ML20101Q673

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Monthly Operating Rept for June 1992 for Lasalle County Nuclear Power Station,Unit 1
ML20101Q673
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 06/30/1992
From: Cialkowski M, Diederich G
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9207150052
Download: ML20101Q673 (25)
v • d • e


Text

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, Commonwe:lth Edison LaSalle County Nuclear Station 2601 it 21st. Rd.

Marsei!!es. Illinois 61341 Telephone 815A57-6761 July 10, 1992 Director of Nuclear Reactor 1:Tilation United States Nuclear Regulatory Comission Mail Station Pl-137  ;

Mashington, D.C. 20555 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for June 1992.

Very truly yours,

~~

r G. J. D' aderich

.p/StationManager LaSalle County Station GJD/MJC/djf Enclosure xt: A. B. Davis, NRC, Region III D.-E. Hills, 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 INPO Records Center D. R. Eggett, NED P. D. Doverspike, GE Resident T. J. Kovach, Manager of Nuclear Licensing ,

-T. A. Rieck, Nuclear Fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor M. M. Servoss, QA/NS Off Site Review 1 Station File Y

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l LASALLE NUCLEAR POWER STATION.

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MONTHLY PERFORMANCE REPORT

~ JUNE 1992 i COM40NHEALTH EDISON COMPANY-P

.- --NRC DOCKET NO. 050-373 LICENSE N0'.-NPF-11.

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TABLE OF CONTENTS

.(UNIT-1)

I INTRODUCTION II. REPORT A. SlM4ARY OF=0PERATING EXPERIENCE B.  :-AMENDMENTS-TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C.  ? MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT D. LICENSEE EVENT-REPORTS

-E. DATA TABULATIONS

1. '_ Operating Data Report 2.- -Average Daily Unit Power Level
3. Unit. Shutdowns and: Power Reductions F. 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 Masto Treatment System

. S. Indications of_ Tailed Fuel Elements -

ZCADTS/5

I. INTRODUCTION (Unit 1)

The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marsellies, Illinois. Each unit is a Bolling Hater Reactor with a designed net electrical output of 1078 Hegawatts. Haste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company.

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

Initial criticality was achieved on June 21, 1982 and commercial power operation was commenced on January 1, 1984.

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

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ZCADTS/5

.* sII. MMTHLY REPORT

, 'A. SlM4ARY OF OPERATING EXPERIENCE (Unit 1) 03y Ijst Event 1 0000 Reactor critical, Generator on-line at 850 Mwe.

1300 Increased power level to 1105 Mwe.

2 0200 Reduced power level to 900 Hwe to perform monthly survelliances.

1100 Increased power level to 1100 Mwe.

6 0230 Reduced power level to 1000 Hve due to system load.

'100 Increased power level to 1100 Mwe.

7 0000 Reduced power level to 850 Mwe due to system load.

8 1330- Increased power level to 1100 Hwe.

9 0030 Reduced power level to '150 Hvo due to system load.

1030 Increased power '+ el () 1100 Hwe.

10 0200 Reduced power level to 850 Mwe due to system load.

1000 Increased poutr level to 1100 Mwe.

12- 0300 Reduced power level to 985 Mwe due to system load.

0930 Increased power level to 1100 Hwe.

13 2030- Reduced power level to 1915 Hwe due to high lake temperature.

14 0700 Increased power level to 1075 Hwe.

'16 0200 Reduced power level to 050 Mwe due to system Icad.

1000 Increased power level to 1090 Mwe.

18 0130' Reduced power level to 750 Mwe to withdrawal all control _ rods, unit in coastdown.

' 1100 ~ . Increased power level'to 1105 Mwe.

_19_ 0230: Redx ed power level to 850 Hwe due to system load.

1000 Increksed power level to 1105 Mwe.

20 .0100- Reduced power level to 850 Mwe due to system load.

1 ZCADTS/S l

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. II. MONTHLY REPORT (CONTINUED)  !

. 'A.- SlM4ARY OF OPERATING EXPERIENCE (Unit 1)

QBy ling Event _

1100 Increased power level to 1105 Mwe.

1300 Reduced power 1cvel to 975 Mwe due to system load. '

1900 Reduced power level to 850 Mwe due to system load. i 21 1330 Increased power level to 1055 Hwe.

1430 Reduced power level to 1000 Hwe to insert a control rod due to APRM high alarm.

22 0030- Reduced power level to 850 Hwo due to system load.

1400 Increased power level to 1090 Mwe.

23 0030 P9duced power level to 830 Hwe due to system load.

1100 Increased power level to 1080 Hwo.

24 0230 Reduced power level to 900 Hwe due to system load.

1000 Increased power level to 1060 Hwe.

2000 N doced power level to 850 Mwe due to system load.

2300 Reduced power level to 775 Hwe due to system load.

25 1100- Increased power level to 1075 Hve.

26 0130 Reduced power level to 750 Hwe to perform rod set.

0230 Increased poyer level to 850 Hve.

1100 Increaseo power Icvel to 1100 Mwe.

28 0130 Reduced power level to 850 Hwe due to system load.

20 1330 Increased power level to 1100 Hwe.

30 0000 Reduced power level to 850 Hwe due to system load, performed monthly surveillances.

1200 Increased power level to 1100 Hwe.

2400 Reactor critical Generator on-line at 850 Mwe, power level reduced due to system load.

l ZCADTS/5

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, . *- B. AMENDNENTS TO THE FACILI1Y LICENSE OR TECHNICAL SPECIFICATION

-(None.) .

C. MJOR CORRECTIVE MINTENANCE TO SAFETY-RELATED EQUIPMENT (including SOR differential pressure switd. tallure reports).

(See Table 1)

D. LICENSEE EVENT REPORTS (Unit 1)

LER Number QAljt Description _

92-008-00 06/22/92 Spurious instrument spike resulting in a Reactor Core Isolation - Cooling systes injection and a level 3 'B' channel 1/2 scram.

E. -DATA TABULATIONS (Unit 1)

1. Operating Data Report (See Table 2) x 2. Average Daily Unit Power Levei (See Table 3) 4
3. ' Unit Shutdowns and Significant Power Reductions (See Table 4) l

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ZCADTS/5_

C. TABLE 1 (Unit 1) -.

MAJOR CORRECTIVE MINTENANCE TO -

SAFETY-RELATED EQUIPMENT RESULTS AND EFFECTS HORK REQUEST CORRECTIVE ACTION COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION NUMBER Instrument stop valve None. Replaced stop valve. i L13045 Residual Heat Removal  ;

High Pressure Alarm lE12-F352 leaking.

Pressure switch IE12-N018 High motor vibrations. Replaced motor bearings.

L15221 Reactor Core Isolation Pump motor.

Cooling Hater Leg Pump 1E51-C003 Nitrogen leakage. Replaced bicr.k cap.

L15743 Hydraulic Control Accumulator instrument Unit 10-51 block cap.

L15787 Residual Heat Removal Suction pressure indicator Inaccurate pressure indication. Replaced pressure gauge &

i: strument stop valve.

Pump 1E12-C002C 1E12-R002C.

Hydraulic Control Scram pilot solenoid None. Rebuilt solenoid valves.

L15938 Unit 06-27 valves.

Instrument stop valve Instrument stop valve leakage. Replaced valve.

L15961 Main Stean Leakage Control System 1E32-F302A Pressure Transmitter IE32-N061A Cassette drive motor out Spurious high level alarms. Replaced drive motor and Ll6004 Control Room HVAC recalibrated.

Ammonia Detector of calibration.

OXY-VC125A

'1A' Diesel Generator Overload relay. Overload relay failed to trip. Replaced relay.

L16202 space heater.

Damper actuator ITZ-VXOO9A. Actuator failed to cycle. Replaced actuator.

L96459 Switchgear Heat Removal Outside Air Supply Damper IVX14Y (No SOR Failures this month.)

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4 TABLE 2 E.1 OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LASALLE ONE DATE July 10, 1992 COMPLETED BY M.J.CIALKOWSKI OPERATING STATUS TELEPHONr '815) 357-6761

1. REPORTING PERIOD: June 1992 GROSS HOURS IN REFORTING PERIOD: 720
2. CURRENTLY AUTilORIZED 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 (IT ANY) (MWe-Net): N/A
4. REASON FOR RESTRICTION (IF ANY):

THIS MONTil YEAR TO DATE CUMULATIVE 5.. REACTOR CRITICAL TIME (HOURS) 720.0 4,305.5 51,662.0

6. REACTOR RESERVE SHUTDOWN TIME (HOU*AS) 0.0 0.0 1,.641.2
7. GENERATOR ON-LINE TIME (HOURS) 720.0 4,272.8 50,651.1
8. UNIT RESERVE SHUTDOWN TIME (llJURS) 0.0 0.0 1.0
9. THERMAL ENERGY GENERATED (MWHt) 2,266,533 13,726,170.8 148,883,150
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 745,059 4,650,003 49,739,775
11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 719,010 4,502,929 47,698,074
12. PEAC'IOR SERVICE FACTOR (%) 100.0 98.6 69.3
13. REACTOR AVAILABILITY FACTOR (%) 100.0 98.6 71.5
14. UNIT SERVICE FACTOR (%) 100.0 97.8 68.0
15. UNIT AVAILIBILITY FACTOR (%) 100.0 97.8 68.0

-16. UNIT CAPACITY FACTOR (USING MDC) (%) 96.4 99.5 61.8

-17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 92.6 95.7 59.4

18. UNIT FORCED OUTAGE FACTOR (%) 0.0 2.2 7.2
19. SHUTDOWNS SCHEDULED OVER 'fHE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

Refval Outage, 09/46/92, 12 Weeks

20. IF. SHUTDOWN AT END 0/ REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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, TABLE 3

, , E.2 AVERAGE DAILY UNIT POWER LEVEL (MWa-Net)

DOCKET NO, 050-373 UNIT LASALLE ONE DATE July 10, 1992 COMPLETED BY H.J. CIALK0WSKI s TELEPilONE (815)-357 6761 s

REPORT PERIOD: June 1992 DAY POWER DAY POWER I 1,003 17 1,050 2 1,022 18 1,025 3 1,073 19 1,023 4 1,077 20 907 5 1,074 21 919 6 1,037 22 953 7 830 ;3 975 8 982 24 947 9 994 25 949 10 1,011 26 1,000 11 1,068 27 1,063 12 1,051 28 831 13 1,036 29 982 14 1,041 30 982 15 1,043 31 16 1,012

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E.3 UNIT SHUTDOHNS AND POWER REDUCTIONS > 201 (Unit 1) -

HETH00 OF CORRECTIVE YEARLY TYPE SHUTTING DOHN ACTIONS /CINENTS SECUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (N) S: SCHEDULED (HOURS) REASON REDUCING PONER applicable) 2 92G607 F 0.0 H 4 Power reduction due to system load.

3 920628 F 0.0 H .4 Power reduction due to system load.

SUMMRY OF OPERATION:

The unit remained on line at high power throughout the month. Several minor power reductions were required due to system loading and maintenance activities.

ZCADTS/S

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f. UNIQUE REPORTII.G 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. Major changes to Radioactive Haste Treatment Systems.

(None.)

5. Indications of failed fuel Elements.

(None.) l_

ZCADTS/S

4 .

(Unit 1)

Table 5 F.2 ECC., System Ontages Note: The year and wit data has been removed from the outage number.  !

OUTAGE NO, [0UIPMENT PURPOSE (0-0) 0497 000004 Adjust discharge valve limit switches.

0502 000004 Inspect transfer pump make up -

I valve.

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l (U-1) 0470 1E12-0026B Inspection.

0471 0482 0472 IE12-F003B Inspection.

0473 0483 0476 IDG01K Rewire annunciator logic.

0480 IDG01K Inspection main feed breaker.

0486 IDr.01K Change soakback oil filter.

0493 1DG01K Replace soakback pump control power transformer.

0505 IE12-F352 Replace instrument stop valve.

0516 1E51-f046 Perform Votes test.

0526 1E51-C002 Administrative control.

ZCADTS/5+

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l LASAll.E NUCLEAR POWER STATION UNIT 2 HONTHLY PERFORMANCE REPORT l l

JUNE 1992 COMMONHEALTH EDIS0N COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 ZCADTS/7

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l TABLE OF CONTENTS  !

(Unit 2)

I. INTRODUCTION II. REPORT A. SlH4ARY OF OPERATING EXPERIENCE J B. AMENDHENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS i C. MAJOR 00RRECTIVE MAINTENANCE TO SAFLTY-RELATED EQUIPMENT D. LICENSEE EVENT REPORTS i

E.- DATA TABULATIONS .

1. Operating Data Report
2. ' Average Daily Unit Power Level
3. ' Unit Shutdowns and Power Reductions i F. UNIQUE REPORTING REQUIREMENTS
1. - Safety / Relief-Valve Operations 2.. ECCS System Outages
3. Off-Site Dose Calculation Manual Changes
4. Major Changes to Radioactive Waste Treatment System

.S. Indications of Failed Fuel Elements t

. ZCADTS/7

I. INTRODUCTION (Unit 2)

The LaSalle County Nuclear Power Station is a two-uait facility owned by Commonwealth Edison Company and located near Marsellies, 111thols. Each unit is a Boiling Hater Reactor with a designed not electrical output of 1078 Hegawatts. Haste heat is rejected to a man-made cooling pond using 1 the Illinois River for make-up and blowdown. The architect-engin;er was l Sargent and Lundy and the primary construction contractor was Cornonwealth Edison Company.

Unit Two was issued operating Itcense number NPF-18 on December 16, i 1983. Initial criticality was achieved on March 10, 1984 and commercial l power operation was commenced on June 19, 1984. )

\

This report was complied by Michael J. Cialkovski, telephone number (815)357-6761 extension 2427.

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II. MONTHLY REPORT A. SLM MRY OF OPERATING EXPERIENCE (Unit 2)

DAY lime .EYent 1 0000 Reactor critical, Generator on-line at 1115 Hve (power level held due to high vibrations on the

  1. 11 Main Turbine bearing).

2 2200 Increased power level to 1125 Hve.

7 0030 Reduced power level to 1115 Hwe due to high vibrations on the Main Turbine.

8 0600 Increased power level to 1125 Hwe.

10 0030 Reduced power level to 850 Hwe. to perform monthly and quarterly surveillances.

1000 Increased power level to 1125 Hwe.

15 0300. Reduced power level to 1050 Hwe due to system load.

0600 Increased power level to 1115 Hve.

16 0100 Reduced power level to 950 Hwe due to system load.

1100 increased power level to 1120 Hwo.

17 0230 RedLc 1 power level to 985 Hve due to the 231A and 2318 switchgears tripping off-line.

1000 Increased power level to 1125 Hve.

0130 Reduced power level to 850 Hwe due to system load.

1100 Increased power level to 1120 Hwe.

20 0100- Reduced power level to 1050 Hwe due to system load.

21 0100 Reduced power level to 830 Hwe due to system load.

1300 Increased power level to 1095 Hwe.

22 0100- Reduced power level to 850 Hwe due to system load.

1400 Increased power level to 1095 Hwe.

0100 ' Reduced power level to 850 Hve due to system load.-

0900 Increased power level to 1095 Hwe.

24- 0300 Reduced power level:to 940 Hwe due.to system load.

ZCADTS/7-

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' II. MONTHLY REPORT

' A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 2) '(CONTINUED) i' Q1y- Event 113f1 0800 Increased power level to 1075 Mwe.

25 0000 Reduced power level to 850 Mwe due to system load.

0900 Increased power level to 1095 Mwe.

2000 Reduced power level to 835 Mwe due to system load, placed the '2B' Turbine Driven Reactor feed Pump of f-line.

26 1000 Increased power level to 1020 Mwe.

27 .0030 Reduced power level to 850 Mwe due to system load.

.1130 Increased power level to 1000 Mwe.

28 0400 Reduced power level to 850 Hwe due to syctem load.

29 1600 Increased power level to 1120 Mwe.

30 0200 Reduceo power level to 850 Mwe due to system load.-

1300 Increased power level to 1120 Mwe.

2400 Reactor critical, Generator on-line at 1115 Hwe, power. level reduced to due system load.

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. D. AHt'NDriNTS TO Tile FACILITY LICENSE OR TECHNICAL SPEC'FICATION _

(Wone.)

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

(Sea Table 1)

D. LICENSEE EVENT REPORTS (Unit 2)

LER Number p_tig pescription 92-007-00 06/13/92 Automatic startup of ti.e 'B' Control Roon./ Auxiliary Electric Equipment Room HVAC Eme genty Make Up Train.

92-008-00 06/15/92 During perf ormance of an inservice test, the breaker for-valve 2E51-F086 tripped on thermal overload.

E. DATA TABULATIONS (Unit 2)

1. Operating Data Report.

(See Table 2)

2. Averace Daily Unit Power Level.

(See Table 2)

3. Unit Shutdowns and Significant Power Reductions.

(See Table 4)

ZCADTS/7

C. . TABLE.1 (Unit 2) .

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t C OR CORRECTIVE MAINTENANCE-TO

  • SAFETY-RELATED EQUIPMENT RESULTS AND EFFECTS NORK sEQUEST COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION TRRECTIVE ACTION NUMBER L13879 Control Room HVAC Damper actuator 0FZ-VC047A. Actuator failed to open damper. Replaed actuaior.

'beper OVC11YB Reactor Core Isolation 74 relay. Inaccurate alarm. Replaced relay.

L15084 Cooling Isolation Valve IE51-F019 l

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l (No SOR Failures this month.)

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TABLE 2 o & *

  • E.1 OPERATING DATA REPORT I* *

" L DOCKET NO. 0$0-373 UNIT LASALLE TWO DATE July 10, 1992 COMPLETED BY M.J.CIALKOWSKI

'OPERATINO STATUS TELEPHONE (815) 357-6761 e i

  1. l'. REPORTING PERIODt June 1992 i GROSS HOURS IN REPORTING PERIODI 720
2. CURRENTLY AUTIIORIZED POWER LEVEL (MWt): 3,323 MAX DEPENDABLE CAPACITY (MWe-Not): 1,036

' DESIGN ELECTRICAL RATING (MWe-Met): 1,078 I

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

'4,' REASON FOR RESTRICTION (IF-ANY):

THIS MONTH YEAR TO DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 720.0 2,017.2 46,953.1 6 REACTOR RESERVE Sif0TDONN TIME (HOURS) 0.0 0.0 1,716.9
7. - GENERATOR ON-LINE TIME (IIOURS) 720.0 1,855.4 46,059.9
8. UNIT RESERVE SifUTDOP s TIME (110URS) 0.0 0.0 0.0
9. ' TIIERMAL ENERGY GENERAhD (MWHt) 2,232,095.0 5,456,772 137,699,171
10. ELECTRICAL ENERGY GENERATED (MNile-Gross) 764,700.0 1,858,324 45,748,074 s 11. ELECTRICAL ENERGY GENERATED (MWile-Net) *i38,424 1,764,992 43,896,496
13. REACTOR SERVICE FACTOR (%) 100.0 46.2 69.5 1

113. REACTOR AVAILABILITY FACTOR (%) 100.0 46.2 72.1

14. UNIT SERVICE 1 ACTOR (%) 100.0 42.5 68.2
15. UNIT AVAILIDILITY FACTOR (%) 100.0 42.5 68.2
161 UNIT CAPACITY FACTOR (USING MDC) (%) 99.0 39.0 62.8 17'.1 UNIT CAPACITY FACTOR (USING DESIGN MWe) 95.1 37.5 00.3 18'.LUNIT FORCED OUTAGE FACTOR (%)-

0.0 5.2 12.8

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y 19. SHUTDOWNS SCIIEDULED OVER THE NEXT 6 MONTHS (TYiE, DATE, AND DURATION OF EACH):

t L20. IF SHUTDONN'AT END OF REPOR'T PERIOD, ESTIMATED DATE OF STARTUP:

, . ... . .. . . . . - _ _ ___ . . ._ - - .~ . _ . . . . . - _ > _ _ .m _-. _ _ _ _ _ _ _ . _ _ . . ..-._m

,, - . TABLE 3_

E.2' AVERAGE DAILY UNIT. POWER LZVEL (MWa-Net)

DOCKET NO. 050 373 UNIT LASALLE TWO DATE July 10, 1992 COMPLETED BY M.J. CIALKOWSK1 TELEPHONE (815).357 6761 REPORT PERIOD: June 1992 DAY POWER DAY POWER

,- 1- -1,069- 17 1,058 2 1,069 18 1,000 3 1,084 19 1,056 4- - 1,084 20- 1,004 5 1,085' 21 950

.6_ 1,082 22 956  :

L 7' - 1,080 23 972 8 - 1,082 24 1,006

_9' _ 1,075 25 -917 10 1,020 26_ 930 11- - 1,081. . 27 918 1; :1,079 28 841 ,

13- '1 074

, 29 992

. 14- 1,074 30 994

'15 1,073: 31-

- 16 l 1,063 u

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C E.3- . IPTIT. SETIDOIERS AND PONEP EEDUCTIONS >20% ,

(UNIT 2) .

I METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DONE ACTIONS /COsedEETS SEQUENTIAL DATE-- F:~ FORCED DURATION- THE REACTOR OR (LER/DVR # if EUMBER (TDeGDD) S: SCHEDULED (HOURS) . RECON REDUCING PONER applicable)

~(None.)

SUte4ARY OF OPERATION:-

Th2 unit' remained.on line at high power throughout the month. Several minor power reductions were required due to system loading and maintenance activities.

ZCADTS/7.

a ^ o 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. Hajor changes to Radioactive Haste Treatment Systems.

(None.)

5. Indications of failed fuel Elements.

(None.)

-ZCADTS/7

.- ._ _., - . , - - --v - , . .

' n /s c (Unit 2)

Table 5 f.2 ECCS System Outages Note: The year and unit data has been removed from the outage number.

OUTAGE N(L. [QUIPHENT L M DSI 1796 2E22-5001 Remove and repair thermocouple.

1810 i 1814 2DG09DB Air dryer calibrations.

1820 2E51-C004 Pump motor inspection.

1821 2E51-F019 Replace 74 relay.

1828 2E51-F080 Administrative control.

1851 2E12-F4110 Inspection, adjust limit switches.

1852 1853 2DG08CA Air compressor suction and discharge valve inspection.

1856 2DG08CB Air compressor suction and discharge valve inspection.

1859 2DG01K Rewire annunciator logic.

ZCADTS/7 t

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