ML20087B344

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Monthly Operating Repts for Dec 1991 for LaSalle County Nuclear Power Station,Units 1 & 2
ML20087B344
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 12/31/1991
From: Cialkowski M, Diederich G
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9201130094
Download: ML20087B344 (24)
v • d • e


Text

,

N C:mm:nw:alth Edison

. . = b tocane county Noticar station

.- ' RuralRoute si, Don ?20

'a Marsed!es, Ilhno's 61341

} leierhone 815/357 6761 January 6. 1992 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Comission Hall Station P1-137 Hashington, D.C. 20555 ATIN: Document Control Desk Gentlemen:

Enclosed for your information is the monthiy performance report covering LaSalle County Nuclear Power Station for Decembcr, 1991.

Very truly yours,

'* l-r-R K.

i,\

WM J.

[grG. fir Diederich J Station Hanager LaSalle County Station GJD/HJC/dj f i

Enclosure xc: A. B. Davis, NRC, Region III T. H. Tongue, NRC Resident Inspector LaSalle J. L. Roman, IL Dept. of Nuclear Safety J. B. Hickman, NRR Project Manager D. P. Galle, CECO D. L. farrar, CECO INPO Records Center D. R. Eggett, NED J. E. Kuskey, GE Resident T. J. Kovach, Manager of Nuclear Licensing H. F. Naughton, Nuclear fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor J. H. Gieseker, Technical Staff Supervisor H. H. Servoss, QA/NS Off Site Review Station File

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1 LASALLE NUCLEAR POWER STAi/0N UNIT I MONTHLY PERFORMANCE REPOR1 DECEMBER 1991 COMMONHEALTH EDISON COMPANV NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 2CADTS/S

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7 TABLE Of CONTENTS (UNIT 1)

1. INTRODUCTION II. REPORT A. SUP04ARY Of OPERATING EXPERIENCE B, . AMENDMENTS TO FACILITY LICEFE OR TECtlNICAL SPECIFICATIONS C. MAJOR CORRECTIVE MINTENANCE TO SAFETY-RELATED EQUIIHENT D. LICENSEE EVENT REPORTS E. DATA TABULATIONS
1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions F. UNIOUE REPORTING REQUIREMENTS
1. Main Steam Relief Valve Operations
2. ECCS System Outages
3. Off-Site Dose Calculation Manual Changes
4. Major Changes to Radioactive Maste Treatment System
5. Indications of failed fuel Elements i-l-

u

(

l

-- ZCADTS/S

. ..- i J. '

-I. INTR 000C1 ION (Unit 1)

The LaSalle County Nuclear Power Station is a two-unit. facility owned by- j Co' m nwealth Edison Company and located near Marseilles, Illinois. Each unit ts a Bolling Hater Reactor with a designed net electrical output ot 1078 Megawatts.. Waste 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 cnd the primary construction-contractor was '

, enmar.nwealth Edison Company.

Unit Onelwas-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 Ja.uary 1= 1984.

i This report was corapiled by Michael J. Cialkowski, telephone number

(815)357-6761', extension 2427.

i A

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i ZCADTS/5-

. .)

~

11. MONTHLY REPORT- l

-- A . - StH4ARY 0F OPERATING EXPERIENCE (Unit 1) ply J_teg Event _

1- 0000 Reactor critical, Generator on-line at 1130 Mwe.

4- 0100 Reduced power level to 1020 Hve to perform maintenance

-on the '15A' Heater Drain Valve and to transfer the-lleater Drain Pumps. -

1100 Increased power level to 1135 Hwe.

7 0100 Redui;ed power level to 1000 Hve to transfer the ,

Hester Drain Pugs and to cycle the #4 Turbine Control Valve.

1100 Increased power level to 1135 Mwe.

-10 0200 Reduced pcwer level to 1110 Hwe due to system load.

0700 Increased power level to 1130 Mwe. ,

'1100 Reduced power level to 1075 Mwe-to transfer the Condensate / Condensate Booster pumps.

1900 Increased power level to 1130 Mwe. -

13:

1500 Reduced power level to 1080 Mwe to transfer the Heater Drain Pumps.  ;

r 1600 In:reased power level to 1135 Mwe.

14 .0100 Reduced power level to 990 Hwe_due to system load.

0230 -Increased power level to 1135 Mwe.

17 0030 Reduced power level to 1000 Mwe 'to perform weekly and monthly surveillances.-

0800- Increased power level to 1115 Mwe.

0930 Reduced power 1evel to'1075 Hwe to transfer the Heater Drain pumps.

1400 Increased power level to 1130 Mse, f

ZCADTS/5'

}I.--HONTHLY REPORT (CONTINUED) -j A; SlMMRY OF OPERATING EXPERIENCE (Unit 1) day Jjn Event 21- _1200 Reduced power level to 890 Mwe due to system load.

22 2200 Increased power level to 1135 Hve.

24 2200 Reduced power level to 850 Mwe due to system load.

25 1200 Increased power level to 1135 Hve.  ;

i Reduced power level to 880 Hwe due to system loao.

26 0030 ~

1000 Increased power level to 1135 Hve.

27 0300 Reduced power level to 870 Hve due to system load.

1000 Increased power level to 1130 Mwe.

28 0130 Reduced power level to 870 Hwe due to system load.

1000 Increased pc,wer level to 1130 Mwe.

29- 0030. -Reduced power leve1 ~ to 850 Ma , due ta system load.

1600 -Increased power leval to 1130 Hwe.

30. 0100 Reduced power level to 950 Hwe due to system load.

1200. Increased power level to 1130 Mwe.

2400 Reduced power invel to 1000 Mwe due to system load. _;

31 1000 Increased power level to 1130 Mwe.

2200 Reduced power level. to 930 Mwe due to system load.

2400 Reactor critical, Generator on-line at 930 Mwe, t

[

l ZCADTS/5- .

4

, , S. AMENDMENTS TO THE FACILITY LICENSE OR TECHNICAL SPECIFICATION l

  • Amendment to Technical Specifications to allow continuous bypass device for valve IE22-f01S.

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

(See Table 1)

D. LICENSEE EVENT REPOR15 (Vait 1)

LER Number plig D31crjp11gn (None.)

E. DATA TABULATIONS (Unit 1)

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

ZCADTS/S l

C. TABLE 1 (Unit 1)

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIFHENT HORK REQUEST' RESULTS AND EFFECTS N'JMBER COMPONENT CAUSE OF MALFUNCTION 01 SAFE PLANT OPERATION CORRECTIVE ACTION L10681 '1B' Diesel Generator Air compressor sensing None. Replaced sensing line.

Air Starter line.

LiO682 'IB' Diesel Generator Air start rotor inlet None. Replace isolation valve.

Air Starter ~ isolation valve.

L12080 Post LOCA Hydrogen Hydrogen regulator. 10-12% oxygen indication during Replaced hydrogen Oxygen Monitoring drywell sampling. regulator.

Panel IPL77J (No SOR Failures this month.)

ZCADTS/5+

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TABLE 4 E3 UNTT SHUIDOHNS AND P0HER REDUCTIONS > 207.

(Unit 1) ,

i McTIO) 0F CORRECTIVE-SHurTING 00HN ACTIONS /COPMENTS YEARLY TYPE F: FORCED DURATION THE REACTOR OR (LER/DVR # if SEQUENTIAL DATE (HOURS) REASON REDUCING POWER appilcable)

NUMBER (YY>HDD) S: SOIEDULFD (None.)

SUMMARY

OF OPERATION:

The Unit remained on-line at high power throughout the month. Several minor power reductions were required due to systco loading, maintenance activities and routine surveillances.

l l

ZCADTS/5

4 F. UNIQUE REPORTING REQUIREMENTS (Unit 1)

1. Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIPTION DAIE 6CTUNiED AClV6110N CDhDil108 0F EVENT (None)
2. ECCS System Octages (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.

(Nore) e i

ZCADTS/S  !

L - -.

(Unit 1)

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

GHAGE NO. EmilfMEM EVEf95E (U-0) 2096 00G01K Replace soak back oil filter, 2098 00G0lK Replace temperature switch.

(ti-1) 2100 1E51-C001 Inspection.

2110 1E22-S001 Repair oil and air line leakagt 2114 IE22-S001 Replace soak back oil filter.

2CADTS/5+

3 LASALLE HUCIEAR POWER STATION UNIT 2 HONTHLY PERFORMANCE REPORT

^'

DECEMBER 1991 COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 j'

l ICADTS/7 m____________________________________________

t 8

i TABLL' 0F CONTENTS (Unit D

m. ~

- I. INTRODUCTION-II. REPORT

. .A.- : StM4ARY OF QPERATING EXPERIENCE

~

B. . AMENDNENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICAT10NS

.C. MAJOR' CORRECTIVE MAINTENANCI TO SAFETY-RELATED EQUIIHENT

' D.- LICENSEE EVENT RFPORTS E.. DATA-TABULATIONS

1. Operating Data Report.

~

2. . Average Daily Unit Power Level  !
3. Unit. Shutdowns and Power Reductions F. -_Ud100E REPORTING REQUIREMENTS
1. - Safety / Relief Valve Operations
2. ECCS. System Outages
3. Of f-Site Dose Calculation Manual Changes
4. Major Changes to Radioactive Haste Treatment System T 5. -- Indications of' Failed fuel Elements l

0

.I

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'ZCADTS/7.

I. INTRODUCTION (Ur.it 2)

The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Harseilles, Illinois. Each anit is a Boiling Hater Reactor with a designed net electrical output of 1078 Hegawatts. Haste heat is rejected to a man-made cooling pona using the Illinois River for make-up and blowdown. The architect-etf neer was Sargent and Lundy and the primary construction contractor ~,es Commonwealth Edison Company, Unit Two was issued operating license number NPF-18 on December 16.

1983. Initial criticality was achieved on March 10, 1984 and commercial power operation was commenced on June 19, 1984.

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

ZCADTS/7

- II. MONTHLY REPORT

, A.. T/M4ARY OF= OPERATING EXPERIENCE (Unit 2) t

Q&Y Ilme Event ,

1 0000 Reactor _ critical. Generator on-line at 1123 Nwo.

3 0000 Core thermal power at 98.5%, all control rods

-withdrawn, commencing coastdown.

8 :0100 Reduced power level to 1080 Mwe-to transfer the Heater Drain Pumps. ,

0400 Increased power level to 1095 Hwe.

18 0030_ Reduced-power level to 850 Mwe due to system load.

0700 Increased power level to 1095 Hve.

25 1500 Reduced power level to 900 Mwe to remove the '2A' Turbine Driven Reactor Feed Pump from service and '

place the Motor Driven Reactor feed Pump in service, 1815 Increased power level to 960 Hwe (power level held due to the '2A' Turbine Driven Reactor feed Pump being out of -service).

29: 1100- Increased power _ level to 1015 Mwe('2A' Motor Driven Reactor Feed Pump placed in-service).

30 2300- Reduced power. level to-900 Nwe due to system load.

131 0800 Increased power level to 1000 Mwe.

2400 Reactor critical, Generator on-line at 995 Hwe. $

d} '

+

ZCADTS/7 ,

y I - - - . . . . . - - - . - . , ,. .- ,

9

, D. AMENDMENTS TO THE FACILITY LICENSE OR TECHNICAL SPECIFICATION Amendment to Technical Specifications to allow continuous bypass device for valve 2E22-f015.

C. MAJOR 00RRECTIVE MAINTENANCE TO SAFETY RELATED EQUIPHENT (including SOR differential pressure switch failure reports).

(See Table 1)

D. LICENSEE EVENT REPORTS (Unit 2)

LEllymher Date Description (None.)

E. DATA TABULATIONS (Unit 2)

1. Operating Data Report.

(See Table 2) 2 Average Daily Unit Power Level.

(See Table 3)

3. Unit Shutdowns and Significant Power Reductions.

(See Table 4)

ZCADTS/7 l

C .- TABLE:1l(Unit'2).

MAJOR CORRECTIVE MAINTENANCE TO

. SAFETY-RELATED EQUIPMENT. .

HORK. REQUEST :RESULTS fMD EFFECTS

N'JMBER - COMPONENT CAUSE OF MALFUNCTION 'ON SAFE PLANT OPERATION- CORRECTIVE ACTION- l Low pressure alarm failed'to Lil660 '2B' Residual Heat Pressure switch. .F.eplaced pressure Removal Pump Discharge. reset. switch.

4 L12047 Control-Room HVAC Detector drive motor. Improper alars indication.: Replaced drive motor.

Annonia Detector '

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i (No SOR, Failures this month.) .

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TABLE 4 E.3 UNIT SHUTDOWNS AND POWEE REDUCTIONS >20% .

(UNIT 2)

METHOD OF CORRECTIVE YEARLT TYPE SHUTTING DOWN ACTIONS / COMMENTS

, SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR I if NY7MBER m (YYMMDD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable)

(None.)

SUMMARY

OF OPERATION:

The unit remained on-line at high power throughout the month. Several minor power reductions were required due to system loading, maintencnce activities and routine surveillances.

ZC4DTS/7

m

. F. UNIQUE REPORTING REQUIREMENIS (Unit 2)

1. Safety / Relief Valve Operations VALVES NO & 1TPE PLANT DESCRIPTION DAIE ACEjalfp ACTUATIQNS CONDITION QElyJNT (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)

ZCADIS/7

(Unit 2)

Table 5 f2 ECCS System Outages Note: The year and unit data has been removed from the outage number.

OUTAGE N(L. EOUIPMENT PURPOSE 179 2 E21..f 012 Repack valve.

2114 2E21-C001 Votes test valve 2DG035.

2131 2E12-f087A Installation of Votes test sensor.

2150 2DGOBCA Valve inspection.

2156 2DG01K 2DG01P pump inspection.

2158 2DG0lK Heter calibrations.

2161 2DG0lK Replace soak back oil filter.

2162 2DG0lK Repack valve.

2173 2E12-C002A Lubrication.

2180 2E22-S001 Meter calibrations.

2181 2182 2E22-S001 Repair fuel line and starting air s.ys t em.

2217 2E12-f048A Administrative control.

ZCADTS/7

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