ML20235V415

Monthly Operating Repts for Sept 1987

ML20235V415
Person / Time
Site:	LaSalle
Issue date:	09/30/1987
From:	Diederich G, Kirchner G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
0043R-0031R, 43R-31R, NUDOCS 8710150143
Download: ML20235V415 (34)

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LASALLE NUCLEAR POWER STATION yy..? ' ,

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' MONTHLY PERFORMANCE REPORT b -j c SEPTEMBER 1987 l

COMMONWEALTH EDISON COMPANY

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TABLE OF CONTENTS

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I? I. INTRODUCTION I p

b II.' MONTHLY REPORT.FOR UNIT ONE

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, A. Summary of Operating Experience B.. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED

. MAINTENANCE o

ir-. '1. . Amendments.to Facility. License or Technical Specifications  !

2. Facility or Procedure Changes Requiring NRC Approval

'3. Tests and Experiments Requiring NRC Approval '

4. Corrective Maintenance of Safety Related Equipment

5. Completed Safety Related Modifications.

' C. LICEMSEE 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 y - 11 Main Steam Relief Valve Operations k

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  !

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l DOCUMENT ID 0043r/0031r r

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

Bach unit is a Boiling 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. l 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 commenced on January.1, 1984.

This report was compiled by Gregory J. Kirchner, telephone number (815)357-6761, extension 704.

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z-_ _ .-

]Y g II : MONTHLY REPORT FOR' UNIT ONE s 4 F-^ , . Al

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE.

e sept. -1, 1987 q 1 ..i 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />;.- .0 MWe, Generator off-line due to outage.

Sept.' 15, - 1987 -

1343 hours0.0155 days <br />0.373 hours <br />0.00222 weeks <br />5.110115e-4 months <br />; Reactor at 10 MWe, Generator synched-to GRID. Ramping up to i

'200 MWe, r-pept.16, ' 1987 I 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />; U-l' Generator'taken off-line.

0322 hours0.00373 days <br />0.0894 hours <br />5.324074e-4 weeks <br />1.22521e-4 months <br />; Rx scram due to low level caused by MDRFP trip. (GCRAM from 37% Rx power)'.

- Sept . 18, 1987 1746 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.64353e-4 months <br />; Generator synched to grid ramping up to 345 MWe.

Sep t . 19, 1987 t-1000 hours; Generttor on line, ramping to 390 MWe. .j 4

g_eg 21, 1987 1415' hours; Generator.on line,. ramping to 620 MWe, ,

Sept. ~ 23, 1987 I 1

0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />; Ramping at 10 MWe/hr. to 916 MWe, 3 pept. 24, 1987

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- 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />; . Drop load to 532 MWe to take data.  ;

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1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />; Ramping at 10 MWe/hr. to 982 MWe.  ;

i Sept.' 29, 1987 1 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; Drop 130 MWe'to 855 MWe per L.D. )

0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br />; . Ramp at 10 MWe/hr. to 990 MWe, 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br />; L.D. dropped load to 850 MWe.

Sept. 30, 1987 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />; Ramp at 10 MWe/hr. to 956 MWe.

2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br />; Drop unit to 860 MWe per L.D. Generator on line. 4 1

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B.u _ PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED I- MAINTENANCE. '

1. Amendments.to Facility License or Technical Specification. J i

There were no Amendments to the facility license or Technical ]

Specifications during this reporting period. j 1

2. Facility or Procedure changes requiring NRC. approval.

.There were no Facility or procedural changes requiring NRC approval j during this reporting period. I l

3. . Tests and Experiments requiring NRC approval, f There were no tests or experiments requiring NRC approval during .

this reporting period.

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4. Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a Summary of j safety-related maintenance completed on Unit One during the. j reporting period. The headings indicated in this summary include: i 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.

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1 TABLE 2-I COMPLETED SAFETY RELATED MODIFICATIONS j U-l MODIFICATION NUMBER: A brief synopsis of incorporated modification objectives with final design resolution. Also, state reviewed or l unreviewed safety questions.

I M-1-1-87-056 This Modification was to facilitate the removal and I reinstallation of the Recirculation IB pump internals and motor during the repair of the IB pump. There were no i unreviewed safety questions.

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C. L'ICENSEE EVENT REPORTS l

The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit one, logged during the reporting l

period, September 1, 1987 through September 30, 1987. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Licensee Event Report Number Date Title of Occurrence 87-030-00 9/2/87 Scram Signal During LIS-RP-107, Improper Communication Technique between NSO and '

Electrician.

87-031-00 9/5/87 Less of IB RPS M-G Set.

87-032-00 9/17/87 Rx Scram on Low Level During Shut Down.

87-033-00 9/17/87 Failure of l'A' Diesel Generator to Close Onto 142Y.

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f D.. ~ DATA TABULATIONS The-following data tabulations are presented in.this report:

l.-Operating Data Report <

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2. Average Daily Unit Power Level f j

3. Unit Ghutdowns and Power Reductions j

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DOCUMENT ID 0.043r/0031r

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1. . OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE October 10, 1987 -'

COMPLETED BY G. J. Kirchner  ;

TELEPilONE (815)357-6761 l

OPERATING STATUS

1. REPORTING PERIOD: September, 1987 GROSS llOURS IN REPORTING PERIOD: 720

2. CURRENTLY AUTilORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY l (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078

3. POWER LEVEL TO WitICil RESTRICTED (IP ANY) (MWe-Net): 1050

4. REASONS FOR RESTRICTION (IF ANY): Administrative TitIS MONTil YR TO DATE CUMULATIVE 5 NUMBER OF llOURS REACTOR WAS CRITICAL 330.45 3474.05 12399.95

6. REACTOR RESERVE SilUTDOWN liOURS 0.0 0.0 1642.0 l

7. IlOURS GENERATOR ON LINE 306.51 3335.4 12137.35 ~

8. UNIT RESERVE SilVTDOWN llOURS 0.0 0.0 0.0 -]

9. GROSS TilERMAL ENERGY GENERATED (MWit) 722664 7079352 34357792

10. GROSS ELEC. ENERGY GENERATED (MWil) 228440 2275264 11329244 j

11. NET ELEC. ENERGY GENERATED (MWil) 212670 2148647 10717172

12. REACTOR SERVICE FACTOR 45.9% 53.03%' 37.7%

i l 13. REACTOR AVAILABILITY FACTOR 45.9% 53.03% 42.7%

l 14. UNIT SERVICE FACTOR 42.6% 51.0% 36.9%

15. UNIT AVAILABILITY FACTOR 42.6% '51.0% 36.9%

16. UNIT CAPACITY FACTOR (USING MDC) 28.5% 31.6% 31.5%  ;

17. UNIT CAPACITY FACTOR (USING DESIGN l MWe) 27.4% 30.4% 30.76 _

l 18. UNIT FORCED OUTAGE RATE 17.2% 14.7% 8.7%

SilUTDOWNS SCllEDULED OVER NEXT 6 MONTilS (TYPE, DATE, AND DURATION OF EACH).

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N/A

20. IF SliUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A 1

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1 DOCUMENT ID 0043r/0031r

52 . AVERAGE DAILY UNIT POWER LEVEL-

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s DOCKET NO: 050-373~ .

UNIT: LASALLE ONE DATE: October- 10, 1987' COMPLETED BY: Gregory Kirchner .

TELEPHONE: (815) 357-6761 ;f

MONTH: SEPTEMBER, 1987

' DAY AVERAGE DAILY POWER' LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)' (MWe-Net) l

' 1. -15 17. -5

'2. -15 18. 25 h -15 19, 347 3 =-

, 4. -16 20. 368

5. -16 21. 553 __

i 6 '. -16 22. 765_ _ q

.7. -16 23, 851 .

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-8. '-16 24. 660

9. -16 25. '814

10. -16 -26. 921

11. -15 27. 925

12. -15 28. 894  !

13. -15 29, 879 i

f, 14. -16 30. 866 l

15. +52 31.

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E' UNIQUE REPORTING REQUIREMENTS r ..

1. Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT l'

There were no Safety Relief Valves Operated for Unit One during this reporting period. -

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2. ECCS Systems'Outcgss

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

i Ot]TAGE NO. EQUIPMENT PURPOSE OF OUTAGE l

U-1 1-934-87 lE12-F004A Repair Torque Switch  ;'

l-940-87 IB21-F002 Repair Snap Ring 1-942-87 .1B21-F019 Repair Throttling Problem-1-957-87 1851-F064 Preserve Primary Containment 1-1002-87 IB21-F423B Repair Limitorque 1-1016-87 16B 11tr Level Switch Repair Flange 1-1012 'B' First Stage MSR Repair Leak at lilD134B Drain Tank L-1014- 87 IB21-F533 Repack i 1-1041-87 D/G 1 'A' Air Move Power Supply Compressor i

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d -i -3; Off-Sito Dosa Calculation Manual j i

There were no changes to the ODCM during this reporting period. )

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4. Radioactive Waste Treatment Systems.

There:were no changes to the Radioactive Waste Treatment Systems f during this reporting period.

5. Indications of Failed Fuel Elements There were no indications of Failed Fuel Elements during this reporting period.

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. LASALLE NUCLEAR POWER STATION UNIT 2 i

MONTilLY PERFORMANCE REPORT SEPTEMBER, 1987 COMMONWEALTil EDISON COMPANY l

NRC DOCKET NO. 050-374 LICENSE NO. NPP-18 l

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l-DOCUMENT ID 0036r/0005r L__---___ - . _ .__ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ]

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-TABLE OF CONTENTS' I'

l- I. INTRODUCTION II. MONTitLY REPORT FOR UNIT TWO A. Summary of Operating Experience B. PLANT OR PROCEDURE Cl!ANGES, TESTS, EXPERIMENTS, AND SAF8TY RELATED MAINTENANCE

1. Amendments to Facility License or Technical Specifications

2. Facility or Procedure Changes Requiring NRC Approval

3. Tests and Experiments Requiring NRC Approval

4. Corrective Maintenance of Safety Related Equipment

5. Completed Safety Related Modifications C. LICENSEE EVENT REPORTS

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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 S. Indications of Failed Fuel Elements I

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e e I .' INTRODUCTION I 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 Boiling Water Reactor with a designed net electrical  ;

output of 1078 Megawatts. Waste heat is rejected to a man-made cooling l 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, 1984. } ;

This. report was compiled by Gregory J. Kirchner, telephone number

~ (815)357-6761 extension 704.

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II. MONTitLY REPORT FOR UNIT TWO A. '

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT TWO 9/01/87 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Unit at 1115 MWe, Generator on Line.

0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> Drop 75 MWe to switch condensate pumps. Unit at 1040 MWe.

0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> Ramp at 10 MWe/hr to 1122 MWe.

9/03/87 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> Drop 200 MWe per L.D. Unit at 922 MWe, 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> Ramp at 10 MWe/hr. to 1123 MWe.

9/10/87 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> Drop power to 928 MWe for Control valve testing and CRD exercising.

1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> Increase Rx power at 10 MWe/hr. to 1110 MWe.

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9/18/87 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> Drop 65 MWe for CRD exercising to 1045 MWe.

0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> Ramp up to 1104 MWe at 10 MWe/hr.

9/24/87 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> 50 MWe/hr drop due to CRD exercising Rx at 1054 MWe.

9/25/87 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> Ramp at 10 MWe/hr M 1111 MWe.

.9/30/87 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> Rx holding steady at 1104 MWe. Generator on line.

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B. , PLANT'OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY REl.ATED MAINTENANCE.

1. Amendments to Facility license or Technical Specification.

There were no Amendments to the facility license or Technical Specifications during this reporting period.

2. Facility or Procedure changes requiring NRC approval.

There were no Facility or procedure changes requiring NRC approval during the reporting period. .

3. Testa and' Experiments requiring NRC approval.

There were no Tests or Experiments requiring NRC approval during the reporting period.

4. Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a summary of Safety-Related Maintenance completed on Unit Two during the reporting period. The headings indicated in this summary include: 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 i a short synopsis explaining details involved with each l modification, i

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MODIFICATION NUMBER: A brief Synopsis of Incorporated Modification Objectives with l final design resolution. Also, state reviewed or unreviewed j safety questions.

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There were no Safety related Mods completed during this reporting period. l l

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i C. LICENSEE EVENT REPORTS l

The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, September 1, through September 30, 1987. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.~13. j Licensee Event Report Number Datg Title of Occurrence N/A I

i DOCUMENT ID 0036r/0005r

D. DATA TABULATIONS The following data tabulations are presented in this report:

1. Operating Data Report

2. Average Daily Unit Power Level

'3. Unit Shutdowns and Power Reductions i

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1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE October 10, 1987 COMPLETED BY Greoory Kirchner TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: September GROSS llOURS IN REPORTING PERIOD: 720

-2. CURRENTLY AUTilORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Ne t): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078

3. POWER LEVML TO VHICil RESTRICTED (IF ANY) (MWe-Net): 1050

4. REASONS FOR RESTRICTION (IP ANY): Administrative THIS MONTH YH TO DATE CUMULATIVE 5 NUMBER OF 1100RS REACTOR WAS CRITICAL 720 2572.34 14575.79

6. REACTOR RESERVE Ul!UTDOWN llOURS 0.0 0.0 29.83__

7. ILOURS GENERATOh ON LINE 720 2490.91 14262.13

8. UNIT RESERVE.SliUTDOWN llOURS C.0 0.0 0.0

9. GROSS TilERMAL ENERGY GENERATED (MWil) 2359608 7559184 41073448

10. GROSS ELEC. ENERGY GENERATED (MWH) 789702 2491461 13553033

11. NET ELEC. ENERGY GENERATED (MWH) 764985 2365543 12905772

12. REACTOR SERVICE FACTOR 100% 39.3% 56.3%

13. REACTOR AVAILABILITY FACTOR 100% 39.31 56.4%

14. UNIT SERVICE FACTOR 100% 38%

• 1%

15. UNIT AVAILABILITY FACTOR 100% 38% _ _ _ ,55.1%

16. UNIT CAPACITY FACTOR (USING MDC) 100% 34.8% 48.2%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 98.6% 33.5% 46.3%

18. UNIT FORCED OUTAGE RATE N/A 2.2% 23%

19. SilVTDOWNS SCllEDULED OVER NEXT 6 MONTilS (TYPE, DATE, AND DURATtON OF EACli):

N/A

20. IF Sl!UT DOWN AT END OF 5% FORT PERIOD, ESTIMATED DATE OF STARTUP N/A l

l DOCUMENT 3D 0036r/0005r 1

i. J ~2. AVERAGE DAILY UNIT POWER LEVEL

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. DOCKET NO:- 050-374 UNIT: LASALLE TWO' DATE: October 10, 1987-

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r, COMPLETED BY:' Gregory Kirchner

' TELEPHONE: (815) 357-6761:

. MONTH: SEPTEMBER 1987-l-l9 ,

DAY. AVERAGE" DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL g, '(MWe-Net) .

-(MWe-Net) i, 9,.

1. 1078' 17. '1065 p' ,

'2.- 1062 18. 1047 3 103'1 19. 1056-4 .' 1076 20. 1063

5. 1074 '21. 1061

6. '1071 22. '1061'

.7. 1067 23. 1059

8. 1066 24. 1056

9. 1064 25 .- 1047

10. 1031' 26. 1064 J11.- 1069 27. 1063

12, 1068 28. 1064

13. 1071 29. 1061 l

1070 '30. 1059 I 14 . _

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E. UNIQUE REPORTING REQUIREMENTS 1

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1. Safety / Relief Valve Operations for Unit Two.

1 DATE VALVES NO & TYPE PLANT DESCRIPTION l ACTUATED ACTUATIONS CONDITION. OF EVENT There were no Safety / Relief Valve actuations during this reporting period.

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

UNIT 2 OUTA04 NO EQUIPMENT PURPOSE OF OUTAGE 2-1672-87 2B21-RSSV2 Repack Valves l

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DOCUMENT ID 0036r/000Sr L-_________________-_ _ _ _ _ - - _ _ _ _ _ _ _ _

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7, ! 33 'offisite Doss calculation Manual (U-2) ]

There were no' chariges to the ODCM during this : reporting period.

4. ; Radioactive Waste Treatment Systems.

There were no changes to the' Radioactive Waste Treatment Systems during:this period.

f 5 '. ' Indications of Failed Fuel Elements.

There'were no indications'of failed fuel elements during this.

reporting period.

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.f X 'Commonr;=lth Edison

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_ Z) . LaSalta County Rur:I Route Nuclear

1. 1, Box 220 Station

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Marseilles, Illinois 61341 j/

L\ Telephone 815/357-6761 October- 10, 1987 Director, Office of Management Information and Program Control-United States Nuclear Regulatory Commission

. Washington, D.C. 20555 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for the period September 1, 1987 through September 30, 1987.

Very truly yours, no. L4 >

G. J. Diederich Station Manager LaSalle County Station GJD/GJK/jdp Enclosure xc: J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety P. Shemanski, NRR Project Manager D. P. Galle, CBCo D.' L. Farrar, CBCo l

'INPO Records Center L'. J. Anastasia, PIP Coordinator SNED M. A. Ortin, GE Resident j H. E. Bliss, Nuclear Fuel. Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle e Dennis Carlson/ Tech Staff *

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-Terry Novotney/ Training i Central File DOCUMENT ID 0043r/0031r y

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