ML20100Q465

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Monthly Operating Repts for Feb 1992 for LaSalle County Nuclear Power Station,Units 1 & 2
ML20100Q465
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 02/29/1992
From: Cialkowski M, Diederich G
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9203160252
Download: ML20100Q465 (24)
v • d • e


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Commonweith Edison I* Lasalle Count) Nucleat Station 2601 N. 21st. M Marse 4Ws, IllinoiW 61341 Telephone 815/357 6761 March 10, 1992 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Comission Hall Station PI 137 Hashington, D.C. 20555 ATiti Docuinent Control Desk Gentlemen:

Enclosed for your information is the acnthly performance report covering LaSalle County Nuclear Power Station far February, 1992.

Very truly yours,

( G. J. Diederich q'c(Station Manager LaSalle County Station GJO/HJC/dj f Ent'40sure xt: A. B. Davis, NRC, Region III D. E. Hil'Is, HRC Resident Inspector LaSalle J. L. Roman, IL Dept. of Nuclear Safety B. Siegel, NRR Project Manager D. P. Galle, CECO D. L. Farrar. CECO INio Records Center D. R. Eggett, NED P. D. Doverspike, GE Resident

  • T. J. Kovach, Manager of Nuc. lear 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 1 Station File .I y

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LASALLE NUCLEAR P0HER STATION ,'

UNIT 1 VONTHLY PERFORMANCE REPORT FEBRUARY 1992- ,

00MHONHEAliH EDISON COMPANY NRC DOCKET NO. 050-373 s

LICENSE NO, NPf-11 a

2CADTS/S J G ____

e TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION II. REPORT A. TJMMARY OF OPERATING EXPERIENCE B. AHENDMENTS TO FACILITY LICEdSE OR TECilNICAL SPECIFICATIONS C. MAJOR CORRECTIVE MAINTEhANCE TO SAFETY-RELATED EQUIPMENT

0. LICENSEE EVENT REPORTS E. DATA TAWLATIOF
1. Operating data Report 2 ., Average Daily Unit Power level -
3. Unit Shutdowns and Power Reductions  ;

F. UNIQJE REPORTING REQUIREMENTS

1. Main Steam Relief Valve Operations 1
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 l

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1. INTR 000CTION (Unit 1)

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

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

Initial critichilty was achieved - on June 21, 1982 and commercial power operation was co m enced on January 1, 1984.

This report was commiled by Michael J.- Cialkowski, telephone-nus.ber (915)357-6761, extension 2427.

ZCADTS/5

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4 J1. MONTl!LY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE ('Jnit 1)

P3.Y I.imit EYfnt 1 0000 Reacter critical, Generator on-line at 1130 Mwe.

3 0030 Reduced power level to 1000 Mwo due to system load.

0900 Increased power level to 1130 Mwe.

4 0100 Reduced power level to 850 Mwe due to system load, l performed Turbine Control Valvo cycling. j i

0700 Increased power level to 1125 Mwe. 1 5 0100 Reduced power level to 865 Hwe due to system load.

1000 Increased power level to 1130 Mwe.

10 0100 Reduced power level to 900 Hwe due to syste9 load.

1000 Increased power level to 1130 Hwe.

2330 Reduced power level to 950 Mwe to perform Turbine Control Valve testing and Reactor Protection monthly surveillances.

Il 0900 Increased power level to 1130 Mwe. I 17 0200 Reduced power level to 1030 Mwe due to system load.

0900 Increased power level-to 1130 Mwe.

18 0130 Reduced power level to-950 Mwe to perform monthly surveillance on the # 4 Turbine Control Valve.

1000 Increased power level to 1130 Mwe.

20 0300 Reduced power level to 880 Mwe dwa to system load.

2000 Increased power level to-1130 Mwe.

22 1500 Reduced power level to.850 Mwe due to system load.

23 1800 _ Increased power level to 1130 Mwe.

25 0100 Reduced power.lovel to 1000 Mwe due to system load,-

performed Reactor Protection Monthly surviellances.

-1000 Increased power level to 1130 Hwe.

29 2400 Reactor critical, Generator on-line at 1130 Mwe.

D., AMENDMENTS TO Tile FACILITY LICENSE OR TEGINICAL SPECIFICATION Amend Division 3 battery specifications for float voltage and specific gravity.

C. MAJOR CORRECTIVE MAINTENANCE 10 SAFETY-RELATED EQUIPMENT (including SOR differential pressure switch failure reports).

(See Table 1)

D. LICENSEE EVENT REPORTS (Unit 1)

LEILEVder Daic DeicIlation (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) l s

ZCADTS/S

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4 C. TABLE 1 (Unit I)

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-AELATED E(yJIPHENT .

-HORK REQUEST RESULTS AND EFFECTS MJMBER COMPONEE CAUSE OF PALFUNCTION ON SAFE P!AMT OPERATION CORRECTIVE ACTION LO2393 'B' Control Room HVAC Differential pressura Dimper cycled repeatedly during Recalibrated pressure Retura Fan Isolatier, switch OPDS-VC051 surveillance testing. switch.

Damper OVC15YB

]

, Li2959 S:spression Pool Mater RTO input module. Inaccurate temperature readings. Replaced RTD input module.

Bulk Teeperatura Mcatter IUY-CH037 L13469 Suppression Dool Clean 'A' phase moveable arcing None. Replaced contact.

, Up ani: Transfer Puae contsct cracked.

. ISF01PB L13745 -C_ontrol Rocs HVAC Braken c&ssette carrier. Detector Inoperable. Replaced cassette carrier. ,

,t,emonia Octector OKf-VC125A (No SOR Failures this' month.-)

ZCADTS!5+

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t TAPLE 2

. E.1 OPERhTING DATA REPORT l DOCKET NO. 050-373 UNIT LASALLE ONE i DATE March 10,1992 .

COMPLETED BY M.J.CIALKOWSKI OPEFATING STATUS TELLTHONE (815) 057-6761

1. REPORTING PERIOD: February 1992 l CROSS HOURS IN REPORTING PERIODt 696
2. CURREPTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPENDABLE CAPACITY (MWe-Net): 1,036  !

DESIGN ELECTRICAL RAT 1HG (MWe-Not): 1,078

3. PCWER LEVEL SV WHICH RESTRICTED (IT ANY) (HWe-Not) N/A
4. REASON FOR R2STRICTION (IF ANY)2 THIS MONTH YEAR TO DATE CUMULATIVE' 5< REACTOR CRITICAL TIME (HOVR$) 696.0 1,410.0. 48,796.5
6. REACTOR AESERVE SHUTDOWN TIME (HOURS) 0.0 0.0. 1,641.2
7. CENERATOR ON-LINE TIME (HOURS) 696.0 1,440.0 ,

47,818.4 W. UNIT RESERVE SHUTDOWN TIME (HOURS) -0.0 0.0 1.0-

9. THERMAL ENERGY GENERATED (HWHt) 2,263,836 4,673,011 139,829,990 1
10. ELECTRICAL ENERGY GENERATED (KWHo-Cross) 774,066 1 599,080 46,688.852 <
11. ELECTRICM. ENERGY GENEDATED (HWHe-Net) 753,594 3,554,424- 44,749,569
12. REACTOk SERVICE FACTOR'(%) 100.0 100.0 68.2
13. REACTOR AVAILABILITY FACTOR f.%) 100.0 100.0 70.5 .

t i 14. UNIT SERVICE FACTOR (%) 100.0 100.0 66.8

15. UNIT AVAILISILITY FACTOR (t) 100.0 '100.0 66.8 l
16. UNIT CAPACITY FACTOR (USING MDC) {t) '104.5 104,2- 60.3
17. UNIT CAPACITY FACTOR.(USINO DESIGN HWe) 100.4 100.1 58.0
18. Uf11T FORCED OUTAGE' FACTOR (%) 0.0 0,0 7.4 l
19. SHUTDOWN $ SCHEDOLED OVER THE NEXT 6 MONTHS-(TYPE, DATE, AND DURATION'OF EACH) -
20. IF. SHUTDOWN-AT.END OF-REPORT PERIOD,-ESTIKATED DATE OF'STARTUP:

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TABLE 3 E.2 4

AVERAGE DA2LY UNIT POWER LEVEL (HWa Net)  !

, DOCKET NO. 050-373 i

UNIT LASALLE ONE l DATE Harch 10, 1992

COMPLETED BY H.J. CIALKOWSKI TELEPHOUE (815)-357-6761 i

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REFORT PERIODt Harch 1992 i

l OAY POWER DAY POWER {

1 1,100 17 .1,099

_ 2 1,106 18 1,064 {

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3 1,071 19 1,105 4 1,043 30 1,060 S 1,044 21 1,103 ,

6 1,105 22 989 ,

3 7 1,106 P3 998 8 1,103 24 1,094 9 1,105 25 1,039 i

10 1,044 26 1,100 -

+

11 1,069. 27 1,101 +

12 1,108 2B- - ",101 13 1,109 29 1,102 j 14- 1,110- 30 15 - 1,109_ 31. -

16 1,106 1

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p TABLE

  • E.3 UNIT SHUTDOHNS AND M ? r E CTIONS > 201 j (Uni; ?

i I

METHOD OF CORRECTIVE i YEARLY TYPE SHUTTING DOHN ACTIONS /CDPMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if '

NIMBER (YY)MDD) S: SCHEDULED (HOURS) REASON REDUCING PONER applicable)

(None.)

St9 MARY OF OPERATION:

The Unit remained on-line at high power throughout the month. Several minor power reductions were required due to systes loading.

't 1

l ZCADTS/S

_.____________-__-________-.mu.-

f. UNIQUE REPORTING REQUIREMENTS (Unit 1)
1. Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIPTION DAIL ACTUATEQ ACTUATION CONDIT10!i Of_ EVENT I.None)
2. ECCS System Outages (See fable 5)
3. Changes to the Off-Site Dose Calculation Manual i (None.)
4. Major changes to Radioactive Haste Treatment Systems.

(None.)

5. Indications of Failed fuel Elements.

(None.)

5 ZCADTS/5

1 (Unit 1)

. Table 5 b

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

QUlAGLtE LOUIPMENT PURPOSE (U-0) 1 0079 ODG01K Administrative control during Unit 2 output breaker testing.

(U-1) 0067 IE12-C300A Pump lubrication.

IE12-C3000 0120 1DG01P Pump lubrication.

10001P ZCADTS/5+

LASALLE NUCLEAR POWER $1ATION tl NIT 2 MONTHLY PERFORMANCE REPORT FEBRUARY 1992 COMMONHEALTH EDISON COMPAfiY NRC DOCKET NO. 050-374 LICENSE NO. NPT-18 i

ZCADTS/7

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

d 4

TABLE OF CONTENTS (Unit 2)

1. INTRODUCTION II. REPORT A. SUMARY Of OPERATING EXPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICA110NS C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUllHENT ,

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. Safety / Relief. Valve Operations *
2. ECCS System Outages
3. Off-Site Dose Calculation Manual Changes ..
4. Major Changes to Radioactive Mcste Treatment System
5. Indications of Failed fuel Elements

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ZCAD_TS/7 _ _ _

I. INTRODUCTION (Unit 2)

The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marseilles. Illinois. Each unit is a Boiling Water Reactor with a designed not electrical nutput 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 Comonwealth Edison Company.

Unit Two was issued operating license number NPT-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and commercial power operation was comenced on June 19, 1984.

This report was compiled by Michael J. Claikowski, telephone number (815)337-6761 extension 2427.

ZCADTS/7 t

I

. II. MONTHLY REPORT I r

. A.

SUMMARY

Or OPERATING EXPERIENCE (Unit 2)

Time Day Eve nt..  ;

1 0000 Reactor suberitical, Generator off-line, l Refuel outage (L2R04) in progress.  ;

29 2400 Reactor suberitical, Generator off line, Refuel outage (L2H04) in progress.  ;

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O. AMENDHENTS TO Tile FACILI1Y LICENSE OR TEGINICAL SPECIFICATI(Q Amend Division 3 battery specifications for float voltage and specific gravity.

C. KAJOR 00RRECTIVE MAINTENANCE TO SAFETY RELATED EQUIPHENT (including ,

SOR differential pressure switch failure reports). I (See Table 1)

D. LICENSEE EVENT REPORTS (Unit 2)

LER_Humber Dale unscription l 92-002-00 02/26/92 A spurious Division I ECCS initiation was received when a false low level signal was sensed due to a pressure spike on the reference leg.

92-003-00 02/28/92 During the 0 Diesel Generator response time test, the Unit 2 output breaker (ACB 2413) failed to close during a simulated under-voltage on bus 241Y.

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 Pover Reductions.

(See Table 4) l l

l ZCADTS/7

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1 C. TABLE 1 (Unit 2) l MAJOR CORRECTIVE MAINTENANCE TO -

SAFETY-RELATED EQUIPMENT -

t i WORK REQUEST RESULTS AND EFFECTS l NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION i i

i Diesel Generator Cylinder head there couple. Inaccurate cylinder head LOO 514 Replaced thermocouple.

Cylinder Head temperature indications.

j Temperature i

i L11883 Main Steam Line Low Pressure switch vent valve None. Replaced valve stem.

i Pressure Switch- leaking.

l 2B21-N0158- i

[

i L12667 . Standby. Gas Treatment Differential pressure Inaccurate pressure indication. Replaced indicator.  !

' System Moisture indicator.  !

! Separator Differential  !

. Pressure  !

I i i

, .L13174 High Pressure Core; Pressure switch 2E22-N513. Erratic switch actuation. Replaced pressure switch.

. Spray Diesel Generator Lube Oil Low Pressure L13269 Diesel Generator left Pressure gauge 2PI-DG098A. Improper pressure indication. Replaced pressure gauge.

Bank Air Supply-

/L13293 High Pressure Core Temperature switch Mone. Replaced temperature 'I Spray Diesel Generator 2E22-N516. switch. 1 Cooling Mater Hot I

Engine Temperature'

. l L133% High Pressure Core- HFA relay. Intermittent grounds. Replaced HFA relay. .

Spray Diesel Generator i i i I 3 i -

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+ ZCADTS/7- I l

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i C. TABLE 1 (Unit 2) -CONTIQED .[

t j MAJOR CORRECTIVE MAINTENANCE TO ['

j: SAFETY-RELATED EQUIPMENT -

i MORK REQUEST RESULT 3 AND EFFECTS ,

IUSER COMPONENT CAUSE nF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION t t

i- i I

] L13446 Hydraulic Control Unit Pressure switch Pressure switch failed during Replaced pressure switch.

Accumulator 58-39 2C11-N138PS surveillance testing.

i L13456 Low Pressure Core Pressure switch. Switch was found out of Replaced switch.

. Spray Minimum Flow tolerance. '

! 'L13653

. Hydraulic Control Nitrogen block valve None. Replaced va've cartridge.

, Unit 38-47 leaking. t

L13670 Suppression Chamber Packing leak. None. Performed packing adjust.

1- Spray Stop Vcive i 2E12-F027A i

! i i .i i.

, (No SOR Failures this month.)

j .ZCADTS/7-

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TABLE 3 E.1 OPERATaNG DATA REPORT ,

DOCKET No. 050-373 UNIT LASALLE TWO DATE March 10,1992 COMPLETED BY M.J.CIALKOWSKI OPERATING STATUS TELEPHONE (815) 357-6761 )

1. REPORTING PERIOD GROSS HOURS IN REPORTING PERIOD: l
3. CURRENTLY AUTHORIEED POWER LEVEL (MWt): 3,323 MAX DEPENDABLE CAPACITY (MWe-Net): 1,036 DESIGN ELECTRICAL RATING (MWe-Net): 1,078
3. POWER LEVEL TO WHICH RESTRICTFD (IP ANY) (MWe-Net): N/A
4. REASON FOR RESTRICTION (IF ANY):

THIS MONTH YEAR TO DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 0.0 84.0 45,019.8
6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.C
7. GENERATOR ON-LINE TIME (HOURS) 0.0 73.9 44,278.5
8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0
9. THERMAL ENERGY GENERATED (MWHL) 0.0 180,986 132,423,385
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 0.0 64,274- 43,954,024
11. ELECTRICAL ENERGY GENERATED (MWHe-Net) -7,682 46,479 47,177,983
13. REACTOR SERVICE FACTOR (%) 0.0 5.8 69.7 i 13. REACTOR AVAILABILITY FACTOR (%) 0.0 5.8 72.4 l

i

14. UNIT SERVICE FACTOR (%) -0.0 5.1 68.6
15. UNIT AVAILIBILITY FACTOR (%) 0.0 5.1 68.6
16. UNIT CAPACITY FACTOR (USING MDC) (%) -1.1 3.1 63.0 l 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) -1.0 3.0 60.6 1.
18. UNIT FORCED OUTAGE FACTOR (%) 0.0 0.0 13.1
19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

REFUELING (L2R04)- 01/04/92 11 WEEKS I

30. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIKATED DATE OF-STARTUP:

04/02/92

4

+

TABLE 3

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

, DOCKET NO. 050-373 UNIT LASALLE TWO DATE March 10, 1992 COMPLETED BY M.J. CIALKOWSKI TELEPHONE (815)-357-6761 l

l.

REPORT PERIOD March 1992 DAY POWER DAY POWER 1 -31 17 -11 2 -11 18 j 3 -11 19 -11 ,

4 -11 20 -11 5 -11 21 -11 6 -11 22 -11 7 -11 23 -11 8 -11 24 -11 9 -11 25 -11 10 -11 26 *11 11 -11 27 -11 12 -11 28 -11 13- -11 29 -11 14 -11 30

- 15 .-11 31 ,

16 -11

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! E.3 UNIT SHUTDOWNS AND POIER REDUCTIOttS 220% .

l (UNIT 2) i 4

METHOD OF CORRECTIVE

, TEARLY TYPE SHUTTING DONE ACTIORIS/CopeEDITS i SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if j- BUMBER (YYDeeJD E* SCHEDULED (BOURS) REASOE REDQCING {yNER aMIicable) l C1 '920104- S 696.0 C 1 Refueling outage L2R04.

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sneseART or oeERATION:

, The unlit entered a scheduled refueling outage 01/04/92.

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..ZCADTS/7 -

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  • UNIQUE REPORTING REQUIREMENTS (Unit 2)
1. Safety / Relief Valve Operations

' $fi

'; - VALVES NO & TYPE PLANT DESCRIPTION 4_ ATL ACAtiUJ) ACTUATIONS C0HDITION OF EVENT Cone.)

E 2. ECCS System Outages (See Table 5.)

3. Changes to the Off-Site Dose Calculation Manual.

(Hone.)

4. Major changes to Radioactive Waste Treatment Systems.

g (None.)

5. Indh::5:. ions of failed fuel Elements.

(None,)

l ZCADTS/7

A f

(Unit 2)

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

QUJ6GE E L EOUIPMENT PURPOSE 1115 2DG08CB Repair relief valve.

1188 1214 2DG08CB Repair compressor.

t ZCADTS/7.

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