ML20235J313
| ML20235J313 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/30/1987 |
| From: | Diederich G, Kirchner G COMMONWEALTH EDISON CO. |
| To: | NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8707150488 | |
| Download: ML20235J313 (39) | |
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LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT JUNE 1987 i
COMMONWEALTII EDTSON COMPANY i
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NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll 4
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8707150488 DR 870630 ADOCK 0500 3 {
\ ,1 DOCUMENT ID 0043r/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 one was issued operating license number NPF-ll on April 17, 1982.
Initial criticality was achieved on June 21, 1982 and commercial power operation was commenced on January 1, 1984.
This' report was compiled by Gregory J. Kirchner, telephone number (815)357-6761, extension 704.
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i II. MONTHLY REPORT FOR UNIT ONE A,
SUMMARY
OF OPERATING EXPERIENCE FOR UNIT ONE JUNE 1987 6-1-87 0000 Hours RX in Shutdown Mode 6-30-87 2400 Hours Rx in shutdown Mode for 50-day Outage l
l DOCUMENT ID 0043r/0005r
B. PLANT OR PROCEDURE CHANGES, TCSTS, EXPERIMENTS AND SAFETY RELRTED MAINTENANCE.
- 1. Amendments to Facility License or Technical Speci'fication.
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 I reporting period. The headings indicated in this summary include:
Work Request number, Component Name, Cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action.
- 5. Completed Safety Related Modifications.
The following Table (Table 2) presents a list of completed Modifications during this reporting period. Each entry will have a short synopsis explaining details involved with each modification.
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DOCUMENT ID 0043r/0005r
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TABLE 2 COMPLETED SAFETY RELATED MODIFICATIONS MODIFICATION NUMBER: A brief synopsis of incorporated modification objectives with final design resolution. Also, state reviewed or unreviewed safety questions.
UNIT ONE M-1-1-85-003 This modification was to install a monrail type sandblasting facility on the turbine deck. The facility will be used to sandblast turbine components. There were no unreviewed safety questions.
M-1 86-026 This modification was to install six (6) threaded UNIONS and relocate one piping support in the lube oil system for the f Unit 'O' diesel generator to remove the lube oil pump and check valves for maintenance. There were no unreviewed safety questions.
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. C. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, logged during the reporting period, June 1, 1987 through June 30, 1987. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.
Licensee Event Report Number pate. I.itle of Occurrence 87-024-00 6/2/87 'B' VC Ammonia Detector trip / broken chem cassette l tape / design deficiency, adjusted chem cassette tepe/Wr to upgrade tape mechanism.
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D. DATA TABULATIONS The following data tabulations are presented in this report:
- 1. Operating Data Report i
- 2. Average Daily Unit Power Level
- 3. Unit Shutdowns and Power Reductions 1
DOCUMENT ID 0043r/0005r
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- 1. -OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One ,
DATE July 10, 1987 COMPLETED BY G. J. Kirchner l TELEPHONE 1815)357-6761 OPERATING STATUS
- 1. REPORTING PERIOD: June, 1987 GROSS HOURS IN REPORTING PERIOD: 720
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX' DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Not): 1078
- 3. POWER LEVEL TO WHICH RESTRICTED (IP ANY) (MWe-Net): 1050 _ _ _ _
- 4. REASONS FOR RESTRICTION (IP ANY): Administrative THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 3143.6 12069.5 _;'
- 6. REACTOR RESERVE SHUTDOWN HOURS. 0.0 0.0 29.83'
- 7. HOUl:S GENERATOR ON LINE 0.0 3028.9 11830.84
- 8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 'O.0
- 9. GROSS THERMAL ENERGY GENERATED (HWH) 0.0 6356688 21635128 i
- 10. GROSS ELEC. ENERGY GENERATED'(MWH) 0.0 2046824 11100804
- 11. NET ELEC. ENERGY GENERATED (MWH) -10048 1957983 10526508
- 12. REACTOR SERVICE FACTOR 0% 72.4% 39.4%
- 13. REACTOR AVAILABILITY FACTOR 0% 72.4% 40%
- 14. UNIT SERVICE FACTOR 0% 69.7% 38.6%
- 15. UNIT AVAILABILITY FACTOR 0% 69.7% 38.6%
- 16. UNIT CAPACITY FACTOR (USING MDC) N/A 43.5% 33.1%
- 17. UNIT CAPACITY FACTOR (USING DESIGN .j MWe) N/A 41.8% 31,8% j
- 18. UNIT FORCED OUTAGE PATE. 0% 14.5% 14.5%
- 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE,.DATE, AND DURATION OF EACH)
N/A Unit is shutdown during this period.
- 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 8/24/87 i
i DOCUMENT ID 0043r/0005r
-2. AVERAGE DAILY' UNIT POWER LEVEL l
DOCKET,NO: 950-373; .
j UNIT: LASALLE ONE DATE: July 10, 1987 j COMPLETED BY: Gregory Kirchner TELEPHONE: (815) 357-6761 MONTH: June. 1987 _,
DAY AVERAGE DAILY POWER LEVEL. DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1.' -15 17. -15
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'2. -15' 18. -16 3 -16 19. -13
- 4. -15 20. '-10' '
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- 5. -15 21. -13
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- 6. -14 22. -13 f
- 7. -14 23. -12 .
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- 8. -14 24. -13
- 9. -14 25. -14 l
- 10. -14 __ 26. -16
- 11. ~14 -27. -12 ,
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- 12. -13 28. -10 !
- 13. -14 __ 29. -14 i 14.- -14 30. -13 1 1
- 15. -13 31. -- I l
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- 16. -13 I l ,
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DOCUMP.NT ID 0043r/0005r
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E. UNIQUE REPORTING REQUIREMENTS
- 1. Safety / Relief valve operations for Unit One.
VALVES NO & TYPE PLANT DESCRIPTION PATE ACTUATED ACTUATION CONDITION OF EVENT There were no Safety Relief Valves Operated for Unit One during this reporting
- period, i
i DOCUMENT ID 0043r/0005r
- 2. BCCS Systems Outagas The following outagas wsre taken on ECCS. Systems during the' reporting pericd.
QUTA9 M BOUIPMEN_I PURPOSE OF OUTAGE U-1 1-253-87 HPCS, Pump Oil Change 1-286-87 RCIC-Head Sparger Remove Piping .
I 1-288-87 HPCS Pump Inspect Motor .
I l-291-87 IB21-F028C Air Valve for U-2 1-294-87 HPCS D/G Refuel Inspection
.1-295-87 HPCS D/G Add Unions to Oil Pumps i 1-296-87 HPCS.D/G Output Control Verify Crimp in Relay Board 1-297-87 HPCS D/G Inspect Airstart Sol.
1-305-87 Main Steam Isolate Steam to Turbine Bldg.
1-308-87 ~1B HPCS D/G B.O.P. Cals.
1-330-87 HD Pumps Oil Change.
1-342-87 IB21-F423A Set Limits 1-351-87 HPCS Injection Line Stop Prevent Injection into Rx )
during Testing
.1-379-87 1HD141A Replace Packing
~1-387-87 1B D/G Fix lE22-R512 1-390 A & B SDC Install Plugs on 'A' RR & Jet Pumps 1-391-87 HPCS D/G Repair Oil Leaks 1-402-87 lE12-F006A Prevent Rpv Drain 1-423-87 RCIC Repack'lE51-F008 1-425-98 lE12-F090A Disconnect Limit Switches 1-427-87 lE12-F004A Inspect Packing DOCUMENT ID 0043r/0005r
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OUTAGB NO, Edi;PMI PURPOSE OF OUTAGE J 1
U-1 e
- 1-432-87' 1821-F067A Repair 1-436-87 .1B RHR Pump, Change Motor 011 .
i 1-437-87 IB RHR Pump Meggar Motor I i
1 1-439-87 1C RHR. Pump Meggar Motor
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1-443-87 IB D/G -Inspect Relays l 1-446-87 RCIC Pump Repair Leak .
1-513-87 Main steam IB21-F429A Repack.
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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-changes to the RadWaste treatment systems for this reporting period.
5 .- Indications of Failed Fuel' Elements There were isc f ndications 'of Failed Fuel Elements during this reporting period.
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l LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT JUNE, 1987 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 1
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i DOCUMENT ID 0036r/0005r
1 TABLE OF CONTENTS l
1 I. INTRODUCTION 1 l
II. MONTHLY REPORT FOR UNIT TWO A. Summary of Operating Experience B. PLAWT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS,'AND SAFETY RELATED MAINTENANCE {
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- 1. Amendments to' Facility License or Technical '.
Specifications j
- 2. Facility or Procedure Changes Requiring NRC {
Approval !
- 3. Tests and Experiments Requiring NRC Approval
- 4. Corrective Maintenance of Safety Related l Equipment' )
- 5. Completed Safety Related Modifications 1 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
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- 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 Failnd Fuel Elements i
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l I.- INTRODUCTION l
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 i, output of 1078 Megawatts. Vaste 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.
l Unit two was issued operating license number NPF-18 on Dece:nber 16, .
1983. Initial criticality was achieved on March 10, 1964 and commercial power operation was commenced on June 19, 1984. i This report was compiled by Gregory J. Kirchner, telephone number (815)357-6761 extension 704.
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DOCUMENT ID 0036r/0005r
II. -MONTHLY REPORT FOR UNIT TWO A..
SUMMARY
OF OPERATING EXPERIENCE FOR UNIT TWO j 6/1/87 0000 Rx in Refuel Mode 6/18/87 1030 Generator on Line, Rx Ramp up to 175 MWe 6/19/87 2100 Ramp up to 188 MWe 6/20/87 1900 Ramp up to 314 MWe at 48 MWe/hr. )
6/21/87 0200. Ramp up to 611 MWe at 95 MWe/hr.
1305 Increase power to 650 MWe.
1700 Ramp up to 720 MWe at 10 MWe/hr.
6/22/87 0630 Decrease Power at 3 MWe/hr to 687 MWe Due to Xenon Building in. :
1800 Ramp up to 720 MWe at 9MWe/hr.
6/23/87 1253 Rx Scram Due to High Turbine Thrust Bearing wear alarm.
6/26/87 1905' Ramp up to 155 MWe, Generator Synched to Grid. [
6/27/87 0630 Ramp up to 308 MWe. '
6/29/87 0300 Ramp up to 820 MWe, 0500 Ramp up to 924 MWe - 10 MWe/hr. i 6/30/87 2400 Rx at 924 MWe. .
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DOCUMENT ID 0036r/0005r i
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'B. PLANT OR PROCEDURE. CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED h ,
MAINTENANCE..
- 1. Amendments to Facility license or. Technical Specification.
[l There were no Amendments-to the facility license or Technical.
> Specifications during this reporting period. ;j L
li 2.' ' Facility or Procedure changes requiring NRC approval.
There were no Facility or Procedure changes requiring NRC approval during the reporting period.- ,
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- 3. Tests and Experiments requiring NRC approval.
l There were no Tests or Experiments requiring NRC. approval during !
the reporting period.
- 4. Corrective Maintenance of Safety Related Equipment.
The following table (Table 1) presents a summary of Safety-Related Maintenance completed on Unit Two during the reporting period. The headings indicated in this summary include: Work Request. number, Component Name, cause of malfunction, results and effects on safe operation, and corrective action.
- 5. '. Completed Safety Related Modifications.
The.following table (Table 2) presents a list of completed
- o. Modifications during this reporting period. Each entry will have i, .a short synopsis explaining details involved with each modification.
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DOCUMENT ID OD36r/0005r
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TABLE 2 COMPLETED SAFETY RELATED MODIFICATIONS MODIFICATION NUMBER: A brief Synopsis of Incorporated Modification Objectives with final design resolution. Also, state reviewed or unreviewed safety questions.
UNIT TWO M-1-2-83-011 This mod was to improve the oil circulating subsystem which supplies oil to the engine during shutdown to keep it ready for an emergency start. There were no unreviewed safety questions.
M-1-2-84-048 This mod was to provide a faster response time in closing of the primary containment vent and purge isolation valves. There were no unreviewed safety questions.
M-1-2-84-061 This mod was for an alternate rod insertion (ARI) and Main steam isolation valve (MSIV) closure design change, is part of the preventative measures being taken to recover from an anticipated transient without scram (ATWS) event. There were no unreviewed safety questions.
11-1-2-84-069 This modification provides an ADS manual inhibit switch and
) Hi drywell pressure bypass timer. There were no unreviewed safety questions.
B-1-2-84-076 This mod allowed for the replacement of the existing instrumentation for the drywell condensate drain flow measurement. There were no unreviewed safety questions.
M-1-2-84-082 This mod was to modify the suppression pool temperature loop to the remote shutdown panel to ensure that this loop is electrically isolated from the control room. There were no unreviewed safety questions.
M-1-2-84-113 This mod was to install time delay relays to the FW pumps low suction pressure alarm / trip logic to eliminate possible FW pumps trips due to spurious pressure surges to the existing pressure switch (2PSL--CB039). There were no .
unreviewed safety questions. l M-1-2-84-135 This mod was to replace the seals and switch mechanisms in the level controllers supplied by Magnetrol International.
Therr are no unreviewed safety questions.
M-1-2-84-170 This mod was to relocate the Drywell ionization detectors (2XY-2-16P-00) to a location away from the air flow. There were no unreviewed safety questions.
DOCUMENT ID 0036r/0005r
TABLE 2 COMPLETED SAFETY RELATED MODIFICATIONS MODIFICATION NUMBER: A brief Synopsis of Incorporated Modification Objectives with final design resolution. Also, state reviewed or unreviewed safety questions.
UNIT TWO M-1-2-85-018 This mod was to install a new drywell chiller 2VP145 and its associated chiller water and service water piping, and electrical equipment. There were no unreviewed safety questions.
f
{
i M-1-2-85-021 This mod was to relocate valve RE043 and orifice E12-0310 from line RE37AB/AA. This will permit warm-up flow from both 'A' and 'B' RHR loops to be sent to the condenser rather than to the reactor building equipment drain tank.
There were no unreviewed safety questions.
M-1-2-85-032 This mod was to revise the calibration constants for the feedwater and condenser RWCU flow elements. There were no unreviewed safety questions.
M-1-2-85-057 This mod was to replace the HTX-series ASCO solenoid valves on the MSIV actuators (2B21-F022A,B,C,D and 2B21-F028A,B,C,D) with equivalent NP-series solenoid valves. There were no unreviewed safety questions.
M-1-2-85-061 This mod was to restore primary containment cooling design redundancy. There were no unreviewed safety questions.
M-1-2-86-028 This mod was to add a one-second time delay to the isolation and alarm circuity associated with the Riley leak detection temperature monitors for the RWCU, RCIC, MSIV, and RHR systems. There were no unreviewed safety questions.
M-1-2-86-065 This mod was for the snubber reduction on subsystem 2RH-C3 per the snubber reduction program. There were no unreviewed safety questions.
M-1-2-86-077 This mod was for the snubber reduction on subsystem 2MS-25A per the snubber reduction program. There were no unreviewed safety questions.
M-1-2-87-017 This mod was to cut the gland seal leak-off line 2MS64B which is attached to valve 2B21-F016 and cap the line going to the gland seal leak-off reservoir. There were no unreviewed safety questions.
M-1-2-87-018 This mod was to cut the gland seal leak-off line which is attached to valve 2E12-F050A to allow maintenance to be performed on valve 2E12-F050A. The gland seal leakoff line will be reconnected during next refuel. There were no
) unreviewed safety questions.
DOCUMENT ID 0036r/0005r
i
)
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C. LICENSEE EVENT REPORTS 1
l The following is a tabular summary of all licensee event reports for
[
LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, June 01, through June 30, 1987. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.
Licensee Event Report Number Date Title of Occurrence
\
87-014-00 6/23/87 Hi Thrust Bearing Wear Scram. '
87-015-00 6/30/87 RWCU Suction Isoation on HI Inlet Temperature.
i i
1 DOCUMENT ID 0036r/0005r
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 1
DOCUMENT ID 0035r/000Sr
l l'.' OPERATING DATA REPORT DOCKET NO. 050-374 3 UNIT LaSalle Two 1 DATE July 10, 1987 COMPLETED BY Grecorv Kirchner ]
TELEPHONE 1815)357-6761 MONTH JUNE, 1987 -i 1
OPERATING STATUS
'1. REPORTING PERIOD: June, 1987 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):
- 1050 I
, 4. REASONS FOR RESTRICTION (IF ANY): Administrative .l THIS MONTH YR TO DATE CUMULATIVE l 5 NUM3ER OF HOURS REACTOR WAS CRITICAL 298.29 364.34 12367.79
- 6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 29.83
.7. HOURS GENERATOR ON LINE 223.29_ 282.91 12054.13 ;
- 8. UNIT RESERVE SHUTDOWN HOURS- 0.0 0.0 0.0 i
- 9. GROSS THERMAL ENERGY GENERATED (MWH) 359160 480024 33994288
- 10. GRO?S ELEC. ENERGY GENERATED (MWH) 104046 143278 11204850
- 11. NET ELEC. ENERGY GENERATED (MWH) 92614 88941 10629170
- 12. REACTOR SERVICE FACTOR 41.4% 8.4% 52.3% !
- 13. REACTOR AVAILABILITY PACTOR 41.4% 8.4% 52.4% j
- 14. UNIT SERVICE FACTOR 31.0% 6.5% 50.9%
- 15. UNIT AVAILABILITY FACTOR 31.0% 6.5% 50.9%
- 16. UNIT CAPACITY FACTOR (USING MDC)
~
12.4% 2.0% 43.4%
- 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 12.0% 2.0% 41.7%
- 18. UNIT FORCED OUTAGE RATE 20% 16.5% 26.2%
- 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
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DOCUMENT ID 0036r/0005r
- 2. AVERAGE DAILY UNIT POWER LEVEL ]
DOCKET NO: 050-374 ]
UNIT: LASALLE TWO i DATE: July 10. 1987 COMPLETED BY: Gregory Kirchner .
TELEPHONE: (815) 357-6761 i MONTH: JUNE 1987 l 1
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) i
- 1. -15 17. -15
- 2. -15 _
18, 78 3 -15 _
- 19. 159
- 4. -15 _
- 20. 192
- 5. -15 _
21, 578 _
- 6. -14 ._
- 22. 680
- 7. -14 .__
- 23. 363 ,
- 8. -14 24. -11 1
- 9. -14 25. -13
- 10. -13 26. -12
- 11. -13 27. 247
- 12. -13 28. 361
- 13. -14 29, 614
- 14. -14 __
- 30. 824
- 15. -12 ,_
- 31. -
- 16. -12 _
)
DOCUMENT ID 0036r/0005r
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N 1 2
E., ' UNIQUE REPORTING REQUIREMENTS
- 1. Safety / Relief. Valve Operations for Unit Two.
DATE' VALVES: NO & TYPE PLANT DE3CRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT 6/18/87 2B21-F013A 2 - Manual- Before Startup
- Note !
6/18/87 '2B21-F013B 2 - Manual " " * "
'6/18/87 2B21-F013C 2 - Manual " '" * "
'6/18/87 2B21-F013D 2 - Manual
- 6/18/87 2B21-F013E 2 - Manual " " * "
6/18/87 2B21-F013F 2 - Manual. " " * "
6/18/87 2B21- F013G 2 - Manual " " * "
6/18/87 2B21-F013H 2 - Manual " " * "
6/18/87 2B21-F013J 2 - Manual " " * "
6/18/87 . 2B21-F013K 1 - Manual " " * "
6/18/87 2B21-F013L 2 - Manual " " * "
6/18/87 2B21-F013M 2 - Manual " " * "
6/18/87- 2B21-F013N 2 - Manual " " * "
6/18/87 2B21-F013P 2 - Manual " " *
- i 6/18/87 2B21-F013R 2 - Manual " " * "
6/18/87 '2B21-F013S 1 - Manual " " * "
I 6/18/87 2821-F013U 2 - Manual " " * "
6/18/87, 2B21-F013V 2 - Manual " " * "
1>
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1
- NOTE: The above S/RV's were manually opened per the requirements of the L LSCS Station Surveillance Schedule.
1 1.
l l'
h DOCUMENT ID 0036r/0005r L
u
I
'I:e _ , _
ii'2. .
ECCS Systcms Outagzs L'
MF The following outages were taken on ECCS Systems during the reporting period.
UNIT 2 OUTAGE NO. EOUIPMENT PURPOSE OF OUTAGE 2-1538-87 2E32-C001 Repair Mounting for
. Circuit Bkr.
2-1549-87' -2E12-F087A Prevent Spurious Open.
2-1549 '2B21-F028C Repair Viv.
2-1550-87 2E51-C004 Troubleshoot Cond. Pump 2-1559-87 2E51-C005 Troubleshoot 2-1562-87 RCIC Repair Water Leg Pump
.Disch, Check 2-1575-87 2B12-F075A Repair Viv. Logic f'
L r l l
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I j' DOCUMENT ID 0036r/0005r
- 3. Off-site Dosa csiculation Minual (U-2)
There were no changes to the ODCM during this reporting period.
- 4. Radioactive Waste Treatment Systems, f
There were no changes to the Radwaste Treatment Systems for this !
reporting period. j 1
Indications of Failed Fuel Elements.
~
5.
There were no indications of failed fuel elements during this i reporting period.
)
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DOCUMENT ID 0036r/0005r
._--_._____________j
Commonwo lth Edison C LaSalle County Nuclear Station
- Rural Route #1, Box 220 O<U ~-
Marseilles, Illinois 61341 Telephone 815/357-6761 July 10, 1987 l l
Director, Office of Ma.7agement 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 June 1, 1987 through June 30, 1987.
Very truly yours,
. l4' -
G. J. Diederich F/dM7 S ation Manager LaSalle County Station GJD/GJK/jdp Enclosure xc: J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety P. Shemanski, NRR Project Manager D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center L. J. Anastasia, PIP Coordinator SNED M. A. Ortin, GE Resident H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle Dennis Carlson/ Tech Staff Terry Novotney/ Training Central File I i i DOCUMENT ID 0043r/0005r i
TABLE OF CONTENTS
- 1. INTRODUCTION II. MONTHLY REPORT FOR UNIT ONE f
A. Summary of Operating Experience l
B. PLANT OR PROCEDURE CilANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED l MAINTENANCE i
- 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. Main Steam Relief Valve Operat. ions
- 2. ECCS System Outages
- 3. Off-site Dose calculation Manual Changes
- 4. Major changes to Radioactive Waste Treatment System
- 5. Indications of Failed Fuel Elements DOCUMENT ID 0043r/0005r
. _ . _ _