ML20236M355

Monthly Operating Repts for Oct 1987

ML20236M355
Person / Time
Site:	LaSalle
Issue date:	10/31/1987
From:	Diederich G, Kirchner G COMMONWEALTH EDISON CO.
To:	NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
0043R-0031R, 43R-31R, NUDOCS 8711130101
Download: ML20236M355 (36)

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LASALLE NUCLEAR FOWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT.

OCTOBER 1987 COMMONWEALTH EDISON COMPANY l

i NRC DOCKET NO. 050-373 i LICENSE NO. NPF-11 I 1

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8711130101 871031 PDR ADOCK 05000373 R PDR h.nP\LY m e _ T ze oo43 oo m i[f

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~v .s TABLE OF CONTENTS I.: - INTRODUCTION 1

II. . MONTHLY REPORT FOR UNIT ONE .

A. Summary of' Operating Experience ,

f B. PLANT OR PROCEDURE CHANOES,' TESTS, EXPERIMENTS, AND. SAFETY RELATED-MAINTENANCE

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1. Amendments.to' Facility License or Technical Specifications: l C

2. . Facility'or Procedure Changes Requiring NRC Approval i

3. Tests and Experiments Requiring NRC_ Approval

4. Corrective Maintenance of Safety Related Equipment i

< 5. " Completed Safety Related Modifications.

C. LICENSEE EVENT REPORTG L

l D. DATA TABULATIONS j L i

1. Operating Data Report l

2. Average Daily Unit' Dower Level l

3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS I

1. Main Steam Relief Valve operations

2. ECCS System Outages-

3. Off-Site Dose Calculation ~ Manual Changes I 4. Major Changes to Radioactive. Waste Treatment System S. Indications of Failed Fuel Elements l

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I I. INTRODUCTION I

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

q 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 pond using the Illinois River for make-up and blowdown. The .

architect-engineer was Sargent and Lundy and the primary construction I contractor was Commonwealth Edison Company. l

. Unit one was issued operating license number NPF-ll on April 17,1982.

Initial criticality was achieved on June 21, 1982 and commercial power operstion was commenced on January 1, 1984 This report was compiled by Gregory J. Kirchner, telephone number l (815)357-6761, extension 7104.

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, II n- MONTHLY REPORT.FOR UNIT ONE' ,

A. SUt9fARY OF OPERATING EXPERIENCE FOR UNIT,0NE ,

10-1-87 ' 0000 Rx at 866~MWe and ramping to 996,at id'MWe/hr.' Generator

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online. l 10-5-87 0100 Drop Ex power to 880'MWe for' load dispatcher. i 10-6-87 0900 Drep Rx power to 858'MWe due.to rod 46-15 position drift.

1200 Fast ramp to 1020 MWe, 2300 Drop Ry power to 915 MWe for load dispatcher, (LD)[ i 10-7-07 0500 Ramp up'to 1026 MWe at.10MWe/hr.

10-11-87 0300 ' Drop Rx power to 964 MWo for load dispatcher.. l 0500 Ramp up to 1004 MWe'at.70MWe/hr.

10-12-87 0100 Drop Rx power to.894 MWe for loadidispatcher, i 10-13-87 0400 Ratap up to 1011 MWe at.10 MWe/hr.

10-14-87 0300 Drop Rx power 858 MWe for load dispatcher.  !

l 0500 Ramp up to 1010 MWe at 10MWe/hr. )

! l 10-15-87 0100 Drop Ex power to 940 MWe for load' dispatcher.

L l 0400 Ramp up to 1012 MWe at.10 MWe/hr.' )

.i 10-18-87 0100 Drop Rx power'to 842 MWe for LD.-

! 10-19-87 0400 Ramp up to 1025 MWe at 10 MWe/br.- l l '10-21-97 2300 Drop Rx power to 859 MWe for CRD exercising, turbine valve i

surveillance. I 10-22-87 0500 Ramp up to 1028 MWe at 5;NWe/hr. -j l

10-25-87 0100 Drop load to 843 MWe for LD. .I 0800 Ramp up to 989 MWe'at 5 MWe/hr.  ;

10-28-87 2000 Drop 150 MWe for CRD exercising...Rx.at 838 MWe.

10-29-87 0200 Ramp up to 1020 MWe at 5 MWe/hr. Ji I

10-31 0200 Drop Rx power to 865 MWe for LD., -g 0400' . Ramp up to 1004 MWo at 10 HWe/hr.

l- 2400 Rx power at 1004 Mwe,-generator,on line.

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-. B '. . PIN T'OR PROCEDURE CHANGES, TESTS, EXPERIMENTS.AND SAFETY'RELATED 9"

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1. Amendments to' Facility License or Technical Specification.-

' Amendment No. 51 - This Amendment revise's the LaSalle County'. .

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Station, Unit 1 Technical Specifications to perform thetrequired; i

snubber functional' testing'in' approximately 22 monthsLiL25C instead _

of 18' months 1 25% on a one-time-basis.: y j 2.

Facility'or procedure changes requiring NRC approval.

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'There'were no Facility or Procedural changes requiring NRC' approval -l during'this reporting period. '

3. Tests and Experiments requiring NRC. approval.

There were no tects or experimenid requiring NRC approval during this reporting period.'

4. Corrective Maintenance of. Safety Related Equipment. ,

The following table (Table 1) presents a Summary of ,

safety-related maintenance conpleted on Unit one during the,4 ,

I reporting period. The headings indicated.in this summary. include:

! Work Request number, Cceponent Name, Cause' of Malfunction,' Results-l- and Effects on Safe Operation, and Corrective Action.

l 5, Completed Safety Related Modifications.

l The Ecllowing Table (Table 2) presents a list of completed Modifications during this reporting period. ~Each entry will have a l

L short synopsis explaining details involved with each modification.

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TABLE 2 .

COMPL.ETED SAFETY RELATED MODIFICATIONS U-l MODIFICATION NUMBER: A brief synopsis of incorporated modification objectives..

with final design resolution. Also, state reviewed or unreviewed safety questions. ,

M-1-2-82-205 This Modification was to separate the Division I steam leakoff solenoid valves into two (2) separate circuits.

There were no unreviewed safety questions.  ;

M-1-1-87-044 This modification concerned RilP shutdown COJling Valve lE12-F009. It replaced the valve stem arcd existing  ;

limitorque operator (model number SB-0) with a larger ]

operator. There were no unreviewed safety questions.

M 1-87-055 This modification was to facilitate tha removal and reinstallation of the recirculation IB pump. There were no unreviewed safety questions.

M 1-87-056 Same as M-1-1-87-055 above. 'i l

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C. LICENSEE EVENT REf.> ORTS \ .

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LaSalle Nuclear' Power Station, Unit One, 16 ed during the reporting . , .r, period, October 1, 1987 through October 31, 1987. This inforrstion is

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'D. ' DATA TABULATIONS ,

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1. Operating Data Report- <

2. ~ Average Daily Unit Power Level

3. Unit Shutdowns and Power Reduct ions

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1. .OPERQTING DATA REPORT .,

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" DOCKET NO. 050-373 UNIT LaSalle One

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DATE November 10, 1987 y COMPLETED BY G. J. Kirchner .'~ t

. TELEPHONE (815)357-6761 -

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OPERATING STATUS 1

f 1. REPGRTING PERIOD: November, 1987 GROSS HOURS IN REPORTING PERIOD: 745

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEstD' ' CAPACITY

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(MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): )M78_.

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): 900 l

4. REASONS FOR RESTRICTION (IF ANY): Administrative f i THIS MONTif,YR TO DATE CUMULATIVE i7- 3 5 NUMBER OF HOURS REACTOR VAS CRITICAL 745 _ ' J 219.I 13145  %

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1642.0

7. HOURS GENERATOR ON LINE 745 < 4080.4 12882.4 j

8. UNIT RESERVE SHUTDOWN HOURS 0.0[ d.0 36533704 0.0 l I

9. GROSS THERMAL EMERGY GENERATED (MWH) 2175912 9255264

10. GROSS ELEC. ENERGY GENERATED (MWH) 731015_ 3006279 12060259

11. NET ELEC. ENERGY GENERATED (MWH) 705605 2854252 11422777 ij

12. REACTOR SERVICE FACTOR 100% 57.8% 39.1%

! 13. REACTOR AVAILABILITY PACTOR 100% 57.8% 44.0%

6

14. UNIT SERVICE FACTOR 100g _56 0% 38.3% I l 15. UNIT AVAILABILITY FACTOR 190% SG.U% 38.3% H j

16. UNIT CAPACITY FACTOR (USING MDC) 91.4% g 37.8% 32.8% j z

l ) 17. UNIT CAPACITY FACTOR (USING DESIGN ,  ;

i MWe) .) 87.90' _36.3% 31.5% ,

I e 18. UNIT FORCED OUTAGE RATE J y N/A 12.4% 19.65

SHUTDOWNS SCHEDULED OVER NEXT 6 MONTi4'S (TYPE, DATE, AND DURATION OP 'EACH) . ,

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19.  ;

N/A 4 ( , l

20. I SHUT DOWN AT END OF REPORT EERIOD, ESTIMATED DATR OF STARTUP: N/A l

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2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: November 10, 1987 )

COMPLETED BY: Gregory Kirchner TELEPllONE: (815) 357-6761 MONTil: OCTOBER, 1987 -

i DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) .,

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2., 947 18. 832 I l 3 941 19, 972_  ;

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11. 962 27. 973 1

.12. 965 28. 948 l

13. 943 29. 935

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1. Safety / Relief valve operations for Unit One. i VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT i i

There were no Safety Relief Valves Operated for Unit One during this reporting )

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

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! OUTAGE NO. EQUIPMENT PURPOSE OF OUTAGE l U-l I i l l-1049-87 IB D/G Repair Differential Pressure indicator 1-1053-87 RCIC Prevent Pump Run.

1-1059-87 RCIC Turbine Change Oil 1-1060-87 0 D/G Air Compressor "A" Revise Wiring for air dryer.

1-1062-87 RCIC Turbine Repair oil leaks.

1-1101-87 lE51-F045 Turbine Supply Repair Control circuit. l Valve f i

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Off-Site Doss Calculation Minual 3.

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

4. Radioactive Waste Treatment Systems.

There were no changes to the Radioactive Waste Treatment Systems during this reporting period. 4-l S. Indications.of Pailed Fuel Elements Off gas levels indicate that no failed fual elements exist in the l

reactor. This has not changed since the last reporting period.

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-LASALLE NUCLEAR POWER STATION .

UNIT 2- ..

MONTHLY PERFORMANCE REPORT OCTOBER,:1987 f COMMONWEALTH EDISON COMPANY' l.

I NRC DOCKET-NO.- 050-374 l

LICENSE NO. NPF-18 l-

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i . TABLE OF CONTENTS

.I. INTRODUCTION

11. 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. Facility or Procedure. Changes Requiring NRC Approval _

3. Teste and Experiments Requiring NRC Approval..

4. Corrective Maintenance of SafetyJRelated Equipment l 5. Completed. Safety Related Modifications l

l C. -LICENSEE EVENT. REPORTS l

D. DATA TABULATIONS

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l- 1. Operating Data Report l 2. Average Daily Unit Power Level l 3. Unit Shutdowns and Power Reductions -

1 E. UNIQUE REPORTING REQUIREMENTS 1 l .

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! 1. Safety / Relief Valve Operations ,

l 2. ECCS. System Outages .

l 3. Off-Site Dose Calculation Manual Changes i

4. Major Changes to Radioactive Waste Treatment l System  !

l 5. Indications of Failed Fuel Elements- '

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1. INTRODUCTION- ,

^1 The LaSalle County Nuclear Power. Station is a two-unit facility owned by Commonwealth Edison Coapany and-located near Marseilles, Illinois.

Each unit is_a Boiling Water Reactor with a designed net' electrical 1 j i

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. :j 1

Unit two was issued operating license number NPF-18 on' December-16, i 1983. Initial criticality was' achieved on March 10, 1984 and )

commercial power operation was '_coaunenced on June- 19, 1984. ]

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

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' II ." ' ModTHLY REPORT' FOR UNIT.TWO  %!

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'A. SUtttARY-OF OPERATING EXPERIENCE FOR UNIT TWO  ;

10/1/87 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Reactor at 1107.MWe, Generator on'Line.  ;

i 0100 Drop 50 MWe for CRD exercising to 1157 MWe.

I 0200 -Increase Rx power to 1107 MWe at a 10 MWe/hr_ l ramp. {

-10/3/87 1300 . Increase-Rx power to 1121 MWe or 99% C.T.P. I 10/8/87 0400 Drop Rx power to 693 MWu to'do scram timing and i rod pattern adjustment.-

jl 10/9/87 0500 Increase Rx power to 953 MWe, hold power at 953 )

MWe for Load dispatcher.

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10/12/87 0')D0 Ramp at 10 MWe/hr to.1126'MWe. 1 10/15/87 2300 Drop.260 MWe for surveillance and Load dispatcher. Rx at 858 MWe.  :

q 10/16/87' 0500 Ramp up to 1040 MWe. .j i

10/19/87 0500 Ramp up to 1113 MWe.  !

2000 Drop Rx power to'931-MWe due to heater 25C trio.

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10/20/87 0600 Ramp up to 1122 MWe at 10 MWe/hr.

10/22/87 2350 Drop Rx power to 1062 MWe for CED exercising.

10/23/87 0100 Ramp up to 1126 MWe at 10 MWe/hr.

10/26/87 1200 Drop Rx power to 886 MWe'due'to 25-C heater problems ramp up to'1065.

10/27/87 1100 . Drop Rx to 850 MWe to fix peaking factor.-

1400 Ramp up to 1050 at 10 MWe/hr.

10/29/87 2000 Drop 50 MWe for CRD exercising Rx at 1000~MWe, 3

10/30/87 0500 Ramp up to 1062 Rx power at 1062 MWe.

10/31/87 2400- Rx at 1057 MWe Generator on line. '

DOCUMENT ID,0036r/0031r

. B. , PLANT OR PROCEDURE CHANOBS, TES*S, EXPERIMENTS AND SAFETY RELATED  !

MAINTENANCE.

1. Amendments to Facility license or Technical Specification. '

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

a

2. Facility or Procedure changes requiring NRC approval.

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

3. Tests and Experiments requiring NRC approval. i 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 a short synopsis explaining details involved with each modification, h

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, ,s , TABLE 2 COMPLETED SAFETY RELATED MODIFICATIONS MODIFICATION NUMBER: A brief Synopsis of Incorporated Modification Objectives with final design resolution. Also, state reviewed or unreviewed safety questions 1 UNIT TWO M-t-2-84-117 This modification was for the replacement of Barksdale or Static-O-Ring pressure switches with new switches from S.O.R., Inc. There were no unreviewed safety questions.

M-1-2-84-153 This modification was to reroute the CRD pump suction line from the Condensate Storage Tank to the Main Condenser.

There were no unreviewed safety questions.

M-1-2-86-079 This modification was to reduce the amount of snubbers on J subsystem 2RR01 per the snubber reduction program. There were no unreviewed safety questions, i

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C. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, October 1, through October 31, 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 I

l 87-018-00 10/17/87 RWCU Isolation l

l 87-019-00 10/21/87 RCIC Steam Flow Isolation Switch out of tolerance.

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D. DATA TABULATIONS I

The following data tabulations are presented in this report: j 1

1. Operating Data Report I l

2. Average Daily Unit Power Level l

3. Unit Shutdowns and Power Reductions l l

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1. OPERATING DATA REPORT DOCKET No. 050-374 UNIT LaSalle Two i DATE November 10, 1987 COMPLETED BY Gregory Kirchner TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: October, 1987 GROSS HOURS IN REPORTING PERIOD: 745

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):RR3 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078

3. POWER LEVEL TO WHICH RESTRICTED (IP ANY) (MWe-Net): 1080

4. REASONS FOR RESTRICTION (IP ANY): Administrative . _ _

THIS MONTH YR TO DATR CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 745 3317.34 15320.8

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 29.83

7. HOURS GENERATOR ON LINE 745 _3235.9 15007.1

8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 2342688 9901872 43416136

10. GROSS ELEC. ENERGY GENERATED (MWH) 790779 3282240 14343812

11. NET ELEC. ENERGY GENERATED (MWH) 764316 3129859 13670088

12. REACTOR SERVICE FACTOR 100% 45.5% 57.6%

13. REACTOR AVAILABILITY FACTOR 100% 45.5%_ _ 57.7%

14. UNIT SERVICE FACTOR 100% 44.4% 56.4%

15. UNIT AVAILABILITY FACTOR 100% 44.4% 56.4%

16. UNIT CAPACITY FACTOR (USING MDC) 99% 41.4% 49.6%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 95.2% 39.8% 47.6%

18. UNIT FORCED OUTAGE RATE N/A 1.7% 22.2%

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

N/A

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

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2. AVERAd8 DAILY UNIT POWER LEVEL i DOCKET NO: 050-374 UNIT:.LASALLE TWO DATE: November 10, 1987 1 COMPLETED BY: Gregory Kirchner TELEPHONE: (815) 357-6161 MONTH: OCTOBER 1987 i

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL )

(MWe-Net)' (MWe-Net)

1. 1063 17. 977 2, 1065 18, 995 3 1073 19. 1018

4. 1076 20. 1008 l

5. 1076 21. 1074 l

6. 1078 22. 1079

7. 1077 23. '1019

8. 1079 _

24. 1078

9. 844 25, 1113 i

10. 910 26. 1039 11, 909 27. 960 1

12. 958 28. 998 1 l

13. 1068 29. 997

14. 1019 30, 986 15, 1081 31. 1010 l

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E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations for Unit Two, f

DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT 1 There were no safety / Relief Valve operated for Unit #2 during this reporting period, ,

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. . 42. ECCS Systems ~ Outages .,--

l The following outages were taken on 8CCS Systems during:

the reporting period.

UNIT 2 OUTAGE NO. EQUIPMENT PURPOSE OF OUTAGE-I 2-1700-87 2A D/G Compressor B6A Relocate Power Supply f i

2-1715-87 Shutdown Cooling Isolation Meet Tech. Spec.23.3.2. j Valve 2-l'122-87 2A D/G Repair Fuel Oil Leaks

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iE . . . . ..3. Off-site Dose calculation Manual'(U-2).

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

4. -Radioactive Waste Treatment. Systems.

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

5. Indications of Failed Fuel Elements. - ,,

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Off Gas Levels indicate one pinhole fuel element failure in the reactor. This does not' represent a change since the last reporting period.

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... r ' N Ctmmonw=lth Edison '

• "y'[ c- 1.) LaSalle CountyNuclear Station  :) j t --s 4 Rural Route #1, Box 220 4

\ 'v' Marseilles, Illinois 61341

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N Telephone 815/357-6761 November 10, 1987 1

Director, Office of Management Information i and Program Control United States Nuclear Regulatory Cennission Washington, D.C. 20555 l

ATTN: ' Document Control Desk 1

.i Gentlemen: j Enclosed for your.information is the monthly performance report covering I LaSalle County Nuclear Power Station for the period October 1, 1987 through j october 31,,1987.

l l Very truly yours, i

s..o. BAu \

hG.J.Diederich Station Manager j LaSalle County Station q GJD/GJK/jdp i

Enclosure j xc: J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle l

Gary Wright, Ill. Dept. of Nuclear Safety P. Shemanski, NRR Project Manager D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center L. J. Anastasia, PIP Coordinator SNED M. A.-Ortin, GE Resident

s. H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle Dennis Carlson/ Tech Staff 9 Terry Novotney/ Training .

Central File ~

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