ML20213G900

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Monthly Operating Repts for Apr 1987
ML20213G900
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 04/30/1987
From: Diederich G, Kirchner G
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
OO43R-OOO5R, NUDOCS 8705190018
Download: ML20213G900 (44)
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a. -y-4 j LASALLE NUCLEAR POWER STATION d UNIT 1

.i 4 MONTHLY PERFORMANCE REPORT APRIL 1987 Cot 990NWEALTH EDISON COMPANY i

i NHC DOCKET NO. 050-373 d

LICENSE NO. NPP-ll I

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n 8705190018 870430 PDR ADOCK 05000373 PDR- ,

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

1. Amendments to Facility Licen.=,e 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. 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

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e 1 I. INTRODUCTION a

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

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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. 1 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. l

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

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II. MONTHLY REPORT FOR UNIT ONE A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE APRIL 1987 4-1-87 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> - Rx Critical, generator at 600 MWe.

4-2-87 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> - Commence power increase to 620 MWe at 10 MWe/hr.

4-13-87 2310 hours0.0267 days <br />0.642 hours <br />0.00382 weeks <br />8.78955e-4 months <br /> - Reduce power to 600 MWe in order to take 'A' TDRFP out of service.

4-14-87 2050 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.80025e-4 months <br /> - Start ramp at 10 MWe/hr to 620 MWe to put

'A' TDRFP on.

4-24-87 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> - Drop 30 MWe to 590 MWe to perform LOS-AA-W1 on HCU pressures, then recover to 625 MWe.

4-30-87 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> - Rx critical, generator on line at_630 MWe.

DOCUMENT ID 0043r/0005r

D. PLANT OR PROCEDURE CHANGES, TESTS,' EXPERIMENTS AND' SAFETY RELATED l

., g MAINTENANCE.

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

There were no ammendments to-Facility License or Technical i Specifications during this reporting period.

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, 2. Facility or Procedure changes requiring NRC approval.

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

3. Tests and Experiments requiring NRC approval.

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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.

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 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 SAFE PLANT OPERATION 63159 RCIC Steam Supply Valve Packing Leaks Repack Valve Valve Repacked.

Drain Pot Steam Trap Assembly Inlet Stop Valve IE51-F038 64940 HPCS D/G Low Air Alarm Setpoint High Calibrate Recalibrated Switch Pressure Alarm lE22- Verified proper Ops.

N504 64941 HPCS D/G Low Air Pressure Alarm lE22--

, N505 1

65144 Isolation Damper to Damper Failed in Close Bad Limit Switch Adjusted Travel Limit East Control Room Position Switch Arm to proper tension.

l l 66051 HPCS Diesel Vent Air Filter Diff. Press. Hi Recalibrate Recalibrated IPDS--VD004 l

Intake Filter D/P Alarm and IPDI-VD004.

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66761 RCIC Water Leg Pump Pump is binding Breaker trip on high current New pump installed.

66766 1A RHR Hx Vent V1v Valve will not full close Vlv not travelling full close Contacts loose on limit-IE12-F073A orque. Tightened contact and assured proper ops.

66800 RCIC Steam Vlv. IF51- Valve didn't auto open Auto open does not function on Adjusted micro-switch N010 High Steam Line Drain Pot Alarm assured proper ops.

I 66832 Ammonia Detector Manual zero adjust is Replace meter Replaced meter and damaged on meter. calibrated.

DOCUMENT ID 0043r/0005r

TABLE 1 CORRECTIVE MAINTENANCE CF .

SAFETY RELATED EQUIPMENT UNIT #1 -

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION 66867 RCIC Water Lcg Pump Valve did not seat Disassemble / Repair Valve cleaned internally, Discharge Valve IE51- properly new bonnet gasket installed F061 proper ops.

66869 Containment Monitoring Paper does not advance. Bad Drive Gear. Replace Drive Gear Temp. Recorder ITR- observed for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> CM037 satisfactorily.

66998 DWEDS Outboard Iso- Valve dos not fully open. Adjust limit switch Adjusted limit switch for lation Valve 1RE025 proper Ops.

67031 D/P Gage & Alarm Gage reading low. Recalibrate Recalibrated and assured IPDI-VX014 proper Ops.

67168 DIV 1 POST LOCA Lvl/ Motor Making Noise. Recorder is oscilloting. Rcplaced faulty servo' Press Recorder 1B21- motor assembly.

R884A 67225 Ammonia Detector Detector Failed. Troubleshoot Replaced photocell board, 0XY- VC125B magnets, drive motor, and calibrated.

67449 Supp. Pool Temp. Does not Print Repair / Replace Adjusted printhead solen-Recorder ITR-CM038 old for proper Ops.

67507 Accumulator 22--19 Vlv. Leaks Repla$e (111) Cartridge. (111) Cartridge replaced.

111 Valve.

67535 Suppression Chamber Temperature Recorder off Recalibrate Calibrated and observed Air Temperature ITR- by 10*F. proper Ops.

CM040 67569 CRD Accumulator #26 -43 (111) Valve leaks Replace cartridge Cartridge replaced.

67399 'D' APRM 'D' APRM Giving Half Scrams Gives half scrams on Hi Neutron Replaced Kl8 Relay verified Flux. proper Ops.

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. i TABLE 2 COMPLETED SAFETY RELATED MODIFICATIONS MODIPICATION NUMBdR: A brief synopsis of incorporated modification objectives with final design resolution. Also, state reviewed or unreviewed safety questions.

UNIT ONE M-1-0-85-008 This Modification provided access to various fire dampers that are not accessable per the August, 19d4, technical basis of the LaSalle County Station Fire Damper Surveillance program. There were no unreviewed safety questions.

M-J-0-85-011 This Modification was to install the interconnections required for the interim Redwaste Storage Facility telephone connection, paging connection, fire detection alarm connection, and the potentially contaminated sump high level alarm connection. There were no unreviewed safety questions.

M-1-0-86-023 This Modification was to improve the exiting method of sampling the flow in the Mid/Hi Range portio of the Stadnby Gas Treatment Wide Range Gas Monitor (WRGM). This change will minimize the amount of iodine plateout in the sample line. There were no unreviewed safety questions.

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.C. ' LICENSEE EVENT REPORTS l I

The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, logged during the reporting period, April 1, 1987 through April 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 87-016-00 4/1/87 RCIC Isolation on Steam Line High Flow.

. 87-017-00 4/2/87 1.69 PSIG DW Pressure Switch

! 5 valved out.

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87-018-00 4/13/87 'A' VC Ammonia Detector spurious trip.

87-019-00 4/3/87 Incomplete surveillance on CRD

' cycling.

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87-020-00 4/16/87 Loss of 12C/208 Distribution at i MCC 136X-1. ,

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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 i

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, 1. _ OPERATING DATA REPORT- )

. DOCKET No. 050-373 UNIT LaSalle One

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DATE May 10. 1987 1 j.  !. COMPLETED BY G. J. Kirchner

,, [ r v TELEPHONE (815)357-6761

, OPERATING STATUS > +

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1.- REPORTING' PERIOD: _ _ _ ADril. 1987 GROSS HOURS IN REPORTING PERIOD: 719

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):2 H1 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

, s vI f THIS MONTH YR TO DATE CUMULATIVE

" 5 719 2471.60 18164.40 NUMBER OF HOURS REACTOR WAS_ CRITICAL

6. REACTOR RESERVII SHUTDOWN HOURS 0.0: 0.0 1642.0,_
7. HOURS, GENERATOR ON LINE , , ,'- 719 2356.90 17506.40 1
g. 8. UNIT RESERVE SHUTDOWN HOURS _ j* 0.0 0.0 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 1399704 5029296 45614218 l 10. GROSS ELEC. ENERGY GENERATED (MWH) 446508 1629188 14319865-
11. NET ELEC.' ENEEGY GENERATED (MWH) 431404 1565969 13588543
12. REACTOR SERVICE FACTOR 100% 85% 62%

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13. REACTOR AVAILABILITY FACTOR 100% 85% _ 68%

i 14. UNIT SERVICE FACTOR 100% 82% 60%

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15. UNIT AVAILABILITY FACTOR 100% 82% 60%
16. UNIT CAPACITY FACTOR (USING MDC) 60% ___ 56% 45%
17. UNIT CAPACITY FACTOR (USING DESIGN-MWe) 55% 50% 43%
18. UNIT FORCED OUTAGE RATE 0% 21% 15.2%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)

On June 13, 1987, Unit I will be shutdown to repair the IB Reactor Recirc Pump. The chutdown is scheduled to last fifty (50) days.

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

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2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: May 10, 1987 COMPLETED BY: Gregory Kirchner i

TELEPHONE: (815) 357-6761 MONTH: April. 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) i 1. 580 17. 606

2. 580 18. 604 3 607 19. 601

<. 608 20. 603

5. . 582 21. 600 l
6. 606 _
22. 601
7. 605 23. 602
8. 604 24. 601 9._ 602 25. 601
10. 602 26. 602 11.__ 600 27. 600 12._ 597 28. 600
13. 599 29. 604
14. 580 30. 602
15. 596 31. ---
16. 598 l

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3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373 ,

UNIT NAME LaSalle One DATE May 10, 1987 REPORT MONTil APRIL, 1987 COMPLETED BY Gregory Icirchner TELEPliONE (815)357-6761 METilOD OF TYPE SliUTTING DOWN F: FORCED DURATION TIIE REACTOR OR CORRECTIVE NO. DATE S: SCl!EDULED (liOURS) REASON REDUCING POWER ACTIONS / COMMENTS Unit was critical for 719 hours0.00832 days <br />0.2 hours <br />0.00119 weeks <br />2.735795e-4 months <br /> during April, 1987 s

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E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT There were no Safety Relief Valves Operated for Unit One during this reporting period.

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2. ECCS Systems Outagns Tha following outagsa were takin on ECCS Systems during' the reporting period.

OUTAGE NO. EOUIPMENT EURPOSE OF OUTAGE U-l and Common il 0-74-87 'O' Diesel Generator Lube and Filter Change 0-75-87 'O' D/G Temperature and Oil Switches I

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3. Off-Site Dose Calculation Manual l

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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! LASALLE NUCLEAR POWER STATION UNIT 2 i

i MONTHLY PERFORMANCE REPORT 1

I ~ APRIL, 1987 l

! COMMONWEALTH EDISON COMPANY i

f NRC DOCKET NO. 050-374 i

t LICENSE NO. NPF-18 i

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TABLE OF CONTENTS 4

I. INTRODL37 TION II. MONTHLY REPORT FOR UNIT TWO A. Summary of Operating Experience

-B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE 4,

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 i
5. Completed Safety Related Modifications C. LICENSEE EVENT REPORTS 1

D. DATA TABULATIONS 4

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 j System
5. Indications of Failed Fuel Elements 1

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Q: 6 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 ir rejseted 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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II.. MCNTHLY REPORT FOR UNIT TWO

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'A. . SU19tARY OF OPERATING EXPERIENCE FOR UNIT TWO APRIL 01-30, 1987 ,

4-1-87, 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> - Rx in refuel 4-30-87, 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> - Rx in refuel.

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, D. , PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED 1 MAINTENANCE.

1. Amendments to Facility license, or Technical Specification.

AMENDMENT

  1. 30 This amendment revises the LSCS Unit 2 Technical Specifications to permit replacing an existing peripheral (02-43) locking piston control rod drive module with a fine motion control rod drive module during one fuel cycle (Cycle 2).
  1. 31 This amendment revises the LSCS Unit 2 Technical Specifications to reflect a low and/or degraded grid voltage modification in Division I of the electrical divisions.
  1. 32 This amendment revises the LSCS Unit 2 Technical Specifications to support operation of Unit 2 at rated power during Cycle 2 operation.
2. Facility or Procedure changes requiring NRC approval.

There were no Facility or Procedure changes requiring NRC approval curing 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.

DOCUMENT ID 0036r/0005r

s 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 49687 HPCS Switchgear Room Door seal is cracked. Replace seal. Seal Replaced.

Water Tight door.

54665 2B RHR S/D Cooling Valve binding. Repair Torque bonnet and stroked Check valve 2E12- valve. No binding problem F050B observed.

61481 Remove indicated Snubbers SC02-2808S and Remove snubbers on piping sub- Snubbers eliminated due to mechanical snubbers SC02-2805 system 2SCO2 reanalyze of subsystem.

61686 Reanalyze piping sub - Snubbers RH73-2003S 2004S, Remove snubbers Snubbers removed.

system 2RH73 to 2005S, and 2006S, delete unnecessary snubbers.

61942 Valve 2VP- 063B Torque switch failed suspect loose contact Tightened loose torque switch contacts, valve cycle sat.

62600 2A RHR SDC Return Valve leaking 'A' RHR discharge pressure Disassembled, repaired Isolation Stop 2E12- pressure slowly increases and reassembled. Proper F053A operations observed.

62888 Drywell Oil Plug Oil Plug on containment Clean and inspect Drain plug cleaned and Fitting wall is leaking re-tapped.

63333 HPCS Suction Isolation Test Valve under design Fould faulty torque switch Torque switch replaced.

Valve conditions. 502A05.

63550 HPCS Water Leg Relief Remove relief valve and Unit--2 Refuel Requirement Valve removed and tested Valve 2E22-F014 test eatisfactorily.

63697 Fuel Zone Level Chart drive does not Repair Cleaned and aligned chart Recorder 2B21-R615 advance drive. Verified proper Ops.

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 63870 Accumulator 38--59 When full closed valve Replace (111) cartridge (111) - cartridge replaced 2Cll-D001--lll leaks badly.

64038 Accumulator 22-03 Packing leak Replace (111) cartridge Cartridge replaced.

64039 Accumulator 18-07 Packing leak Replace (111) cartridge Cartridge replaced.

64040 Accumulator 10-11 Packing leak Replace (111) cartridge Cartridge replaced.

64041 Accumulator 14-11 Packing leak Replace (111) cartridge Cartridge replaced.

i 64042 Accumulator 30-15 Packing leak Replace (111) cartridge Cartridge replaced.

64043 Accumulator 22-15 Packing leak Replace (111) cartridge Cartridge replaced.

64044 Accumulator 18- 15 Packing leak Replace (111) cartridge Cartridge replaced.

64045 Accumulator 10-15 Packing leak Replace (111) cartr idge Cartridge replaced.

64046 Accumulator 02- 19 Packing leak Replace (111) cartridge Cartridge replaced.

I 64047 Accumulator 06-19 Packing leak Replace (111) cartridge Cartridge replaced.

64048 Accumulator 18--19 Packing leak Replace (111) cartridge Cartridge replaced.

64049 Accumulator 22 19 Packing leak Replace (111) cartridge Cartridge replaced.

64050 Accumulator 26-19 Packing leak Replace (111) cartridge Cartridge replaced.

64051 Accumulator 30-19 Packing leak Replace (111) cartridge Cartridge replaced.

64052 Accumulator 30- 23 Packing leak Replace (111) cartridge Cartridge replaced.

64053 Accumulator 26-23 Packing leak Replace (111) cartridge Cartridge replaced.

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TABLE 1 i .

CORRECTIVE MAINTENANCE OF l SAFETY RELATED EQUIPMENT I

Unit #2 i WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION l ON SAFE PLANT OPERATION l 64054 Accumulator 10-23 Packing leak Replace (111) cartridge Cartridge replaced.

64056 Accumulator 06-31 Packing leak Replace (111) cartridge Cartridge replaced.

64057 Accumulator 02-31 Packing leak Replace (111) cartridge Cartridge replaced.

64058 Accumulator 02--35 Packing leak Replace (111) cartridge Cartridge replaced.

64059 Accumulator 14-35 Packing leak Replace (111) cartridge Cartridge replaced.

64060 Accumulator 18-35 Packing leak Replace (111) cartridge Cartridge replaced.

64061 Accumulator 02-39 Packing leak Replace (111) cartridge Cartridge replaced.

64062 Accumulator 06-43 Packing leak Replace (111) cartridge Cartridge replaced.

64063 Accumulator 10-43 Packing leak Replace (111) cartridge Cartridge replaced.

64064 Accumulator 26-47 Packing leak Replace (111) cartridge Cartridge replaced.

E4065 Accumulator 14-47 Packing leak Replace (111) cartridge Cartridge replaced.

64066 Accumulator 06-47 Packing leak Replace (111) cartridge Cartridge replaced.

64067 Accumulator 26-51 Packing leak Replace (111) cartridge Cartridge replaced.

64068 Accumulator 26-59 Packing leak Replace (111) cartridge Cartridge replaced.

64104 Accumulator 38-43 Packing leak Replace (111) cartridge Cartridge replaced.

64105 Accumulator 58-43 Packing leak Replace (111) cartridge Cartridge replaced.

64106 Accumulator 54-43 Packing leak Replace (111) cartr.dge Cartridge replaced.

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 64116 Damper Actuators for To prevent seals from de- Remove / Replace Cylinders. Two (2) cylinders replaced 2VR04YB (2FZ-VR015) grading, vendor recommends with new ones.

air cylinders be replaced each refueling outage.

264117 Damper actuators for To prevent seals from de-- Remove / Replace Cylinders. Two (2) cylinders replaced 2VR04YA (2FZ-VR014) grading, vendor recommends with new ones.

air Cylinders be replaced each refueling outage.

264118 Damper actuators for To prevent seals from de- Remove / Replace Cylinders. Two (2) cylinders replaced 2VR05YD (2FZ-VR002) grading, vendor recommends with new ones.

air cylindars be replaced each refueling outage.

64141 Accumulator 42-55 Packing leak Replace (111) Cartridge. Cartridge replaced.

64142 Accumulator 42-51 Packing leak Replace (111) Cartridge. Cartridge replaced.

64144 Accumulator 38-51 Packing leak Replace (111) Cartridge. Cartridge replaced.

64145 Accumulator 34-47 Packing leak Replace (111) Cartridge. Cartridge replaced.

64146 Accumulator 42-47 Packing leak Replace (111) Cartridge. Cartridge replaced.

64147 Accumulator 46-47 Packing leak Replace (111) Cartridge. Cartridge replaced.

64148 Accumulator 34-43 Packing leak Replace (111) Cartridge. Cartridge replaced.

64202 Accumulator 34-35 Packing leak Replace (111) Cartridge. Cartridge replaced.

64248 Accumulator 42"27 Packing leak Replace (111) Cartridge. Cartridge replaced.

64249. Accumulator 42-23 Packing leak Replace (111) Cartridge. Cartridge replaced.

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TABLE 1

  • I f CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT .

CORRECTIVE ACTION Unit #2 RESULTS AND EFFECTS COMPONENT CAUSE OF MALFUNCTION WORK REQUEST ON SAFE PLANT OPERATION Cartridge replaced.

Packing leak Replace (111) Cartridge.

64250 Accumulator 38--27 Cartridge replaced.

Packing leak Replace (111) Cartridge.

UI251 Accumulator 34--27 Cartridge replaced.

Packing leak Replace (111) Cartridge.

64253 Accumulator 46-27 Cartridge replaced.

Packing leak Replace (111) Cartridge.

64055 Accumulator 18-27 Reading full scale. Transmitter recalibrated RCIC Pressure Gage Pressure gage damaged and assured proper Ops.

64294 Set limimts and cycled Valve does not cycle. Troubleshoot valve satisfactorily.

64441 *B* RHR S/D Cooling Test. Check Valve 2R12-F0508 Snap ring replaced.

Yaglve 2E32-F002E Handwheel rises when valve Repair 64490 is stroked, declutch lever does not work properly.

Troubleshoot Solenoid valve found off.

RHR Testable Check No indication of the Reterminated and tested 64602 Control Room. satisfactorily.

Valve 2E12-F050A Dirty or intermittent contacts Replaced relay 74Fl.

Relay 74F1 at SVGR Relay not functioning. on relay.

64937 243 ACB 2433 Cartridge replaced.

Packing Leak Replace (111) Cartridge.

65096 Accumulator 54--23 Cartridge replaced.

Packing Leak Replace (111) Cartridge.

65097 Accumulator 50 -23 Cartridge replaced.

Packing Leak Replace (111) Cartridge.

65098 Accumulator 50-19 Cartridge replaced.

Packing Leak Replace (111) Cartridge.

65099 Accumulator 34-15 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 65100 Accumulator 34-19 Packing Leak Replace (111) Cartridge. Cartridge replaced.

65101 Accumulator 38--15 Packing Leak Replace (111) Cartridge. Cartridge replaced.

65102 Accumulator 50--15 Packing Leak Replace (111) Cartridge, Cartridge replaced.

65103 Accumulator 46-11 Packing Leak Replace (111) Cartridge. Cartridge replaced.

65104 Accumulator 38--07 Packing Leak Replace (111) Cartridge. Cartridge replaced.

65105 Accumulator 42-07 Packing Leak Replace (111) Cartridge. Cartridge replaced.

65106 Accumulator 34-03 Packing Leak Replace (111) Cartridge. Cartridge replaced.

65107 Accumulator 42-03 Packing Leak Replace (111) Cartridge. Cartridge replaced.

65319 Penetration E-26 Leak found at the input to Repair Repair leak and charged the flange. to 30 lbs.

65368 FBCCW Otbd. Isol. Snap ring missing from Replace Snap ring replaced.

Valve 2WR029 handwheel.

65371 RWCU Otbd. Isol. Valve failed L.L.R.T. Repair Torque switch adjusted.

Valve 2G33-F004 Proper Ops. observed.

65384 Valve 2E12-F041C Valve does not cycle Air cylinder leaks. Replaced air cylinder and spring.

65553 MCC 235x--I Contactor sticks Repair Adjusted mechanical interlocks assured proper Cps, i

DOCUMENT ID 0036r/0005r

TABLE 1

CORRECTIVE MAINTENANCE OF i SAFETY RELATED EQUIPMENT 1

Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION l

I ON SAFE PLANT OPERATION l

l l

l 67570 2H-IRM 2C51AZ009D 2H-IRM will not drive Investigate -- Drive Cable Reset the limits and out. insulation was worn allowing repaired the insulation.

l l water to drain through the Assured proper Ops.

drive cable, into the gear box.

65735 RHR Heat Exchanger Torque Switch contacts Internal mechanical problem. Replaced worm and worm Shell Side Bypass make after torquing out. gear. Verified proper 2E12-F048B Ops.

65957 RHR S/D Cooling Vlv Stem is leaking water. Repack Valve repacked.

2E12-F006A 66050 HPCS p.p. Breaker Nylon bushings for Cam Replace Removed and replaced nylon 2E22-C001 shaft bearings are badly bushings.

frayed.

66109 RHR Pump Min Flow Stem end of viv operator. Replaced Missing bolts have been bypass viv 2E12-F064C Missing bolts and lock-- replaced, washers.

66164 Flange Upstream of Flange leaking when Repair - Torque as needed. Bolts not torqued as re--

2E12- F003B pressure testing. quired. Cleaned faces of flange and torqued to 750 Ft. Lbs.

66211 valve 2B21-N020D Valve Leaks Repair Valve repaired and Q.C.

Inspected for no leaks.

66212 Mechanical Snubber Damaged Snubber Replace Damaged snubber replaced MSO4-2794-S with a new one.

66213 Mechaalcal Snubber Damaged Snubber Replace Damaged snubber replaced MS00 2013-S with a new one.

66214 Mechanical Snubber Damaged Snubber Replace Damaged snubber replaced MS06-2004-S with a new one.

DOCUMENT ID 0036r/0005r

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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 l ON SAFE PLANT CPERATION 66215 Mechanical Snubber Damaged Snubber Replace Damaged snubber replaced M334-2810-S with a new one.

66216 Mechanical Snubber Damaged Snubber Replace Damaged snubber replaced MS04-2645-S with a new one.

i 66217 Mechanical Snubber Damaged Snubber Replace Damaged snubber replaced MSO4-2808-S with a new one.

66218 Mechanical Snubber Damaged Snubber Replace with new snubber. Damaged snubber replaced.

LC01-2967-S 66409 2E31- F005B4 Broken Flex on 2LD184. Determ Cable and repair. Flex repaired and cable reterminated.

66420 2E12-F050B Broken Flex on Cable 2RH253 Determ cable and repair. Flex repaired and cable reterminated.

66459 2E12-F041C Actuator Wiring to Solenald are Replace Replaced Solenoid Valve twisted and appear heat Coll, cable and sealtite.

damaged.

66587 Accumulator 50-23 Solenoid Blowing Air Repair Bonnet screws loose.

Retorqued to 120 inch-lbs.

66612 3/4" Flex conduit at Conduit damaged Replace Replaced damaged flex.

2E22-S001 66720 Mechanical Snubber Damaged Snubber. ' Replace snubber Damage snubber replaced M204-2711-S with a new one.

66755 Rx. Vessel Shroud Transmitter does not re- Replace New transmitter installed Level Transmitter spond to test inputs. and calibrated.

2B21-N044B l DOCUMENT ID 0036r/0005r

TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT Unit #2 WORK REQUEST COMPONENT CAUSE Ot7 MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION 66774 Div I Battery Gnd. Alarm sounds whenever viv Troubleshoot and repair. Removed limitorque cover Alarm 2E12-F006A is open and found pinched wire between body and cover.

Repair and assured proper Ops.

66830 Valve 2E12-F026A No light indication in Bad Relay Replaced relay and assured Control Room. proper Ops.

66848 Fuse Holder for 2E22- Side broken out of fuse Replace holder Replaced fuse holder C001 Block.

66885 Mechanical Snubber Snubber damaged Replace snubber Snubber replaced.

RH27-2003-S 66935 CRD HCU 34-39 Blowing Air from gaskets Check torque Tightened union above l

scram valve.

l 66968 HPCS Pump Disch. Threads on body of trans- Replace transmitter. Transmitter replaced and l Pressure Indicator mitter are gone. calibrated.

2E22- N004 I 67003 Directional Control Valve is leaking water Repair leak Leak repaired.

l Valve Solenoid 123 HCU 26-59 l

67016 Mechanical Snubber Snubber damaged Replace snubber Snubber replaced with new RIA2 2999-S one.

67076 HCU 58-35 Scram Pilot Solenoid has a Rebuild 118 Viv. Rebuilt 118 Valve.

blown diaphragm.

67129 RHR B/C Water Leg Control relay contacts are Repair / replace Cleaned relay contact and

! Pump 2E12-C003 intermittent. verified proper ops.

DOCUMENT ID 0036r/0005r

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l TABLE 1 l

l CORRECTIVE MAINTENANCE OF l SAFETY RELATED EQUIPMENT 1

i l Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION l ON SAFE PLANT OPERATION 67131 RHR Heat Exchanger A Overload Relay would not Repair / Replace Overload relay replaced.

Discharge 2E12--F068A trip when tested.

67188 RHR S/D Cooling Inj. Breaker contacts show Replace Replaced breaker for a new valve 2E12-F053A evidence of pitting / mis- one.

alignment.

l l 67194 Supp. Pool Temp Reading Downscale Troubleshoot Replaced wiring harness.

Monitoring Recorder 2TR-CM037 67350 2E12-F020 Loose Limit Switch Arm on Repa?r Tightened limit switch the valve stem. actuating arm. Verified proper ops.

67368 HCU 42-03 Packing Leak Replace (113) cartridge. Cartridge replaced.

67496 HPCS Water Leg Pump Does not hold pressure. Repair Lapped seat, reassembled Check Valve and seal welded bonnet.

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DOCUMENT ID 0036r/0005r i

. . . 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-1-2-82-014 This Modification was to remove a G.E. pushbutton and control switches located in the Diesel Generator 2A engine gauge panel from the engine skid to meet NRC requirements.

There were no unreviewed safety questions.

M-1-2-83-012 This Modification was to implement the Electrical Maintenance Department M.I. 9644 lube oil system change on the '2B' diesel generator. This will improve the oil circulating subsystem which supplies ol' to the engine for emergency starts. There were no unreviewed safety questions.

M-1-2-84-110 This Modification was for the addition of new pressure switches and also new relays for the low RHR pump discharge pressure alarms and the engineered safety feature status.

There were no unreviewed safety features.

M-1-2-84-111 This modification was to install a Thermowell in the RHR Shutdown cooling line 2RH04C-20. There were no unreviewed safety questions.

M-1-2-84-129 This modification was to separate the High/ Low pressure alarms in the LPCS pump discharge pressure switches. There were no unreviewed safety questions.

M-1-2-85-049 This modification was for the replacement of the GE Model NA-200 Local Power Range Monitors (LPRM's) with the Westinghouse model WL-24286 LPRM. There were no unreviewed safety questions.

M-1-2-86-039 This modification was to add a high point vent to the existing piping of the RHR system on line 2RH41AA-3" and 2RH70A-3". There were no unreviewed safety questions.

M-1-2-86-041 This modification was to add a high point vent to the existing piping of the RHR system in line 2RH038B-12".

There were no unreviewed safety questions.

M-1-2-86-042 This modification was to add a high point vent to the existingpiping of the RHR system on lines 2RH03BA-12" and 2RH34A-6". There were no unreviewed safety questions.

DOCUMENT ID 0036r/0005r

. *. . TABLE 2 (cont'd)

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

M-1-2-86-050 This mod was to add a redundant contact from a different relay in series with the existing contact. This will prevent a single short of a relay from operating the pilot valve. There were no unreviewed safety questions.

M-1-2-86-053 This modification was part of the snubber reduction program for subsystem 2SC02. There were no unreviewed safety questions.

M-1-2-86-054 This modification was part of the snubber reduction program for subsystem 2RIO3. There were no unreviewed safety questions.

M-1-2-86-058 This modification was part of the snubber reduction program for subsystem 2RRC2. There were no unreviewed safety questions.

M-1-2-86-060 This modification was part of the snubber reduction program for subsystem 2RRA9. There were no unreviewed safety questione.

M-1-2-86-061 This modification was part of the snubber reduction program for subsystem 2MS648. There were no unreviewed safety questions.

M-1-2-86-066 This modification was part of the snubber reduction program for subsystem 2MS64F. There were no unreviewed safety questions.

M-1-2-86-068 This mexlification was part of the snubber reduction program for subsystem 2RHBl. There were no unreviewed safety questions.

M-1-2-86-069 This modification was part of the snubber reduction program for subsystem 2RRC7A. There were no unreviewed safety features.

M-1-2-86-071 This modification was part of the snubber reduction program for subsystem 2HpA1. There were no unreviewed safety )

questions. l M-1-2-86-078 This modification was part of the snubber reduction program for subsystem 2MS258. There were no unreviewed safety questions.

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e *. s TABLE 2 (cont'd)

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

M-1-2-86-085 This modification was to remove the existing Static-o-Ring level switch and replace it with a qualified Barton Level switch. There were no unreviewed safety questions.

l DOCUMENT ID 0036r/0005r

, o. o 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 I

period, April 01, through April 30, 1987. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CPR 50.73.

Licensee Event Report Number Date I.itle of Occurrence 87-005-00 4/2/87 Auto start of 2B D/G during testing.

87-006-00 4/2/87 Group II pCIS Isolation during Mod Test.

87-007-00 4-12-87 Group II Isolation during 1

testing due to failed 2C71-K4Dl.

i

87-008-00 4-14-87 Scram Signal while moving mode l switch due to blown fuses.

i 87-009-00 4-15-87 ESP Actuation during LLRT due to leakage past stop valve.

i 87-010-00 4-17-87 Scram Signal while defueled/ contractor bumped APRM Cable under RPV.

87-011-00 4-30-87 Static 'O' Ring differential i pressure switch out.

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DOCU:1ENT ID 0036r/0005r

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l 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

I DOCUMENT ID 0036r/0005r i

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

. a. ,

1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT ],aSalle Two DATE May 10. 1987 COMPLETED BY Gregory Kirchner TELEPHONE (815)357-6761 MONTH APRIL 1987 OPERATING STATUS f
1. REPORTING PERIOD: April, 1987 GROSS IlOURS IN REPORTING PERIOD: 719
2. CURRENTLY AUT140RIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078,
3. POWER LEVEL TO WiiICH RESTRICTt!D (IF PNY) (MWe-Net): 1050
4. REASONS FOR RESTRICTION (IP ANY); Administrative TilIS MONTH YR TO DATE . CUMULATIVE 5 NUMBER OF llOURS REACTOR WAS CRITICAL 0.0 66.05 'l"069.5
6. REACTOR RESERVE SHUTDOWN }{OURS 0.0 0.0 29.83
7. HOURS GENERATOR ON LINE 0.0 59.92 11830.84

]

8. UNIT RESERVE SHUTDOWN llOURS 0.0 0.0 0.0
9. GROSS TIIERMAL ENERGY GENERATED (MWil) 0.0 120864 23635128
10. GROSS ELEC. ENERGY GENERATED (MWH) 0.0 39232 11100804
11. NET ELEC. ENERGY GENERATED (MWil) -7324 4757 10544986
12. REACTOR SERVICE FACTOR 0% 2.2% 53.3%
13. REACTOR AVAILABILITY FACTOR 0% 2.2% 54.5%
14. UNIT SERVICE FACTOR 0% 2.1.% 53%
15. UNIT AVAILABILITY FACTOR Q1 2.1.% 53%
16. UNIT CIPACITY FACTOR (USING MDC) -0.9% 0.16% __.45,81_
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) -0.9% 0.15% 44%

, 18. UNIT FORCED OUTAGE RATE 0% 0% 26.2%

19. bHUTDOWNS SCllEDULED OVER NEXT 6 MONTilS (TYPE, DATE, AND DURATION OF EACH):

N/A Unit is in shutdown during this period.

20. IF S!!UT DOVN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP 5/30/87 I

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2. AVERAGE DAILY UNIT POWER LEVEL' DOCKET NO: 050-374 '

UNIT: ' LASALLE 'i'WO DATE: May 10. 1987 COMPLETED BY: Gregory Kirchner TELEPHONE: (815) 357-6761 MONTH: April 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l (MWe-Net) (MWe-Net) l 4

l

1. -8 17. -10
2. - -9 18. -9 3 -10 19. -9
4. -10 20. -9
5. -9 21. -9
6. -9 22. -9'
7. -10 23. -11
8. -9 24. -13 s
9. -10 25. -

12

10. -10 26. -

14

11. -9 27. r14
12. -8 28. -

14 >

13. -8 29. -14
14. -7 30. -14
15. -8 31. ---
16. -10 f I I

l DOCUMENT ID 0036r/000Sr

%,y.,--, --, , - -w-_m_ .-

.,...#,,,p,, , , . . . . , ,-.-. y. , , ._ _,.-_..,.-,,,.~,%., _ , .

y, , . _ ,;-r- ,--%- , y--

3. UNIT SHUTDOWNS AND POWER REDUC' CIONS

. DOCKET NO. 050-374-UNIT NAME LaSalle Tt_oo , ,

DATE May 10, 1987 REPORT MONTH April, 1987 COMPLETED BY G.J. Kircfaner 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 / COP 9fENTS a
1 4/1/87 S 719 C 1 Refuel i

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DOCUMENT ID 0036r/0005r i

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

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i s .. s E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations for Unit Two.

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

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DOCUMENT ID 0026r/0005r

e

. . J. ECCS Systcm3 Outcg:s The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO. ROUIPMENT PURPOSE OF OUTAGE 2-1036-87 2E12-C300D Prevent use of motor which is torn apart.

2-1044-87 2HG-006A Rebuild 2HG006A.

2-1047-87 2E12-F092B Prevent inadvertantly filling the reactor.

2-1048-87 D/G 2B - Soak Back oil pump Replace damaged flex.

2-1051-87 2B D/G Calibrate relays.

2-1056-87 2E51-F064 Perform E.Q. Inspection.

2-1063-87 2A D/G Replace Air Start motors.

2-1069-87 RCIC Turbine Trip Throttle Replace Packing bushing.

2-1070-87 2E12-F050B Replace Flex.

2-1075-87 2E12-F024A and B Install temporary system change for full closure of valves.

2-1076-87 2E51-F059 Troubleshoot Limitorque.

2-1101-87 2A RHR Heat Exchanger Switch Replace overload relay.

Outlet.

2-1102-87 B and C RHR Water Leg Pump Replace control relay.

2-1104-87 2E12-F074B Replace nicked wire.

2-1107-87 2B RRR System Repair leaking flow orifice.

2-1111-87 2E12-F006A Repack Valve.

2-1118-87 2E12-F050B Repair sealtite.

2-1121-87 2E12-F041B Replace limit switch.

2-1122-87 2E12-F041C Replace sealtite and solenoid.

2-1127-87 2E12-F099A Replace reverse contactor.

2-1128-87 2E12-F053A Replace circuit breaker.

2-1150-87 ".CIC Division 1 Power Ground Isolate.

2-1158-87 ZE12-F047B Repair / Replace Butt Splice.

2-1157-87 2E12-F048B Repair / Replace Butt Splice.

2-1159-87 2E12-F006B Repair / Replace Butt Splice.

2-1160-87 2E12-F009 Repair / Replace Butt Splice.

2-1161-87 2E12-F049B Repair / Replace Butt Splice.

2-1162-87 2E12-F042B Repair / Replace Butt Splice.

2-1163-87 2E12-F016B Repair / Replace Butt Splice.

2-1165-87 2E51-F019 Limitorque Work.

2-1170-87 2E51-F054 Replace cable 2RIO95.

2-1173-87 2E12-F027B Repair overload relay and wires.

2-1174-87 2E12-F050A Reconnect solenoid.

2-1191-87 2A RHR Pump Inspect motor.

2-1203-87 2E12-F332C Lock throttle at 4000 G.P.M.

while 2 'D' Service Water Pump is Out-of-Service.

DOCUMENT ID 0036r/0005r

e OUTAGE NO. EOUIPMENT PUNPOSE OF OUTAGE 2-1215-87 HCU 22-23 Repair leaking 113 viv.

2-1224-87 2A RHR Pump Seal Cooler Clean and inspect.

2-1228-87 2A RHR Pump inspect Motor.

2-1241-87 2E12-F083B and -F084B Laak Repair.

2-1242-87 2E12-F087B Repair contactor.

2-1245-87 2E51-F064 Repair limitorque compartment cover.

2-1250-87 2E12-F049A Replace overload relay.

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

2-1253-87 HPCS D/G Air Start Solenoid Repair / Replace Air Start Solenoid Vlv.

2-1261-87 RI Hd Spray Remove blank flange and install HD Spray Line.

2-1262-87 2E12-C300D 2D RHR Service Repair Seized Pump.

Water Pump.

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_w_.c ._, ,e. _ _

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d * . 8. Off-site Doso calculation Manual There were no changes to the ODCM diiring 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 Puel Elements.

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

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DOCUMENT ID 0036r/0005r

I May 7, 1987 I

Director, Office of Managemc7t Information and Program Control j 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 April 1, 1987 through April 30, 1987.

Very truly yours, fh-

+G.J. Diederich Station Manager LaSalle County Station GJD/GJK/sjc l Enclosure xc: J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle 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 /

/(f.

r C. F. Dillon, Senior Financial Coordinator, LaSalle J. C. Klika, Surveillance Group Leader I

(

Dennis Carlson/ Tech Staff (

Terry Novotney/ Training Central File DOCUMENT ID 0043r/0005r

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