ML20197D463

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Monthly Operating Repts for Apr 1986
ML20197D463
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 04/30/1986
From: Diederich G, Peters J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM)
References
NUDOCS 8605140278
Download: ML20197D463 (35)
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9 LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT APRIL, 1986 COfMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 8605140278 860430 PDR ADOCK 05000373 ,

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t O TABLE OF CONTENTS I. INTRODUCTION i

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 Changes Requiring NRC Approval ,
3. Tests and Experiments Requiring NRC Approval
4. Corrective Maintenance of Safety Related Equipment C. LICENSEE EVENT REPORTS D. DATA TABULATIONS
1. Operating Data Report
2. Average Daily Unit Power Level
3. tilt 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 i

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4 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 i contractor was Commonwealth Edision 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 i commenced on January 1, 1984.

This report was compiled by James P. Peters, telephone

] number (815)357-6761 extension 325.

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II. MONTHLY REPORT FOR UNIT ONE i

A. SUNULRY OF OPERATING EXPERIENCE FOR UNIT ONE April 1 - 30 April 1, 0001 Hours. The Unit entered April with the reactor subcritical and Unit Off-Line in cold shutdown for first refueling outage.

April 30, 2400 Hours. Reactor in cold shutdown for first refueling outage.

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

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1. Amendments to facility license or Technical Specification.

AMENDMENT 37 - Vent and Purge Isolation Valves Upgrade Revision.

AMENDMENT 38 - Chlorine Detector Removal.

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2. Facility or procedure changes requiring NRC approval.

There were no Facility or Procedure Changes Requiring Ntc 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.

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I TABLE 1 o.

l CORRECTIVE MAINTENANCE OF

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SAFETY RELATED BQUIPMENT NORK RBQUEST Coff0NENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS -CORRECTIVE ACTION ON SAFE PLANT OPERATION I

L22535 RHR Discharge Pressure Tech. Spec. Requirements Conflict between instrument Installed new IE12-N512 Inst. IE12-N022A/B/C accuracy and Tech. Spec. A/B/C instruments.

Requirements.

4 L31439 LPCS Testable Check M-1-1-84-003 No Potential Effect. Remove Valve Per ECN-Bypass Valve IE21-F333 PFL-49-LS/ED-85.

t 1 L31440 HPCS Testable Check M-1-1-84-003 No Potential Effect. Remove Valve Per ECN-l Bypass Valve IE22-F354 PFL-49-LS/ED-85.

L31441 RCIC Testable Check M-1-1-84-003 No Potential Effect. Remove Valve Per ECN-Bypass Valve IE51-F355 PFL-49-LS/ED-85.

L31442 LPCI INBD Testable M-1-1-84-003 No Potential Effect. Remove Valve Per BCN-Check Bypass Valve PFL-49-LS/ED-85.

  • IE12-F327A.

L31443 LPCI Outbd Testable M-1-1-84-003 No Potential Effect. Remove Valve Per BCN-

Check Bypass Valve PFL-49-LS/ED-85.

I 1E51-F354 1

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L40863 Barton Diff. Press M-1-1-84-106 Environmental Qualifications. Replaced Per BCN-BD-141/

i Switches IB21-N026. PFL-158.

j L40974 Barton Diff. Press. M-1-1-84-106 Environmental Qualifications. Replaced Per ECN-ED-141/

Switched IB21-N044 PFL-158.

f L43683 RCIC Isolation Valves Leakage Through the packing. Valve Leaking, Hampering Level Cleaned Seating Surface.

, Por Level Switches switch Calibration.

l lE51-F331.

l L51383 1A RHR Min. Flow Valve Leakage through Packing LTS-900-12 LLRT Repacked Valve.

IE12-F064A.

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Tall.E 1 O

CORRECTIVE MAINTENANCE OF SAFETY RELATED BQUIPMENT ,

WORK RBQUEST CONONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L535% S/D Cooling Testable Limit Swltches incorrectly Valve indicates closed when Upset limit switches.

check valve IE12-P050B set. valve is actually open.

L54558 H2 Recombiner Inlet Limit Switches incorrectly Valve opens, but will not full Reset limit switches Valve from U2 lHG0028 set, close from control room, per L8S-BQ-ll2.

L55159 Limitorque Valve Broken Clutch gear. Motor Runs but does not Replaced clutch gear.

IE51-F064. engage with valve.

L55957 RBCCW D/W outbd Isol. Bad Pinion Gear on Limit LTS-100-30, LLRT. Replaced Pinion gear on Valve IWR040. Switch. Limit Switch.

L55993 Mechanical Snubbers Bad Snubber Failed LTS-500-14. Replaced Snubt;er.

RH53-1562S.

L56 M7 Mechanical Snubbers Bad Snubber Failed LTS-500-4 Replaced Snubber.

, LP02-1059S l

l l L56232 Mechanical Snubber Bad Snubber Failed LTS-500-14. Replaced Snubber.

! RH13-1154S.

i L56235 RCIC Pump Suction Bad Main En Aux. Contactors Valve Spuradically opens from Replaced Main and Aux.

Valve IE51-F010 Control Room. Contactors.

L56387 Mechanical Snubber Bad Snubber. Failed LTS-500-14. Replaced Snubber.

LC01-1005S.

L56388 Mechanical Snubber Bad Snubber. Failed LTS-500-14. Replaced Snubber.

MGil-1003S.

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j L56389 Mechanical Snubber Bad Snubber. Failed LTS-500-14 Replaced Snubber.

RH-1213 H02s.

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TABLE 1 CORRECTIVE MAINTENANCE OF i

SAFETY RE'ATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L56423 Mechanical Snubber Bad Snubber. Failed LTS-500-14. Replaced Snubber.

RH-1207-H093 L56424 Mechanical Snubber Bad Snubber. Failed LTS-500-14. Replaced Snubber.

RH23-H07S L56425 Mechanical Snubbers Bad Snubbers. Failed LTS-500-14. Replaced Snubbers.

RIl09-1005S/1008S/

1026S.

L56426 Mechanical Snubber Bad Snubber. Failed LTS-500-14. Replaced Snubber.

RR69-H09S.

L56614 RHR Hx Vent Valve Pinch wire on Limit Switch When valve is full open Repaired pinched wire.

IE12-F073A. No indication.

L56902 RHR Test Return Valve M-1-1-84-090 No Potiential Effect. Reset thermal O/L and IE12-F021. Magnetic settings per ECN-ED-167-3.

L56952 RBCCW D/W outed Isol. Bad Packing. Amperage Higher than acceptable Repacked valve.

Valve IWR040. criteria.

i L57118 LPRM String 16-41. Bad LPRM String 16-41. Inoperble LPRM String Replaced LPRM String 16-41.

L57140 RHR S/D cooling Isol. Misadjusted limit switch Valve would not open with Diff. Readjusted limit switch.

Valve IE12-F009. in Open Circuit. Press Across valve.

L57162 RBCCW LWR 179 Valve Bad Thermal O/L. Thermal O/L Does Not Trip Replaced Thermal O/L.

MCC 136Y-2-Compt. Manualy during LES-GM-109.

A4 O/L Trip.

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TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L57163 RBCCW IWR180 Valve Sticking and Dirty Forward and reverse contactors. Cleaned and lubricated Forward and Reverse contactor. Stick when manually actuated. contactors.

contactors.

L57175 H2 Recombiner Supply Burned Transformer in Valve will not cycle open Replacer

  • burned valve from U2. breaker. electrically, transformer.

lHG018.

L57216 1AP71E, MCC 135X-1 Interconnecting Linkage contactor sticks when manually cleaned, Lubricated and Compt.-E3 for was binding, actuated. realigned linkage.

IB21-F067C Valve.

L57233 1AP76E, MCC 135Y-2 Bakelite on Main circuit No Potiential Effect, Valve Replaced Breaker.

Compt. B6 For Breaker is broken. cycled.

IE12-F006A valve.

L57246 Mechanical Snubber Bad Snubber. Failed LTS-500-14. Replaced Snubber.

RH40-1539S.

L57247 Mechanical'SnubDer Bad Snubbers. Failed LTS-500-14. Replaced Snubbers.

RH53-1565S and RH14-1047S.

L57250 Mechanical Snubbers Bad Snubbes. Failed LTS-500-14. Replaced Snubbers.

RH40-154ES/1544S/

1554S.

L57251 Mechanical snubbers Bad Snubber. Failed LTS-500-14. Replaced Snubber.

RR00-1004S.

L57268 LPRM 16-41 LPRM Housing is Bent. LPRM is obstructed from seating Straighten and Grounded in Guide Tube. LPRM.

L57272 Mechanical Snubber Bad Snubber Failed LTS-500-14. Replaced Snubber.

RH-1209-H03S.

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TATLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED BQUIPMENT +

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L57274 Mechanical Snubber Bad Snubber Failed LTS-500-14 Replaced Snubber.

RR17-1005S.

, L57275 Mechanical Snubber Bad Snubber Failed LTS-500-14. Replaced Snubber.

RR17-1008S.

I L57276 Mechanical Snubber Bad Snubber Failed LTS-500-14. Replaced Snubber.

RH50-1017S.

L57277 Mechanical Snubber Bad Snubber Failed LTS-500-14. Replaced Snubber.

RR01-1032S.

L57279 Mechanical Snubber Bad Snubber Failed LTS-500-14. Replaced Snubber.

RRCO-1011S L57280 Mechanical Snubber Bad Snubbers. Failed LTS-500-14. Replaced Snubbers.

RHB4-1008S/1011S.

L57281 Mechanical Snubber Bad Snubbers Failed LTS-500-14. Replaced Snubbers.

RR17-1003S/1004S/

1007S L57282 Mechanical Snubber Bad Snubbers. Failed LTS-500-14. Replaced Snubbers.

RHB4-1007S and RH52-H09S.

!. L57283 Mechanical Snubbers Bad Snubbers Failed LTS-500-14. Replaced Snubbers.

M-1302-28-84/22-110/

21-40.

L57284 Mechanical Snubbers Bad Snubbers Failed LTS-500-14 Replaced Snubbers.

RR00-1030S/1061S.

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TABLE 1

  • I CORRECTIVE MAINTENANCE OF l SAFETY RELATED EQUIPMENT .

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WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION l ON SAFE PLANT OPERATION l l

l L57285 Mechanical Snubbers Bad Snubbers Failed LTS-500-14. Replaced Snubbers. I

, ' RR00-1022S/1043S.

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L57315 Mechanical Snubbers Bad Snubbers. Failed LTS-500-14. Replaced Enubbers.

RR00-1062S. l l

L57316 Mechanical Snubbers Bad Snubbers. Failed LTS-500-14. Replaced Snubbers. l RR00-1014S.

L57368 Mechanical Snubbers Bad Snubber. Failed LTS-500-14. Replaced Snubbers.

SC02-1045T/G.

L573 9 Mechanical Snubber Bad Snubber Failed LTS-500-14. Replaced Snubber.

ER00-1059S.

L57465 LPCS Full Flow Test Motor Pinion Gear Key Inoperable Valve. Replaced Pinion Gear Valve IE21-F012. Sheared. Key.

L57480 Mechanical Snubber Bad Snubber. Failed LTS-500-14. Replaced Snubber.

M-1302-30-52.

L57483 "A" RHR LPCI Testable Limit Switches incorrectly Valve has dual indication in Reset Limit Switch Check valve IR12-F041A set. cohtrol room, and wil1 not go Cams.

full closed.

L57517 Mechanical Snubbers Bad Snubber. Failed Stroke Check. Replaced Snubber.

M1302-26-110.

L57649 H2 Recombiner Valve Bad Worm Gear Asse. ably and Motor will not stop running on Replaced worm gear From U2 lHG005B. Tripper Finger Assembly. limitorque. Assembly and Tripper Finger Assembly.

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TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L57695 A RHR Hx Vent Motor Cut and Pinched wires. Motor keeps blowing control Repaired and relugged Operated valve power fuses. wires.

IE12-F073A.

L57338 "A" VE Return Fan Actuator was bound at Damper was stuck open. Replaced Actuator.

Inlet Damper 90% open when deenergized.

OVE06YA.

L57873 IC71-K14A/E contacts. Aux. Contact Clip had No control Room Alarm. Replaced Clip.

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i C. LICENSEE EVENT REPORTS 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 through April 30, 1986. This information is provided pursuant to the reportable occ!!rrence reporting requirements as set forth in 10CFR 50.73.

Licensee Event Report Number Date Title of Occurrence 86-011-00 03/17/86 Primary Containment Isolation Due to Operator ordering jumpers removed.

86-012-00 04/02/86 "A" VC Emergency Make-Up Train ,

spurious trip of "A" Hi Radiation Monitor Due to calibration procedure.

86-013-00 04/03/86 Loss of Bus 141Y and Auto Start of "0" Diesel Generator.

86-014-00 04/12/86 Spurious Trip of NH3 Detector Due to a Broken Chem-Cassette Tape.

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. D. DATA TABULATIONS 4

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 DATE 5/10/86 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS 1

l. REPORTING PERIOD: April 1986 GROSS HOURS IN REPORTING PERIOD: 719 j 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): N/A

! 4. REASONS FOR RESTRICTION (IF ANY): N/A THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 12039.00 l 6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1642.00

7. HOURS GENERATOR ON LINE 0.0 0.0 11642.00
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 0.0 0.0 32213650
10. GROSS ELEC. ENERGY GENERATED (MWH) 0.0 0.0 10499394
11. NET ELEC. ENERGY GENERATED (MWH) -10967 -36437 9968020
12. REACTOR SERVICE FACTOR 0.0% 0.0% 58.9%
13. REACTOR AVAILABILITY FACTOR 0.0% 0.0% 66.9%
14. UNIT SERVICE FACTOR 0.0% 0.0% 56.9%

, 15. UNIT AVAILABILITY FACTOR 0.0% 0.0% 59.0%

16. UNIT CAPACITY FACTOR (USING MDC) -1.5% -1.2% 47.0%

! 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) -1.4% -1.2% 45.2%

18. UNIT FORCED OUTAGE RATE 0.0% 0.0% 17.4%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)

The First Refueling, Maintenance, Surveillance and Modification Outage began October 18, 1985 and will last into June, 1986.20.

IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: June 18, 1986 l

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2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: 5/10/86 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761 MONTH: APRIL 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

< 1. -14 17. -15

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

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

UNIT NAME LaSa11e One DATE 5/10/86 REPORT MONTH APRIL 1986 COMPLETED BY James P. Peters 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 /COPMENTS Thrre were no Unit shutdowns or power reductions during this reporting period i

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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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i 2. ECCS Sy2tems OutEgCs The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO. BOUIPMENT PURPOSE OF OUTAGE l-653-86 lE12-F009 Reset Limit Switch.

1-667-86 IE12-F009 Change Breaker.

1-668-86 IE12-F049A Change Motor 1-677-86 lE12-N010A Replace 3 Valve Manifold.

1-680-86 IE51-F063 Install Redundant Fault Protection.

1-681-86 1E51-F076 Install Redundant Fault Protection.

! 1-687-86 RHR S/D Cooling LES-PC-06.

1-688-86 lE51-F076 Install Redundant Fault Protection.

1-690-86 IE12-N010CA Repair 3 valve manifold.

1-697-86 lE12-F074B Replace Breaker.

1-698-86 IE12-F073B Replace Breaker.

1-700-86 lE32-F001E Replace Motor 1-710-86 lE21-F012 Repair Limitorque.

1-717-86 lE22-F010 Re-Lug Limitorque.

1-718-86 HPCS Snubbers 1-723-86 lE12-F063C Fill Suppression Pool 1-727-86 lE12-F050A Repack Valve 1-737-86 lE17-F041A Reset Limits.

1-740-86 lHG006B Ul/U2 Seperation l-748-86 lE21-F012 Repair Pinion Gear 1-754-86 lE12-F040B Set Magnetics 1-756-86 lE12-F090A Snubbers 1-759-86 A RHR WS System Inoperable to incomplete modifiction.

1-761-86 LPCS Pump LES-LP-101 1-762-86 LPCS Waterleg Pump Inspect / Repair '!

1-777-86 A RHR D/W Spray Install ILRT Spool Piece.

l-773-86 A RHR S/D Cooling LES-RH-100 LPCI Inj.

1-778-86 IB Fuel Pool Make-Up Pp. Rewind Motor.

1-780-86 IE12-F073A Inspect Blown Fuses 1-801-86 lE51-F064 Repack Valve 1-807-86 A RHR Keep System Filled with Waterleg Pp OOS.

1-814-86 IE12-F027A Install Limiter Plate, i 1-815-86 IB HPCS DG Change Oil. j l

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.~ 3. Off-Site Dose Calculation Manual There were no changes to the ODCM during this reporting period.

4. Radioactive Waste Treatment Systems.

There were no significant cheages to the radioactive waste treatment system during this reporting period.

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I i LASALLE NUCLEAR POWER STATION' UNIT 2 l

MONTHLY PERFORMANCE REPORT APRIL 1986 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 i

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. TABLE OF CONTENTS I. INTRODUCTION l

II. MONTHLY REPORT FOR UNIT TWO I

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 C. LICENSEE EVENT REPORTS D. DATA TABULATIONS

.i 1. Operating Data Report

2. Average Daily Unit Power Level l 3. Unit Shutdowns and Power Reductions l

E. UNIQUE REPORTING REQUIREMENTS .

1. Safety / Relief Valve Operations
2. ECCS System Outages
3. Off-Site Dose Calculation Manual Changes
4. Major Changes to Radioactive Waste Treatment System 1

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e' 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.

1 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 James P. Peters, telephone number (815)337-6761 extension 325.

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, II . MONTHLY REPORT FOR UNIT TWO O A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT TWO April 1-30 l

April 1, 0001 Hours. The Unit entered April with the i Reactor critical at 98% power and l Generator on line at 1097 MWe. I April 4, 0130 Hours. Reactor Power Reduced to 92% (1037 l MWe) Due to CRD Exercising per LOS-AA-W1.

April 4, 0700 Hours. Reactor Power increased to 95%

(1078 MWe and 3208 MWt).

April 11, 1910 Hours. Reactor Power Reduced to 88% (995 MWe) Due to CRD Exercising Per LOS-AA-W1.

April 12, 0700 Hours. Reactor Power Increased to 95%

(1064 MWe and 3170 MWt)

April 12, 2200 Hours. Reactor Power Reduced to 51% (600 MWe) Due to control rod manipulations.

April 16, 2300 Hours. Reactor Power Increased to Full Power, 99% (1103 MWe). Also, Power is drifting down due to Xenon Build In and Control Rods Held For Jet Pump Calibration.

April 19, 0050 Hours. Reactor Power Reduced to 90% (1019 MWe) Due to control rod manipulation.

April 19, 0700 Hours. Reactor Power Increased to 95%

(1070 MWe) limited by flow control line.

April 20, 0500 Hours. Reactor Power Reduced to 77% (861 MWe) Due to control rod manipulation.

April 21, 1500 Hours. Reactor Power Increased to 97%

(1093 MWe and 3259 MWt) Limited by Condensate Polisher Flow.

April 22, 2300 Hours. Reactor Power Decreased and Steady at 99% (1105 MWe and 3302 MWt).

April 25, 0245 Hours. Reactor Power Reduced to 92% (1034 MWe) Due Control Rod Manipulation.

April 25, 1500 Hours. Reactor Power Increased and Steady at 96% (1080 MWe and 3238 MWt).

April 26, 0240 Hours. Reactor Power Reduced to 73% (850 MWe) for MSIV/TSV surveillances and EGC Test.

April 26, 083 Hours. Reactor Power Ramp Held at 78%

(888 MWe) Due to failure of A RR M/A Station.

April 27, 0100 Hours. Reactor Power Increased to 92%

(1032 MWe).

April 27, 0315 Hours. Reactor Power Decreased to 80%

(900 MWe) Per Load Dispatcher.

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. April 1-30 April 28, 0700 Hours. Reactor P m r Increased to 99%

(1105 We and 3294 N t) but drifting down with Xenon built in.

April 30, 1500 Hours. Reactor Power Deceased to 96%

(1082 We).

April 30, 1530 Hours. Reactor Power Reduced to 75% (850 We) Due to repairs on Heater Drain Pump Forward Valve.

April 30, 2400 Hours. Reactor Power Steady at 75% (850 We and 3272 Nt).

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

1. Amendments to facility license or Technical Specification.

AMENDMENT 20 - Chlorine Detector Removal.

2. Facility or procedure changes requiring NRC approval.

There were no facility or procedure change requiring NRC approval during the reporting period.

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, 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.

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TABLE 1 ,

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CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT ,

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L56655 2B DG Fuel Oil Level Indicator 2CI-DOO12 Failure of LOS-DG-M3 Recaled Level Switches.

Transfer Pump System. Slightly out of Tolerance.

L57135 HCU 06-15 2Cll- Excessive Leakage HUC 06-15 Requires Recharging Replaced Cartridge D001-Ill Valve. once Per Day. Valve.

L57267 RCIC Water Leg Pump Pump Impeller Clearance Pump Generates Excessive Dis- Readjust Pump Impeller 2E51-C003. to High. charge Pressure. Clearance.

L57337 H2 Recombiner Inlet Improper Finger Base Valve Would Not Open During Replaced Finger Base Valve 2HG-FV-1 Assembly. Performance of LOS-HG-Ql.

L57!02 Div.-II Post Loca Pressure Switch 2PS- Alarm is Up with no actual Low Recalibrated Pressure Low Bottle Pressure CM102 was out of Bottle Pressure. Switch 2PS-CM102.

Alarm. Tolerance.

L57636 Mechanical Snubber Bad Snubber Failed LTS-500-4. Replaced Snubber.

RIA3-2990s.

DOCUMEN*2 ID 0036r/0005r

  • 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, April 1 through April 30, 1986. 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 86-006-00 03/02/86 Reactor Water Clean-Up Isolation Due to Mispositioned Valves from Procedural Problem.

86-007-00 04/04/86 Excessive Static-O-Ring Pressure Switch Drift High Out of Tolerance.

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DOCUMENT ID 0036r/0005r

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.e 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 d

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. 1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE 5/10/86 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: April, 1986 GROSS HOURS IN REPORTING PERIOD: 719
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): N/A
4. REASONS FOR RESTRICTION (IF ANY): N/A THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 719 2775.59 8164.99 4 6. REACTOR RESERVE SHUTDOWN HOURS 0.0 29.83 29.83
7. HOURS GENERATOR ON LINE 719 2748.44 7984.74
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 2218512 8171616 23680168
10. GROSS ELEC. ENERGY GENERATED (MWH) 740608 2731931 7842000
11. NET ELEC. ENERGY GENERATED (MWH) 717755 2651337 7474552
12. REACTOR SERVICE FACTOR 100% 96.4% 60.7%
13. REACTOR AVAILABILITY FACTOR 100% 97.4% 60.9%
14. UNIT SERVICE FACTOR 100% 95.4% 59.4%
15. UNIT AVAILABILITY FACTOR 100% 95.4% 59.4%
16. UNIT CAPACITY FACTOR (USING MDC) 96.3% 88.8% 53.7%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 92.6% 85.4% 51.6%
18. UNIT FORCED OUTAGE RATE 0.0% 4.5% 20.9% l

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

The Units First Refuel is scheduled to start September 1, 1986. ,

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

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DOCUMENT ID 0036r/0005r

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.,2. AVERAGE DAILY UNIT POWER LEVEL

.', DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: 5/10/86 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761 MONTH: April 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWEh 1.EVEL (MWe-Net) (MWe-Net)

1. _ _

1059 17. 1046 2._ 1053 18. 1035 3_ _

1050 19. 1024 4._ 1042 20. 928

5. _

1043 21. 1032

6. 1041 22. 1046
7. _

1037 23. 1058 8._ _

1032 24. 1050 l 9._ 1030 25. 1036

10. 1024 26. '921
11. _

1010 27. 913

12. 1014 28. 1055
13. _

653 29. 1043 14._ _ _ 766 30. 974

15. 871 31. N/A 16._ _ 1021 DOCUMENT ID 0036r/0005r

ATTACHMENT E

3. UNIT SHUTDOWNS AND POWER REDUCTIONS '*

DOCKET NO. 050-373 UNIT NAME LaSalle Two -*

DATE 5/10/86 REPORT MONTH APRIL 1986 COMPLETED BY James P. PetersE 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 /COfMENTS 18 4/12/86 S 8.33 H-Adjustment 5 Control Rod of core Flux. Manipulations t

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DOCUMENT ID 0036r/0005r

. ,e 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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,. . 2. ECCS Systems Outag:s The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO. EOUIPMENT PURPOSE OF OUTAGE 2-162-86 RCIC Waterleg Pump Testing.

2-166-86 RHR S/D Cooling Valves LIS-RH-412 2-170-86 2B DG Cooling Water Modify Control Switch System 2-175-86 RCIC Repair Oil Relief and Change Oil 2-176-86 RCIC Steam Supply Repair Steam Leak.

Drain Trap 2E51-D003 2-177-86 2E51-N010 Repair Leak.

2-178-86 2DG08CB Move Piping Interference For EMD.

2-179-86 U2 LPCS Pump Lubrication.

2-180-86 2E51-F012 Troubleshooting.

2-181-86 2DG08CB Replace Bolts.

2-187-86 RCIC Water Leg Pump Change Orifice.

2-189-86 2DG061A Re-Condition Valve.

2-192-86 2A DG Cooling Water Wiring Modification System 2-196-86 2DG0lP Coupling Lubrication 2-197-86 2DG0lK Clean Lube 011 Seperator Ejector Screen.

2-198-86 RHR S/D Cooling LIS-RH-212.

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3. Off-Site Don Calculation Minual

+

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 system during this reporting period.

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Comm:nw dth Edison

/- o LaSalle County Nuclear Station

,--; Rural Route #1, Box 220

,e'~e V Marseilles, Illinois 61341 Telephone 815/357-6761 l

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l May 8, 1986 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 April 1, 1986 through April 30, 1986.

Very truly yours, f h-G. J. Diederich Station Manager LaSalle County Station GJD/JPP/jdp -

Enclosure xc: J. G. Keppler, NRC, Region III '

NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center

' L. J. Anastasia, PIP Coordinator SNED J. E. Ellis, GE Resident H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle

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Document 0043r/0005r

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