ML20210R404
| ML20210R404 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 01/31/1987 |
| From: | Diederich G, Kirchner G COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 0043R-0005R, 43R-5R, NUDOCS 8702170401 | |
| Download: ML20210R404 (41) | |
Text
4 4 LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT JANUARY 1987 COfMONWBALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll 9702170401 870131 PDR ADOCK 05000373 R PDR f6kk y
DOCUMIDTI ID 0043r/0005r Iff
= . - - . - _ . .- - - - -. . _ - , _
TABLE OF CONTENTS I. INTRODUCTION II. MONTHLY REPORT FOR UNIT ONE l
4 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 j 3. -Tests and Experiments Requiring NRC Approval
- 4. Corrective Maintenance of Safety Related Equipment
- 5. Completed Safety Related Modifications.
h C. LICENSEE EVENT REPORTS D. DATA TABULATIONS
- 1. Operating Data Report
- 2. Average Daily Unit Power Level a 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 Weste Treatment System
- 5. Indications of Failed Fuel Elements I
I l
i i
l DOCUMENT ID 0043r/0005r i
- . . . _ _ _ _ _ _ _ . - - . _ . _ , ~ . . _ ~ , _ , _ _ . . , . . _ - , . . _ . _ _ _ _ - - , _ _
I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois.
Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company.
Unit one was issued operating license number NPF-ll on April 17, 1982.
Initial criticality was achieved on June 21, 1982 and commercial power operation was conenenced on January 1,1984.
This report was compiled by Gregory J. Kirchner, telephone number (815)357-6761, extension 704.
DOCUMENT ID 0043r/0005r
II. MONTHLY REPORT FOR UNIT ONE A. SUPMARY OF OPERATING EXPERIENCE FOR UNIT ONE January 1-31, 1987 January 1, 0000 Hours. Reactor at 1010 We, Turbine Generator on line.
January 9, 1155 Hours. Commence load drop to 925 We to observe TCV oscillations.
January 9, 1615 Hours. Reduce power by 200 We/hr. to maximum valve position on PCV (620 We) to fix CV limit switch in steam chest area.
January 9, 2015 Hours. Ramp up 150 We/hr. to 850 We, then 10 We/hr. to 1010 We.
January 16, 0620 Hours. Dropped 50 We for CRD exercising, then return to 1000 We.
January 23, 2200 Hours. Commence load drop of 225 We/hr. to 660 We to work on number 3 C.V.
January 24, 0040 Hours. Inserted groups 981 and 9E2 to position no.
- 40. Started 150 We/hr. to 890 We, then 10 We/hr. to 1000 We.
January 26, 1135 Hours. Reactor scram due to blown generator pot fuse, generator off-line.
January 27. 1600 Hours. Reactor critical.
January 30, 1245 Hours. Generator synchronized to grid.
January 31, 1120 Hours. Reactor scram due to loss of alternator exciter field. Turbine trip at 350 We.
January 31, 2400 Hours. Reactor in hot shutdown.
DOCUMENT ID 0043r/0005r
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 Procedural changes requiring NRC approval during this reporting period.
- 3. Tests and Experiments requiring NRC approval.
There were no Tests or Experiments requiring NRC approval during this reporting period.
- 4. Corrective Maintenance of Safety Related Equipment.
The following table (Table 1) presents a Summary of Safety-Related maintenance completed on Unit One during the reporting period. The headings indicated in this summary include:
Work Request number, Component Name, Cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action.
- 5. Completed Safety Related Modifications.
The following Table (Table 2) presents a list of completed Modifications during this reporting period. Each entry will have a short synopsis explaining details involved with each modification.
DOCUMENT ID 0043r/0005r
TABLE 1 ...
CORRECTIVE MAINTENANCE OF SAFETY RELATED SQUIPMENT .
UNIT #1 WORK REQUEST COMONBHT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L53315 VC Filter Bypass During LIS-VC-01 damper No indication at ~131' R/15. Damper Actuator rebuilt Damper OVE08YA position did not change. per LEP-89-129.
L56332 Outer Trackway Door Damaged pin locking Door hard to open. R/R guide sleeves and
- 20, Handwheel is sleeves, adjusted springs.
broken off.
L62489 LPRM 3C-48-41 Diode CR2 on LPRM Nhen LPRM card is placed in Replace diode CR2 and 3C-48-41 is defective. cal position, the bypass returned to service.
light comes on.
L62914 "B" Rx. Recirc. Flow Plunger core of coil is Coll is overheating and fuse Replace control box and Control Viv. Hyd. not being pulled up into interrupts immediately. coil. Set limits and Pwr. Unit Outboard the coll. verify proper operation.
Isol. Viv.
IB33-F343B L62967 Irrywell Penetration Loose fitting at pressure Penetration lost pressure was Tighten loose pressure E-14 gage. at 3 PSIG. gage, charge penetration to 30 PSIG.
L63419 IB RR FCV Hydraulic Bad open limit switch. Valve cycling indicated dual Replace limit switch, O.B. Isol. Vlv. operation for open and closed verified proper cycling.
positions. operation.
143979 HCU 22-55 Bad Cartridge valve (111) #111 Valve leaks badly when Replaced valve like for taken off back seat position. like.
L64129 Snubber Collar on Unknown. Loose snubber collar to be Retighten snubber collar.
"C" RHR Inj. Line tightened.
DOCUMENT ID 0043r/0005r
+e TABLE 1 ,.
CORRBCTIVE MAINTENANCE OF SAFETY RELATED SQUIPMENT ,
UNIT 81 WORK R8 QUEST C0ff0NENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRBUTIVE ACTION j ON SAFE PLANT OPERATION L64131 SP DW, Temp Paper Tape not advancing. SP DW temp. recorder not Replace chart drive motor, Recorder. ITR-CM037 operating, verify proper ops.
L64175 Main Steam Line PRM Sporadic, unreliable Occasionally provided Replaced discrete com-Drawers readings. half scrams. ponents with more reliable 1D18-K610 A/B/C/D microprocessor system.
1 L64180 Div I, W.R. Level Level Indicator out of Indicated level is between Recalibrate level-l Recorder calibration. +12" to +15" on Div I, but indicator.
1821-R884A shows +21" on Div II.
4 L64182 'lB' VR Exhaust PRM PRM spiked Hi-Hi initiat- Isolated Case. Checked set point and RIY-ID18-K609B ing annunciator lH13-P601. monitored for 1 day.
L64198 RCIC Steam Line Spring adjustment nut Valve does not cycle fully. Adjusted spring nut to Drain Viv. ,lE51-F026 loose. close valve as required.
) L64267 A RHR to Rad Waste Bad torque switch. Valve will not " seal in" Replace torque switch.
Valve. IE12-F049A close, verify proper operation.
l L64293 S/P Temp. Recorder Bad Love Controller. Pts. 14 and 15 are reading Replaced Love Controller j ITR-Ch037 20* F lower than other pts. ITY-CM057EA & EB.
l L64303 CRD HCU 46-43 Valve Stem Leaks. Unable to charge viv. for Replaced valve like for 111 Valve, leak test. like.
L64316 Div. II Supp. Pool Loose Allen screw on Recorder jumped from 65* F to Tighten Allen screw Temp. Recorder. Servo motor. 125' F. verified proper operation.-
ITR-CM038 DOCUMENT ID 0043r/0005r
TABLE 1 .
CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT ,
UNIT #1 WORX REQUEST C0ff0NENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L64320 RCIC Pump Disch. Bad transmitter. Indicator pegged downscale. Replaced transmitter.
Pressure Indicator.
IE51-R601 L64322 Supp. Pool Dry Well Loose set screws in Recorder prints same value ' Tighten set screws, Temp. Recorder. clutch, for all 17 points. verify proper Ops.
ITR-09038 L64477 HCU 34-43. Bad valve leak. Viv, leaks when taken off Replace Vlv. like for its backseat. like. -
L64565 Div. II Post-Loca Bad Vacuum Pump. Monitor indicates oxygen Replace vacuum pump.
Oxygen Monitor, concentration to high.
LAIR-09048 L64724 HCU 58-27 CRD Bad Valve (111). Valve is leaking when Replace valve.
Accumulator. partially open and full closed.
L64897 HCU 30-27. Bad Valve (111). Valve leaks around the stem. Replace valve.
L57853 control Room Supply Defective Actuator. Damper Sticks. Rebuilt actuator.
Damper. OVC-24YA L63690 SBGT WRGM. Defective Pump and Intermittent Shutdown of WRGM Replaced pump and LOlD18000 Transducer Assemblies. due to process sample flow transducer assemblies.
loss.
L64130 Ammonia Detector Defective Photocell OXY-VE165A would not trip Cleaned photocell board C.R. HVAC System. Board. during test. and replaced paper drive OXY-VC165A motor.
DOCUMENT ID 0043r/0005r
TABLE 1 ,
CORRECTIVE MAINTENANCE OF SAFETY RELATED SQUIPfEENT .
UNIT #1 WORK REQUEST COWONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTIOtt ON SAFE PLANT OPERATION L64371 DVE09YB Damper. Two welds and a bushing Damper difficult to cycle by Replaced the welds, in-were broken on the linkage. hand, stalled new bushing.
1 L64372 OVE07YB Damper. Three welds on the coupl- Damper difficult to cycle by Repaired the welds and ings were broken. hand. lubricated the bearings.
4 l
4 i
l i
4 DOCUMENT ID 0043r/0005r
TABLE 2 COMPLETED SAFETY RELATED MODIFICATIONS MODIFICATION NUMB 8R: A brief synopsis of incorporated modification objectives with final design resolution. Also, state reviewed or unreviewed safety questions.
The following is a list of the Safety Related Modifications completed from January 1, 1987 through January 31, 1987.
M01-0-84-060 - This was to modify existing air, water, and electrical services to provide interconnections to the Interim Radweste Storage Facility. There were no unreviewed safety questions. j M01-0-85-014 - This modification was to extend service air and clean condensate tie-ins. This will provide extension lines outside the turbine building to the Interim Radweste Storage Facility. There were no unreviewed safety questions.
M01-0-85-017 - This modification provided for the actuator on OFZ-VC141 with a new upgraded model. This new model is nuclear grade, has improved viton seals, and an increased torque rating. There were no unreviewed safety questions.
M01-0-86-001 - Replace refrigeration compressor low oil pressure switch with PENN model P45-NCA-82. There were no unreviewed safety questions.
301-0-83-088 - This modification provided the capability to isolate air cylinders during operation of the Control Room Breathing Air System. In addition to this, it also provided high pressure service valves to replace the current valves to eliminate air leakage. There were no unreviewed safety questions.
M01-1-84-051 - This modification provided for the addition of piping restraints in the low pressure heater bay to prevent the i piping from moving excessively. There were no unreviewed
- safety questions.
, M01-1-85-014 - This modification provided for the installation of a new drywell chiller IVP145. The associated chilled and service water piping, and electrical equipment was also installed.
There were no unreviewed safety questions.
4
' M01-1-85-036 - This modification updated drawings / references and evaluated approved replacement of any LPRM's with Westinghouse model WL24286 LPRM's with LEMO connector. There were no unreviewed j
safety questions.
M01-1-85-044 - This modification was for the design and installation requirements for attaching the new chiller water and service water piping to the existing plant systems. There were no unreviewed safety questions.
DOCUMENT ID 0043r/0005r
C. LICENSEE EVENT REPORTS 1
The following is a tabular susunary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, logged during the reporting period, January 1, through January 31, 1987. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.
Licensee Event Report Number Date Title of Occurrence 87-001-00 01/09/87 Possible procedure deficiency.
87-002-00 01/15/87 Failure of 'O' Diesel Generator to close onto BUS 241Y.
87-003-00 01/26/87 Reactor Scram - Main Generator lockout and turbine trip.
87-004-00 01/28/87 'A' ammonia detector trip due to jam in cassette tape.
87-005-00 01/31/87 Reactor Scram as a result of generator trip.
87-006-00 01/06/87 Div II DC inoperable due to personnel error, i
i l
1 l
DOCUMENT ID 0043r/0005r 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 9
DOCUMENT ID 0043r/0005r
. 1, OPERATING DATA REPORT.
DOCKET 110. 050-373 UNIT LaSalle One DATE February 10. 1987 COMPLETED BY Orecory Kirchner TELEPHONE (815)357-6761 OPERATING STATUS 1.- REPORTING PERIOD: January. 1987 GROSS HOURS IN REPORTING PERIOD: 744
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3_Ul MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078
- 3. POWER LEVEL TO WHICH RESTRICTED (IP ANY) (MWe-Net): 1050
- 4. REASONS FOR RESTRICTION (IF ANY): Administrative THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 702.9 702.9 15138.5
- 6. REACTOR RESERVE SHU""vnfN HOURS 0.0 0.0 1642.0
- 7. HOURS GENERATOR ON LINE 634.1 634.1 14608.0
- 8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 9. GROSS THERMAL ENERGY GENERATED (MWH) 1829280 1829280 40584922
- 10. GROSS ELEC. ENERGY GENERATED (MWH) 614078 614078 13304755
- 11. NET RLEC. ENERGY GENERATED (MWH) 593383 593383 12615957 '
- 12. REACTOR SERVICE FACTOR 94.5% 94.5% 55.9%
- 13. REACTOR AVAILABILITY FACTOR 94.5% 94.5% 61.9%
j 14. UNIT SERVICE FACTOR 85.2% 85.2% 53.9%
- 15. UNIT AVAILABILITY FACTOR 85.2% 85.2% 53.9%
i 16. UNIT CAPACITY FACTOR (USING MDC) 77.0% 77.0% 45.0%
- 17. UNIT CAPACITY FACTOR (USING DESIGN .
MWe) 74.0% 74.0% 43.2%
- 18. UNIT FORCBD OUTAGE RATE 6.1% 6.1% 14.9%
e 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF RACH)
NOME.
! 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
02/01/87 i
l l
l l
i l
l t
l t
DOCUMENT ID 0043r/0005r
. 3. AVERAGE DAILY UNIT POWER L8 VEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: February 10. 1987 COMPLETED BY: Gregory Kirchner TELEPHONE: (815) 357-6761 MONTH: January. 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)
- 1. 976 17. 967
- 2. 971 18. 966 3 967 19. 964
- 4. 978 20. 967
- 5. 977 21. 968
- 6. 977 22. 968
- 7. 992 23. 955
- 8. 995 24. 886
- 9. 880 25. 966
- 10. 932 26. 461
- 11. 977 27. -12 12, 981 28. -14
- 13. 985 29. -14
- 14. 986 30. 49
- 15. 985 31. 113 16, 963 DOCUMENT ID 0043r/0005r
- 3. tafIT SfAFTDolmes AaB POWER REDUCTIO 0fS DOCKET 300, 050-373 unfit seues LaSalle one DATE pobruary 10. 1987 REPOftT N00ffH JANUARY. 1987 00 m BY Gr m y Kis ' --
TELEP90000E (415)357-4761 l
j DETHOD OF
-j TYPE SHUTTItfG DOIAf F: F0ftCED DURATIOti THE REACTOR Oft N IVE j MD. DATE S: SCHEDULED (HOURS) REASOIf REDUCIlfG POWER ACTIcefS/COfGEBffS 4
( 1 01/26/87 F 97.17 A 3 Blown Generator Pot Fuse.
I 2 01/31/8~l F 12.67 A 3 Alterrex Problems.
l I
i 1
I
~
j' l
i j
I DOCUMENT ID 0043r/0005r
E. UNIQUE REPORTING REQUIREMENTS
- 1. Safety / Relief valve operations for Unit One.
VALVES NO & TYPE PLANT DESCRIPTION M ACTUATBD ACTUATION CONDITION OF EVENT There were no Safety Relief Valves Operated for Unit One during this reporting period.
1 i
\
i DOCUMENT ID 0043r/0005r
- 2. ECCS Sy2tems Outtg u ,
The following outages were taken on'ECCS Systems during the reporting period.
I OUTAGR WO. BOUIPMENT PURPOSE OF OUTAGE 01-01-87 Div. 1 Water I,eg Impeller Adjustment Pump IE21-C002' 01-07-87 IE12-F049A Repair Limitorque 01-14-87 'B' RHR System Flush 'B' RHR Shutdown Cooling Section 01-17-87 O - Diesel Generator Maintain receiver pressure
. Air Receiver with one air compressor
. .g
?
-. i k
e l
A s
k s
v' 3
i i
l l T s i l
l '
l DOCUMENT ID 0043r/0005r '
. - _ _ .._._.L__
- 3. Off-Sita Don Calculation Manual There were no changes to the ODCM during this reporting period.
- 4. Radioactive Waste Treatment Systems.
There were no changes to the Radioactive Waste Treatment Systems during this reporting period.
- 5. Indications of Failed Fuel Elements There were no indications of Failed Fuel Elements during this reporting period.
l 1
l DOCUMENT ID 0043r/0005r
l i
1 l
l i
LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT JANUARY, 1987 COPMONWBALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 l r i
l DOCUMENT ID 0036r/0005r
.- , - . . . . - . . , . , , . - . - - - - - - - .._- --. . . - _ . ~ - .- . . -
TABLE OF CONTENTS I. INTRODUCTION II. MONTHLY REPORT FOR UNIT TWO A. Summary of Operating Experience B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE
- 1. Amendments to Facility License or Technical Specifications
- 2. Facility or Procedure Changes Requiring NRC Approval
- 3. Tests and Experiments Requiring NRC Approval
- 4. Corrective Maintenance of Safety Related Equipment
- 5. Completed Safety Related Modifications C. LICENSEE EVENT REPORTS D. DATA TABULATIONS
- 1. Operating Data Report
- 2. Average Daily Unit Power Level
- 3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS
- 1. Safety / Relief Valve Operations
- 2. ECCS System Outages
- 3. Off-site Dose Calculation Manual Changes
- 4. Major Changes to Radioactive Waste Treatment System
- 5. Indications of Failed Fuel Elements i
DOCUMENT ID 0036r/0005r
I. INTRODUCTION ,
The LaSalle County Nuclear power Station is a two-unit facility cwned by Cosumonwealth 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
. conumercial power operation was commenced on June 19, 1984.
This report was compiled by Gregory J. Kirchner, telephone number (815)357-6761 extension 704.
DOCUMENT ID 0036r/0005r
II. MONTHLY REPORT POR UNIT TWO ,
. . . l A. SU N Y OF OPERATING EXPERIENCE FOR UNIT TWO ,
l January 1-31, 1987 January 1, 0000 Hours. Reactor Critical, Generator at ~155 MWe.
January 3, 0020 Hours. Ramping down at 150 MWe/hr. by decreasing core flow, then downshift to 125 MWe preparing for refuel.
January 3, 1100 Hours. Control Rods inserted.
January 3, 1155 Hours. Generator taken off-line.
January 3, 1803 Hours. Scram on Reactor Water Level.
t l
l l
l l
I l
i i
DOCUMENT ID 0036r/0005r
~. * ' O. - PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE. .
t 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 changes requiring NRC
~
4 approval during the reporting period.
- 3. Tests and Experiments requiring NRC approval.
1 There were no Tests or Experiments requiring NRC approval during l- 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 f
corrective action.
- 5. Completed Safety Related Modifications.
3.
The following table (Table 2) presents a list of completed i Modifications during this reporting period. Each entry will have a short synopsis explaining details involved with each ,
modification.
i e
d l
l .
l i
i j.
l DOCUMENT ID 0036r/0005r
, , - , ,. . - , . . . - , . . - . , . , , . . , - - . - , . . . - - _ _ . . - . . - . . - . - . _ . . - . - . - , . . . - ~ . - . - . - . .
TABLE 1 CORRECTIVE MAINTENANCE OF .
SAFETY RELATED EQUIPMENT ,
Unit #2 WORK REQUEST C0ff0NENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L62766 CRD Accumulator Bad Cartridge (111) Viv.. leaks nitrogen in every Replace with a new valve 38-59 Valve (111) valve position. 4 L63738 HCU 22-55 Instr. Bad Cartridge (111) Viv. leaks nitrogen. Replaced with a new Block Stop Valve valve.
L63777 HCU 22-59 Instr. Bad Cartridge (111) V1v. leaks through stem Replaced with a new Block Stop Valve valve.
L63838 HCU 10-47 Instr. Bad Cartridge (111) Vlv. leaks in every Replaced with a new Block Stop position. valve.
L63946 2VOO6C Exhaust Blade axle does not move. Exhaust damper stays closed Lubricated axle and Damper. when HPCS Battery Room fan on, adjusted center weight.
L64020 S/P Temp. Indicator / Defective love controller. Local indicator reading Replaced defective love Transmitter erratic. controller / calibrated.
2TY-CM057JB L64069 HCU 50-51 Defective (111) Cartridge valve is leaking. Replaced with a new valve.
L64075 HCU 34-43 Defective (111) Cartridge Valve leaks Replaced with a new valve.
L64138 Post LOCA Drywell Defective open limit Shows dual indication for Replaced defective limit Suction - 2CM021B switch. closed position. switch.
L64214 HCU Accumulator 46-23 Defective (111) Cartridge Valve leaks around packing. Replaced with a new velve.
(111) Valve.
L64325 HCU 30-39 (111) Valve. Defective (111) Cartridge Valve leaks when backseated. Replaced with a new valve.
L64431 C IRM Defective IRM Drawer Spikes causing 1/2 scrams. Replaced IRM Drawer and.
and IRM Pre-amp Pre-amp and calibrated.
DOCUMENT ID 0036r/0005r
/ o TABLE 1 COICECTIVE MRINTENANCE OF SAFETY RELATED EQUIPMENT ,
Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION
. ON SAFE PLANT OPERATION i
t L64507 Thermal O.L. Relay Defective torque switch Thermal overload relay will Replaced torque switch SBGT Discharge and thermal overload relay not trip, and overload relay.
L64654 LPRM SB-24-17 Defective LPRM Card Card will not reset after Replaced diode VR-2 and SB-24-17 LPRM-HI alarm is initiated. transistor 95 on LPRM Card.
L64737 IRM "H" Defective Hi-Voltage Connection caused spurious Installed new hi-voltage Connector half scrams. connector on IRM "H" Pre-amp.
l 1
1 o
DOCUMENT ID 0036r/
TABLE 2 COMPLEiMD SAFETY RELATED MODIFICATIONS MODIFICATION NUMBER: A brief Synopsis of Incorporated Modification Objectives with final design resolution. Also, stato reviewed or unreviewed safety questions.
The following list below has all the Safety Regulated Modifications completed from December 1, 1986, through December 31, 1986.
M01-2-84-185 - This Modification added a relay to interlock the drywell equipment drain sump pump alarms. This will allow the pumps to run in the recirculation mode without causing an alarm. There were no unreviewed safety questions.
M01-2-86-034 - This Modification will upgrade cable tray hangers to prepare for additional loading in trays. This additional loading is due to new cable being installed for alternate rod insertions. There were no unreviewed safety questions.
M01-2-86-045 - This Modification will remove the horizontal fuel pool cooling return line spargers, which will allow the future installation of high density spent fuel storage racks. There were no unreviewed safety questions.
I i
I I
l DOCUMENT 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, January 1 through January 31, 1987. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CPR 50.73.
kicensee Event Report Number Date Title of Occurrence 87-001-00 01/07/87 2A Diesel Generator failed to auto start.
87-002-00 01/17/87 Containment leakage limit exceeded.
87-003-00 01/20/87 Auto start of "B" VC EMU train due to contractor bumping breaker.
DOCUMENT ID 0036r/0005r
D. DATA TABULATIOWJ 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 E
t i
i I
4 1
DOCUMENT ID 0036r/0005r
- 1. OPERATING DATA REPORT DOCKET NO. 050-374 i UNIT LaSalle Two DATE February 10. 1987 COMPLETED BY Gregory Kirchner TELEPHONE (815)357-6761 l
OPERATING STATUS i
- 1. REPORTING PERIOD: January. 1987 GROSS HOURS IN REPORTING PERIOD: 744
- 2. CURRENTLY AUTHORIEED PONER LEVEL (MWt):3323 MAX DEPEND CAPACITY
,) (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078
- 3. POWER LEVEL TO NHICH RESTRICTED (IF ANY) (MWe-Net): 1050
- 4. REASONS FOR RESTRICTION (IF ANY): Adsninistrative THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR NAS CRITICAL 66.05 66.05 12069.5
- 6. REACTOR RESERVE SHUTDOWN HOURS _ 0.0 0.0 29.83
- 7. HOURS GENERATOR ON LINE 59.92 59.92 11830.84
- 8. UNIT RESERVE SHUTDOWN HOURS -
0.0 0.0 0.0
- 9. GROSS THERMAL ENERGY GENERATED (MWH) 120864 120864 33635128
- 10. GROSS ELEC. ENERGY GENERATED (MWH) 39232 39232 11100804
- 11. NET ELEC. ENERGY GENERATED (MWH) _ 27226 27226 10567455
- 12. REACTOR SERVICE FACTOR _ 8.9% 8.9% 60.1%
- 13. REACTOR AVAILABILITY FACTOR _ 8.9% 8.9% _
60.3%
- 14. UNIT SERVICE FACTOR _ 8.0% 8.0% 58.9%
- 15. UNIT AVAILABILITY FACTOR _ 8.0% 8.0% 58.9% '
- 16. UNIT CAPACITY FACTOR (USING MDC) 3.5% 3.5% _
50.8%-
i
- 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) _ 3.4% 3.4% 48.8%
- 18. UNIT ICRCED OUTAGE RATE 0% 0% 26.4%
- 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF BACH):
j N/A Unit is in shutdown during this period.
- 20. IF SHUT DOWN AT END OF REPORT PERIOD, BSTIMATED DATE OF STARTUP 5/9/87 i
1 l
l l 4
1 4
l i
DOCUMENT ID 0036r/0005r
7-
)
- 2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374
!- UNIT: LASALLE TWO DATE: February 10, 1987 COMPLETED BY:_ Gregory Kirchner TELEPHONE: (815) 357-6761 i MONTH: January. 1987 1
l DAY AVERAGE DAILY POWER LEVRL DAY AVERAGE DAILY POWER LEVEL 1 (MWe-Net) (MWe-Net)
- 1. 716 17. -14
- 2. 715 18. -14 3 115 19. -14
- 4. -16 20. -15
- 5. -16 21. -14
- 6. -15 22. -13
- 7. -16 23. -14
- 8. -16 24. -13
- 9. -16 _
- 25. -14
- 10. -15 26. -12
- 11. -16 27. -11
- 12. -15 28. -14
- 13. -15 29. -14
- 14. -14 30. -14
- 15. -14 31. -12
- 16. -14 l
DOCUMENT ID 0036r/0005r
t
- '. e 7 n 8 h 1 9 c 6 o1 r 7 w i 6 T . K - .
4 0 7 S e g
7 e1 . 5 T 3 l J. )3 N a
- l y t 0ar G 5 E u 1Sa 1 9 f O 9au Y8 EO g
,Lrb B( VC I/ n O e DE TS i NmFh EN TO CN BO l
e TM EH RI u E LP RT f KTEFE OC e CI Tf L CA R ONAOE DUDCT RR NOE W W FORO ODOP T DGCG ONAN 1 S HIEI N TTRC O ET U I MUED T HHE C STR U
D 7 E 8 R 9 1
R E .
W y O r P a u
n m a N A J O S
S A E
W O
H T
R C D N T O U M H
S T R
T O I P N) f 2 E OS L R IR 5 TU 9 AO
. RH 7 3 U( 7 D 6
_ D E
FS S
/
r
_. 7 6 8 3
/ 0 E 3 0 T /
A 1 D
_ D 0 I T
_ N E
- M U
. C O O N 1 D
R. UNIQUE REPORTING REQUIREMENTS
- 1. Safety / Relief Valve Operations for Unit Two.
^
DATR VALVRS NO & TYPE PLANT DESCRIPTION
&CTUATRD ACTUATIONS gONDITION OF EVRNT 01/04/87 2B21-F013A 2-Manual Shortly after
- Note Shutdown 01/04/87 2B21-F013B 2-Manual After S/D
- Noto 01/04/87 2D21-F013C 2-Manual After S/D
- Note 01/04/87 2B21-F013H 2-Manual After S/D
- Note 01/04/87 2821-F013F 2-Manual After S/D
- Note 01/04/87 2821-F013G 2-Manual After S/D
- Note 01/04/87 2H21-F013H 2-Manual After S/D
- Note i
- NOTR: The above SRV's were manually opened to reduce reactor pressure and facilitate cooldown following shutdown for refueling.
i DOCUMENT ID 0036r/0005r
. *
- 2. ECCS Systems Outtge3 The following outages were taken on ECCS Systems during the reporting period.
OUTAGE NO. ROUIPMENT PURPOSE OF OUTAGE 2-02-87 2B Diesel Generator D/G Local Switch Mod.
2-10-87 2B Diesel Generator 2B D/G Inspection.
2-11-87 2B D/G Diesel Air Compressor Repair Air Leak.
2-12-87 2B D/G Motor Air Compressor Adjust Oil Drain.
2-16-87 2B D/G Calibrations.
2-36-87 2B D/G Install Prelube Pump.
2-41-87 2B12-F092 B/C LTS-500-10 Div. 2 BCCS Response Time.
2-57-87 2821-F051 LES-LP-201 LPCS Relay Logic Test.
2-59-87 RHR "2A" Valves and RCIC LES-RH-200.
Steam to HX 2-83-87 RCIC Steam to Turbine Limitorque Surveillance.
2851-F045 2-85-87 RCIC Pump Discharge Limitorque Surveillance.
2851-F013 2-87-87 2821-F017 Monitor MSL Leakage Past MSL Plugs.
2-96-87 RCIC Suction from CY Valve Limitorque Surveillance.
2851-F010 2-97-87 2E51-F019 Limitorque Surveillance.
- 2-98-87 RCIC Suppr. Pool System Limitorque Surveillance.
2351-F031 2-99-87 RCIC Steam Isol. Limitcrque Surveillance.
2851-F063 2-100-87 RCIC Steam Line Warmup Limitorque Surveillance.
2851-F076 4
2-101-87 PCIS Steam Line Isolation Limitorque Surveillance.
2851-F008 2-102-87 RHR B Test Check Valve Repair Solenoid.
f DOCUMENT ID 0036r/0005r i
OUTAGE NO. BOUIPMENT PURPOSE OF OUTAGE 2-101-87 RCIC Steam Line Isolation Limitorque Surveillance.
Valve - 2851-F008 2-102-87 RHR B Test Check Valve Repair Solenoid.
2B12-F041B 2-103-87 RHR B Test Check Valve Repair Solenoid.
2812-F015 2-124-87 2/B D/G Disconnect for Operational Control.
Motor Starter K24A 2-133-87 RCIC Steam Supply Bypass Valve Limitorque Surveillance.
to Heat Exchanger 2851-F091 2-134-87 RCIC Steam Supply Valve to Limitorque Surveillance.
RH MX - 2851-F064 2-135-87 HP Suction from CY Valve Limitorque Surveillance.
2822-F015 2-136-87 HP Test to Supp. Pool Valve Limitorque Surveillance.
2812-F023 2-138-87 HPCS Pump Pump Protection No Suction.
2-143-87 2812-F009 Inspection.
2-151-87 LPCS Repack 2821-F011 and F012 2-154-87 2822-F012 Limitorque Surveillance.
To Prevent Inadvertant 2-161-87 IN Valves SRV. Actuation.
2-167-87 HPCS Pump Change 011.
2-182-87 2812-F026B Rotate Actuator.
2-183-87 HPCS D/G Output Check Breaker Adjustments BKR ACB 2433 and Relay Connection.
2-184-87 HPCS Pump Breaker check Aux. Cab. Adjust.
2-187-87 2851-F086 Limitorque Surveillance.
2-188-87 2E51-F080 Limitorque surveillance, I
f i
i DOCUMENT ID 0036r/0005r
i ouraGE No. _aQUTPfpSrf _ PURPOSE OF OUTAGE
'2-189-87 2851-F069 Limitorque Surveillance.
2-190-87 2E51-F046 Limitorque Surveillance. l l
2-191-87 2851-F068 1.initorque Surveillance. !
$ 2-196-87 2A RHR CY Fill / Flush Supply To Fill and Flush 2A RHR.
2-198-87 2E21-N005 Add Pressure Switch 2821-N0058.
2-199-87 2E12-N022A Changeout 'A' RHR Pressure Switch 2512-N022A.
2-204-87 IIPCS Limitorque Work.
2-205-87 HPCS D/G CW Pump Repack Strainer B/D Valve.
2-207-87 2851-F063, 2B33-F067B, LES-AP-201.
2B33-F023B 2-215-87 RCIC Vacuum Pump Replace Pump.
i 2-216-87 RCIC 2551-F063 ' Repack.
2-221-87 2B Diesel Generator Replace Air Start Solenoids, and Lube 011 Pump.
2-233-87 2822-F004 Limitorque.
2-238-87 2E12-F063A To Fill and Vent 'A' RHR.
2-239-87 .' A' RIIR Prevent Draining Vessel.
2-240-87 2H12-F017A I.imitorque Surveillance.
2-241-87 2E12-F048A Limitorque Surveillance.
l 2-242-87 2H12-F027A Limitorque Surveillance.
2-243-87 2E12-F042A Limitorque Surveillance.
2-244-87 2R12-F004A 1.imitorque Surveillance.
2-245-87 2812-F049A Limitorque Surveillance.
2-246-87 2H12-F047A Limitorque Surveillance.
2-247-87 2812-F064A Limitorque Surveillance.
i e
i DOCUMENT ID 0036r/0005r
t-OUTAGE NO. 80UIPMENT PURPOSE OF OUTAGE 2-248-87 2B12-F068A Limitorque Surveillance.
2-249-87 2B12-F052A Limitorque Surveillance.
2-250-87 'A' RHR Min. Flow Check Inspect and Repair.
Valve - 2B12-F046A 2-251-87 Aux. Equipment on 2B D/G Repair Air Compressor "BB" Breaker.
2-260-87 2-B D/G Air Start System To Assist in Charging Air Receivers.
2-263-87 S/D Cooling Return Valve Limitorque Inspection.
2B12-F053A 2-264-87 Steam Line Isolation Valve Limitorque Inspection.
2B12-F087A 2-265-87 Heat Exchanger Outlet Valve Limitorque Inspection.
2E12-F003A 2-271-87 Common D/G LES-DG-100.
2-272-87 Common D/G Check Wiring Term on Output BKR 2413 ODG11JB 2-273-87 Common D/G Check Wiring Term on Output BKR 1413 ODGilJA 2-274-87 Common D/G Refuel Inspection.
, 2-278-87 2B12-N022A Install New Pressure
. Switch 2812-N512A 4
2-279-87 2B12-N022B Install New Pressure Switch 2E12-N512B a
- 2-280-87 2B RHR Prevent Inadvertant Drain of Reactor.
2-281-87 LPCS Pump Motor Change Oil.
2-284-87 2B21-F005 Limitorque Surveillance.
2-285-87 2821-F001 Limitorque Surveillance.
2-286-87 2821-F011 Limitorque Surveillance.
DOCUMENT ID 0036r/0005r
. - . . - - . , . - . - - . ~ . . - . _ . , , - . - . - - - - - . - - , - . . . . , . - . . _ - - - . , - - - . - .
- '* OUTAGE NO. BOUIPMNT PURPOSE OF OUTAGE 2-287-87 2521-F012 Limitorque Surveillance.
2-288-87 2D0035 Limitorque Surveillance.
2-289-87 Division III BUS 243 Calibrate UV Relays.
2-290-87 LPCS System Prevent Draining Reactor.
Protect Pump During Limitorque Surveillance.
2-302-87 'A' RHR CY Flush Line To facilitate flushing, and Filling.
2-309-87 28 D/G LES-DG-202 2-310-87 28 D/G Fix 011 Leaks.
2-311-87 2B12-F099A LimLtorque Surveillance.
2-312-87 2512-F011A Limitorque Surveillance.
2-317-87 2512-F006A Limitorque Surveillance.
2-326-87 2512-F0638 Fill 'B' RHR.
2-330-87 'A' RHR Install 2 New Vents.
2-331-87 Shutdown Cooling Suction Install Thermowell.-
2-334-87 28/C RHR Discharge Flow Split Hi/Lo Flow Switches Alarm into 2 Switches.
2-335-87 HPCS Relief Valve Testing.
2-341-87 2A RHR 2512-F031A Repair Check Valve 2B12-F031A 2-379-87 2512-F024A Limitorque Surveillance.
2-380-87 2512-F053B Limitorque Surveillance.
2-381-87 2E12-F0428 Limitorque Surveillance.
f 2-382-87 2E12-F0168 Limitorque Surveillance.
! 2-383-87 2B RHR Vent Modification.
! 2-384-87 200036 Trouble Shoot and Repair
]
1 i
- DOCUMENT ID 0036r/0005r
. o. e QUTA05 NO. BOUIPMRNT _ PURPOSE OF OUTAGE 2-385 28 D/G Replace Cooling Water Temperature Switch.
2-379-87 2E12-F024A Limitorque Surveillance.
2-380-87 2H12-F0538 Limitorque Surveillance.
2-381-87 2H12-F042B Limitorque Surveillance.
2-382-87 2M12-F016B Limitorque Surveillance.
2-383-87 2B RHR Vent Modification.
2-384-87 2DG036 Trouble Shoot and Repair Check Valve.
2-385-87 2B D/G Replace Cooling Water Temperature switch.
2-389-87 2K12-F074R Limitorque Surveillance.
2-390-87 2H12-F040A Limitcrque Surveillance.
2-391-87 2E12-r0998 Limitorque Surveillance.
2-392-87 2H12-P003B Limitorque Surveillance.
2-393-87 2X12-F047B Limitorque Surveillance.
2-394-87 2812-F048B Limitorque surveillance.
2-395-87 2E12-F068B Limitorque Surveillance.
2-399-87 LPCS check Out Ammeter.
2-401-87 2H12-P064B 1.imitorque Inspection.
2-402-87 2E12-F0llB Limitorque Surveillance.
2-403-87 2R12-F0048 Limitorque Surveillance.
2-404-87 2H12-P027R Limitorque Surveillance.
2-423-87 2B D/G Repair / Calibrate Oil Temperature System.
2-535-87 2B D/G Hework Termination at K24A Starter Cabinet.
DOCUMENT ID 0036r/0C05r
a ee o OUTAGE No. BQUIPIENT PURPOSE OF OUTAGE 2-538-87 2812-F068A Repack.
2-539-87 2851-F064 Repack.
2-540-87 2A/D/G Prelube Modification.
2-541-87 2A/D/G 18 Month LEs's.
2-542-87 2A/D/G 18 Month M.M. Inspections.
2-544-87 2B/D/G Flush D/G Cooler.
2-546-87 2512-F4098 Replace Valve.
2-549-87 2E12-F026A Limitorque surveillance.
2-550-87 2812-C300D Inspect Motor Winding.
2-551-87 2/C RHR Prevent Draining Reactor Vessel During Limitorque LES t DOCUMENT ID 0036r/0005r
-*Gr Off-Sito Dose C:1culction Manual There were no changes to the ODCM during this reporting period.
- 4. Radioactive Weste 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.
DOCUMENT ID 0036r/
'[D Commonwealth Edison
,% g [ 2
) Rur:IRoute #1, Box 220LaSalb County Nucl=r Station
(
i
'v'
] Marseilles, Illinois 61341 Telephone 815/357-6761 February 6, 1987 l
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 January 1, 1987 through January 31, 1987.
Very truly yours, n'
f,0. $3w gV'
.f. G. J. Diederich Station Manager LaSalle County Station GJD/GJK/jdp Enclosure l
xc: J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety 1 A. Bournia, NRR Project Manager l D. P. Galle, Ceco D. L. Farrar, CBCo INPO Records Center L. J. Anastasia PIP Coordinator SNED M. A. Ortin, GE Resident H. B. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Fineacial Coordinator, LaSalle J. C. Klika, Surveillance Group Leader Central File l
DOCUMENT ID 0043r/0005r
/%
- - . - -.