-11 on April 17, 1982.

Initial criticality was acaleved on June 21, 1982 and commercial power operation was commenced on January 1, 1984.

This report was compiled by John W. Thunstedt, telephone number (815)357-6761, extension 2463.

DOCUMENT ID 0043r/0031r

o II. MONTMLY REPORT FOR UNIT ONE A. SUM 4ARY OF OPERATING EXPERIENCE FOR UNIT ONE September 1, 0000 hours0 days 0 hours 0 weeks 0 months Unit One on-line, reactor critical, 1100 MWo.

(Various) Rc.ip down and up per Load Dispatchor.

September 23, 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months Ramp down to 900 MWe to correct heater drain tank level control problem.

September 23, 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months Ramping up 1050 MWo.

September 29, 2335 hours0.027 days 0.649 hours 0.00386 weeks 8.884675e-4 months R;wp down to 815 MWe for control-valva testing.

September 30, 0530 hours0.00613 days 0.147 hours 8.763227e-4 weeks 2.01665e-4 months Ramping up to 1120 MWo.

September 30, 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months Unit One on-line, reactor critical, 1100 MWo.

DOCUMENT ID 0043r/0031r

, Bo PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED o

MAINTEN ANCE.

1. knendments to Facility License or Technical Specification.

Amendment 59 - Resolved difference in Suppression Pool Hi-Level Switch Setpoints.

Amendment 60 - Provided additional requirements for monitoring core performance in high-power / low-flow regions.

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

There were no changes to procedures which are described in the Safety Analysis Report.

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

There were no changes to procedures which are described in the Safety Analysis Report.

4. Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a Summary of safety-related maintenance completed on Unit One during the reporting period. The headings indicated in this summary includes Work Request number, Component Name, Cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action.

5. Completed Safety Related Modifications.

The following Table (Table 2) presents a list of completed Modifications during this reporting period. Each entry will have a o short synopsis explaining details involved with each modification.

t l

l I

i I

l DOCUMENT ID 0043r/0031r

r ,

i i

l TABLE 1 1

1 J CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT a

1

' UNIT ll WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS ANu ~7FECTS CORRECTIVE ACTION I

ON SAFE PLANT OPERATION

! f,83091 PIS-lCllN616C Instru:nent drift Low indication while in-service Recalibrated instrument Charging Water I

1DC07E Cell 8 Div. Low ICV & Specific gravity Low battery capacity Replaced amplifier and

]L83008 1 125 VDC recalibrated instrument L83334 LPRM 50-48.17 Instrument drift Lower power indication Replaced amplifier and recalibrated instrument a

! L83202 OD18-N524 SBGT WRGM Instrument failure No flow indication Replaced transducer, recalibrated loop L83524 1APO4E J. rec.ker Electrical short due to Breaker inoperable Clenned cubicle, replaced mechanical failure breaker i

i L83753 IVYO22 Alarm Instrument drift Alarm received before desired Recalibrated instrument setpoint L83771 ODG000 C Diesel Excessive wave or. valve Diesel inoperable Rebuilt solenoid Generatae internals L83955 1CM000 Lg/02 Failed surveillancu Indicator oscillating Recalibrated instrument Monitor L83986 1 CMC 47 H2 /02 Failed regulators Instrument oscillating Replaced regulators, Monitor recalibrated instrument L83778 1C11000 LPRM Power Failed surveillance Inoperale LPRM Replaced power supply, Supplies recalibrated loop DOCUMENT ID OC43r/0031.

o TABLE 2 CCNPLETED SAFETY RELATED MODIFICATIONS HQQIFICATION NUMBER: A brief synopsis of incorporated modification objectives with final design resolution. Also, state reviewed or unreviewed safety questions.

URII_ftlE M-1-1-83-098 Install new valve positioners, controllers and level transmitters for the regulation of valves 1HD062A, B, C and 1DH065A, B, C. This will permit the valves to modulate on increasing heater level rather than open on nigh level only.

M-1-1-86-086 Change and support configurations of subsystemn IDV-23, IDV-27, and 1DV-31 with the installation of one (1) new restraint per subsystem. Repair damage of support M09-DV15-1004R and the auxiliary steel of restraine M09-DV15-1403X which occurred during higher power levels of plant operation, excessive vibrations on vent lines between the 13A/B/C L.P. Heoters and the condenser.

M-1-1~86-087 Change and support configurations of subsystems 1HD-07 and 1HD08 with the lusta11ation of five'(5) new restraints per

, subsystem. One (1) hardware change on support M09-HD10-1024R s to reinforce the 3" back-to-back channel. The damage has occurred during high pwoer levels of plant operation, encossive vibrations on vent lines between 15A/B/C and 16A/B H.P. Heaters. >

DOCUMENT ID 0043r/0031r

e c

. C.. LICENSEE EVENT REPORTS

[11 The following 1s a tabular sumary of all licensee event reports for LaSalle Nuc1 car Power Station, Unit One, logged during the reporting period, September 1, 1988 through September 30, 1908. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

L1.C.9Etee Event Report Numh9I DA.t1 Title of Occurrenritt 88-020-00 09/26/88 "B" VO Train A Ammonia Detector Trip 88-021-00 09/28/88 "A" VE Oupply Fan Breaker Trip.

f

(

i f

t DOCUMINT ID 0043r/0031r ,

-- - - - , - - - ~ , -

, m_ . . . _ . , -,. -

m ' '

A ;y.

.D i '. p O' ,

i, , .

D. DATA TABULATIOffS

'2 ' ... .

The following' data tabulations avo. presented in this reports

4. .

1. Operating'Deta Report

2. Average Daily Unit Power Level.

s'

, , 3.~ Unit'. Shutdowns and Power Reductions

?

4

!)'

I i

I l

1 J ..

?

i i

1 J

J e

i 1

l

. DOCUMENT ID 0043r/0031r 1

y 4

w-,-- v -- - - . , . , , , . .

i

1. OPERATING DATA REPORT DOCKET NO. 050 '173 .

UNIT LaSplie One DATE Qar/2b er 10, 1988 COMPLETED BY L W. ThunatadL_

TELEPHONE (815)357-67(t1 OPERATING STATUS

1. REPORTING PERIOD: SmptembtL_19Aj_ GROSS HOURS IN REPORTING PERIOD _7,2Q_

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):1121 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net) _.107B

13. POWER LEVEL TO WHICH RESTRICTED (IF ANY).(MWe-Net): None

4. , REASONS FOR RESTRICTION (IF ANY): None TIIIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 _3722.1 23766.6

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1642.0

7. HOURS GENERATUR ON LINE 720.0 __3610.3 23040.3

8. UNIT RESERVE SHUTDOWt HOURS 0.0 0.0 0.0

9. GROSS T;{ERMAL ENERGY GENERATED (MWH) 2269560.- 1Q157120 ft2391418

10. GROSS ELEC. ENERGY GENERATED (MWH) 758701_ 1011602 2042831R_

11. NET ELEC. ENERGY GENERATED (MWH) 725647 3792985 19.42161A_

12. REACTOR SERVICE FACTOR 100.0% 56.6%_. 57.0%

13. REACTOR AVAILABILITY FACTOR 100.0%._ 56.6% 61.0%

14. UNIT SERVICE FACTOR ._10 0. 0% .. . 54.9% 55.3%

15. UNIT AVAILABILITY FACTOR _ _100 . 0% ,_!it. 9% 55.3% -

16. UNIT CAPACITY FACTOR (USING MDC) 97.3% 55.7% 46.0%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 93.5%- 53.5% 44.3%

18. UNIT FORCED OUTAGE RATE 0.0% 3.9% 12.8%

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

None

20. IF SHUT DOWN IS AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

N/A i

l I

1 l

I l DOCUMENT ID 0043r/0031r l

i

. 2. AYZBAGE DAILY UNIT _ POWER LEYIL DOCKET NO: 050-371 UNIT: LASALLE ONE DATE: Qctober 10. 19J1 COMPLETED BY J. W. ThunstedL TELEPHONE: (815) 357-6761 MONTH: SEPTEMBER,.1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (WWe-Net) (MWe-Net)

1. 1041.4 17. 1043.0

2. 1023.9 18. 1035.8 3 978.4 19. 1034.3

4. 936.6 20. 983.1

5. 891.8 21. 1049.0

6. 966.0 22. 1066.3

7. 974.9 23. 1007.7

8. 1006.6 24. 1008.9

9. 911 3 25. 991.1

10. 984.4 26, 1061.8

11. 1004.6 27, 1067.2

12. 1002.3 28. 1064.1

13. 1016.8 29. 1060.5

14. 1004 7 30. 968.1

15. 1004.0 31.

16. 971t2 DOCUMENT ID 0043r/0031r

3. UNIT SHUTDOWNS AND POWER REDUCTIONS

~

DOCKET NO. 050-373 UNIT NAME LaSalle One DATE October 10. 1988 REPORT N0tCH SEPTEMBER. 1988 COMPLETED BY J. *rhunetedt -

TELEPIKMIE (815)357-6761-METHOD OF TYPE SHUTTING DOtet F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POtfER ACTICIES/CODGENTS None 4

I 1

l I

l l

1

\

I l

l l

l I

DOCUMEN'A' ID OC43r/0031r i __ _ ._ . . _ __

.- E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUAT10t[ CONDITICM OF EVENT There were no Safety Relief Valves actuations for Unit One during the reporting period September 1, 1988 through September 30, 1988.

l l

l I

DOCUMENT ID 0043r/0031r

. 2. ECCS System] Outtg:0 Th3 following outag;3 waro takin cn ECCS Sy3tems during the reporting period.

OUTAGE NO. KQUID Gl[I PURPOSE OF OUTAGE 0-234-88 "0" D/G Isolate leaking air-start solenoid to air motor.

0-235-88 "0" D/G Repair ODG035B air-start valve.

1-1684-88 LPCS Pump Megger Motor 1-1689-88 1E22-C302A Repair Compressor.

1-1694-88 1E12-C300D "D" RHR Service Water Pump ,

1-1695-88 1E12-C003 B/C RHR Water Leg Pump 1-1696-88 1E51-C004 RI Motor brush inspection 1-1697-88 1E51-C005 RI Motor brush inpsection 1-1704-88 1E22-C302A DG air fitting 1-1706-88 HPCS D/G Air Compressor Replace Compressor 1-1707-88 "B" D/G Calibrate pressure switches I

i 2 ;

i i

DOCUMENT ID 0043r/0031r l-

3. Off-Sits Doss Calculation Minual No changes to Off-site Dose Calculation Manual during the reporting period.

4. Radioactive Waste Treatment Systems.

No changes to Radioactive Waste Treatment systems during the reporting period.

5. Indications of Failed Fuel Elements No indications of Failed Fuel Elements on Unit One during this reporting period.

1

?

t 1

i i

l i

i i

1 i

l DOCUMENT ID 0043r/0031r

~

LASALLE NUCLEAR POWER STATION UNIT 2 MONTilLY PERFORMANCE REPORT SEPTEMBER, 1988 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 DOCUMENT ID 0036r/0031r

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

1. Amendments to Facility License or Technical Specifications

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

3. Tasts 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 Failed Fuel Elements 1

)

i I

I DOCUMENT ID 0036r/0031r

I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marsellies, Illinois.

Each unit is a Bolling 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 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, 1994.

This report was complied by John W. Thunstedt, telephone number (815)357-6761 extension 2463.

DOCUMENT ID 0036r/0031r 1

4.' II. MONTHLY REPORT FOR UNIT WO A. SUM 4ARY OF OPERATING EXPERIENCE FOR UNIT WO August 1-31 September 1, 0000 hours0 days 0 hours 0 weeks 0 months Unit Two off-31ne, reactor subcritical per Tech Spec compliance due to A.D.S. Inoperability September 3, 0045 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months Reactor critical.

September 3, 1110 hours0.0128 days 0.308 hours 0.00184 weeks 4.22355e-4 months Generator on-line, ramping to 750 MWe.

September 16, 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months Ramping down to 512 MWe to complete various surveillances.

September 30, 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months Unit Two on-line, reactor critical, 665 MWes unit is in coastdown for refuel.

DOCUMENT ID 0036r/0031r

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

1. Amendments to Facility license or Technical Specification.

Amendment 39 Resolved difference in Suppression Pool hi-level switch setpoints.

Amendment 40 Provided additional requirements for monitoring core performanmce in high-power / low-flow regions.

2. Changen to procedures which are described la the Safety Analysis Report.

There were no changes to procedures which are described in the Safety Analysis Report.

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

There were no tests or experiments conducted which are not described in the Safety Analysis report.

4. Corrective Maintenance of Safety Related Equipment.

The following table (Tnble 1) presents a summary of Safety-Helated Maintenance completed on Unit Two during the reporting period. The headings indicated in this summary includes Work Request number, Component Name, cause of malfunction, results and effects on safe operation, and corrective action.

5. Completed Safety Related Modifications.

The following table (Table 2) presents a list of completed Modifications during this reporting period. Each entry will have a short synopsis explaining details involved with each modification.

DOCUMENT ID 0036r/0031r

w TABLE 1 CORRECTIVE MAINTENANCE OF SAFETT RELATED EQUIPMENT Unit 82 RESULTS AND EFFECTS WORK REQUEST COMPCNENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L65026 2VR05YA Solenoid Excessive Wear Radiological release Replaced solenoid valt.es valves L81846 2E31-N0llA MS High- Loose packing Inoperable instrument Tightened packing Flow Detector L81847 2E31-N0llA MS High- Fitting leaking Inoperable instrument Tightened fitting Flow Detector L83186 2VQO37 Containment Debris in valve Inoperable valve Cleaned valve isolation valve L83316 2CM057J Temperature Instrument drift Inoperbale instrument Recalibrated instrument Indicator L83419 2INO35 Control Excessive wear Slow to respond Replaced worn elements valve L83791 2C11-N616C fuse 2B21-N702C faulty Half-scram Replaced 2B21-N702C L83800 2E12-N015A RHR Flow Instrument failed Loop inoperable Replaced transmitter Indicator L83990 2C41-F029B Relief Ruptured bellows Valve leaked Repaired valve ,

Valve L84084 CD18-N535 WRGM Flow Check valve sticking Erratic flow indication Cleaned valve Indicator L84089 OVC-165A Ammonia Fan HY chem cassette No level indication Replaced cassette Detector L84107 2C51-K605GH APRM B Faulty power supply Erratic indication Replaced power supply L84131 2C51-K605GR APRM Faulty power supply Erratic indication Replaced power supply DOCUMENT ID 0036r/0031r

TABLE 2 COMPLETED SAFETY RELATED MODITICATIONS i

HQDIFICATICH_NUNSERL A brief Synopsis of Incorporated Modification Objectives with i final design resolution. ).lso, state reviewed or unreviewed safety questlo'as.

UNIT TWO M-1-2-86-089 Snubber reduction on subsystem 2DG-03 and permanently ,

removing snubber and replacing the snubber with a rigid ,

support. Per Snubber Reduction Program. (

M-1-2-87-087 Snubber reduction on subsystem arrangement of MSIV Leakage 1 Control piping by permanently removing snubber. Per !

Snubber Reduction Program.

i L

t 4 ,

f I

)

i i

i I L d

i i

I r

t 1

1 DOCUMENT ID 0036r/0031r 4

e 0

C. LICENSEE EVENT REPORTS The following la a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, July 1, through July 31, 1988. This information js provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

LICRAtte Event Report Number DRtg Title of Occurrence 88-011-00 09/01/88 RCIC Steam Isolation Auto Closure instrument not properly returned to service due to procedural inadequacy.

f e

]

j l

l 1

4 4

i

! DOCUMENT ID 0036r/0033r

~1 s

o ?.

. g. ,

D. DATA TABULATIONS The follow 4ng data tabulations are presented in this reportt

/> 1. Operating Data Report 5

2. Average Daily Unit Power Level

, 3. Unit Shutdowns and Power Reductions s.

i.

4 i

I 4

4 e

DOCUMENT ID 0036r/0031r

s ... g

\

0

.!\

Os

\ 1. OPERATING DATA REPORT t DOCKET NO. 050-374 UNIT LaSalle Two DATE October 10, 1988,

' COMPLETED BY J. W. Thuantedt TELEPHONE (815)357-6761 OPE. ATING STA'IUS

1. . A ' PORTING PERIOD: Septasaber. '198tLGROSS HOURS IN REPORTING PERIOD: _720

2. Cb RENTLY AUTHORIEED POWER LEVEL (MNt):1121 MAX DEPEND CAPACITY (Mh -Net) .1036 DESIGN ELECTRICAL RATING (MNa-Net.) _1078

3. POWL LEVEL TO WHICH RESTRICTED (IF ANY) (MNo-Met): 847.5-757.1

4. REASO65 FOR RESTRICTION (IF ANY): Fuel Depletion (CgAgidnun)

THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER s T HOURS REAC'!OR WAS CRITICAL . 6 71. 3 _ __ _j306.8 23109.6.

6. REACTOR ,ESERVE SHUTDOWN HOURS 0, Q__,

0.0 29.8

7. HOURS GER RATOR ON LINE 660.8 - _6272.5_ 12743.6

8. UNIT RESE1TE SHUTDOWN HOURS 0.0 0.0 O dL_.

9. GROSS THERh 'AL ENERGY GENERATED (NWH) 2 1 1 H 5 D._ M H3312 1603831t_

10. GROSS ELEC. ENERGY GENERATED (MWH) 758701_ _1913Q12._ 11H1218._

11. NET ELEC. EntRGY GENERATED (MWH) 725647 _1747468- 20830081

12. REACTOR SERV 1 'E FACTOR 93.2% 95.9% 66.7%

13. REAC'IOR AVAILA?ILITY FACTOR J J 2%_ 95.9%,, 66.8%

14. UNIT SERVICE FACTOR 91A 95.4%_ 65.6%

15. UNIT AVAILABILITY FACTOR 91.8% 95.4%_ 65.6%.

16. UNIT CAPACITY FACTOR (USING MDC) 97.3% 84.4% 58.0%

17. UNIT CAPACITY FACTOR (USING DESIGN MNo) 93.5%- 81.1%- 55.8%

18. UNIT FORCED OUTAGE RATE 8.2) 4.2%- 16.7%_

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

Refueling, 10/15/88, 15 weeks.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STAR'IUP: N/A 1

i t

i 1

i, DOCUMENT ID 0036r/0031r

2. AVERAGE DAILY UNIT POWER LEVEL

. '.9 DOCKET NO: 050-374 UNIT: LASALLE 'Df0 DATE: October 10. 1938 COMPLETED BY:_J.phn W. Thunstedt TELE'/ HONE : (815).357-6761 MONTH: SEPTEMBER. 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -8.0 17. 623.1

2. -7.2 18. 693.0

3. 89.8 19. 683.2

4. 533.0 20. 688.8

5. 729.2 21. 684.2 I

6. 725.8 22. 678.5

7. 727.5 23. 678.8

8. 727.7 24. 675.1

9. 722.0 25. 669.0

10. 712.2 26. 666.9

11. 709.2 27, 663.0

12. 102 3 28. 656.8

13. 703.8 29. 653.8

14. 694.0 30. 643.4

15. 690.0 31.

16. 679.0 DOCUMENT ID 0036r/0031r

e i E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT There were no Safety Relief Valve actuations during the reporting period September 1, 1988 through September 30, 1988 for Unit Two.

4 l

i i

i t

i i

P

.i DOCUMENT ID 0036r/0031r F

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

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

- s

3. UNIT SHUTDONNS AND POWER REDUCTIONS DOCKET NO.- 050-374 *-

UNIT NAME LaSalle Two DATE Ocenhor 10. 1988 REPORT MONTH SEPTDmre. 1988 CC3dPLETED BT J. rhnantedt TELEPHONE f815)357-6761 ME"IHOD OF TYPE SHUITING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS /CObe6ENTS 14 F 59.2 D 1 Shutdown to comply with T.S. ADS Div. I & II Inoperative due to IN system problems.

DOCUMENT ID 0036r/0031r

o.

't.

/ 2. 'ECCS System 3 Outtg38 1

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

OUTAGE NO. EQUIPMENT PURPOSE OF OUTAGE 2-476-88 2E12-F052A EQ MOV Inspection 2-482-88 2B RHR Service Water Replace vent valve 2-483-88 2Dr035 EQ MOV Inspection 2-484-88 2E12-F049B EQ MOV Inspection 1: 2-285-88 2E12-F003A EQ MOV Inspection 2-495-88 2E12-r049B Remove Limitorque operator 2-499-88 2DG035 Change Limitorque grease 2-501-88 2DG035 Keep jack on and valve open c

2-506-88 2E12-F006A & 2A EQ MOV Inspection !

r 2-508-88 RI Vacuum Pump Motor Inspection 2-509-88 RI Condensate Pump Motor Inspection 2-522-88 2DG035 Admin Control i 2-525-88 2DG035 Admin Control- i r

4 i

1 4

l i

+

1 1

i l

l l

l DOCUMENT ID 0036r/0031r l

l L

5,,-

- j 3. Off-Sito Domo Calculation Mtnual No changes to the Off-Site Dose Calculation Manual during this reporting period.

4. Radioactive Waste Treatment Systems.

No changes to Radioactive waste treatment systems during this reporting period.

5. Indications of ralled Fuel Elements.

i Off Gas levels indicate that there is one pinhole Fuel Element failure L in the reactor vessel. This does not represent a change from the previous reporting period.

There were no further Indications of failed fuel elements during this ,

reporting period. .- *!

4

?

i 1

1 t

i t

l

)

i i

i DOCUMENT ID 0036r/^031r

.i

,,, Commonw:alth Edison f C LaSalle County Nuclear Station RuralRou'.e 81 Box 220 V Marseilles, Illinois 61341 Telephone 815/357 6761 a

October 10, 1988 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Hall Station F1-137 Washington, D.C. 20555 ATnt Document Control Desk

"_ ' . J 'a

. . ..>g Utntlement 2nclosed for your information is the monthly performance report covering LaSc11e County Nuclear Power Station for the period September 1, 198u through

?-

Seatember 30, 1988.

Very truly yours, it N G, J.Diederichd/t///

Station Manager LaSalle County Station GJD/JWT/sjc Enclosure xc A. B. Davis, NRC, Region III HRC Resident Inspector LaSalle Garv Wright, Ill. Dept. of Nuclear Safety P. Shm anski, NRR Project Manager D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center L. J. Anastasia, AIP Coordinator, Nuclear Services H. A. Ortin, GE Residant H. E. Bliss, Manager of Nuclear Licensing W. F. Haughton, Nuclear ruel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle Dennis Carlson/ Tech Staff Terry Novotney/INPO Coordinator, Tech Staf f Central File i I DOCUMENT ID 0043r/0031r

- - - - - _ _ _ _ _ _ - _ __

ML20207N612

Text

Navigation menu

Search