Text

Monthly Operating Repts for Sept 1986
	ML20203N848
Person / Time
Site:	LaSalle
Issue date:	09/30/1986
From:	Diederich G, Rohrer R; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	0043R-0005R, 43R-5R, NUDOCS 8610200068
	Download: ML20203N848 (38)
	v • d • e

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y-1 LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT SEPTEMBER 1986 COfMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll 4

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Doctament 0043r/0005r

TABLE OF CONTENTS I.

INTRODUCTION II.

MONTHLY REPORT FOR UNIT ONE A.

Sunusary 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.

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 Document 0043r/0005r

r I.

INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Comunonwealth 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 Comunonwealth Edison Company.

Unit one was issued operating license number NPF-11 on April 17, 1982.

Initial criticality was achieved on June 21, 1982 and comunercial power operation was commenced on January 1, 1984.

This report was compiled by Richard J. Rohrer, telephone number (815)357-6761 extension 705.

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1 Document 0043r/0005r

. Ya II.

MONTHLY REPORT FOR UNIT ONE A.

SUt9UutY OF OPERATING EXPERIENCE FOR UNIT ONE September 1-17 Sept. 1 0001 Hours Reactor Subcritical, Unit Off-line.

September 17 Sept. 17, 0634 Hours Reactor Critical.

Sept. 17, 0645 Hours Reactor Taken Sub-critical for IRM Performance checks.

September 17-18 Sept. 17, 0826 Hours.

Reactor Critical.

Sept. 18, 1440 Hours.

Generator Synchronized to Grid.

Sept. 18, 1950 Hours.

Generator taken off-line.

Sept. 18, 2012 Hours.

Manual Reactor Scram per "LOS-RD-R2."

September 21-24 Sept. 21, 0945 Hours.

Reactor Critical.

Sept. 21, 2100 Hours.

Generator Synchronized to Grid.

Sept. 24, 1352 Hours.

Generator taken off-line.

Sept. 24, 1555 Hours.

Reactor Scram from Level Deop Test, LST-86-208.

September 25-3_0 Sept. 25, 1830 Hours.

Reactor Critical.

Sept. 26, 0625 Hours.

Generator Synchronized to the Grid.

Sept. 27, 0700 Hours.

Unit Power held steady at 550 MWe for Administrative reasons.

Sept. 30, 2400 Hours.

Unit at 600 MWe.

1 Document 0043r/0005r

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B.

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

MAINTENANCE.

j 1.

Amendments to facility license or Technical Specification.

l There were no Amendments to the facility license or Technical Speciafications during this reporting period.

2.

Facility or procedure changes requiring NRC approval.

There were no procedure changes requiring NRC approval during this reporting period.

-The following facility changes which required NRC Approval were made during this reporting period.

MODIFICATION NUMBER DESCRIPTION 1-1-84-036 ADS Logic Change 1-1-82-305 CRD Low Header Pressure Scram, i

1-1-82-080 Addition of excess flow check valve ICM102.

l-1-84-026 Replacement of Primary Containment Vent and Purge Valves.

1-1-82-012 Degraded Voltage Modification.

i 1-1-82-284 Degraded Voltage Modification.

3.

Tests and Experiments requiring NRC approval.

}

There were no tests or experiments requiring NRC approval during this reporting period.

1 4.

Corrective maintenance of safety related equipment.

l The following table (Table 1) presents a sununary of l-safety-related maintenance completed on Unit one during the

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reporting period. The headings indicated in this summary include: Work Request number, Component Name, Cause of Malfunction, Results and Effects on Safe Operation, and l

Corrective Action.

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TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED SQUIPMENT WORK REQ' JEST COr@ONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION CM SAFE PLANT OPERATION L60723 SOR-1821-W024D Broken, Bad Application, Inappropriate Switch Replaced and Recalibrated Repeatability Problems, Operations. New SOR Switches. Drift and Static Shift of SOR Switches. L60982 SOR-lE31-N013BB L60983 SOR-lE31-N007AA L60984 SOR-1831-N012BB L19405 Scram Discharge M-1-1-82-263 Install Redundant vent and Installed per Mod-Volume Drains, and Redundant Scram ification Package. Instumentation. L26229 HPCS Pp Outlet M-1-1-83-119 This replaces the old instru-Installed per Mod-Pressure Transmitter mentation that had a large ification package. IR22-N004. zero shift. L33222 VQ Butterfly Isol-M-1-1-84-026 These Butterfly Valves will Installed per Mod-l ation valves close s 10 seconds. ification Package. IVQO26/27/31/34/36/ 29/30/40/42/43 1 L44930 LC Flow Elements M-1-1-85-Oll Replaced with environmentally. Installed Per Modification IE32-N006A/E/J/N qualified flow elements. Package. L58821 RCIC Sta Outbd Valve leaks Past Seat Failure of LLRT LTS-100-24 Lapped Seats and re-Isolation valve packed valve. i lE51-F064 L53885 VQ Inbd Isolation valve Leaks Past Seat Failure of LLRT Replaced with new Valve IvgC30. LTS-100-5/15 Valve. L5 331 D MSL Monitor Unstable Drawer (circuitry) Gave 1/2 Scram and went Down-Replaced Entire Drawer ID18-K610D Scale. (circuitry). i Document 0043r/0005r

TABLE 1 CORRBCTIVE MAINTENANCE OF S?.FETY RELATED SQUIpfENT WORK RBQUEST COff0NENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L60319 Level 3 Scram To accomodate observed New Setpoint is 58.9 inches Changed pressure switch switches characteristics of SOF WC. Setpoints. IB21-N024A-D. Differential Pressure Switches. L60323 Level 3 ADS Low Level To accomodate observed New Setpoint 58.9 inches WC. Changed Pressure Switch. Switches IB21-NO38A/B. characteristics of SOR Setpoints. 1 Differential Pressure l Switches. L60321 Level 2 HPCS Switch To accomodate observed New Setpoint 134 inches WC. Changed Pressure Switch. IB21-NO31A-D. Characteristics of SOR Setpoints. I Differential pressure i Switches. i L60322 Level 2 Isolation To Accomodate observed New setpoint 134 inches WC. Changed Pressure Switch. Switches characteristics of SOR Setpoints. IB21-NO26AB/BB/CB/DB Differential Pressure Switches. l L60323 Level 2 RCIC To accomodate observed New setpoint 134 inches WC. Changed Pressure Switch Initiation switches characteristics of SOR Setpoints. IB21-NO3* LAB /BA/CB/DB Differential Pressure 4 switches. i j L60324 Level 1 BCCS Switches To accomodate observed New Setpoint 184 inches WC. Changed Pressure switch. IB21-NO31AA/BA/CA/DA characteristics of SOR Setpoints, j Differential Pressure j Switches. i Document 0043r/0005r

_.m_ TABLE 1 CORRBCTIVE MAINTENhthCE OF 4 SAFETY RELATED BQUIPIMIT l UDItK RBQUEST C0f90bfENT CAUSE OF MALFUtfCTION RESULTS AND EFFBCTS CORRECTIVE ACTIOtf f Otf SAFE PIANT OPERATION i i L60325 HPCS Min. Flow To Accomodate observed afew setpoint is 23 inches WC. Changed Pressure Switch. Switch IE22-M006 characteristics of SOR Setpoint. Differential pressure Switches. L60326 LPCS Min Flow switch -To acen=adate observed tiew setpoint is 23 inches WC Changed Pressure Switch. l. 1521-80004. characteristics of SOR WC. Setpoint. Differential Pressure i Switches. L60327 RHIt Min Flow Switches ' To accomodate observed tiew Setpoint is 23 inches WC. Changed Pressure Switch. IE12-N010AA/AB/BA/BB characteristics of SOR Setpoint. CA/CB. Differential Pressure j switches. ] L60328 RMt/RCIC High Steam To accomodate observed New setpoint is 111.4 inches WC Changed Pressure Switch. j Flow Switches characteristics of SOR

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IE31-es007AA/AB/BA/BB. Differential Pressure Switches. l L60329 RMt High Suction To accomodate observed New setpoint is 168.4 inches Changed Pressure j Flow Switches characteristics of SOR WC. Switch. Setpoints. IE31-tf012AA/AB/BA/BB Differential Pressure Switches. l l 4 L60330 RCIC High Steam Flow To Accomodate Observed New setpoint is 166.4 inches Changed pressure ) Switches. characteristics of SOR WC. Switch setpoints. i IE31-af013AA/AB/BA Differential Pressure 88. Switches. i l L60331 ptSL High Flow switches To Accomodate observed New setpoint is 97.6 PSID. Changed Pressures Switch } 1E31-80008/09/10/11 characteristics of SOR Setpoints. l A/B/C/D. Differential Pressure i Switches l l Document 0043r/0005r ~

TABLE 1 CORRBCTIVE pmINTENiufCE OF SAFETY REIATED BQUIPISBfT 1 WORK REQUEST C0fEG ENT CAUSE OF IRLFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L60387

A* IRM Pre-regulator problems.

Drifting indication causing Repaired preregulator. half-scrams. L60909 DWEDS Inboard Limit Switch out of Valve would not indicate Reset Limit Switch. Isolation valve . Adjustment. ful1-closed. IRE 024. L60541 VQ Isolation Valves Faulty Valve. Excessive Leakage failed LLRT. Replaced IVg040. IVg031/32/40. L60917 Reactor Water Clean-up Relay was Mechanically Incorrect function of Reactor Replaced Relay. relay IE31-K18. binding. Water Clean-up Isolations. L60941 Withdraw / Vent Valve Valve stem bent and valve could not be closed. Rebuilt valve. for CRD 18-15. galled. L60980 PEIV-LCS valve Control Power transformer Valve could not be motor-Repaired ground and IE32-F002A. burned up.

operated, replaced transformer.

L60986 VQ isolation valve Faulty seat / disc. Excessive leakage failed Relapped seat and replaced IVgG32. LLRT. disc. L60989 SBGT WRGM Fau1ty Pump. Indicetion wou1d not read Rep 1 aced pump. Imr Range Flow. correctly. L61006 Control Rod 18-31. Mispositioned reed switch. Loss of position indication. Repositioned reed switches. L61075 RHR A pressure equal-Faulty valve seats. Excessive leakage. Relapped seats. izing bypass valve, 1E12-F050A. L61195 RHR A Suction from Broken torque switch. Valve ground into seat. Replaced torque switch suppression pool, would not open, and cycled valve. IE12-P004A. Document 0043r/0005r

-s.. TABLE 1 i CORRSCTIVE MINTENhtfCE OF SAFETY REIATED EQUIPMNT i l i NORK REQUEST 000eOserr CRUSE OF fWu.PUNCTION RESULTS AND BFFECTS CORR 8CTIVE ACTION ON SAFE PLANT OPERATION j L61300 Inboard M IV "B" Failed Limit Switch. Incorrect position indication. Replaced limit switch. IB21-F0228. 1 s j L61331 W L Low pressure Faulty switch. Repeatedly failed calibration Replace switch. l j Isolation Switch test. j IB21-N0158. 1 L61374 Suppression Pool Bent contact on torque Valve would not close fully. Replaced torque switch. i Nitrogen nake-up switch. I Valve, Ivg051. I j L61383 M L Drain Valves, Faulty torque switches. Valve would not seal-in in Cleaned or replaced IB21-F067A & D. closed direction. torque switches. L61387 Inboard M IV "B" Limit Switch out of Improper position indication. Adjusted limit switch. l IB21-F0228. Adjustment. l L61554 Inboard E IV "B" Limit switches out of No " Closed" indication. Adjusted Limit switches. 1 IB21-F0228. Adjustment. l A L61555 Outboard M IV "C" Limit switch out of 800 " Closed" indication. Adjusted Limit switch. IB21-P028C. adjustment. i n-4 o 8 .t i t l Document 3043r/0005r t-

C. LICENSEE EVENT REPORTS The following is a tabular sununary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, logged during the reporting period, September 1, through September 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-373/86-033-00 8-6-86 "RCIC High Ambient Temperature Switch Trip." 373/86-034-00 8-7-86 " Auto-Start of IB DG." 373/86-035-00 8-11-86 "1B DG Fall to Start." 373/86-036-00 9-12-86 " Documentation of Unit 1 First Refuel Snubber Failures." 373/86-037-00 9-8-86 " Spurious Group II and IV Isolation." 373/86-038-001 9-21-86 " Mode Switch to Run < 854 PSIG." l l t i 1 l s Document 0043r/0005r

l i D. DATA TABULATIONS The following data tabulations are presented in this report: i 1. Operating Data Report 2. Average Daily Unit Power Level 3. Unit Shutdowns and Power Reductions I ) i l i i l Doctament 0043r/0005r

1. OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE October 10, 1986 COMPLETED BY R. J. Rohrer TELEPHONE (815)357-6761 OPERATING STATUS 1. REPORTING PERIOD: September, 1986 GROSS HOURS IN REPORTING PERIOD: 720 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): 948 4. REASONS FOR RESTRICTION (IF ANY): Administrative THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 239.65 239.65 12278.65 6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 1642.00 7. HOURS GENERATOR ON LINE 183.62 183.62 11825.62 8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00 9. GROSS THERMAL ENERGY GENERATED (MWH) 248280 248280 32461930

10. GROSS ELEC. ENERGY GENERATED (MWH) 72534 72534 10571928 11.

NET ELEC. ENERGY GENERATED (MWH) 58541 -24097 9980360 12. REACTOR SERVICE FACTOR 33.3% 3.7% 50.9% 13. REACTOR AVAILABILITY FACTOR 33.3% 3.7% 57.7% 14. UNIT SERVICE FACTOR 25.5% 2.8% 49.0%

15. UNIT AVAILABILITY FACTOR 25.5%

2.8% 49.0% 16. UNIT CAPACITY FACTOR (USING MDC) 7.8% -0.4% 39.9%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 7.5%

-0.3% 38.4% 18. UNIT FORCED OUTAGE RATE 0.0% 0.0% 10.2%

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

N/A. 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A. l l l l Document 0043r/0005r t - ~..

2.AVERAGEDAILYUNITPOWERLEVEb^ DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: October 10. 1986 COMPLETRD BY: R. J. Rohrer TELEPHONE: (815) 357-6761 MONTH: September 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1. -16 17. -17 2. -16 18. 9 3 -57 19. -17 4. -17 20. -17 5. -17 21. -5 6. -17 22. 164 7. -19 23. 169 8. -19 24. 144 9. -17 25. -18 10. -17 26. 147 11. -17 27. 488 12. -16 28. 520 13. -16 29. 561 14. -16 30. 581 15. -16 31. N/A 16. -16 Document 0043r/0005r

ATTAOMENT C 3. UNIT SHUTDOWNS AND POWER REDOCTIONS DOCKET NO. 050-373 UNIT MiWEE LaSalle Orm DATE October 10,5 1986 REPORT MONTH SEPTEMBER, 1986 CUMPLETED BY A J. Rohrer TELEPHONE (815)35'r-5761 I METHOD or TYPE SHUTTING DOWN F: PORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) ERASON REDUCING PONER ACTIONS /CONEBNTS 1. 9/1/86 S 422.7 C 4 (continuation Refueling outage beacn of Outage from October 18, 1985. previous month) 4 2. 9/18/86 S 73.2 B 2 Scrammed manually per LOS-RD-R2. 3. 9/24/86 S 40.6 B 3 Scrammed automatically per LST-86-208, Level Drop Test. l l i i Document 0043r/0005r

E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CVNDITION OF RVENT 9-18-86 IB21-F013C 2 Manual Critical Opened for Surveillance 1B21-F013D Low Power Test LOS-MS-R2. IB21-F013E 950 PSIG 1821-F013R 1B21-F013S 1821-F013U IB21-F013V 1821-F013G 9-18-86 IB21 F013A 1 Manual Critical Opened for Surveillance 1B21-F013B Low Power Test LOS-MS-R2. 1B21-F013F 950 PSIG 1B21-F013H 1B21-F013J IB21-F013K 1B21-F013M 1821-F013N 1B21-F013P I l 1 \\ l Docussent 0043r/0005r

2. ECCS Syntens Outtges The following outages were taken on ECCS Systems during i the reporting period. OUTAGE NO. BOUIPMENT PURPOSE OF OUTAGE 0-187-86 0 D/G Air Repair Compressor "A" 0-186-86 0 D/G Air Repair Compressor "A" 0-189-86 0 D/G Air Repair Compressor "A" 0-191-86 0 D/G Air Repair Trap Compressor "B" Air Dryer. 1-1395-86 "B" D/G. Replace Relay. 1-1397-86 RHR High Suction Replace Switch. Flow Switch. 1-1398-86 RCIC High Steam Replace switch. Flow Switch. 1-1399-86 RCIC High Steam Replace Switch. Flow Switch. 1-1400-86 Valve 1E12-F0993 Determinate. 1-1404-86 Switch 1821-N503 A/b Modifiction Test. 1-1406-86 RCIC Steam Valve, Overload Testing. lE51-F045. 1-1418-86 "B" D/G Cooling Strainer inspection. Water Streiner. 1-1426-86 Valve IE22-F368 Crosstie Air Recievers, 1-1430-86 Valve lE12-F004A Inspect Torque switch. 1-1434-86 ADS Division I. Troubleshooting. 1-1439-86 LPCS Manual Injection Repair Terminations. Valve Indication. 1-1457-86 RCIC Water Leg Lubricate Coupling. Pusp. 1-1459-86 RCIC Condensate Install Heater. Pump. 1-1405-86 RCIC DC Breaker. Panel Inspection. Document 0043r/0005r

~ 3. Off-Site Dose Calculation Manual There were no changes to the Off-Site Dose Calculation Manual during this reporting period. 4. Radioactive Waste Treatment Systems. There were no changes to the radioactive waste treatment system during this reporting period. E Document 0043r/0005r

1 } f A IJ.SALLE NXiEAR POWER STATION 2 UNIT 2 MONTHLY PERFORMANCE REPORT i SEPTEMBER, 1986 COleDNWEALTH EDISON COMPANY t NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 l l J l l l l i DOCUMENT ID 0036r/0005r

TABLE OF CONTENTS I. INTRODUCTION II. MONTHLY REPORT FOR UNIT TWO. A. Susunary of Operating Experience B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE 1. Amendments to Facility License or Technical Specifitations 2. Facility or Procedure Changes Requiring NRC Approval 3. Tests and Experiments Requiring NRC Approval 4. Corrective Maintanance of Safety Related Equipment C. LICENSEE EVENT REPORTS D. DATA TABULATIONS 1. Operating Data Report 2. Average Daily Unit Power Level 3. Unit Shutdcwns 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 System ? 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 comir.snced on June 19, 1984. This report was compiled by Richard J. Rohrer, telephone number (815)357-6761 extension 705. DOCUMENT ID 0036r/G005r

II. MONTHLY REPORT FOR UNIT TWO A. SUl9ULRY OF OPERATING EXPERIENCE FOR UNIT TWO September 1-30 Sept. 1, 0001 Hours. Reactor critical, unit on-line at 85'& power, (921 MWe). Sept. 5, 0035 Hours. Power reduced to 855 We for CRD exercising. Sept. 5, 0130 Hours. Ramped up to 911 We. Sept. 11, 1800 Hours. Power reduced to 580 MWe for control Rod Manipulation. Sept. 11, 2110 Hours. Ramped up to 730 MWe. Sept. 12, 1400 Hours. Power reduced to 595 MWe. Sept. 12, 1445 Hours. Power ramped up to 915 MWe. Sept. 19, 0315 Hours. Power reduced to 865 MWe for CRD exercising. Sept. 23, 1130 Hours. Power further. reduced to 815 MWe for Bus Duct observation. Sept. 26, 0615 Hours. Power ramped up to 925 MWe. Sept. 30, 2400 Hours. Unit on-line, Power at 81% (925 MWe). l DOCUMENT ID 0036r/0005r l

B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE. 1. Amendments to facility license or Technical Specification. There were no amendments to the facility license or Technical Specifications during this reporting period. 2. Facility or procedure changes requiring NRC approval. There were no facility or procedure change 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. l t l I d DOCUMENT ID 0036r/0005r

TABLE 1 CORRECTIVE MAINTENANCE OF . SAFETY RELATED BQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALPUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L50485 Suppression Pool Incorrect installation Incorrect Level Indication. Blew moisture from Narrow Range Level of sensing line. sensing line and corrected Indication, installation. L59578 Control Room . Faulty detector. Read too high causing Replaced detector. i ventilation intake Emergency Make-up train to air radiation monitor, Auto-start. 2D18-K751D. L60843 Computer Point Out-of-Calibration. Reactor Pressure read high Recalibrated SPDS signal A907, Reactor Pressure on SPDS. card. L61367 Post-LOCA Oxygen Failed Monitor. Errr. tic reading. Replaced Monitor. monitor, 2AIT-CM016. L61941 RPS bus circuit Breaker was " smoked". Half-scram and Half-isolation Jumpened breaker,. breaker 2A. signals were present, until replacement could be made. 1 4 1 DOCUMENT ID 0036r/0005r

l C. LICENSEE EVENT REPORTS j The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, logged during the reporting j l period, September 1 through September 30, 1986. This information is 1 I provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73. Licensee Event Report Number Date Title of Occurrence 374/86-015-00 8-23-86 "RWCU Delta-Flow Isolation". 374/86-016-00 9-14-86 "No Euppression Pool Level Alarm". 374/86-017-00 9-17-86 "RSP Instrumentation Inop > 7 Days". I I l i l l DOCUMENT ID 0036r/0005r 1

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

1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE October 10, 1986 COMPLETED BY R. J. Rohrer TELEPHONE (815)357-6761 OPERATING STATUS 1.

REPORTING PERIOD: September 1986 GROSS HOURS IN REPORTING PERIOD: 720 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): 948 4. REASONS FOR RESTRICTION (IF ANY): Administrative THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 720.00 4405.05 9794.45 6. REACTOR RESERVE GHUTDOWN HOURS 0.00 29.83 29.83 7. HOURS GENERATOR ON LINE 720.00 4325.62 9561.92 8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00 9. GROSS THERMAL ENERGY GENERATED (MWH) 1961280 12222456 27731008

10. GROSS ELEC. ENERGY GENERATED (MWH) 637873 4038293 9148362 11.

NET ELEC. ENERGY GENERATED (MWH) 614615 3878360 8701575 12. REACTOR SERVICE FACTOR 100.0% 67.2% 57.2% _13. REACTOR AVAILABILITY FACTOR 100.0% 67.7% 57.4% 14. UNIT SERVICE FACTOR 100.0% 66.0% 55.9% j

15. UNIT AVAILABILITY FACTOR 100.0%

66.0% 55.9% i 16. UNIT CAPACITY FACTOR (USING MDC) 82.4% 57.1% 49.1% 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 79.2% 54.9% 47.2% 18. UNIT FORCBD OUTAGE RATE 0.0% 34.0% 24.6%

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

A refueling outage is scheduled to begin January 3, 1986. 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP NA l 4 r DOCUMENT ID 0036r/0005r

~

2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: October 10, 1986 COMPLETED BY:

R.J. Rohrer TELEPHONE: (815) 357-6761 MONTH: August, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGS DAILY POWER LEVEL (MWe-Net) '(MWe-Net) 1. 879 17. 886 2. 877 18. 884 3 873 19. 874 4. 874 20. 840 5. 869 21. 838 6. 872 22. 832 7. 868 23. 804 8. 867 24. 782 9. 864 25. 783 10. 867 26. 835 11. 813 27. 887 12. 693 28. 901 13. 835 29. 892 14. 882 30. 887 15. 870 31. N/A 16. 878 DOCUMENT ID 0036r/0005r

j1' r e 6 r 1 8 h 6 o 9 o 7 o 1 R6 t T 7 S 3 7 e 0 J 5 T 3 l 1 3 N l . ) E 0 a r R 5 M 5 S e 1 P 0 a b Y8 EO .Lo B( VC t I/ OEc DE TS NMO EN CN A TO EO TN EH RI E LP RT KTEPE OC CITML CA ONAOE DUDCT 689 1 ,r RR e NOE b W W m FORO e ODOP t S T p N DGCG e O ONAN S I HIEI T TTRC g C 6 ET U n U 8 MUED i D 9 HHE r E 1 STR u R D R R o E E w W B T EO M P E t T T i D D P n f N E U MA S e ICS N l AN O l TW H S a TO T A S AD N E a T O R L U M H r S T o R f T O I P s N E n U R o N) i OS t IR c 3 TU u AO d RH e U( r D rewop tna D c E i L f ~ DU i ED n CE g ERH i POC s YFS T r o r FS 5 s 0 e 0 g 0 a / t r u 6 o 3 0 E o 0 T n A D D e I re T w N E e M r U e C O h O N T D {ll ll llll lllll l l l

E. UNIQUE REPORTING REQUIREMENTS 1. Safety / Relief Valve Operations for Unit Two. DATR VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUAFIONS CONDITION OF EVENT There were no safety relief valves operated for Unit #2 during this reporting period. 9 A l i l l i i l I i l DOCUMENT ID 0036r/0005r l

2. ECCS SyItems Outige3 The following outages were taken on ECCS Systems during the reporting period. OUTAGE NO. BOUIPMENT PURPOSE OF OUTAGE 2-547-86 "B" D/G Repair Access Cover. 2-557-86 RCIC Repair Vacuum Pump. I 2-567-86 "A" RHR Heat Exchanger Flush Heat Exchanger. 2-570-86 RCIC Turbine Trip Repair Limit Switches, and' Throttle Valve. l l 4 ( DOCUMENT ID 0036r/0005r

3. Off-Sito Dosa CElculation Manu21 There were no changes to the Off-Site Dose calculation Manual during this reporting period. 4. Radioactive Waste Treatment Systems. There were no changes to the radioactive waste treatment system during this reporting period. i f DOCUMENT ID 0036r/0005r

Commonwe:lth Edison c:. LaSalls County Nuclear Station _.4 RuralRouta #1, Box 220 J Marseilles, Illinois 61341 Vj Telephone 815/357-6761 1 October 10, 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 September 1, 1986 through September 30, 1986. Very truly yours, J/ W l G. . Diederich S ation 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 S&fety D. P. Galle, CECO D. L. Farrar, Ceco IMPO 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 A. Bournia, NRR Project Manager - LaSalle \\/ 4 f \\ Document 0043r/0005r _ _ _ _ _ _ _ _ _}}

ML20203N848

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