ML20096D354

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Monthly Operating Repts for Apr 1992 for LaSalle County Nuclear Power Station
ML20096D354
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 04/30/1992
From: Cialkowski M, Diederich G
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9205180001
Download: ML20096D354 (27)
v • d • e


Text

.

b C:mm:nwe:lth Edison

, LaSalle County Nuclear Station 2001 N. 21st. Rd.

Marseilles, Illinois 61341 Telephone 81W357-6761 May-11, 1992 Director of Nuclear Reactor Regulation United States Nuc1 car Regulatory Commission Hall Station P1-137 Hachingt;n, D.C.

20555 ATTH: Document Control Desk Centlemen:

Enclosed for your information is the monthly performance r_ port covering LaSalle County Nuclear Power Station for April, 1992.

Very truly yours, y

gbsY Ytf 6,-c G. lJ. Diederich Station Manager LaSalle County Station GJD/HJC/djf Enclosure xt:

A. B. Davis, NRC, Region III D. E. Ilills, NRC Resident Inspector LaSalle J. L. Roman, IL Dept. of Nuclear Safety B. Siegel, NRR Project Manager D. P. Galle, CECO D. L. Farrar, CECO j

INPO Records Center l

D. R. Eggett, NED l

P. D. Doverspike, GE Resident T. J. Kovach, Manager of :.uclear Licensing -

T. A. Rieck, Nuclear Fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor J. H. Gieseker, Technica'l Staff Supervisor l

H. H. Servoss, QA/N9 Off Site Review Station File A

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LASALLE NUCLEAR P0HER STATION UNIT 1 MONTHLY PERFORRANCE REPORT APRIL 1992 C0W;0NWEALTH EDISON COMPANY

(

j NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 5

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TABLE OF CONTENTS (UNIT-1)'

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I.

INTRODUCTION r

1-s l-i II.

REPORT

{

A.

SUMMARY

OF OPERATING EXPERIENCE

{

t-I B.

AMENDHENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS-1 C.

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATErt EQUIPMENT F

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i 0.

LICENSEE EVENT REPORTS l-i E.

DATA TABULATIONS l-1.

Operating Data Rsport F

2.

Average _ Daily Unit Power Level-l 3.

Unit Shutdowns and Power Reductions F.

UNIQUE REPORTING-REQUIREMENTS 1.

Main Steam Relief-Valve 0perations.

l l

2.

ECCS System Outages t

3.

Off-Site Dosc Calculation Manual Changes 4.

Major-Changes-to Radioactive Maste-. Treatment System 1

5.

Indications of failed Fuel Elementsi i

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I.

INTRODUCTION (Unit 1) j j_

The LaSalle County Nuclear Power Statio-is a two-unit facility owned by j-Commonwealth Edisbn Company and located near Marseilles, Illinois.

Each j

unit is a Boiling Hater Reactor with a designed net electrical-output of L

1078 Megawatts.

Haste heat is rejected M a man-made' cooling pond-using the Illinois River for make-up and blowdown.

The architect-engineer was l

Sargent and Lundy - -and the primary construction contractor was Commonwealth Edison Compi-4

}

Unit One was issued operating license _ number NPF-11 on-April 17, 1982.

j Initial criticality was achieved on ' June 21, 1982 and. commercial. power j

operation was commenced on January 1, 1984.

i This report was complied by Michael J.

Cialkowski, telephone number-3 l

(815)357-6761, extension 2427.

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7 II. MONTitLY REPORT-A; SU R RY OF OPERATING EXPERIENCE (Unit 1)

Day Time Event 1

0000 Reactor critical, Generator on-line at 1130 Mwe.

3 0200 Reduced power level to 1000 Mwe due to system load.

1000 Increased power ~ level to 1130 Mwe.

4 0?00 Reduced power level to 1025 Mwe to' transfer the lleater Drain _ system pumps.

0600 Increased power level to 1130 Mwe.

2300 Reduced power level to 1025 Mwe to transfer the Heater Drain system pumps.

5 0500 Increased power level to 1130 Mwe, 7

0200 Reduced power level to 950 Mwe to perform monthly-survaillances.

1000 Increased power level to 1135 Mwe.

11 0330 Reduced power level to 900 Mwe to perform rod set, 1130 Increased power level to 1130 Mwe.

14' 0200 Reduced power level to 1030.Mwe to transfer tiie Condensate / Condensate Booster pumps.

0930 Increased power level to 1130 Mwe.

21 0130

. Reduced power _ level to 1020 Mwe to transfer i n Condensate / Condensate Booster pumps.

1000 Increased power level to 1130'Mwe.

22 1800 Reduced power level-to 990 Mwe to place the Motor Driven Reactor Feed Pump on-line for Maintenance.

2330 Increased power level to 1130 Mwe.

25 0330 Reduced power level to 995 Hwe due to system load.

1000 Increased power-level-to 1130 Mwe.

27

_0200 Reduced power level to 995 Mwe'due to system load.

1000 Increased power level to 1130 Mwe.

ZCADTS/S j

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II. HONTHLY REPORT (CONTINUED)

A.~

SUMMARY

OF OPERATING EXPER12NCE (Unit 1)

Day Time Event __

28 0330 Reduced power level to 1000 Hwe due to system load.

1000 Increased power level to 1130 Hve.

1300 Reduced power level to 1000 Hwe due to system load.

29 0220 Reduced power level to 870 Hwe due to system load.

1200 Increased power level to 1130 Hwe.

2300 Reduced power level to 850 Hwe due to system load.

30 2400 Reactor critical, Generator on-line at 850 Hwe.

U l

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B.

AMENDHENTS TO TtlE FACILITY LICENSE OR TECHNICAL SPECIFICATION (None.)

C.

MAJOR CORRECTIVE HAINTENANCE TO SAFETY-RELATED EQUIPMENT (including SOR differential pressure switch failure reports).

(See Table 1) i O.

LICENSEE EVENT REPORTS (Unit 1)

L p Nusher Dale QcitriotiQIL_

92-005-00 04/06/92 During performance of the Reactor Core I?olation-Cooling system cold quick start surveillance, tha RCIC turbine tripped on overspeed during the initial start sequence.

92-006-00 04/27/92 Per engineering evaluations, the design setpoint of the 4KV _ degraded voltage relays may not be sufficient to assure operation and protection of safety ralated equipment.

E.

DATA TABULATIONS (Unit 1) 1.

Operating Data Report (See Table 2) 2.

Average Daily Unit Power Lovel (See Table 3) 3.

Unit Shutdowns and Significant Power Reductions (See Table 4) i i

i ZCADTS/5

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TABLE I (Unit 1)

MAJOR CORRECTIW MAINTENANCE TO SAFETY-RELAitD EQUIPMENT RESULTS AND EFFECTS MORK REQUEST

, COMPONENT CAUSE Of MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION NUMBER L10727 Auxiliary Electric Oli temperature indicating Inaccurate temperature readings. Replaced temperature Equipment Room.

switch.

switch.

Ventilation Compressor Motor CVE04CA Ll4938-Reactor Core Isolation Governor valve IE51-361.

Turbine tripped on overspeed Replaced valve plug and Cooiing System Turbe during surveillance testing.

stem.

1E51-C002 L15272

-Control: Room HVAC-Anmonia detector D =tector-alarming below alarm Rebuilt detector.

At unia Detection OXY-VC125B.

setpoint.

System L

.L15311 Standby Gas Treatment' 74 relay.

Int anerance relay operation.

Replaced replay.

l Equipment Train:

j I-Cooling Fan-IVG02C.

l

.(No SOR Failures'this month.)

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TABLE 2 E.1 OPERATING DATA REPORT =

3 DOCKET MO. 050-373 UNIT LASALLE ONE DATE May 11,1992 COMPLETED BY M.J.CIALKOWSKI TELEPHONE (815) 357-6761 OPERATING T,TATUS 1.

REPORTING PERIOD:

April 1992' GROSS HOURS IN REPORTING PERIOD:

719 2.

CUERENTLY AUTHORIZED POWER LEVEL (Mwt):

3,323

-l MAX DEPENDABLE CAPACITY (Mwe-Net)?

1,036 DESIGN ELECTRICAL RATING'(Mwe. Net):

1,078 3.

POWER LEVEL TO WHICH RISTRICTED (IF ANY):

N/A 4.

REASON FOR RE: M CTI7.4 (IF ANYJ:

..THIS MONTH YEAR-TO-DATE CUMULATIVE 5.

REACTOR CRITICAL TIME-(HOURS) 719.0-2,843.5

.50,198.0 6.

REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2 7.

GENERATOR ON-LINF TIME (HOURS) 719.0 2,808.8 49,187.1 8.

UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0 9.

THERMAL ENERGY GENERATED (MWHt) 2,359,085 9,098,837_ 144,255,816

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 806,389 3,10P,252 48,198,004-
11. ELECTRICAL ENERGY GENERATED-(MMHe-Net) 779,720 3,014,071 46,209,216-
12. REACTOR SERVICE FACTOR (%)

100.0 97.9 68.4 y

13. REACTOR AVAILABILITY r' ACTOR (%)

100.0 ~

97.9-70.7

14. UNIT SERVICE FACTOR (%)

100.0' 96.8 67.0 g,

15. UNIT AVAILABILITY FACTOR (%)

100.0 96.8 67.0

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

104.7-32.3 60.6

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 101.6

- 96. 6-58.3

18. UNIT FORCED OUTAGE FACTOR (%)

0.0 3.2 7.4

19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE AND DURATION Of EACH): Refuel Outage, 09/16/92, 12 Weeks
20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUPt i

. ~... ~. -

TABLE 3'

' E.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net)

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DOCKET NO. 050-373.

UNIT LASALLE ONE

-DATE May-11,1992 COMPLETED BY M.J.CIALK0WSK TELEPHONE (815) 357-6761 j

REPORTING PERIOD: April 1992 1~

l I

1 DAY POWER DAY POWER i

1 1,096 17 1.100 l

2 1,098 18 1,098 l

1 3

1,078 19 1,094 i

4 1,082 20 1,094 i

5 1,048 21 1,085-l 6

1,098 22 1,082 l

7 1,069 23 1,095 i

l 8'

1,093 24 1,094 9

1,095 25 1,077 10 1,092.

26 1,094 i

11 1,050 27 1,075 12 1,095 28

'1,082 l

13 1,097 29 1,034 14 1,085 30 1,012-i 15 1,099 16 1,098 1

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TABLE 4 i

E.3 UNIT SHUTD0HNS AND POWER REDUCTIONS > 201 e

' (Unit 1) f l

METH00 0F CORRECTIVE YEARLY TYPE SHUTTING DOHN

. ACTIONS /CO MENT 3

. SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR f if 1

- NUMBER (YYMMD3) S: SCHEDULED (HOURS)

REASON REDbCING POWER applicable)

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(None.)

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l SiM1ARY Oc OPERATION:

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' The unit remained on line at 'high.' power throughout the montii. Several minor power reductions were required due.to syslem:

loading.and maintenance activities..

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F.

UNIQUE REPORTIRG REQUIREMENTS (Unit 1) 1.

Safety / Relief valve operations (None.)

2.

ECCS System Outages (See Table 5) 3.

Changes to the Off-Site Dose Calculation Manual (None.)

4.

Hajor changes to Radioactive Haste Treatment Systems.

(None.)

-5.

Indications of Failed Fuel Elements.

(None.)

i ZCADTS/5 e

_______________.____.a

- 4 (Ur.it 1)

Table 5 F.2 ECCS System Outages Note:

The year and unit data has been removed from the outage number.

OUTAGE NO.

LOUIPMENT PURPO's (0-0) 0269 ODG0lK Check valve inspection.

0284 0288 ODG0lK Disassemble and clean drains.

(U-1) 0179 IE22-S001 Fuel oil suction valve inspection.

0226 lE21-C003 Coupling lubrication.

0237 IE51-C002 Govenor valve inspection.

0242 lE51-C002 Change oil and filters.

0250 lE22-C302A Inspection.

0252 lE22-F001 Hiring inspection.

0269 1DG0GCB Valve inspection.

0270 1E12-f052B EQ inspection.

0280 1DG08CA Valve inspection.

0286 CG0lK Inspection.

1 ZCADTS/5+

4 LASALLE NUCl. EAR POWER STATION UNIT 2 HONTHLY PERFORMANCE REPORT APRIL 1992 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 e

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TABLE OF CONTENTS.

j (Unit'2)..

l I.

INTR 0l/ JCT 70N 5

i II.

REPORT i

A.

SUW4ARY 'S OPERATING EXPERIENCE

!I B.

AMENDMENTS TO FACILITY LICENSE.OR TECHNICAL SPECIFICATIONS i

C.

MAJOR CORRECTIVE MAINTENANCE 10 SAFETY-RELATED EQUIPMENT n.

LIC?sSEE EVENT REPORTS i

E.

DATA TABULATIONS l

1.

Operating Data Heport 2.

Average Daily Unit Power Level 3.

Unit Shutdowns and Power Reductions--

l F.

UNIOUE REPORTING REQUIREMENTS i

1.

Safety / Relief Valve Operations 2.

.ECCS System Outanes 3.

Off-Site Dose C

'ation Manual Changes'-

1 4.

Major Changes tc

1oactive Haste Treatment System l

S.

Indications of Failed Fuel Elements i

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F t

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I.

INTRODUCTION (Unit 2)

The LaSalle County Wuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Harsellies, Illinois.

Each unit is a Boiling Hater Reactor with a designed net electrichl output of 1078 Hegcwatts.

Haste heat is rejected to a man-made colling pond using the Illinois River for make-up and blowdown. The architect-engineer was h

Sargent and Lundy and the primary construction contracte was Comonwealth Edison Company.

~

Unit Two was issued operating license nuraber NPF-18 on Decoraber 16, 1983.

Initial criticality was achieved on Harch 10, 1984 and commercial power operation was commenced on June 19, 1984.

This report was compiled by Michael J. Cialkowski, telephone numbcr (815)357-6761 extension 2427.

of ZCADTS/7

i 1

l II. HONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 2) 3 DE Ilme Erent 1

0000 Reactor subcritical, Generator off-line, Refuel outage (L2R04) in progress.

2 1814 Reactor critical.

2144 Reactor subtritical, all control rods inserted due to problems with the Reactor Water Cleanup isolation valves.

7 2330 R.

jor critical.

12 1907 Generator on-line.

2043 Hanual Turbine trip due to high vibrations caused by rubs on the recently installed turbine rotors.

13 0420 Generator on-line.

0640 Hanual Turbine trip due to high vibratias caused by rubs on the recently installed turbine rotors.

1335 Generator on-line.

14 0200 Increased power level to 225 Hwe.

15 1509 Hanual Reactor scram due to erratic behavior of the Main Turbine Electro-Hydraulic. Control system.

19 0555 Reactor critical.

2230 Generator on-line.

20 0231 Hanual Turbine trip to perform overspeed testing.

0404 Generator on-line.

21 1345 Increased power level to 225 Hwe.

1730 Increased power level to 315 Hwe.

2045 Increased power level to 400 Hwe.

2205 Increased power level to 524 Hwe.

22 1030 Increased power level to 833 Hve.

24 2130 Increased power level to 900 Hwe.

ZCADTS/7 q

II. MONTHLY REPORT (CONTINUED)

A.

StM4ARY-0F OPERATING EXPERIENCE-(Unit 2)

-1 Rgy Jima Event 25 0300 Increased power. level to 1000 Mwe (level held due toe the 'A' Turbine Driven Reactor Feed Pump Being Out Of Service for maintenance).

27 1000 Reduced' power level to 950 Mwe due to low Condensate.

Booster pump suction pressure.

1600 Increased power level-to 1000 Mwe.

30 2400 Reactor ( *itical, Generator on-line at 1000 Mwe.

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B.

AMENDNENTS TO THE FACIl.ITY LICENSE OR TECHNICAL SPECIFICATION (None.)

C.

MAJOR CORRECTIVE MAINTENANCE TO SAFETY RELATED EQUIPMENT (including SOR differential pressure switch failure reports).

(See Table 1)

D.

LICENSEE EVENT REPORTS (Unit 2)

LER Number Qttg DescriDtion 92-004-00 04/15/92 Manual Reactor scram caused by the Turbine Bypass; Valves cycling excessively due to_a Electro-Hydraulic Control system malfunction.

92-006-00 04/20/92 Reactor Mater Cleanup system isolation caured by high differential flow.--

E.

DATA TABULATIONS (Unit 2)

1. _

Operating Data Report.

(See Table 2)-

2.

Average Daily Unit Power Level.

'i (See Table 3) 3.

Unit Shutdowns and Significant Power Reductions.

(See Table 4)

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C.

TABLE 1 (Unit 2)

MAJOR CORRFCTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT HORK REGilEST RESULTS AND EFFECIS NUMBEL _

COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L10025 Control Rod Drive Valve positioning.

Control rod double notched.

Replaced valve.

42-47 L11386 Hydraulic Control Hater accumulator.

Frequent water alarms.

Replaced accumulator.

Unit 14-15 L12099 Hydraulic Control Hater accumulator.

Frequent water alarms.

Replaced accumulator.

Unit 34-11 L12148 Hydraulic Control Hater accumulator.

Frequent water alarms.

Replaced accumulator.

Unit 22-19 L12149 Control Rod Dr ive Unit degradation.

Degraded operation.

Replaced control rod.

06-31 L12150 Control Rod Drive Unit degradation.

Degraded operation.

Replaced control rod.

10-39' L12151 Control Rod Drive Unit degradstion.

Degraded operation.

Replaced control rod.

42-31 L12152 Control Rod Drive Unit degradation.

Degraded operation.

Replaced control rod.

38-43 L12153 Control Rod Drive Unit degradation.

Degraded operation.

Replaced control rod.

34-59 L12154 Control Rod Drive Unit degradation.

Degraded operation.

Replaced control rod.

34-59 L12155 Control Red Drive Unit degradation.

Degraded operation.

Replaced control rod.

22-19 L12156 Control Rod Drive Unit degradation.

Degraded operation.

Replaced control rod.

14-27 ICADTS/7

4 C.

TABLE 1 (Unli 2) -CONTINUED MAJOR CORRECTIVE MAINTENANCE TO l

SAFETY-RELATED E(yJIPMENT HORK REQUEST RESULTS AND EFFECTS NUMBER-COMPON_ENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L13673 Safety Reller Valve

'A' solenoid electrica-None.

Replaced solenold.

l l

2B21-f013C connection.

l L13820_

Hydraulic Coatrol Valve. leakage.

Degraded operation.

Replaced valve.

Unit 10-27

.L13926.

Hydraulic Control Hater accumulator.

Frequent water alarms.

Replaced accumulator.

Unit 42-11 i

L14467 Hydraulic Control Valve leakage.

Degraded operation.

Replaced v6sve.

Unit 42-55 i.

L14468 liydraulic Control Valve leakage.

Degraded operation.

Replacdd valve.

Unit 22-27 y

l Ll4469-Hydraulic Control Valve leakage.

Degraded-operatic:1..

Replaced valve.

l Unit 18-07 L14470

' Hydraulic Control Valve leakage.

Degraded operation.

Replaced valve.

Unit'14-07

'L14723

. Hydraulic Control Valve leakage.-

Degraded operation.

Replaced v-ive..

Unit 10-47 l

L14838 Division II. Battery Current. sensing and.

Charger putting out low voltage. Replaced current sensing i

Charger 2DC17E -

amplifier boards.

and amplifier boards.

l L15162

. Hydraulic Control.

Valve leakage.-

Degraded operation.

Replaced valve.

i:

Ur.1t 06-27 L15184-Hydraulic Control Valve leakage.

Degraded. operation.

Replaced valve.

Unit 38-11 L15421 Residual Heat Removal Differential. pressure Switch exceeded rejection limits Replaced: switch'.

Shutdown Cooling switch 2E31-N012AA-during testing.

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C.

TABLE 1 (Unit 2) -CONTINUED MAJOR 00RRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT RESULTS AND EFFECTS HORK REQUEST NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION 00RRECTIVE ACTION L97545 Hydraulic Control Hater accumulator.

Frequent water alarms.

Replaced accurulator.

i Unit 02-23 L97549 Hydraulic Control Hatar accumulator.

Frequent water alarms.

Replaced accumulator.

Unit 02-35 L97553 Hydraulic Control Hater accumulator.

Frequent water alarms.

Replaced accumulator.

Unit 30-27 L97554 Hydraulic Control Hater accumulator Frequer.t water alarms.

Peplaced accumulator.

Unit 34-07 L97572 Hydraulic Control Hater accumulator.

Frequent water alarms.

Replaced accumulator.

Unit 26-35 L99501 Hydraulic Control Valve leakage.

Degraded operation.

Replaced valve.

l Unit 54-31 L99502 Hydraulic Control Valve leakage.

Degraded operation.

Replace.1 valve.

Unit 38-51 L99553 Control Rod Drive Seal leakage.

Degraded operation.

Replaced seals.

26-27 I

L99554 Control Rod Drive Seal leakage.

Degraded operation.

Replaced seats.

46-35 (See attached SOR Failure Repcrt.)

ZCADTS/7

]

SQR dp SWITCH FAILUfjLDAESliEET Equipment Piece Number: 2E31-N012Ah Model Number: 1DJ_-AS-B2D3-NX-JJTTX6 Serial Number 30-8-6434 Applieation EllILShutdoyA_foolingJ119hjiuction_Eloxlanlat i o n Date and Time of Discovery: 04/29/91 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br /> Reactor Mode 1_(Runl Power Level: 323 Calibration Tolerance: 16.7. 4 - 159_d "WC Nominal Setpoints (11L.s "WC Action Limits:

(if3.J or >12L 3 "WC Reject Limits:

<l5La or >178.0 "WC Technical Specification Limits:

11$1Q "WC As Found Setpoints 151 d "HC Date and Time of Return to Service: 91/30/92 0845 hour0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br />s-Model Number of Replacement Switch JD3-AS-B203-MK-JJTTKQ Serial Number of Replacement Switch 90-8-6433 DVR Number 1-2-92-051 Cause: Switch wRS.lound out of calibration d pparent__cause is instrument drift.

Corrective Action: Ihe switch was replaggd.

I,

~

TABLE 2 E.1 OPERATING' DATA REPORT

+

DOCKET NO. ; 050-373 UNIT LASALLE TWO DATE May 11,1992 COMPLETED BY M.J.CIALKOWSKI TELEPHONE (815) 357-6761 OPERATING STATUS 1.

REPORTING PERIOD:

April 1992 GROSS HOURS IN REPORTING PERIOD:

719 2.

CURRENTLY AUTHORIZED POWER LEVEL (Mwt):

3,323 MAX DEPENDABLE CAPACITY.(Mwe-Net):

-1,036 DESIGN ELECTRICAL RATING (Mwe-Net): '

1,078 3.

POWER LEVEL TO WHICH RESTRICTED (IF ANY):

N/A 4.

REASON FOR RESTRICTION (IF ANY):

l THIS MONTH YEAR-TO-DATE CUMULATIVE 5.

REACTOR CRITICAL TIME (HOURS) 469.2-553.2-45,489.0 6.

REACTOR RESERVE SnUTDOWN TIME (HOURS) 0.0 IO.0 1,716.9:

7.

GENERATOR-ON-LINE TIME (HOURS) 317.5 391.4 44,596.0 8.

UNIT RESERVE SHUTDOWN TIME (HOURS)~

0.0' O.0 0.0 9.

THERMAL ENZRGY GENERATED (MWHt) 667,956 848,942 133,091,341

10. ELECTRICAL ENERGY GENERATED.(MWHe-Gross) 222,732 287,006-44,176,756.

11.' ELECTRICAL ENERGY GENERATED (MWHe-Net) 209,025 246,745 42,378,249

12. REACTOR SERVICE FACTOR (%)

65.3 19.2

6 8. ').
13. REACTOR AVAILADILITY FACTOR (%)

65.3 19.2 71.5 l

14.. UNIT SERVICE FACTOR (%)

44.2

' 1'3. 6 67.8

15. UNIT AVAILABILITY FACTOR (%)

44.2

.13.6

.67.8 l

l' 16.~ UNIT CAPACITY FACTOR (USING MDC)-(%)

28.1~

'8.3 62.3 l

l.

17.' UNIT CAPACITY FACTOR'(USING DESIGN MWe) 27.0 8.0:

59.9-

18. UNIT FORCED OUTAGE FACTOR (%)

21.5

.' 5. 4 13.17

19. SHUTDOWNS SCHEDULED OVER THE'NEXT 6 MONTHS'(TYPE, DATE AND. DURATION OF_

EACH):

20.~ IT SHUTDOWN AT FNU OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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w.

TABLE 3 E.2 WERAGE DAILY UNIT POWER LEVEL _(MWe-Net)

DOCKET NO. 050-373-UNIT LASALLE 'IWO-DATE May 11,1992f COMPLETED BY M.J.CIALKOWSKI TELEPHONE (815) 357-6761

-REPORTING PERIOD: April 1992 DAY POWER DAY POWER-1

-12 17

-11 2

-12 18-

-12 3

-12 19

' -5 4

-12 20 129

)

5

-12 21-232 6

-12 22 764-7

- 12 '22-801 0 24 792 9

-12 25 962 10

-12 26 962--

11

-12 27 950 12

-2

'28.

973 13 69 29-972 14 203 30 967--

15-108 16

-12 4

TAllLE 4 E.3 IIHIT SIIUTDOWNS AND POWER REDtlCTIONS >20%

(UNIT 2)

METIIOD OF CORRECTIVE YEARLY TYPE SIRTITING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE F: FO'2CED DURATION TIIE REACTOR OR (LER/DVR l if NUMBER

{][YMMDDJ S-JCIIEDULED

[IlOUR$)_

REASON REDUQ1NG POWER applicable _)

1 Refueling outage L2R04.

01 920104 S

282.12 02 920412 F

7.62 A

4 Manual turbine trip due to high vibrations caused by rubs on the newly installed turbin<.

rotors (reactor remained critical).

03 920413 F

6.92 A

4 Manual turbine trip due to high vibrations caused by rubs on the newly installed turbine rotors (reactor remained crit ical).

04 920415 F

8 6. "J 7 A

2 Manual reactor scram due to erratic behavior of the main turbine electro hydraulic control system.

(LER

  1. 92-004-00 -- DVR #1-2-92-0048) 05 920420 S

1.55 B

4 Turbine overspeed trip test (reactor remained critical).

SUMMARY

OF OPERATION:

The unit ended a scheduled refueling outage on 4/12/92.

Following the return to service the unit experienced three separate manual Main Turbine trips and a manual Reactor scram.

The unit was returned to service on 04/20/92 and remained at high power for the remainder of the month.

ZCADTS/7

F.

UNIQUE REPORTING REQUIREMENTS (Unit 2) 1.

Safety / Relief Valve Operations (None.)

2.

ECCS System Outages (See Table 5.)

3.

Changes to the Off-Site Dose Calculation Manual.

(None.)

4.

Major changes to Radioactive Haste Treatment Systems.

(None.)

5.

Indications of failed fuel Elements.

(None.)

l 1

i i

2 7CADTS/7

~

T (Unit 2)

Table 5 F.2 ECCS System Outages Note:

The year and unit data has been removed from the outage number.

OUTAGE NL EQUIPMENT F1LR_PQ1E 1556 2E51-C002 Recouple turbine.

1557 2E51-D316 Remove blind flange.

1624 1575 2E12-F024B Shutdown cooling requirements.

2E12-F027B 1602 2E12-F009 Administrative control.

1605 2E22-F038 Valve inspection.

1607 2E51-C005 Pump and motor maintenance.

1609 2E51-F045 Repair trip linkage.

1614 2E51-C002 Repair trip / throttle valve.

1622 2E51-C001 Inspection of manual trip assembly.

(

1623 2E51-C005 Repair vacuum pump seal.

1629 2E22-C302A Inspection.

1631 2E22-C3028 Inspection.

1637 2E12-F024A Shutdown cooling requirements.

2E12-F027A 1651 2E12-F332B Inspection 1696 2E22 S001 Administrative control, s

ZCADTS/7

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