Text

Monthly Operating Rept for Feb 1984
	ML20087E745
Person / Time
Site:	LaSalle
Issue date:	02/29/1984
From:	Diederich G, Lin D; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8403160261
	Download: ML20087E745 (16)
	v • d • e

. __ . _ _ . - - ._. - _ . ._ _. _ _ _ __ __ __

I 1

i l

LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT FEBRUARY 1984 COMMONWEALTH EDISON COMPANY 1

NRC DOCKET NO. 050-373 '

LICENSE NO. NPF-11 8403160261 840229 PDR ADOCK 05000373 R pg i

Document 0043r i

TABLE OF CONTENTS

1. INTRODUCTION II.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A, Amendments to Facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NRC Approval D. Corrective Maintenance of Safety Related Equipment IV. LICENSEE EVENT REPORTS V. DATA TABULATIONS A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions VI. UNIQUE REPORTING REQUIREMENTS A. Main Steam Relief Valve Operations E. ECCS System Outages C. Off-Site Dose Calculation Manual Changes D. Major Changes to Radioactive Waste Treatment System 1

Document 0043r

- - . , .- ~

I. INTRODUCTION The LaSalle Nuclear Power Station Unit One is a Boiling Water Reactor with a designed electrical i output of 1078 MWe net, located in Marseilles, 1

Illinois. The Station is owned by commonwealth Edison l

l Company. The Architect / Engineer was Sargent & Lundy, 1

I and the primary construction contractor was l

l Commonwealth Edison Company.

l l

l The condenser cooling method is a closed cycle cooling pond. The plant is subject to License Number NPF-11, issued on Apell 17, 1982. The date of initial criticality was June 21, 1932. Ths unit commenced commercial generation of power on January 1, 1984.

This report was complied by Diane L. Lin, telephone number (815)357-6761, extension 499.

Document 0043r

)

II.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE FEBRUARY 1-3 The unit started the reporting period at approximatley 87% power. On February 3 at 1345 hours0.0156 days 0.374 hours 0.00222 weeks 5.117725e-4 months the reactor scrammed due to an inadvertent initiation of RCIC during the performance of LIS-NB-04, Reactor Vessel Low Low Water Level RCIC Initiation, Low-Low-Low Water Level LPCS/RHR Initiation, and ADS Permissive Calibration and Functional Test. The reactor was critical for 61 hours7.060185e-4 days 0.0169 hours 1.008598e-4 weeks 2.32105e-5 months and 45 minutes.

FEBRUARY 4-29 The reactor went critical at 0450 hours0.00521 days 0.125 hours 7.440476e-4 weeks 1.71225e-4 months on February 4. At 1108 hours0.0128 days 0.308 hours 0.00183 weeks 4.21594e-4 months on February 4 the main generator was synchronized to the grid and loaded. At 1145 hours0.0133 days 0.318 hours 0.00189 weeks 4.356725e-4 months on February 4 reactor power was 25%. At 0740

, hours on February 5 reactor power was 66%. At 0645

! hours on February 9 reactor power was 86%. On February l 13 at 0044 hours5.092593e-4 days 0.0122 hours 7.275132e-5 weeks 1.6742e-5 months the reactor scrammed due to the 'A' 1

condenser boot seal which failed and subsequent loss of

}

condenser vacuum. The reactor was critical for 211

} hours and 54 minutes.

l 1

)

I i

i i

1 i

a 5

Document 0043r

I .

III. PLANT OR PROCEDURE CHANCES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.

A. Amendments to Facility License or Technical Specifications.

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

B. Facility or Procedure Changes Requiring NRC Approval.

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

C. Tests and Experiments Requiring NRC Approval.

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

D. Corrective Maintenance of Safety Related Equipment.

The following tables present a summary of safety-related 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, Results and Effects on Safe Operation, and Corrective Action.

.r.,

LTP-3OO-7 ATTACHMENT A Favinica 3 M rch 1, 1983 CORRECTIVE MAINTENANCE OF 5 SAFETY RELATED EQUIPMENT

~

l I i i I WORK REQUEST LER COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION I I I I I L25546 Valve Open limitswitch not Open indicating light Set open limitswitch 1B33-F340A making does not work ,

L29956 'C' RHR Full Bad packing Valve was leaking Repacked valve.

Flow Test to Suppression Pool Valve.

L3213D Ccaputer Room Indicator hanging from Upscale indication " pegged Placed indicator Temperature wires, high." back in panel.

Indicator L32201 'B' IR*f Bad drive motor, IRM will not withdraw. Replaced drive motor, flexible shaft and flexible shaft and gear box. gear box.

L32529 Standby Gas Bad pump diaphragm Skid leaks. Replaced pump Treatment diaphragm.

WRGM Detection Skid.

L32559~ 'S' ADS Valve Switch out-of-calibration Hathaway alarm is up, ESF Recalibrated switch.

Accumulator alcra is not up.

Low Pressure Switch.

DOCUMENT 0044r

LTP-300-7 ATTACHMENT A C st'd Rsvisies 3 March 1, 1983 CORRECTIVE MAINTENANCE OF 5 SAFETY RELATED EQUIPMENT I I 1 I I CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION WitK REQUEST LER COMPONENT ON SAFE OPERATION I I I I I L32624 ,LPCI 'A' Pump Pressure indicator cause reads 23 psis, should Rezeroed pressure Suction Pres- out-of-adjustment, read v10psig. Indicator.

sure Gauge.

Recorder sticks on point 4. Olled pivot.

L32661 Recorder ITR Pivot on alarm switch

-CMO38 mechanism was. impeding movement.

Suppression Out-of-calibration A and B channel read Performed calibration L32741 differently.

Pool Water RTD HPCS Water Out-of-calibration Gauge reads high Recalibrated gauge.

L32783 Leg Suction ,

Gauge.

Gauge reads 08 should be Recalibrated gauge.

L32784 .HPCS Suction Out-of-calibration Low Pressure 15-25#

Gauge.

'L33091 Scram ~ Limit switch out-of- Dual indication when valve Adjusted limit switch

. Isolation adjustment is closed.

Drain Valve.

DOCUMENT 0044r i

LTP-300-7 ATTACHMENT A (CONT'D) R;v:sica 3 CORRECTIVE MAINTENANCE OF March 1, 1983 SAFETY RELATED EQUIPMENT 5 I I I I I WRK REQUEST LER COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION I l l l I L33197 Valve Bad torque switch Valve would not open Replaced torque switch.

1832-FOO? automatically.

L33250 RHR 'B' - - Contact screw on torque Valve indicates full closed Tightened contact Testable check switch loose out can be manually closed screw.

bypass valve further.

L33235 'ALPCI Limit switch not made Limit switch doesn't pick Adjusted limit switch Testable check in the closed position. up when valve is full Valve, closed.

L33256 'C' LPCI Bad air cylinder Air cylinder is blowing air. Replaced air

. Testable cylinder.

Check Valve.

e DO N 0044r

IV. LIC3NSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Lisalle Nuclear Power Station, Unit One, occurring during the reporting period, February 1 through February 29, 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.

1 Licensee Event Report Number Date Title of Occurrence 84-002-00 1/6/84 Loss Feed Pump Causing Scram j 84-003-00 1/13/84 Reactor Scram-Main Generator Trip.

84-004-00 1/18/84 Secondary Containment Isolation 84-005-00 1/16/84 Scram 84-006-00 1/21/84 B&F APRM's Reading Non-conservative.

84-007-00 2/3/84 Unit 1 Reactor Scram.

Document 0043r

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

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

l i

l l

l I

Document 0043r I

ATTACHMENT C LTP-300-7 Revision 3 March 1, 1983 7

OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE March 9. 1984 COMPLETED BY Diane L. Lin TELEPHONE 1815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: February 1984 GROSS HOURS IN REPORTING PERIOD: 696

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):100% MAX DEPEND CAPACITY (NWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net):1078

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):

4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 273.7 817.7 817.7

6. REACTOR RESERVE SHUTDOWN HOURS 407.3 589.4 589.4

7. HOURS GENERATOR ON LINE 267.4 734.9 734.9

8. UNIT RESERVE SHUTDOWN HOURS 0 1.0 1.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 7040020 1803672 1803672

10. GROSS ELEC. ENERGY GENERATED (MWH) 229288 576910 576910

11. NET ELEC. ENERGY GENERATED (MWH) 211758 539632 539632

12. REACTOR SERVICE FACTOR 39.3% 56.8% 56.8%

13. REACTOR AVAILABILITY FACTOR 97.8% 97.7% 97.7%

14. UNIT SERVICE FACTOR 38.4% 51.0% 51.0%

15. UNIT AVAILABILITY FACTOR 38.4% 51.1% 51.1%

16. UNIT CAPACITY FACTOR (USING MDC) 29.4% 36.7% 36.7%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 28.2% 34.8% '34.8%

18. UNIT FORCED OUTAGE RATE 61.6% 44.8% 44.8%

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:3/6/84

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 I

i

. LTP-300-7 Rsvisica 3 M:rch 1, 1983 6

ATTACHMENT B AVERACE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: March 9. 1984 COMPLETED BY: DTANE L. LIN TELEPHONE: (815) 357-6761 MONTH February 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 926 17. 0

2. 923 18. 0 3 517 19. 0

4. 161 20. 0

5. 696 21. 0

6. 646 22. 0

7. 685 23. O j 8. 756 24. 0

9. 954 25. 0

10. 1015 26. 0

11. 966 27. 0

12. 875 28. 0

13. 6 29. 0

14. 0 30.

15. 0 31.

16. 0 l INSTRUCTIONS l On this form list the average daily unit power level in NWe-Net for each day l

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 l daily unit power output sheet should be footnoted to explain the apparent l

anomaly.

Document 0043r

- v ~-

o i LTP-300-7 R;vicion 3 Harch 1, 1983 .

9 (Final)

ATTACHMENT E UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373 UNIT NAME LaSalle One DATE March 9. 1984 REPORT MONTH FEBRUARY 1984 COMPLETED.BY Diane L. Lin TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FOkCED DURATION THE REACTOR OR CORRECTIVE NO, DATE S: SCHEDULED (HOURS) REASON (1) REDUCING POWER ACTIONS /COIREENTS 5 2/3/84 F 21.4 B 3 %x Scram due to an inadvertent initiation of RCIC during performance of LIS-NB-04.

6 2/13/84' F 407.2 A 3 Rx scram due to "A" condenser boot seal which failed and subsequent loss of condenser vacuum.

DOCUMENT 0044r

l VI.' UNIQUE REPORTING REQUIREMENTS A. Main Steam Relief Valve Operations for Unit 1.

Relief valve operations during the reporting petlod 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 Conditions of Events 2/13/84 IB21-F013E 1 Auto 1050 psig To control pressure after scema 2/13/84 IB21-F013E 1 Manual 1000psig To control pressure after scram.

2/13/84 1821-F013C 2 Manual 570 psig LOS-MS-R2 2/13/84 IB21-F013D 2 Manual 570 psig LOS-MS-R2 2/13/84 IB21-F013E 2 Manual 570 psig LOS-MS-R2 2/13/84 IB21-F013V 2 Manual 570 psis LOS-MS-R2 2/13/84 1821-F013R 2 Manual 570 psig LOS-MS-R2 2/13/84 1B21-F013U 2 Manual 570 psig LOS-MS-R2 2/13/84 IB21-F013S 2 Manual 570 psig LOS-MS-E2 2/13/84 IB21-F013K 1 Manual 570 psis LOS-MS-R2 2/13/84 1821-F013A 1 Manual 570 psig LOS-MS-R2 l

l l

l Document 0043r l

2/13/84 1821-F013M 2 Manual 570 psig LOS-MS-R2 2/13/84 1B21-F013N 1 Macual 570 psig LOS-MS-R2 2/13/84 IB21-F013G 2 Manual 570 pulg LOS-MS-R2 2/13/84 IB21-F013H 1 Manual 570 psig LOS-MS-R2 2/13/84 IB21-F013L 1 Manual 570 psig LOS-MS-R2 2/13/84 1B21-F013P 1 Manual 570 psig LOS-MS-R2 2/13/84 IB21-F013F 1 Manual 570 psig LOS-MS-R2 2/13/84 1821-F013B 1 Manual 570 psig LOS-MS-R2 2/13/84 IB21-F013J 1 Manual 570 psig LOS-MS-R2 2/14/84 IB21-F013C 6 Manual 135 psig LOS-MS-R2 2/14/84 1B21-F013N 5 Manual 135 psig LOS-MS-R2 B. ECCS Systems Outages The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO. EQUIPMENT PURPOSE OF OUTAGE l

1-159-84 '1B' D/G Electric To repair air compressor Motor Driven Air Compressor 1-160-84 '1B' D/G No starting air pressure 1-162-84 '1B' D/G Recal immersion heater.

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

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

Document 0043r

. ~ , . -

- . . . ~ - _ . _ - . . . . - . - . . - - . _ - - . - - . . - - . . _ . _

4 '- '-

l fc-U N commonweenh Edison LaSille County Nucitar Station

) RuralRoute #1, Box 220 Marseilles,lilinois 61341

Telephone 815/357-6761 1-l I

i

. March 9, 1984 1

] Director, Office of Management Information and Program Control

! United States Nuclear Regulatory Commission ,

Washington, D.C. 20555 ATTN: Document Control Desk d'

Gentlemen: -

Enclosed for your information is the monthly performance report covering I LaSalle County Nuclear Power Station, Unit One, for the period covering February 1 through February 29.-1984. L i

Very truly yours, i

, f e G. J. Diederich l Station Superintendent-1 LaSalle County Station GJD/DLL/bej Enclosure xc: J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle Gary Wright 'Ill. Dept.'of Nuclear Safety I

D. P. Galle CECO i D. L. Farrar CECO INPO Records Center I Ron A. Johnson, PIP Cc ordinator 'SNED .

. W. R. Jackson, GE Resident.'

t

?

e I

i

,y

.

ML20087E745

Text

SUMMARY

SUMMARY

Navigation menu

Search