ML20215A380

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Monthly Operating Repts for May 1987
ML20215A380
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 05/31/1987
From: Diederich G, Kirchner G
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8706160638
Download: ML20215A380 (37)
v • d • e


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t i LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT MAY 1987 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll 8706160638 870680 PDR R

ADOCK 050N373 PDR DOCUMENT ID 0043r/0005r

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I 3 TABLE OF CONTENTS l I. INTRODUCTION II. MONTHLY REPORT FOR UNIT ONE 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 Changer 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. 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 DOCUMENT ID 0043r/0005r
  • s I. 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-ll 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.

DOCUMENT ID 0043r/0005r

II. MONTHLY REPORT FOR UNIT ONE A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE MAY 1987 5-1-87 0000 Hours Rx Critical Generator on Line at 626 MWe.

5-3-87 1110 Hours Dropped to 607 MWe Due to 'A' RR flow control valve stepped closed position indicating reading 4% too high, 5-3-87 1400 Hours Ramp up to 626 MWe.

5-8-87 0200 Hours Rx Drifting down to 613 MWe due to losing condenser vacuum.

5-9-87 2300 Hours Efficiency and MWe increased to 621 MWe due to Amertap System being turned on.

5-15-87 1100 Hours Rx Dropped 20 MWe to 601 MWe due to CRD Exercising.

1300 Hours Ramp up to 621 MWe 5-22-87 0730 Hours Drop to 600 MWe. Inserted Four(4)

Peripheral Rods to Drop FCV for CRD Exercising.

1020 Hours Ramped up to 624 MWe, 5-29-87 2400 Hours Rx Scram on Low Reactor Water Level. 'B' TDRFP Demand went low and 'A' did not compensate on flow.

5-31-87 2400 Hours Rx is shutdown mode.

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[D. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED e o MAINTENANCE.

1. Amendments to Facility License or Technical Specification.

Ammendment #50 allows LSCS to lower MSIV Isolation setpoint from level 2 to Level 1.

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 this reporting period.

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 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.

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TABLE 1 CORRECTIVE MAINTENANCE OF ,

SAFETY RELATED EQUIPMENT UNIT #1 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFB PLANT OPERATION 67937 'A' SBLC Pump Pump crankcase breather is Replace Replaced cap.

IC41-C001A missing the top of cover.

67107 Valve lE51-F038 Steam leaking out of stem. Adjust packing. Adjusted packing until leak stopped.

67138 CRD HCU 38-15 Valve allows Nitrogen Replace Replaced Valve.

to leak by.

67578 136X-1 Compt. B-1 The feed breaker to the Replace breaker. Found two wires shorted U-l refuel platform in the floor to bridge periodically trips. power cable connector, replaced connector.

67738 OPDS-VD004 Pressure indicator in Recalibrate Recalibrated and returned out of calibration. toservice.

67759 IE51-F019 Bad Control Relay. Replace Replaced 74 Relay.

67625 CRD 58-39 Valve leaks Repair / replace Replace the cartridge as required.

67825 lE51-N021 Water Leaking around Repair / replace Replaced pressure switch, switch.

67909 1C41-F004A Continuity Ammeter for Repair / Replace Replaced the meter relay.

'A' squib valve reads high.

DOCUMENT ID 0043r/0005r

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TABLE 1 ,

CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT ,

UNIT #1

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION 69063 ITR-CM038 Chart Drive does not Replace clutch Replaced clutch.

4 advance paper.

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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.

UNIT ONE M-1-1-83-147 This modification allowed for the replacement of the existing diesel fire pump flow element OFE-FP012 and flow indicaion 0FI-FP012 so that flow can be monitored from 0-4500 GPM, as opposed to, 0-3500 GPM. There were no unreviewed safety questions.

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C. LICENSEE EVENT REPORTS l

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

period, May 1, 1987 through May 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 87-021-00 5/13/87 Emergency Make-up Train Auto Start.

87-022-00 5/28/87 Rx Scram from Low Level.

87-023-00 5/31/87 SDV-Level Switch Found valved out.

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j- D. DATA TABULATIONS i

The following data tabulations are presented in this report:.

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1. Operating Data Report
2. Average Daily Unit Power Level

! 3. Unit Shutdowns and Power Reductions 1

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e el. OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE June 10, 1987 COMPLETED BY G. J. Kirchner TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: May, 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
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 672 3143.6 12069.5
6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 29.83
7. HOURS GENERATOR ON LINE 672 3028.9 11830.84
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 1327392 6356688 33635128
10. GROSS ELEC. ENERGY GENERATED (MWH) 417636 2046824 11100804
11. NET ELEC. ENERGY GENERATED (MWH) 402062 1968031 10536556
12. REACTOR SERVICE FACTOR 90.3% 86.8% 52.6%
13. REACTOR AVAILABILITY FACTOR 90.3% 86.8% 52.6%
14. UNIT SERVICE FACTOR 90.3% 83.6% 51.6%
15. UNIT AVAILABILITY FACTOR 90.3% 83.6% 51.6%
16. UNIT CAPACITY FACTOR (USING MDC) 52.1% 52.4% 44.3%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 50.1% 50.4% 43.3%
18. UNIT FORCED OUTAGE RATE 9.7% 14.5% 14.5%
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 DOCUMENT ID 0043r/0005r

. .2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: June 10, 1987 COMPLETED BY: Gregory Kirchner J TELEPHONE: (815) 357-6761 1 MONTH: May, 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

(MWe-Net) (MWe-Net)
1. 603 17. 597
2. 601 18. 597 3 599 19. 598 4, 605 20. 593
5. 604 21. 596

! 6. 601 22. 596 J-

7. 596 23. 600
8. 591 24. 600 l
9. 590 25. 601
10. 598 26. 603
11. 601 27. 603
12. 601 28. 604
13. 602 29. -14 i
14. 600 30. -15 1
15. 601 31. -15 1 l i 16. 600 i  !

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3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373
  • UNIT NAME LaSalle One
  • DATE June 10, 1987 REPORT MONTH MAY, 1987 COMPLETED BY Gregory Kirchner TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS / COMMENTS 6 5/29/87 F 72 A 3 Rx Scram on Low Rx Water Level.

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E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION DATS ACTUATED ACTUATION CONDITION OF EVENT i '

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

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2. ECCS Systems Outtgsa Tha following outagss were taktn on ECCS Systcms during the reporting period.

OUTAGE NO. EOUIPMENT PURPOSE OF OUTAGE U-l and Common 1-212-87 lE51-F019 Repair ESP Indiction.

1-225-87 lE12-F004A Repair Motor.

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-3. Off-Site Dose Calculation Manual P

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

4. Radioactive Waste Treatment Systems.

r 4 i There were no changes to the RadWaste treatment systems.

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

i MONTHLY PERFORMANCE REPORT 1

_MAY, 1987 l

a i COMMONWEALTH EDISON COMPANY 7

9 NRC DOCKET NO. 050-374 j LICENSE NO. NPF-18 1

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DOCUMENT ID 0036r/0005r

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TABLE OF CONTENTS

. I. INTRODUCTION

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II. MONTHLY-REPORT FOR UNIT TWO 4

A. Summary of Operating Experience' .

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

1. Amendments to Facility License or Technical l Specifications
2. Facility or Procedure Changes Requiring NRC Approval j 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 j

E. UNIQUE REPORTING REQUIREMENTS

l. 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 t

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f DOCUMENT ID 0036r/0005r.

I. 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 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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DOCUMENT ID 0036r/0005r

II. MONTHLY REPORT FOR UNIT TWO A. SUIMARY OF OPERATING ' EXPERIENCE FOR UNIT TWO -

5-1-87, 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> - Rx Subcritical Refueling in Progress 5-31-87, 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> - Rx Subcritical Unit in Refuel Mode i

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  • B. PLAkT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.
1. Amendments to Facility license or Technical Specification.

AMENDMENT 33 - This allows LSCS to lower MSIV Isolation Setpoint from Level 2 to Level 1.

2. Facility or Procedure 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.

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.

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e TABLE 1 .

CORRECTIVE MAINTENANCE OF -

SAFETY RELATED EQUIPMENT Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION 51654 RR Pump Suction Valve Stem Leaks Repack Valve Repacked valve per Packing 2B33-F023A procedure.

51658 Reactor Head Vent Valve leaks past its seat Repair seat / disc Repaired and leak tested, Valve Packing 2B21-F001 satisfactory.

51924 RWCU Discharge Hdr. Stem found damaged Replace stem Replaced stem and Stop Valve 2G33-F040 repacked.

54920 RR Pump Suction Vlv. Packing Leak Repack Replaced Valve 2B33-F023B 55299 2A RHR Full Flow Test Valve 2E12-F024A 55507 LPCI Valve 2E12-F042A "

55859 Valve 2E12-F336B "

57688 Valve 2E21-F0ll 57860 Valve 2E21-F012 "

60067 Valve 2Cll-F102 Valve Leaks Repair Replaced stem, 0-rings, stem retainer. Verified no leaks.

62704 Valve 2E12-F031A Valve disassembled and cleaned, verified no leaks.

63280 conduit 2E31-N007BA Flex conduit broken Repair Repair flex conduit.

64313 Flex at 2VQ188 Broken Flex Repair Repaired damaged flex.

DOCUMENT ID 0036r/0005r

TABLE 1 e

COREECTIVE MAINTENANCE OF , ,

SAFETY RELATED EQUIPMENT Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION b4460 Valve 2B21-F020 V1v. is tripping thermals. Troubleshoot Motor found bad, replaced motor.

64464 Damper 2VX074 Damper Leaking oil Bad actuator Rebuilt actuator.

64474 Valve 2B33-F067B Observed dirt on stem of Clean stem Cleaned and lubed stem as valve required.

64523 Valve 2P21-F032B Failed leak rate Disassemble / repair Reseated valve by grinding. Verified no leaks.

64540 2E51-F008 Packing Leaks Repack / adjust packing. Adjusted packing, no leaks 64589 Isol. Vlv 2IN101 Indication is incorrect Set limits Limits set and proper indication verified.

.64623 Viv 2B21-F032A Failed leak rate. Repair Valve repaired and verified correct.

64664 Vlv. 2IN074 Valve Leaking Repair Disassembled and repaired.

64809 Vlv. 2E12-F041A Valve does not cycle 64810 Viv. 2E12-F050A Valve leaks 64910 V1v. 2E12-F099A Valve leaks 65064 V1v. 2E12-F041B Valve failed to open "

Disassembled and replaced hinge pin indicating rod.

65219 SRV 2B21-F013-0002 Send to Wyle Labs for Unit refuel maintenance Installed new gasket, disc testing and nozzle.

DOCUMENT ID 0036r/0005r

TABLE 1 t

CORRECTIVE MAINTENANCE OF ' ~

SAFETY RELATED EQUIPMENT Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION 65220 SRV 2B21-F013-0016 Send to Wyle Labs for Unit refuel malntenance Installed new gasket, disc testing and nozzle.

65203 SRV 2B21-F013-0010 65204 SRV 2B21-F013-0011 65205 SRV 2B21-F013-0006 65206 SRV 2B21-F013-0003 65207 SRV 2B21-F013-0108 65208 SRV 2B21-F013-0007 65209 SRV 2B21-F013-0009 65210 SRV 2B21-F013-0013 65211 SRV 2B21-F013-0015 65212 SRV 2B21-F013-0004 65213 SRV 2B21-F013-0014 65214 SRV 2B21-F013-0012 65215 SRV 2B21-F013-0018 65216 SRV 2B21-F013-0008 65217 SRV 2B21-F013-0102 65218 SRV 2B21-F013-0001 i DOCUMENT ID 0036r/0005r a

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TABLE 1 .

CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION 65468 V1v 2HG006A Failed Leak Rate Repair Repaired viv.

65548 MCC 235X-1 (G2) 74 Relay does not change Replace Replaced 74 relay.

state.

65555 MCC 235x-1 (A-4) Reverse Contactor sticks Repair Removed a burr from interlock mechanism 65560 MCC 235x-1 (C-1) 74 relay does not change Replace / repair Replaced 74 relay.

state.

65588 viv. 2G33-F004 Valve failed leak rate Disassemble and repair Lapped the secting surfaces.

65597 Viv. 2G33-F001 Valve failed leak rate Disassemble and repair Repaired valve seats and discs by lapping.

65712 O/B Isol. Valve No light indication Inspect and repair Replaced 5 lugs that were 2WR040 improperly crimped.

65736 MCC 236Y-2 F3 Reset button broken and 74 Repair / replaced Replaced thermal overload 2VQ050 relay does not cycle. and 74 relay.

65739 MCC 236Y-2 El Broken reversing contactor Replace Replaced reversing 2E12-F099A contactor.

65827 Guage 2PI-DG057B Guage found out of calib- Recalibrate Recalibrated and installed ration.

65912 Vlv. 2B21-F016 Valve leaks past the seat Repack Lapped seat and repacked.

65962 Vlv. 2E12-F325A "

65983 V1v. 2E12-F041A Limit switch shows dual Adjust Adjust limit switch and indication. cycled valve.

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TABLE 1 .

CORRECTIVE MAINTENANCE OF

  • SAFETY RELATED EQUIPMENT Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION 66239 2C51-KL605GU RBM "A" Gain change card will not Replace Replaced gain change card.

Gain Change Card zero.

66952 Viv. 2E51-F059 Dual indication when Repair Replaced bad motor on closed valve, cycled and verified proper ops.

66061 Vlv. 2E51-F008 Valve will not operate Repair Repaired forward and electrically. reversing contactors.

67070 Vlv. 2VQO32 No control room Troubleshoot Repaired nicked wire at indication valve.

67123 2VP113A/2AP82E 74 device contacts 19 and Repair / replace Replaced 74 relay.

20 are intermittent.

67124 2VPll4A/2AP82E Contacts 21 and 22 are "

sticky.

67185 2PI-E21-R001 Pressure indicator out of Recalibrate Recalibrated and verified calibration. proper Ops.

67424 2WR179/2AP83E Nicked insulator on Replace Replaced 2 wires and 4 control wires. lugs.

67445 2VQ051 Forward / reverse contactor Adjust or replace contactor Adjusted mechanical requires adjustment. mechanical interlock. interlock 67556 2E22-F382A Air is leaking from Rebuild Rebuilt solenoid and solenoid. bench tested - SAT 67557 2822-F382B - "

67638 2E12-N010CA Switch exceeded its rejec- Replace Replaced switch like for tion ILuit during-test like.

DOCUMENT ID 0036r/0005r

TABLE 1 CORRECTIVE MAINTENANCE OF , ,

SAFETY RELATED EQUIPMENT Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION 67762 2Cll-601C Receiving intermittent 1/2 Troubleshoot / repair Replaced relay on scram on Channel A-2 from 2C11N601C SDV no 111 level alarm.

67772 2E12-RS27 Gauge needle sticks Repair / replace Replaced gauge and calibrated.

67883 Valve 2E12-F064A Water leaking from min. Adjust packing Adjusted packing until flow valve leak stopped.

67944 2PI-E12-C002C Pressure indicator reading Calibrate Recalibrated and returned low. to service.

67958 2PR-CM027 S/P Narrow range recorder recorder reading high 69200 "D" RiiR Service Water Received auto trip when Repair Removed piece of fire-Pump 2E12-C300D tried to start pump proofing material from 52X relay.

DOCUMENT ID 0036r/0005r

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.

UNIT TWO M-1-2-84-153 This mod allowed the rerouting of the scram contactor wiring in panels 2H13-P609/611 such that line and load side wiring do not come in contact with each other. There were no unreviewed safety questions.

M-1-2-84-186 This mod allows for the installation of regulators (WKM Model 73-68) to the inlet air supply lines of RR isolation valves. There were no unreviewed safety questions.

M-1-2-85-845 This mod allowed for the addition of a General Electric Auxiliary Relay (HMA) in Panel 2H13-P623 located in the main control room. This assures long term leak tightness of the containment in the post LOCA conditions. There were no unreviewed safety questions.

M-1-2-85-052 This mod was for the redesign of the water sprinkler system in the MSR and LP heater bays. This is done in order to meet the hydraulic demand for the sprinkler system with either one fire pump or one service water pump in service.

There were no unreviewed safety questions.

M-1-2-86-062 This mod was for the snubber reduction on subsystem 2RH-73 per the snubber reduction program. There were no unreviewed safety questions.

The following snubber subsystems had snubber reductions per the snubber reduction program.

MOD NO SNUBBER SUBSYSTEM M-1-2-86-063 2RH71 M-1-2-86-064 2RHC4 M-1-2-86-067 2RR-59 M-1-2-86-072 2NB-01 M-1-2-86-094 2HG-06 M-1-2-87-001 2RH-C9 M-1-2-87-014 2RR-58 M-1-2-87-015 2RR-53 There were no unreviewed safety questions for the above listed Mods.

M-1-2-87-004 This mod was to provide cooling air to be supplied from the Unit 2 primary containment (VP) HVAC system to the reactor recirculating pump flow control valve linear voltage differential transmitters (LVDT's). There were no

, unreviewed safety questions.

DOCUMENT ID 0036r/0005r 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, May 01, through May 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 87-012-00 5/22/87 Trip of Sat Feed Breaker 87-013-00 5/29/87 RWCU and SDC Isolation during MOD Test I

DOCUMENT ID 0036r/0005r t

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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 DOCUMENT ID 0036r/0005r
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1. OPERATING DATA REPORT DOCKET NO. 050-374

'JNIT LaSa11e Two DATE June 10, 1987 COMPLETED BY Gregory Kirchner TELEPHONE (815)357-6761 MONTH MAY 1987 OPERATING STATUS

1. REPORTING PERIOD: May, 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
3. POWER LEVEL TO WHICH RESTRICTED (IP ANY) (MWe-Net): 1050
4. REASONS FOR RESTRICTION (IF ANY): Administrative THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 66.05_ 12069.5
6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 29.83
7. HOURS GENERATOR ON LINE 0.0 59.62 11830.84
8. UNIT RESJRVE SHUTDOWN HOURS 0.0 0.0 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 0.0 _ 120864 33635128
10. GROSS ELEC. ENERGY GENERATED (MWH) 0.0 39232 11100804
11. NET ELEC. ENERGY GENERATED (MWH) -8320 -3673 10536556
12. REACTOR SERVICE FACTOR 0% 1.8% 32.6%
13. REACTOR AVAILABILITY FACTOR 0% 1.8% 52.6%
14. UNIT SERVICE FACTOR 0% 1.6.% 51.6%
15. UNIT AVAILABILITY FACTOR 0% 1.6.% __ 51.6%
16. UNIT CAPACITY FACTOR (USING MDC) -0.1% 0.09% 44.3%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) -0.1% 0.09% ,

42.6%

18. UNIT FORCED OUTAGE RATE 0% 0% 26.2%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

N/A Unit is in shutdown during this period.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARIUP 6/14/87 DOCUMENT ID 0036r/0005r l
2. AVERAGE DAILY UNIT POWER LEVEL e *. .

DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: June 10. 1987 COMPLETED BY: Gregory Kirchner TELEPHONE: (815) 357-6761 MONTH: MAY 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -13 17. -10
2. -13 18. -10 3 -10 19. -10
4. -10 20. -9
5. -10 21. -9
6. -11 22. -10
7. -9 23. -13
8. -9 24. -14
9. -8 25. -12
10. -10 26. -12
11. -9 27. -13
12. -10 28. -13
13. -10 29. -14
14. -9 30. -14
15. -10 31. -14
16. -9 i

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DOCUMENT ID 0036r/0005r i

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3. UNIT SHUTDOWNS.AND POWER REDUCTIONS 'P'f*~

DOCKET NO. 050-374 , .

UNIT MAME LaSalle hso , ~

DATE JUNE 10, 1987 REPORT MONTH May, 1987 COMPLETED BY G.J. Kirchner TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS /COlWEENTS 1 5/1/87 S 744 C 4 Refuel Mode l

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DOCUMENT ID 0036r/0005r

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,n, + +-o e+h- .,2- a up --W aM+2- u a ,

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E. UNIQUE REPORTING REQUIREMENTS l 1. Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT j There were no safety relief valves operated for Unit #2 during this reporting

period.

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  • 2. ECCS Systems Outog:s The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO. EOUIPMENT PURPOSE OF OUTAGE 2-1250-87 2E12-F049A Replace O.L. Relay.

2-1251-87 2E12-F086 Replace 74 Relay.

2-1253-87 HPCS D/G Air Replace /Replair Air-Start Start Solenoid Solenoid Valves 2-1262-87 2E12-C300D 2D RHR WS Pump Repair Siezed Pump 2-1263-87 2B RHR Pump Flush Pump Seal Coolers 2-1264-87 2C RHR Pump Flush Pump Seal Coolers 2-1276-87 HPCS Pump Inspect Motor 2-1294-87 2E51-F031 Inspection 2-1295-87 2E51-F068 Inspection 2-1317-87 2B21-2BSFV-1 Repack 2B21-2BSFV-1 2-1319-87 2B RHR Pump Inspect and Megger Motor 2-1320-87 2C RHR Pump Inspect and Megger Motor 2-1323-87 2A D/G 2DG0lK Replace 2A D/G Cooling Water Pump 2-1398-87 RCIC EFCV 2B21-F415A Repair EFCV 2-1399-87 RCIC EFCV 2B21-F415B Repair EFCV 2-1400-87 RCIC EFCV 2B21-F413B Repair EPCV 2-1402-87 RCIC EFCV 2B21-F348 Repair EPCV 2-1405-87 RCIC EFCV 2B21-F359B Repair EFCV 2-1416-87 2E51-F06C Repair Limit Switch 2-1428-87 2DG0lP 2A D/G Cooling Water Lube Coupling 2-1429-87 2D00lP Lube Coupling 2-1433-87 RCIC Repair turbine overspeed trip mechanism 2-1444-87 D RHR Service water pump Replace control switch 2-1445-87 2E51-F013 RCIC injection 2-1446-87 2E51-F045 RCIC steam inlet 2-1447-87 2E12-C002A 'A' HHR Pump heater 2-1458-87 2B D/G Motor Driven Replace High Pressure Valve Air Compressor Assembly DOCUMENT ID 0036r/0005r

      • 6 3. Off-site Do2a Calculation Manuel (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.

There were no indications of failed fuel elements during this reporting period.

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DOCUMENT ID 0036r/0005r

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E.

Commonwealth Edison L SillsCountyNuclearStation I

> Rural Route #1, Box 220 Marseilles, Illinois 61341 l

Telephone 815/357-6761 June 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 May 1, 1987 through May 31, 1987.

Very truly yours, R.r;. GLA hG.J.Diederich Station Manager LaSalle County Station GJD/GJK/sjc Enclosure xc: J. G. Keppler, NRC, Region III ,

NRC Resident Inspector LaSalle l

Gary Wright, Ill. Dept. of Nuclear Safety A. Bournia, 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 H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle i J. C. Klika, Surveillance Group Leader I Dennis Carlson/ Tech Staff Terry Novotney/ Training Central File DOCUMENT ID 0043r/0005r ,V s ,l

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