Text

Monthly Operating Repts for Oct 1984
	ML20100N128
Person / Time
Site:	LaSalle
Issue date:	10/31/1984
From:	Diederich G, Dus R; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM)
References
	NUDOCS 8412120587
	Download: ML20100N128 (30)
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l LASALLE NUCLEAR POWER STATION l

t UNIT 1 i

MONTHLY PERPORMANCE REPORT OCTOBER 1984 COfMONWEALTH EDISON COMPANY l

NRC DOCKET NO. 050-373 l' LICENSE NO. NPF-ll l

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PDR ADDCK 05000373 R PDR M2.f Document 0043r/0005r /

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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 Comunonwealth 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-ll, issued on April 17, 1982. The date of initial criticality was June 21, 1982. Unit Two is subject to license number NPF-18, issued on December 16, 1983. The date of initial criticality was March 10, 1984.

This report was compiled by Randy S. Dus telephone number (815)357-6761, extension 324.

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s TABLE OF CONTENTS I. INTRODUCTION II. MONTHLY REPORT POR UNIT ONE A. Suussary 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 j 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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s II. MONTHLY REPORT FOR UNIT ONE A. SUltuutY OF OPERATING EXPERIENCE FOR UNIT ONE OCTOBER 1-31 The Unit was shutdown for the entire inonth of October.

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

1. Amendments to facility license or Technical Specification.

There were no facility license or Technical Specification Amendments during the reporting period.

2. Facility or procedure changes requiring NRC approval.

There were no facility or procedure changes requiring NRC approval.

3. Tests and Experiments requiring NRC approval.

There were no tests or experiments requiring NRC approval.

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: Nork Request numbers, LER numbers, Component Name,

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l Cause of Malfunction, Results and Effects on Safe Operation, and l

l Corrective. Action.

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, TABLE 1 ,

CORRECTIVE MRINTENANCE OF

SAFETY.RELATED EQUIPMENT ',

i I I I I I I WORK REQUEST LER COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION See Section ON SAFE OPERATION I II.C. l l l l lL27305 RHR "C" Pump High pump vibrations. None: Pump still operational Replaced original pump 1 which could cause pump shaft & column with damage. modified shaft.

i L34618 VE Isolation Damper continuously auto Inadequate ventilation in Removed damper i damper to unit closes. Aux. Elec. Equip. Room. actuator, sent out two for repair and

! reinstalled.

i L3'7048 VC Ventilation Damper drifts closed Redundant train still Damper actuator Damper when"A" train is running available defective, sent out for repair.and j reinstalled 4 L40465 HPCS Suction Pressure gauge indicating Adequate suction pressure Recalibrated 1 4

Pressure gauge zero pressure at pump verified to be present via pressure gauge.

i suction. water leg pump discharge pressure gauge.

1 L40661 Drywell Provide support for Routine check for heat S & L inspection

! wiring drywell cable and . related degradation. team assisted by equipment inspection. CECO personnel j as required.

} L41921 Fuel Pool Valve has packing leak Subject drain valve is not Replaced and

{ drain valve which affects outcome a containment boundary. tightened packing.

of local leak rate tests.

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' L42083 APRM B Top row of APRM B down- Redundant channels still Changed out blown scale lights not lit. available. fuse.

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TABLE 1 , .,

CORRECTIVE MAINTENANCE OF

[ SAFETY RELATED EQUIPMENT

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WORK REQUEST LER' COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION.

, ON SAFE OPERATION I I I I I

~ L42159 Inboard Feed Subject check valve Potential loss of cont- Corrected bushing water check failed LLRT. Due.to containment integrity. alignment and per-4 valve. misalligned bushing ,

formed LLRT.

j wedging disc off seat.

'. L42228 Diesel Fire Specific gravities are Low battery charge affecting Charged batteries. I

, pump bat- low for pilot cells. start capabilities. for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ..

teries.

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' L42448 RHR SW PRM "A" Loop PRM has con- Rad Chem samples show no Disassembled PRM,'

l- tinuous Hi-Rad signal contamination present in cleaned and recal-above alarm setpoint. service water. ^

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L42930 Rx Water Variable leg has leaking Temporary loss of shutdown Replaced segment Level Instru- fitting, range. of tubing and conn-

. ment.line. ectors.

L40210 I.S.H.I. Welds Determine location of Required for 1985 I.H.S.I. Walked down RF and i . welds for hanger re- Inservice inspection. RH welds. Checklist moval and inspection gener'ated.

j L42048 Shutdown Unable to open valve Established alternate Repaired valve i cooling following unit shutdown, shutdown cooling mode. operator.

l. Isolation

! Valve i ,

! L421"l6 Outboard Valve Failed local Potential loss of primary Repaired valve 1 feedwater -Leak rate test. containment integrity. and retested.

I ' check valve.

1 L42999 RHR Heat Valve needs limit' switch Valve difficult to open. Adjusted limit exchanger adjustment. switch so that valve 1

outlet will not torque

-valve. closed.

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C. . LICENSEE EVENT REPORTS The following is a tabular susunary of all licensee event reports for i LaSalle Nuclear Power Station, Unit One, occurring during the reporting period, October 1 through october 31, 1984. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.~13.

Licensee Event Report Number Date Title of Occurrence 84-052-00 9/27/84 RWCU High Pump Room Differential Temperature Isolation.

84-053-00 9/16/84 RWCU High Differential Flow Isolation.

84-054-00 9/21/84 Reactor Core Isolation Cooling Isolation.

t 1 84-055-00 9/21/84 Reactor Water Cleanup Isolation.

84-056-00 9/21/84 Rx Scram on Group I Isolation While Performing LIS-MS-01.

4 84-057-00 10/1/84 Group I Isolation.

84-058-00 10/1/84 Start of VC/VE Emergency Makeup Train.

84-059-00 10/2/84 HPCS Discharge Relief Valve Bellows Seal Failure.

l 84-060-00 9/29/84 RCIC Steam Line High

. Differential Pressure

, Isolation.

{ 84-061-00 10/1/84 LLRT of MSIV's Exceeding 100 SCFH.

84-062-00 9/30/84 Loss of Shutdown Cooling Due to 1E12-F009 Valve Failure.

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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

3. Unit Shutdowns and Power Reductions

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1. OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE November 7, 1984 COMPLETED BY Randy S. Dus TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: October 1984 GROSS HOURS IN REPORTING PERIOD: 745

2. CURRENTLY AUTHORIEED 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 dAS CRITICAL 0.0 5377 5377

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 1165 1165

7. HOURS GENERATOR ON LINE 0.0 5194 5194

8. UNIT RESERVE SHUTDOWN HOURS 0.0 1.0 1.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 0.0 14581709 14581709

10. GROSS ELEC. ENERGY GENERATED (MWH) 0.0 4739789 4739789

11. NET ELEC. ENERGY GENERATED (MWH) 0.0 4512808 4512808

12. REACTOR SERVICE FACTOR 0.0 73.5% 73.5%

13. REACTOR AVAILABILITY FACTOR 0.0 89.4% 89.4%

j 14. UNIT SERVICE FACTOR 0.0 71.0% 71.0%

15. UNIT AVAILABILITY FACTOR 0.0 71.0% 71.0%

16. UNIT CAPACITY FACTOR (USING MDC) 0.0 59.5% 59.5%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 0.0 57.2% 57.2%

18. UNIT FORCED OUTAGE RATE 0.0 17.1% 17.1%

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

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: November 21, 1984

, 21. UNITS IN TEST STATUS (PRIOR TO COf9EERCIAL OPERATION):

( FORECAST ACHIEVED f

INITIAL CRITICALITY 6/21/82 INITIAL ELECTRICITY 9/04/82 COfWlERCIAL OPERATION 1/1/84 l

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2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: .LASALLE ONE.

DATE: N ER 7, 1984 OOMPLETED BY: Randy S. Dus TELEPHONE: (815) 357-6761 -

' MONTH: OCTCBER, 1984 I

DAY AVERAGE DAILY POWER LEVEL PAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) i .

1. 0 17. 0 .

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2. 0 18. 0 3 0 19. 0 >

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4. 0 '20. 0 3

5. 0 21.s 0

6. 0 22. 0 7.- 0 23. 0

8. O 24. 4 0

9. 0 25. 0 >

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12, 28. 0

13. _. _. 29. 0

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3. UNIT SHOTDOWNS AND pf5fgR REDUCTIONS f DOCKET NO. 050-374 .

UNIT WAME LaSa11e One DATE Novesaber 1984 REPORT MONTH OCTOBER 1984 COMPLETED BY Randy S. Dus a- _

TELEPHONE (815)357-6761-

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SHUTTING DOWN

" F: FORCED DURATION -' THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS /COfftIDITS 20 84/09/29 S , . .

744 H 4 Continuation of outage which started on September 29.

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E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations for Unit One.

4 VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION _ CCNDITION OF EVENT There were no relief valve actuations during the month of October.

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2. ECCS Systems Outcge2 The following outages were-taken on ECCS Systems during the reporting period.

OUTAGE NO. EQUIPMENT PURPOSE OF' OUTAGE

.1-764-84 IB HPCS D/G Recalibrate Instrumentation 1-775-84 IB HPCS D/G Oil & Filter Change 1-789-84 HPCS Water Leg Pump Lubrication 1-790-84 HPCS Pump Discharge Relief Valve Replacement.

1-847-84 HPCS Pump & IB D/G Equipment Protection for LES-HP-02 1-873-84 "C" RHR Pump Piping Strut $ Inoperable 1-887-84 lE12-F094 Valve cable splice Repair 1-891-84 1B HPCS D/G Circuit Breaker Inspection 1-898-84 HPCS Water Leg Pump Lubrication 1-900-84 HPCS D/G Cooling Water Lubrication Pump 1-924-84 LPCS Pump Equipment Protection for LES-LP 1-952-84 IB D/G Reenergize Bus 143 1-1029-84 1A D/G Recalibrate Instrumentation i

1-1036-84 RHR SW Ptump Lubrication 1-1069-84 LPCI Testable Check Disassemble and repair valve 1-1121-84 HPCS Pump Discharge Relief Valve

3. Off-Site Dose Calculation Manual

!- / There were no changes to the off-site dose calculations manual during this reporting period.

4. Radioactive Waste Treatment Systems.

Attached is a synopsis of the change that was made to the Radioactive waste treatment system during the month of October.

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-I october 15, 1984 l

l During the last few months, there have been many operational difficulties j associated with the Stock Equipment System used to solidify Radweste. Now that most of the difficulties have been resolved, radweste solidification is j proceeding in a timely manner. However, during the interim, a significant backlog of radwaste needing solidification has a.ccumulated. This inventory l hinders efficient operation of the radweste system as a whole- i.e. limited available tank space, carryover in concentrators, and higher than desired tank dose rates.

In addition, new federal legislation on radweste compacts goes into effect January 1, 1986. At that time, it may not be possible to send solidified waste to our present burial sites. Consequently, Commonwealth Edison has elected to be at zero inventory (empty tanks and no solidified barrels in storage on site) by January 1, 1986.

For the above reasons, it has been decided to employ NUS Process Services Corporation to solidify the contents of the lA and IB Phase Seperator Tanks, and the Waste Sludge Tank. The solidification and subsequent transportation of waste off-site is expected to begin October 22, 1984. Startup will require.

approximately two weeks, solidification / transportation will take six weeks, based on 3 weekly shipments and tear down will take one week.

PURPOSE i

Our Stock System will have to be modified to allow interface with the Contractors equipment. These changes, although temporary, constitute major 1 changes to the radwaste system, and need review per Technical Specification .

6.9.1.

As the contractor will be using his own equipment, personnel, and procedures to perform the solidification, Technical Specification 4.11.3.1.b requires the solidification be performed in accordance with a Process' Control Program to ensure the requirements of 10CFR61 are met. Technical Specification 6.7.1. requires approval by on-site review prior to the implementation at these procedures.

MODIFICATION DETAILS All equipment is to be maintained within the Radweste Truck Bay, with the exception of the cement truck, which will remain outside the Truck Bay. The initial solidification, mixing, curing, and inspection will take place in the Truck Bay, under Health Physics supervision. At that time, Health Physics personnel will determine, based upon area dose rates, and any airborne considerations, whether subsequent curing may proceed.in a lined truck outside the Truck Bay. Entry level status of the Truck Bay will be upgraded at the discretion of the Health Physics personnel.

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l An intsrfEc3 to the existing drum procscaing unit will be needed to cupply waste to the Contractor's equipment. Flanges on the existing transfer lines will be broken, and a manual valve with a Chicago fitting will be flanged in line. The vendor's supply hose will be attached to the Chicago fitting.

! An interface to our ventilation system may be needed to handle equipment off-gas. A hose, with a HEPA filter attached, will be vented to the Truck Bay ventilation system.

An air supply, uncontaminated water supply, and electrical hookup are presently available in the Truck bay.

No liquid or gaseous radioactive material releases are expected. During the 1st solidification, samples will be drawn at the outlet of the 1$ner vent i HEPA filter to determine if any net release of radioactive material occurs, and if so, its extent. If there is any radioactive material measurable at the HEPA outlet, all subsequent solidifications will route the IEEPA outlet directly to the Radwaste ventilation system - resulting in no release.

Increased exposures to individuals in the unrestricted area and to the general population are not expected. If curing does take place outdoors, dose rates at the boundary to the unrestricted area will be measured at this time to determine if any excess exposure to individuals at the boundary would occur Mone is expected.

An estimate of exposure to plant operating personnel as a result of the change will be performed by Rad / Chem personnel as standard procedure.

Exposure will be estimated based on expected man-hours required for the flange modifications times measured dose rates observed prior to the modification.

Two days prior to the solidification, test solidifications will be performed by NUS. These tests will verify proper solidification of our waste at the chemical / cement concentrations prescribed in their Process Control

i Procedures. After a thorough recirculation of the-tanks to mix the contents, one solidification of each of the phase seperators will be performed. Between three and five solidifications will be performed on the waste sludge tank, approximately one per week.

This document, the contractor procedures, and the 10CFR50.59 safety evaluation are being routed through onsite review prior to the commencement of the solidification, and will be included in the Semiannual Radioactive Effluent' Release Report as detailed in Technical Specification 6."T.2, and.in ths NRC Monthly Operating Report as detailed in Technical Specifical 6.9.1.a.

Both the reports require evidence that an on-site review of the changes was made.

Any comments or questions involving the above propos31 should be addressed to JoAnn Shields, x330.

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LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT OCTOBER 1984 COletONWEALTH EDISON COMPANY NRC DOCKE1 NO. 050-374 LICENSE NO. NPF-18 i

DOCUMENT ID 0036r/0005r

o TABLE OF CONTENTS I. INTRODUCTION II. MONTHLY REPORT FOR UNIT TWO A. Sununary 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. Safety / Relief Valve Operations

2. ECCS System Outages

3. Off-Site Dose Calculation Manual Changes

4. Maj< '- Changes to Radioactive Waste Treatment System DOCUMENT ID 0036r/0005r

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 comanonwealth Edison Cosspany. The Architect / Engineer was Sargent & Lundy, and the primary construction contractor was cousnonwealth Edison Company.

The condenser cooling method is a closed cycle celing pond. Unit One is subject to License Number NPF-ll, issued on April l~l, 1982. The unit commenced cosamercial generation of power on January 1, 1984. Unit Two is subject to license number NPF-18, issued on December 16, 1983. The date of initial criticality was March 10, 1984.

This report was compiled by Randy S. Dus, telephone number (815)357-6761, extension 324.

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II. MONTHLY REPORT POR UNIT TWO A. SUlWEARY OF OPERATING EXPERIENCE FOR UNIT TWO october 1-27 The Unit started the reporting period at 87% power. At .I 2038 hours0.0236 days 0.566 hours 0.00337 weeks 7.75459e-4 months on October 4, power was reduced to 60% due to r heater drain flow oscillations. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on October 6, reactor power was raised to 86%. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on October 7, reactor power was raised to 98%. At

- 0450 hours0.00521 days 0.125 hours 7.440476e-4 weeks 1.71225e-4 months on October 27, the reactor scrammed on an APRM Hi-Hi actuation caused by the reactor tecirc flow control valves. The reactor was critical for 628 hours0.00727 days 0.174 hours 0.00104 weeks 2.38954e-4 months and 50 minutes.

October 28-31 The reactor went critical at 1947 hours0.0225 days 0.541 hours 0.00322 weeks 7.408335e-4 months on October 28.

At 0103 hours0.00119 days 0.0286 hours 1.703042e-4 weeks 3.91915e-5 months on October 29, the main 9enerater was synchronized to the grid. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on October 29, reactor power was raised to 48%. At 1433 hours0.0166 days 0.398 hours 0.00237 weeks 5.452565e-4 months on October 29, reactor power was raised to 72%. At 0000 hours0 days 0 hours 0 weeks 0 months on October 31, reactor power was raised to 85%.

The reactor was critical for 76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months and 13 minutes.

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': s B. PLANT OR PLOCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.

1. Amendments to facility license or Technical Specifications.

There were no amendments to the facility license or Technical Specification during the reporting period.

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.

i 4. Cctrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a summary of i

( safety-related maintenance completed on Unit One during the reporting period. The headings indicated in this summary include: Work Request numbers, LER Numbers, Component Name, l

cause of malfunction, results and effects on safe operation, and i

[ corrective action.

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TABLE 1 P CORRECTIVE MAINTENANCE OF ..

SAFETY RELATED BQUIPMENT I I I i I WORK, REQUEST LER COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION '

.See Section 04 SAFE OPERATION l II.C. I l l l L38906 RCIC Drain Light indication shows Valve locally vesit;.ed to Readjusted limit switch stop valve valve to be partially cycle properly and fully acturor arm.

open with C/S in closed closed with C/S in closed

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position. position.

L41991 CRD Low header Low charging header Still provides trip but not Recalibrated trip set-pressure scram pressure setpoint not at required setpoint, point to Tech-Spec.

at required value. value.

L42334 HPCS Water Leg Pump Discharge gauge HPCS piping locally verified Recalibrated pump pump indicating 100 psig. to be filled and pressurized discharge gauge.

pressure gage L42489 _

ADS "S" ac- Low pressure alarm up for Locally verified N2 Recalibrated pressure ciuuulator ADS "S" accumulator. pressure adequate and all switch, pressure other accumulator pressures switch. adequate L42850 2A' Diesel Air start motors have Preventative maintenance Air Start motors generator _45 starts on them. measure to assure adequate replaced.

Should be replaced. start capabilities.

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4 C. -LICENSEE EVENT REPORTS The following is a tabular stannary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, occurring during the reporting period, October 1 through October 31, 1984. 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 84-063-00 9/1/84 RCIC Hanually Isolated for Inop LD PCIS switch.

84-064-00 9/7/84 RWCU High Differential Flow Isolation.

84-065-00 9/24/84 .RWCU High Ambient Temperature Isolations.

84-066-00 9/27/84 RWCU High Differential Flow Isolation.

84-067-00 9/27/84 RWCU Pump Room Differential I

Temperature Isolation.

84-068-00 9/6/81 HPCS System Inoperable.

84-069-00 9/12/84 Group I Isolation on Low Condenser vacuum.

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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 h

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1. OPERATING DATA REPORT DOCKET NO. 050-3*14 i UNIT LaSalle Two DATE November 10. 1984 COMPLETED BY Randy S. Dus TELEPHONE (815)357-6761 OPERATING STATUS 4

1.. REPORTING PERIOD: October 1984 GROSS I:OURS IN REPORTING PERIOD: 745

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3323 MAX DEPEND CAPACITY

. (IGde-Net) : 1036 DESIGN ELECTRICAL RATING (Infe-Net):1078

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (IGfe-Net): N/A

4. REASONS FOR RESTRICTION (IF ANY):

, THIS MONTH YR TO DATE CUMULATIVE

' 5 NUMBER OF HOURS REACTOR WAS CRITICAL ~105.1 273.0* 273.0*

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

l. 7. HOURS GENERATOR ON LINE 699.8 267.7 267.~1

8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 2184610 817298 817298

10. GROSS ELEC. ENERGY GENERATED (MWH) 723745 2'103~13 270373

11. NET ELEC. ENERGY GENERATED (MWH) ~101050 222697 222697 i 12. REACTOR SERVICE FACTOR 94.6% 87.5% 87.%

l '

13. REACTOR AVAILABILITY FACTOR 94.6% 87.% 87.5%

14. UNIT SERVICE FACTOR 93.9% 85.8% 85.8%

15. UNIT AVAILABILITY FACTOR 93.9% _ 85.8% 85.8%

16. UNIT CAPACITY FACTOR (USING MDC) 90.8% 68.9% 68.9%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 87.3% 66.2% 66.2%

18. UNIT FORCED OUTAGE RATE 6.1% 14.5% 14.%

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

There is an outage scheduled to begin on March 1, 1985 for maintenance l and surveillances. This outage is expected to last approximately four l weeks.

!

Unit two was placed in commercial operation on October 19, 1984.

Year-To-Date and cumulative totals are based on operating data starting October 19, 1984.

l 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A l 21. UNITS IN TEST STATUS (PRIOR TO COltlERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 3/10/84

! INITIAL ELECTRICITY 4/20/84 COltlERCIAL OPERATION 10/19/84 l

l 1

l DOCUlGINT ID 0036r/0005r L- ._ _ _ , _ . . _ _ .._,. . _ _ , _ . . _ , , _ _ . . _ _ . . _ . _ _ _ . _ _ _ _ _ _ _ _

.o c

2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: November 10, 1984 COMPLETED BY: Randy S. Dus TELEPHONE: (815) 357-6761 MONTH: October 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 1024 17. 1042

2. 1035 18. 1042 3 1041 19. 1065*

4. 1024 20. 1067

5. 749 21. 1067

6. 937 22. 1067

7. 1053 23. 1069

8. 1017 24. 1072

9. 1055 25. 1069

10. 1058 26. 1070

11. 1051 27. 202

12. 1049 28. 0

13. 1044 29. 548

14. 1046 30. 792

15. 1040 31. 832

16. 1000

October 19, 1984 marks the first date of commercial service.

DOCUMENT ID 0036r/0005r

ATTAQ94ENT R I.

3. UNIT SHUTDOWNS AND POWER REDUCTIONS

~

DOCKET NO. 050-374 UNIT NAME LaSalle Two DATE November 1984 REPORT MONTH OCTOBER 1984 COMPLETED BY Randy S. Dus TELEPHONE (815)357-6761 s

METHOD OF TYPE SHUTTING DOWN F: PORCED DURATION THE REACTOR OR CORRECTIVE

.NO. DATE S: SCHEDULED (HOURS) REASON (1) REDUCING POWER ACTIONS /COlWEENTS 33 841004 F 0.0 A 5 Power reduction due to

-heater drain flow oscillations.

1 *841027 F 45.2 A 3 Reactor scram on APRM Hi-Hi actuation caused by the-reactor'recirc flow control.

OCTOBER 19, 1984 MARKS THE FIRST DATE OF COlWEERCIAL OPERATION.

DOCUpmMT 0044r/0005r

O E. UNIQUE REPORTING REQUIREMENTS e

4 s

1. Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT THERE WERE NO SAFETY R:: LIEF VALVE ACTIVATIONS DURING THE MONTH OF OCTOBER.

1 i

l DOCUMENT ID 0036r/0005r

jo 67

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

OUTAGE NO. ROUIPMENT PURPOSE OF OUTAGE 2-1174-84 HPCS Pump Discharge Relief Valve 2-1177-84 HPCS Pump Discharge Relief Valve 2-1180-84 RHR Shutdown Cooling Instrument surveillance 2-1191-84 RHR Heat Exchanger Set limit switches

. Outlet valve 2-1200-84 2A D/G Replace air start motor 2-1204-84 2B D/G Air Replace temperature switch compressor

3. Off-Site Dose Calculation Manual There were no changes to the off-site dose calculations manual during this reporting period.

4. Radioactive Waste Treatment dystems.

4 See report for Unit One for changes to radioactive waste traatment system.

4 DOCUMENT ID 0036r/0005r

_ . _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ . . _ . _ _ _ _ _ _ .__._..____ _.. -.~ _. _ _ _, _ .-,_ _ _ . _ . . _ _ _ _ , . _ . . _ _ _ . _ _ . _ _

t k F (I Commonwealth Edison LaS;lla County Nucle:r St; tion Rural Route #1, Box 220 Marseilles, Illinois 61341 Telephone 815/357-6761 November ~7, 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 October 1 through Octobcr 31, 1984.

Very truly yours, t

G J. Diederich Superintendent LaSalle County Station GJD/RSD/crh Enclosure xc: J. G. Keppler, NRC, Region III IIRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center Ron A. Johnson, PIP Coordinator SNED W. R. Jackson, GE Resident J. M. Nowicki, Asst. Comptroller Document 0043r/0005r

ML20100N128

Text

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