Text

Monthly Operating Repts for Jul 1987
	ML20237G775
Person / Time
Site:	LaSalle
Issue date:	07/31/1987
From:	Diederich G, Kirchner G; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	NUDOCS 8708140192
	Download: ML20237G775 (34)
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LASALLE NUCLEAR POWER STATION UNIT 1 h

MONTHLY PERFORMANCE REPORT 4

JULY 1987 COMMONWEALTH EDISON COMPANY l

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NRC DOCKET NO. 050-373 l

LICENSE NO. NPF-11 f

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INTRODUCTION II.

MONTHLY REPORT FOR UNIT ONE

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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 1

3.

Tests and Experiments Requiring NRC Approval

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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 1

E.

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 Waste Treatment System 5.

Indications of Failed Fuel Elements i

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DOCUMENT ID 0043r/0005r i

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INTRODUCTION 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 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-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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MONTHLY REPORT FOR UNIT ONE A.-

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE JULY 1987 7-1-87 0000 Hours RX in cold shutdown for RECIRC pump repair.

7-31-87 2400 Hours Rx in cold shutdown, Generator off-line.

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DOCUMENT ID 0043r/0005r

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PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED i

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-MAINTENANCE.

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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 Procedural changes requiring NRC approval during this reporting period.

3.

Tests and Experiments requiring NRC approval.

There were no tests or experiments requiring NRC approval during 1

this reporting period.

4.

Corrective Maintenance of Safety Related Equipment.

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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 include:

Work Request number, Component Name, Cause of Malfunction, Results

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and Effects on Safe Operation, and Corrective Action.

5.

Completed Safety Related Modifications.

i 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 modit'ication.

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

l M-1-1-83-005 This modification was to replace the temporary baffle plate for the crankcase pressure switch with a permanent baffle in the '1A' Diesel Generator. There were no unreviewed safety questions.

M-1-0-84-054 This mod is to remove from service, various unqualified pressure transmitters (Rosemount 1151, Rosemount 1152, Bailey 556) and replace with the Rosemount 1153, which is environmentally qualified. There were no unreviewed safety questions.

M-1-1-86-080 This mod was to install six (6) threaded unions and relocate one (1) piping support in each of the lubricating oil systems for the '1B' Diesel Generator. There were no unreviewed safety questions.

M1-1-86-081 This mod was to install six (6) threaded unions and relocate one (1) piping support in each of the lubricating oil systems for the '1A' Diesel Generator. There were no unreviewed f

safety questions.

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LICENSEE EVENT REPORTS l

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

period, July 1, 1987 through July 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 87-025 6/18/87 A mechanical snubber was not functionally tested, not included in procedure, and not turned over from construction.87-026 7/13/87 NON-EQ RHR Pump Motor Terminations.87-027 7/20/87 ECCS Pump Motors Termination / Splice Discrepancy.

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

1. Operating Data Report i

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions I

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OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE August 10, 1987 COMPLETED BY G. J. Kirchner

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TELEPHONE (815)357-6761

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OPERATING STATUS 1.

REPORTING PERIOD:

July, 1987 GROSS HOURS IN REPORTING PERIOD: 744 i

2.

CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078 3.

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

1050 4.

REASONS FOR RESTRICTION (IF AN7):, Administrative THIS MONTH YR TO DATE CUMULATIVE 5

NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 3143.6 12069.5 6.

REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 29.83 7.

HOURS GENERATOR ON LINE 0.0 3028.9 11830.84 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 0.0 6356688 33635128 1

10.

GROSS ELEC. UNERGY GENERATED (MWH) 0.0 2046824 11100804 11.

NET ELEC ENERGY GENERATED (MWH)

-1114J_

1946842 10515367 12.

REACTOR SERVICE FACTOR 0.0%

61.8%

38.a 13.

REACTOR AVAILABILITY FACTOR 0.0%

61.8%

38.5%

14.

UNIT SERVICE FACTOR 0.0%

60%

37.5%

15.

UNIT AVAILABILITY FACTOR 0.0%

60%

37.5%

16.

UNIT CAPACITY FACTOR (USING MDC)

N/A 40%

32.3%

17.

UNIT CAPACITY FACTOR (USING DESIGN MWe)

N/A 35.5%

31%

18.

UNIT FORCED OUTAGE RATE 0%

14.5%

70.6%

19.

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

N/A - Unit is shutdown during this period.

20.

IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 8/24/87

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DOCUMENT 1D 0043r,0005r

2. ByFEAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: August 10, 1987 COMPLETED BY: Grecory Kirchner TELEPHONE: (815) 357-6761 MONTH: July, 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

-14, 17.

-15 2.

-14 18.

-15 3

-15 19.

-15 4.

-15 20.

-14 5.

-15 21.

-14 6.

-15 22.

-15 7.

-15 23.

-14 8.

-15 24.

-14 9.

-15 25.

-14 10.

-15 26.

-15 11.

-15 27.

-14 12.

-15 28.

-14 13.

-15 29.

-14 14.

-15 30.

-14 15.

-14 31,

-15 16.

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

There were no safety Relief Valves Operated for Unit One during this reporting l

period.

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. 2. g ECCS Systtms'Outagas

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Tha following outagss ware taken on ECCS Systems during' the reporting period.

. OUTAGE NO.

BOUIPMENT PURPOSE OF OUTAGE U-l 1-520-87

'lB21-F020 Repack Valve.

1-523-87.

-1B21-F019 Determinate Motor.

1-536-87 B-RHR System Repack lE12-F006B l-537-87 1 C&D RHR Switch pumps Disassemble, clean and lube coupling.

1-540-87 lE12-F064C Troubleshoot breaker and repair.

1-542 RCIC Repair RCIC exhaust check'lE51-F040.

1-543-87 Div II RHR water Oil change leg pump.

I l-546-87 1-D RHR WS Breaker inspection l-547-87 1-C RHR WS d

l-549-87 lE12-F411B Unable to get a closed.

indication.

1-559-87 IB21-F430B Set limits.

1-569-87 1-C RHR LPCI Repair IE12-F041C.

Injection check valve.

1-574-87 IE12-F008 Determinate 1-585-87 1DG0lP Disassemble and lube coupling.

1-586-87 1A D/G Various Instrument Calibration.

1-587-87 1A D/G Auxillary Change Oil IDOO1P/lDG OlP l-588-87 lE12-F008 and lE12-F009 Repair 1-702-87 lE51-F059 Remove motor to install on 1E51-F046.

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OUTAGE NO.

EOUIPMENT PURPOSE OF OUTAGE U-l 1-710-87 lE51-F063 Remove MOVATS equipment I

l-711-87 1E51-F076 1-712-87 1E12-F041A Repair Valve.

1E12-F042A Repack Valve.

l 1-715-87 lE51-F068 MOVATS.

1-735-87 1E12-C002A 1A RHR pump motor 1-A RHR pump 1-737-87 lE12-F068A Repack valve.

1-739-87 IB RHR Heat Hydrolaze heat exchanger exchanger.

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1-742-87 IB21-F425B Repair valve.

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Off-Site Dose Calculation Manual 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 There were no indications of Failed Fuel Elements during this reporting period.

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l-LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPGRT JULY, 1987 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 DOCL' MENT ID 0036r/0005r

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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.

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 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 Outagea 3.

Off-Site Dose Calculation Manual Changes 4.

Major Changes to Radioactive Waste Treatment System 5.

Indications of Failed Fuel Elements DOCUMENT ID 0036r/0005r

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.I, INTRODUCTION L

The LaSalle County Nuclear Power Station is a two-unit facility owned j

by Commonwealth Edison Company and located near Marseilles,' Illinois, j

Each unit is a Boiling Water Reactor with a designed net electrical l

output of 1078 Megawatts. Vaste heat is rejected to a man-made cooling j

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

architect-engineer @.4 Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company.

i Unit two was issued operating license number NPF-18 on December.16, i

1983.

Initial criticality was achieved on March 10, 1984 and I

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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DOCUMENT ID 0036r/0005r o

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MONTHLY REPORT FOR UNIT TWO l

A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT TWO l

7/]/87 0000 hours0 days 0 hours 0 weeks 0 months Rx at 807 MWe and ramping to 1060 MWe at 10 MWe/hr. Turbine Generator on line.

7/03/87 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months Rx decreased to 1020 MWe due to Condensate Booster pump suction pressure decrease.

7/04/87 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months Drop Rx power to 950 MWe due to CV-4 oscillations.

0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months Ramp up to 1000 MWe at 10 MWe/hr, to 1015 MWe.

7/07/87 2330 hours0.027 days 0.647 hours 0.00385 weeks 8.86565e-4 months Decrease Rx power to 850 MWe to bring up FCL.

7/09/87 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months Ramp up to 1080 MWe at 5 MWe/hr.

7/11/87 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months Drop power to 645 MWe for jet pump cals and heater bay work.

2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months Ramp up to 1088 MWe at 10 MWe/hr.

7/14/87 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months Ramp down 100 MWe per L.D.

0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months Ramp up to 1089 MWe at 10 MWe/hr.

7/17/87 0000 hours0 days 0 hours 0 weeks 0 months Drop power to 850 MWe to perform control rod exercising.

0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months Rasnp up to 1084 MWe at 10 MWe/hr.

7/20/87 1235 hours0.0143 days 0.343 hours 0.00204 weeks 4.699175e-4 months Drop 100 MWe to help system voltage (increase VARS).

7/20/87 1900 hours0.022 days 0.528 hours 0.00314 weeks 7.2295e-4 months Ramp up to 1038 MWe at 10 MWe/hr.

7/23/87 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months Ramp up to 1081 MWe.

7/31/87 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months Dropped to 950 MWe to pull rod 02-23.

7/31/87 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months Rx at 1070 MWe.

Generator on-line.

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

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.l.

Amendments to Facility license or Technical Specification.

r L

L There were no Amendments to the' facility license or Technical l

Specifications during this reporting period.

.2.

Facility or.Procedur3 changes requiring NRC approval.

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

3.

Tests 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.

i 1

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.

1 The following table (Table 2) presents a list of completed l

Modifications during this reporting period. Each entry will have

-a short-synopsis explaining details involved with each modification.

1 DOCUMENT ID 0036r/0005r a : _-.

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TABLE 2 l

COMPLETED SAFETY RELATED MODIFICATIONS MODIFICATION NUMBER 1 A brief Synopsis of Incorporated Modification Objectives with final design resolution. Also, state reviewed or unreviewed safety questions.

UNIT TWO M-1-2-84-119 This mod was to install six (6) area coolers at various locations on the two (2) top elevations inside the drywell. There were no unreviewed safety questions.

M-1-2-86-001 This mod was to remove existing INC77B negative sequence relay and replace it with a modernized SGC21A negative sequence relay. There were no unreviewed safety questions.

M-1-2-86-059 This mod was for snubber reduction on subsystem 2RH77K per the snubber reduction program. There were no unreviewed safety questions.

l M-1-2-86-070 This mod was for snubber reduction on subsystem 2RH70 per l

the snubtsr reduction program. There were no unreviewed j

safety eaestions.

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DOCUMENT ID 0036r/0005r i_-

e s e

i C.

LICENSEE EVENT REPORTS

}

l Die following is a tabular summary of all licensec event reports for LaSalle Nuclear power Station, Unit Two, logged during the reporting period, July 01, through July 31, 1987. This information is provided i

pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

)

bicensee Event Report Number Date Title of Occurrence l

87-016-00 7/13/87 LPCS Min Flow Bypass Switch Failure l

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I DOCUMENT ID 0036r/0005r I

i 1

A

e.

D.

DATA TABULATIONS l

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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DOCUMENT ID 0036r/0005r i

l I

a-e, 1.' OPERATING DATA REPORT DOCKET NO. 050-374

-UNIT LaSalle Two DATE August 10, 1987 COMPLETED BY' Gregory Kirchner TELEPHONE (815)357-6761 MONTH JULY, 1987 f

OPERATING STATUS 1.

REPORTING PERIOD:

July, 1987 GROSS HOURS IN REPORTING PERIOD: 744 2.

CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078 f-3.

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

1050 4.

REASONS FOR RESTRICTION (IF ANY): Administrative THIS MONTH YR TO DATE CUMULATIVE 5

NUMBER OF HOURS REACTOR WAS CRITICAL 744 4108.34 13111.79 6.

REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 29.83 7.

HOURS GENERATOR ON LINE 744 1026.91 12798.13 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 2311080 2791104 36305368 10.

GROSS ELEC. ENERGY GENERATED (MWH) 758333 901661_

11963233 11.

NET ELEC. ENERGY GENERATED (MWH) 735203 824144 11364373 12.

REACTOR SERVICE FACTOR 100%

21.8%

53.7%

13.

REACTOR AVAILABILITY FACTOR 100%

21.8%

53.8%

14.

UNIT SERVICE FACTOR 100%

20.2%

52.4%

15.

UNIT AVAILABILITY FACTOR 100%

20.2%

52.4%

16.

UNIT CAPACITY FACTOR (USING MDC) 95.4%

15.6%

44.9%

17.

UNIT CAPACITY FACTOR (USING DESIGN MWe) 91.7%

15.1%._

43.2%

18.

UNIT FORCED OUTAGE RATE N/A 5.1%

25.0%

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 i

i DOCUMENT ID 0036r/0005r

-_____-_______-______--_-_-_-______A

2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374 UNIT: MEALLE TWO f

DATE: August 10, 1987 COMPLETED BY: Gregory Kirchner TELEPHONE: (815) 357-6761

' MONTH: JULY 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL f.

(MWe-Net)

(MWe-Net) f 1.

706 17.

967 1

2.

861 18.

1058

\\

{-

3 990 19.

1047 4,

957 20.

1000 l

l 5.

978 21.

979

'l 6.

970-22.

994 7,

964 23.

1022 8.

977 24, 1043 l

9.

922 25.

1040 l

10.

1028 26, 1038 11.

922 27, 1039 12, 840 28, 1041 13.

1018 29, 1044 14.

1004 30.

1042 15.

1054 31.

1020 f

16.

1053 I

L i

DOCUMENT ID 0036r/0005r

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E.

UNIQUE REPORTING REQUIREMENTS 1.

safety / Relief Valve Operations for Unit Two, DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED

&CTUATIONS CONDITION OF EVENT There were no safety / Relief Valve actuations during this reporting period.

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1 DOCUMEN1 ID 0036r/0005r 1

a 2.

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

UNIT 2 OUTAGB_NO EOUIPMENT PURPOSE OF OUTAGE 2

2-1607-87 2E21-C001 Inspect Terminal Connections.

2-1609-87 2A RHR Inspect Motor Connections.

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l DOCUMENT ID 0036r/0005r 1

I

e N '. "..

3.

off-Sito Dose calculation Minual-(U-2)

There were no changes to the'oDCM-during this reporting period.

'4.

Radioactive Waste Treatment Systems.

There were no changes to the Radwaste Treatment Systems for this

. reporting period.

5.

Indications of Failed Fuel Elements.

On July 24, 1987, there was an. indication of a failed fuel element.

At this time it is impossible to determine which bundle is leaking.

When further information becomes available, the location will be reported at a.later date.

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I DOCUMENT ID 0036r/0005r l.

J

~

O Telephone 815/357-6761 Commonwealth Edison

~

LaSalle County Nuclear Station Rural Route #1, Box 220 Marseilles, Illinois 61341 I

August 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 repe-t covering LaSalle County Nuclear Power Station for the period July 1, 1987 through July 31, 1987.

Very truly yours, Q,0. b0 h" 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 Nuclect 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, GB Resident H. B. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle Dennis Carlson/ Tech Staff Terry Novotney/ Training Central File DOCUMENT ID 0043r/0005r I I

ML20237G775

Text

SUMMARY

SUMMARY

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