Text

Monthly Operating Repts for Mar 1984
	ML20083M348
Person / Time
Site:	LaSalle
Issue date:	03/31/1984
From:	Diederich G, Dus R; COMMONWEALTH EDISON CO.
To:	; NRC
References
	NUDOCS 8404180003
	Download: ML20083M348 (28)
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l j LASALLE NUCLKAR POWER STATION l UNIT 1 l

NONTHLY PERFORMANCE REPORT MARCH 1994 C00gIONWEALTH EDISON CONFANY NRC DOCKET No. 050-373 LICENSE NO. NPF-11 l

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,; TABLE OF CONTENTS 1

I. INTRODUCTION 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. 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

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I. INTRODUCTION The LaSalle Nuclear Power Station is a Two Unit Facility Located in Marseilles, Illinois. Each Unit is a Boiling Water Reactor with a designed electrical output of 1078 MWe net. The Station is owned by Commonwealth Edison Company. The Architect / Engineer was Sargent & Lundy, and the primary construction contractor was Commonwealth Edison Company.

The condenser cooling method is a closed cycle cooling pond. Unit One is subject to License Number NPF-11, issued on April 17, 1982. The date of initial

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criticality was June 21, 1982. The unit commenced commercial generation of power on January 1, 1984.

Unit Two is subject to license number NFP-18, issued 3

on December 16, 1983. The date of initial criticality was March 10, 1984. The Unit is expected to commence commercial generation of power in August, '84.

This report was compiled by Randy S. Dus, telephone

- _ number (815)357-6761, extension 324.

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J t II. MONTHLY REPORT FOR UNIT ONE i l

A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE l

MARCH 1-5 The Unit started the reporting period in cold shutdown due to repairs on the extraction steam line expansion bellows and the condenser boot seal.

MARCH 6-18 The reactor went critical at 2240 hours0.0259 days 0.622 hours 0.0037 weeks 8.5232e-4 months on March 6. At 1235 hours0.0143 days 0.343 hours 0.00204 weeks 4.699175e-4 months on March 7 the main generator was synchronized to the grid. At 1508 hours0.0175 days 0.419 hours 0.00249 weeks 5.73794e-4 months on March 7 reactor power was at 25%. At 2130 hours0.0247 days 0.592 hours 0.00352 weeks 8.10465e-4 months on March 7 a Rx shutdown was commenced to analyze stress loading of temporary ventilation ductwork in drywell. At 0050 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months on March 8 the turbine generator was tripped. At 0640 on March 8, the Rx was shutdown. The reactor was critical for 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months and 0 minutes.

MARCH 19-31 The reactor went critical at 0315 hours0.00365 days 0.0875 hours 5.208333e-4 weeks 1.198575e-4 months on March 19. At 2335 hours0.027 days 0.649 hours 0.00386 weeks 8.884675e-4 months on March 19, the main generator was synchronized to the Grid. Reactor power was raised to 23% at 1730 hours0.02 days 0.481 hours 0.00286 weeks 6.58265e-4 months on March 20. At 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months on March 20, reactor power was raised to 44%. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on March 21, reactor power was 8.ncreased to 64%.

Reactor power was reduced to 39% at 1330 hours0.0154 days 0.369 hours 0.0022 weeks 5.06065e-4 months on March 22 for a drywell entry to investigate the source of water in the "B" Ex recirc motor cm.ing. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on March 24, reactor power was increased to 67%.

Reactor power was decreased to 47% at 1645 hours0.019 days 0.457 hours 0.00272 weeks 6.259225e-4 months on March 27 due to a feedwater heater string isolation. At 1150 hours0.0133 days 0.319 hours 0.0019 weeks 4.37575e-4 months on March 28, reactor power was reduced to 23%

due to additional feedwater heater problems. At 1720 hours0.0199 days 0.478 hours 0.00284 weeks 6.5446e-4 months on March 29, commenced pulling rods to increase power. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on March 30, reactor power was at 70%. The reactor was critecal for 308 hours0.00356 days 0.0856 hours 5.092593e-4 weeks 1.17194e-4 months and 45 minutes.

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

1. Amendments to Facility License or Technical Specifications.

Amendment No. 16- This amendment revised the electrical power systems Technical Specification 3.8.1.1. The Amendment changes the LaSalle Unit One Technical Specification Requirements for fast starts on the Diesel Generators, consistent with the provisions of the LaSalle Unit Two Technical Specifications.

4 This involves the reduction in the number of required fast, cold start surveillances.

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2. Facility or Procedure Changes Requiring NRC Approval.

There were no facility or procedure changes 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 tables present a summary of safety-related i'

maintenance completed on Unit One during the reported period.

The headings indicated in this summary include: Work Request Numbers, LER Numbers, Component Name, Cause of Malfunctions, t

Results and Effects on Safe Operation, and Corrective Action.

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LTP-300-7 ATTACHMENT A Rivisien 3 M rch 1, 1983 '

CORRECTIVE MAINTENANCE OF 5 e SAFETY RELATED EQUIPMENT i

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i. WORK REQUEST- LER COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION I I' I I I L24025 Botton Head Valve Seat Eroded Additional Drywell Equipment Line Temporarily capped Drain Valve Drain Sump Input until valves can be repaired.

L31534 Control Rod Rod uncoupled when fully Loss of Rod Control Changed out Control Rod withdrawn.

L32576 D/G Daytank Valve Does not open fully. Unable to fill day tank Reset limits on fill fill valve completely valve.

L32968 84-012-00 H2 RecombinerValve failed local leak. Potential degradation of Repaired valve Isolation rate test primary containment valves integrity L33098 84-012-00 RI Blds Equip Valve Failed local-leak Potential degradation of Repaired valve i drains isola- rate test primary containment tion valves integrity L33680 Div I Post' Erratic Indication No effect on operation. Replaced faulty LOCA 02 Rec Less than 20% Div II still operable. Resistor and Recalibrated, L33778~ , RHR HI Steam Valve has dual valve position unknown Limit switch reset Inlet Stop indication when closed valve L33802 A IBM BAD connection under IRN indicates upscale Cleaned connection vessel under vessel.

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LTP-300-7 ATTACHMENT A Cent'd Ravioica 3 -

g M:rch 1, 1983 CORRECTIVE MAINTENANCE OF 5 .

SAFETf RELATED EQUIPMENT I I I l l !

WORK REQUEST LER COMPC :#ENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS. CORRECTIVE ACTION ON SAFE OPERATION 1 I I I I

- L33871 1RE024 Open limit switch contacts Will not allow RK Blds Equip Adjusted limit switch 4 not picking up drain sump to start actuator and bracket.

L34054 84-017-00 Ammonia / Defective Detectors Will not isolate control Repaired Detectors-Chlorine room supply dampers and recalibrated Detector L34155 RWCU Inboard Packing leak Leakage into drywell sump Valve Repacked Isolation valve L3.';185 "A" RHR HK Overload contacts Loss of position indication Replaced thermal bypass valve open- overloads.

L34399 Stack Gas Purge Gas Bottle pressure Control Room indication Replaced purge Gas WRGH recorder low causing faulty reading is high Bottle L344 2 Rx Level Switch Intermittently Inaccurate Rx Level Replaced microswitch Indicating contacts Indication Switch L34556' Rx Mode switch Contacts for run mode causes " Rod out Block" Cleaned circuit board input to Rx manual' control ground contacts system not picked up.

L34929 VR Rad Defective Monitor does not None. Redundant channels Replaced faulty relay Monitor alera or indicate still operable board L34947 Ammonia Detector wired Would not isolate supply Rewired and verified

' Detector incorrectly dampers on high asumonia proper operation signal PM:UNENT 0044r '

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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, occurring during the reporting period, March 1 through March 31, 1984. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in section 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

Licensee Event Report Number Date Title of Occurrence 84-008-00 2/18/84 IRM Cable Bumped /Non-coincident Reactor Scram 84-009-00 2/19/84 Upscale spike on "A" IRM/Non-coincident Scram 84-010-00 2/19/84 RPS Actuation from "A" IRN/Non-coincident Scram 84-011-00 2/13/84 Rx scram due to condenser boot Seal failure 84-012-00 2/14/84 Leak rate limit exceeded 84-013-00 2/14/84 Main steam line high flow isolation 84-014-00 3/1/84 Procedure error in LES-RI-01 84-015-00 2/27/84 Group II and Group IV isolation 84-016-00 [ 3/7/84 RHR B & C injection valves Ex Pressure Interlock

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2 84-017-00 3/8/84 Failure of control room vent-11ation ammonia / chlorine doctection system Document 0043r 1

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I D. DATA TABULATIONS

- The following data tabulations are presented in this report

A. Operating Data Report i B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions i

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g ATTACHMENT C LTP-300-7

. Revision 3 March 1, 1983 7

OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE April 15. 1984 COMPLETED BY Randy S. Dus TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: March 1984 GROSS HOURS IN REPORTING PERIOD: 744

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):

THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 340.8 1158.5 1158.5

6. REACTOR RESERVE SHUTDOWN HOURS 403.2 992.6 992.6

7. HOURS GENERATOR ON LINE 300.7 1035.6 1035.6

8. UNIT RESERVE SHUTDOWN HOURS 0.0 1.0 1.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 578129 2381801 2381801

10. GROSS ELEC. ENERGY GENERATED (MWH) 182356 759266 759266

11. NET ELEC. ENERGY GENERATED (MWH) 165230 704862 704862

12. REACTOR SERVICE FACTOR 45.8% 53.0% 53.0%

13. REACTOR AVAILABILITY FACTOR 100% 98.5% 98.5%

14. UNIT SERVICE FACTOR 40.4% 47.4% 47.4%

15. UNIT AVAILABILITY FACTOR 40.4% 47.5% 47.5%

16. UNIT CAPACITY FACTOR (USING MDC) 21.4% 31.2% 31.2%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 20.6% 29.9% 29.9%

18. UNIT FORCED OUTAGE RATE 48.8% 46.1% 46.1%

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

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

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 6/21/82 INITIAL ELECTRICITY 9/04/82 COMMERCIAL OPERATION 1/1/84 Document 0043r

Document 0043r LTP-300-7

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6 ATTACHMENT B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: APRIL 15. 1984 COMPLETED BY: RANDY S. DUS TELEPHONE: (815) 357-6761 MONTH March 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 0.0 17. 0.0

2. 0.0 18. 0.0 3 0.0 19. 0.0

4. 0.0 20, 206

5. 0.0 21. 682

6. 0.0 22. 639

7. 70 23, 456

8. 0.0 24. 708

9. 0.0 25. 736

10. 0.0 26. 846

11. 0.0 27. 764

12. 0.0 28, 321

13. 0.0 29. 204

14. 0.0 30. 759 l

15. 0.0 31. 804 l i

16. 0.0 INSTRUCTIONS l On this form list'the average daily unit power level in NWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the not electrical rating of the unit there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line.) In such cases the average daily unit power output sheet should be footnoted to explain.the apparent anomaly.

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LTP-300-7 R;vioica 3

March 1, 1983 9 (Final) -

ATTACHMCNT E UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373 UNIT NAME LaSalle One g DATE April 15. 1984 REPORT MONTH MARCH 1984 COMPLETED BY Randr S. Dus TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN

F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON (1) REDUCING POWER ACTIONS /COletENTS 6 2/13/84 S 156.5 B 4 Condenser Boot Seal and extraction steam expansion joint repaired 7 3/8/84 F 286.7 F 1 Temporary drywell vent-ilation ductwork evaluated for loadinE on containment structural members. Analysis <

0.K. No corrective action taken. Remained shutdown to perform electrical cable butt splices inspection required by NRC.

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E. UNIQUE REPORTING REQUIREMENTS i

1. Main Steam Relief Valve Operations for Unit 1.

There were no relief valve operations for Unit One for this reporting period.

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, 2. ECCS Systems Outtgos

. The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO. EQUIPMENT PURPOSE OF OUTAGE l-227-84 "D" RHR Service Megger Motor Water Pump 1-230-84 1A D/G Lubrication 1-265-84 "C" RHR Service Remove Breaker to Water Pump use on Unit Two.

1-275-84 "A" RHR HX Bypass Inspect Limits and Torques Valve 1-276-84 "A" RHR HX Repair conductivity Cell Valve 1-334-84 HPCS Water Leg Pump Replace

3. Off-Site Dose calculation Manual There were no changes to the Off-Site Dose Calculations Manual during this reporting period.

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4. Radioactive Waste Treatment System There were no changes to the Radioactive Waste Treatment System during this reporting period.

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l LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT MARCH 1984 i

COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 l

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TABLE OF CONTENTS i

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 i

Equipment C. LICENSEE EVENT REPORTS D. DATA TABULATIONS

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions i

E. UNIQUE REPORTINC REQUIREMENTS

1. Main Steam Relief Valve Operations

2. ECCS System Outages

3. Off-Site Dose Calculation Manual Changes 3

4. Majcr Changes to Radioactive Waste Treatment System t

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I II MONTHLY REPORT FOR UNIT TWO ]

A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT TWO MARCH 1-9 The Unit started the reporting period in a shutdown condition. Initial criticality has not yet been achieved MARCH 10 The Unit achieved initial criticality at 0808

! hours on March 10. The reactor was shutdown at 1650 hours0.0191 days 0.458 hours 0.00273 weeks 6.27825e-4 months on March 10 per STP 6.2 Seq. B-2. The reactor was critical for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and 42 minutes. l 1

MARCH 10-25 The reactor went critical at 2027 hours0.0235 days 0.563 hours 0.00335 weeks 7.712735e-4 months on March 10. At 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months on March 10, the reactor was shutdown per STP 6.2, Seq A-2. The reactor was critical I

for I hour and 33 minutes.

MARCH 26-29 The reactor went critical at 0330 hours0.00382 days 0.0917 hours 5.456349e-4 weeks 1.25565e-4 months on March 26. At 1715 hours0.0198 days 0.476 hours 0.00284 weeks 6.525575e-4 months on March 29, the reactor was manually scrammed to repair a leak on the MDRFP discharge piping low point drain. The reactor was critical for 85 hours9.837963e-4 days 0.0236 hours 1.405423e-4 weeks 3.23425e-5 months and 45 minutes.

MARCH 30-31 The reactor went critical at 1925 hours0.0223 days 0.535 hours 0.00318 weeks 7.324625e-4 months on l March 30. The reactor was critical for 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months and 35 minutes.

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B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED i NAINTENANCE.

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1. Amendments to Facility License or Technical Specifications.

Amendment No. 1 - This amendment revised paragraphs 2.c.(1) and 2.c.(15) of operating license No. NPF-18. Paragraph 2.c.(1) authorizes the operation of the Unit at full power level (3323 i

i NWT). Paragraph 2.c.(15) outlines the required changes to be made to the fire protection system to effectively reduce system I

frictional losses.

i. 2. Facility or Procedure Changes Requiring NRC Approval.

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

3. Tests and Experiments Requiring NRC Approval.

There were no tests or experiments requiring NRC approval during l the reporting period, i 4. Corrective Maintenance of Safety Related Equipment.

The following tables present a summary of safety-related maintenance completed on Unit One during the reported period.

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! The headings indicated in this summary include: Work Request Numbers, LER Numbers, Component Name, Cause of Malfunctions, Results and Effects on Safe Operation, and Corrective Action.

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LTP-3OO-7 ATTACHMENT A Rivioics 3 March 1, 1983 CORRECTIVE MAINTENANCE OF 5 SAFETY RELATED EQUIPMENT I I I I I WORK REQUEST LER COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECIS CORRECTIVE ACTION ON SAFE OPERATION I I I I I L33274 SBLC Pump Heat Tracing insulation Solidification at low temps Replaced insulation

- Suction line broken off.

L33855 "B" RHR Outboard bearing damaged Potential pump failure Replaced bearing Service Water Pump L33861 Div. II post Pump failure None. Div. I monitor still Rebuilt pump LOCA sample operable Pump L33988 "B" IRM Defective Detector Causes spikes and half scrams Replaced Detector L34037 Reactor Transmitter Defective Recirc Flow unknown Replaced faulty Recirc Pump circuit board and Flow recalibrated Transmitter L34110 "D" IRM Does not respond correctly Causes upscale spikes Repaired connection from range switch L34158 RHR shutdown Failed local leak rate Potential degradation of Machined seat to cooling test containment integrity remove clearance.

isolation valve L34198 Control wiring Inadequate Butt Splices Potential wire breaks Repair Butt Splices Butt Splices per specification DOCUMENT 0044r

LTP-300-7 ATTACHMENT A (C:nt'd) Ravicica 3

M:rch 1, 1983 CORRECTIVE MAINTENANCE OF 5 -

SAFETY RELATED EQUIPMENT l I I I I WORK REQUEST LER COMPONENT CAUSE OF 18ALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON EAFE OPERATION I I I I I L34263 Inboard feed- Failed local leak rate Potential degradation of Machined hinge pins to water check test containment integrity reduce side clearance valve L34320 RHR "A" water Check valve does not Permits reverse flow thru Removed and cleaned les Pump Disch seat water les pump from RHR seat and disc.

system.

L34554 Suppression Transmitter does not Gives wrong suppression cleaned sensing pool wide respond properly / pool level line and recalibrated range level sensing line clogged transmitter L34706 Mechanical Snubber movement Will prevent piping move- Notched grating to Snubber restricted due to ment on heatup provide clearance.

grating interferance L3',980 "A" VP Fan Breaker keeps tripping Potential high drywell Replaced breaker after 20 minutes. temps, Do m 0044r

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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 Two, occurring during the reporting period, March 1 through March 31, 1984. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in section 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

Licensee Event Report Number Date Title of Occurrence 84-001-00 1/5/84 "E" IRN/ Reactor Scram 84-003-00 2/2/84 Reactor Scram 84-003-00 2/2/84 Failure of ACB 2432 to trip 84-004-00 2/12/84 Div. II PCIS Isolation 84-005-00 2/15/84 HDCS Pump Feeder Breaker 84-006-00 2/23/84 RWCU High AT Isolation 84-007-00 2/18/84 RWCU High 6T Isolation 84-008-00 2/29/84 Croup I Isolation Reset Malfunction 84-009-00 3/8/84 RHR SDC Isolation l

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D. DATA TABULATIONS The following data tabulations are presented in this report:

1. Operating Data Report

2. Average Daily Unit Power Level

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i 3. Unit Shutdowns and Power Reductions '

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,. ATTACHMENT C LTP-300-7

Revision 3 March 1, 1983 7

OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE April 15, 1984 COMPLETED 3Y Randy S. P2s TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: March 1984 GROSS HOURS IN REPORTING PERIOD: 744

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):

THIS MONTH YR TO DATE CUMULATIVE i 5 NUMBER OF HOURS REACTOR WAS CRITICAL 124.5 124.5 124.5 l 6. REACTOR RESERVE SHUTDOWN HOURS 395.3 395.3 395.3

7. HOURS GENERATOR ON LINE 0.0 0.0 0.0

8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 8278 8278 8278

10. GROSS ELEC. ENERGY GENERATED (MWH) 0.0 0.0 0.0

11. NET ELEC. ENERGY GENERATED (MWH) 0.0 0.0 0.0

12. REACTOR SERVICE FACTOR N/A N/A N/A

13. REACTOR AVAILABILITY FACTOR N/A N/A N/A

14. UNIT SERVICE FACTOR N/A N/A N/A

15. UNIT AVAILABILITY FACTOR N/A N/A N/A

16. UNIT CAPACITY FACTOR (USING MDC) N/A N/A N/A

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) N/A N/A N/A

18. UNIT FORCED OUTAGE RATE N/A N/A N/A

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

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

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 3/10/84 4

INITIAL ELECTRICITY April 84 l CONMERCIAL OPERATION Aua. 84

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Docume;t C20@r LTP-300-7

R3visicn 3

March 1, 1983

6 ATTACHMENT B l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: APRIL 15. 1984 COMPLETED BY: RANDY S. DUS TELEPHONE: (815) 357-6761 MONTH March 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (NWe-Net) (NWe-Net)

1. 0.0 17. 0.0

2. 0.0 18. 0.0 3 0.0 19. 0.0

4. 0.0 20. 0.0

5. 0.0 21. 0.0

6. 0.0 22. 0.0

7. 0.0 23. 0.0

8. 0.0 24. 0.0

9. 0.0 25. 0.0

10. 0.0 26. 0.0

11. 0.0 27. 0.0

12. 0.0 28. 0.0

13. 0.0 29. 0.0

14. 0.0 30. 0.0

15. 0.0 31. 0.0

16. 0.0 l

INSTRUCTIONS l On this form list the average daily unit power level in MWe-Net for each day j in the reporting month. Compute to the nearest whole megawatt. l These figures will be used to plot a graph for each reporting month. Note l that when maximum dependable capacity is used for the not electrical rating of l the unit there may be occasions when the daily average power level exceeds the ;

I 100% line (or the restricted power level line.) In such cases the average daily unit power output sheet should be footnoted to explain the apparent anortly.

Document 0043r f

e LTP-300-7

Revision 3.

March 1, 1983 9 (Final)-

ATTACHMENT E UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-374 UNIT NAME LaSalle Two DATE April 15. 1984 REPORT MONTH MARCH 1984 COMPLETED BY Randy S. Dus CONTINUED TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON (1) REDUCINC POWER ACTIONS / COMMENTS NOME a-DOCUMENT 0044r

o 5

E. UNIQUE REPORTING REQUIREMENTS i

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1. Main Steam Relief Valve Operations for Unit 2.

Relief valve operations during the reporting period are summarized in the following Table. The table included information as to which relief valve was actuated, how it was activated and the circumstances resulting in its actuation.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATIONS CONDITTON OF EVENT 3/27/84 2B21-F013A 1 Manual 250 PSIG STP-26 3/27/84 2821-F0138 1 Manual 250 PSIC STP-26 3/27/84 2B21-F013C 8 Manual 250 PSIC STP-26 3/27/84 2B21-F013D 8 Manual 250 PSIG STP-26 3/27/84 2B21-F013E 8 Manual 250 PSIG STP-26 3/27/84 2B21-F013F 1 Manual 250 PFT' STP-26 3/27/84 2821-F013G 1 Manual 250 P' 'P-26 3/27/84 2B21-F013H 2 Manual 250 1 P-26 3/27/84 2B21-F013J 1 Manual 250 P1 -26 3/27/84 2821-F013K 3 Manual 250 P1 -lh5 3/27/84 2821-F013L 1 Manual 250 P' I

3/27/84 2B21-F013M 2 Manual 250 F 3/27/84 2B21-F013N 1 Manual 250 T 3/27/84 2B21-F013P 3 Manual 250 1. L A. 5 3/27/84 2B21-F013R 8 Manual 250 PSIL STF 6 l 3/27/84 2B21-F013S 8 Manual 250 PSIG STP-26 3/27/84 2B21-F013U 8 Manual 250 PSIG STP-26 3/27/84 2B21-F013V 13 Manual 250 PSIG STP-26 Document 0043r

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2. ECCS Systets Outcgos The following outages were taken on ECCS Systems during 1 the reporting period.

OUTAGE NO. EQUIPMENT PURPOSE OF OUTAGE 2-357-84 "C" RHR Service Test Overload Water Pump i

2-359-84 2A D/G Lubrication 2-364-84 A RHR Service Bearing Repair Water Pump 2-365-84 8 RHR Service Bearing / Shaft Water Pump Inspection 2-368-84 HPCS D/G and Inspect AC/DC Bus Bus 243 2-387-84 "C" & "D" RHR LES-GN-120 Service Water Pump 2-429-84 "A" RHR Water Leg Repair Valve Fill Valve a 2-465-84 RHR Service Repair Strainer Water Strainer 2-468-84 "B" RHR Service Lubrication Water Pump

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

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4. Radioactive Waste Treatment System l l

There were no changes to the Radioactive Weste Treatment System during this reporting period. j Document 0043r

Comm:nwccith Edissn LaSalle County Nuclear Station RuralRoute #1, Box 220 Marseilles, Illinois d1341 Telephone 815/357-6761 l

April 15, 1984 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 covering March 1 through March 31, 1984.

Very truly yours, I

i

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, C J. Diederich

x Superintendent

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LaSalle County Station i

GJD/RSD/bej

. - -Eaclosure-

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xt: J. G. Keppler, FRC, Region III j NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety

~

D. P. Galle, Ceco

D. L. Farrar CECO i INp0 Records Center l Ron A. Johnson, PIP Coordinator SNED i W. R. Jackson, GE Resident

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SUMMARY

SUMMARY

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