ML20058P121

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Monthly Operating Repts for Jul 1990 for LaSalle County Nuclear Power Station Units 1 & 2
ML20058P121
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 07/31/1990
From: Diederich G, Thunstedt J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9008160086
Download: ML20058P121 (24)
v • d • e


Text

,

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  1. .f" - Commonwealth Edison

.< LtSalle County Nuclear Station Rural Route #1. Box 220 Marseilles, Illinois 61341 Telept.one 015/357-6761 August- 10, 1990 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mail Station F1-137

' Washington, D.C. 20555 ATTNt Docwnent Control Desk Gentlement Enclosed for your.information is the' monthly performance report covering LaSalle County Nuclear Power Station-Ior July, 1990.

Very truly yours, O

G. J. Diederich .

Stution Manager, LaSalle County Station.

GJD/JWT/msh Enclosure i i

xc A. B. Davis, NRC, Region III l NRC Resident inspector LaSalle l Ill. Dept. of Nuclear Safety l R. Pulsifer, NRR Project Manager ,

D. P. Galle, CECO I D. L. Farrar, Ceco INPO Records Center D. R. Eggett, NED I J..E. Kuskey, GE Resident I T. J. Kovach, Manager of Nuclear Lixensing W. F. Naughton, Nuclear Fuel Services Manager C. F.-Dillon, Senior Financial Coordinator, LeSalle T. R. Novotney, INPO Coordinator, LaSalle Station-T. A. Hammerich, Regulatory Assurance Supervisor J. W. Gieseker, Technical Staff. Supervisor Central File

. ZCADTS/5 1 9008160086 900731 -)

, PDR .ADOCK 05000373 l R  : PDC

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t LASALLE NUCLEAR POWER STATION

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UNIT 1 t MONTHLY PERFORMANCE REPORT JULY 1990 ,

COMMONWEALTH EDISON COMPANY ,

'I NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 r >

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ZCADTS/5 1

TABLE OF CONTENTS (UNIT 1)

X. INTRODUCTION II. REPORT A. SUW'.RY OF OPERATING EXPERIENCE B. PLANT OR PROCEDURE CHANGES,- TESTS, EXPERIMENTS, AND SAFETY RELATED MPINTEN ANCE

1. Amendments to racility License or Technical Specifications
2. Changes to procedures which are described in the Safety.

Analysis Report

3. Tests and Experiments not covered in the Safety Analysis Report
4. Corrective Maintenance of Safety-Related Equipment
5. Completed Safety-Related Modifications C. LICENSEE EVENT. REPORTS D. DATA TABULATIONS
1. Operating Data Report
2. Average Daily Unit Power Leve)
3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING RECUIREMENTS
1. Main Steam Relief Valve Operations
2. ECCS System Outages
3. Off-Site Dose Calculation Manual Changes
4. Major Changes to Radioactive Waste Treatment System
5. Indications of Failed Fuel Elements i

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1. INTRODUCTION (Unit 1)

The LaSalle County Nuclear Power Station is a two-unit f acility owned by Commonwealth Edison Company and located near Marsellies, Illinois. Each unit'is a Boiling Water Reactor with a designed net electrical output of 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 Sergent.and Lundy and the primary construction contractor was Commonwealth Edison Company.

Unit One was issued operating license number NPT-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 complied by John W. Thunstedt, telephone number (815)357-6761, extension 2463.

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, II. MONTHLY REPORT j l

A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 1) j 4

Day- Ilmn Event 1 0000 Reactor critical, generator off-line 1035 Generator on-line 1

4 0030 Unit at 1000 MWE i

5 0200 Reduced load to 690 MWE-for rod-set j 1400 Increased load to 1075 MWE 6 0100 Reduced Icad to 850 MWL for System load ,

1400 Increased load to 1093 MWE 7 0300 Reduced load to 850 MWE for System load 1500 Increased load to 1100 MWE j

i 8 0100- Reduced load to 750 to repair steam leak 1500 Increased load to 1090 MWE 10 0300 Reduced ~1oad to 1000 MWE for CRD exercising i 1400 Increased load to 1090 MWE 12 0100 Reduced load to 850 MWE for System load 1400 Increased load to 1100 MWE l i

13 0100 Reduced load to 750 MWE for Heater Bay work j i

l 2000 Increased load to 1100 MWE  !

14 0130 Reduced' load to 750 MWE.for Heater-bay work-15 0200 Increased load to 1100 MWE q 17 0130 Reduced load to 750 MWE for CRD exercising and Heater-bay work 2200 Increased load to 1119 MWE-18 0400 Reduced load to 850 MWE for System load ,

1400 Increased load to 1120 MWE ZCADTS/5 i

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m A.

SUMMARY

OF OPERATIT.'G EXPERIENCE (U2it 1) (CO2titued)

Day Ilma Event 20 0100 Reduced load to 750 MWE for System. load 1500 Increased load to 1110 MWE 22 0100 Reduced load to 850 MWE for System load 1100 Increased load to 1062 MWE 23 0100 Reduced load to 900 MWE for System load 1100 Increased load to 1060 MWE 24 0100 Reduced load to 050 MWE for System load 1400 Increased load to 1100 MWE 25 0030 Reduced load to 850 MWE for System load 0900 Increased load to 1053 MWE 26 0030 Reduced load to 740 MWE for Heater-bay work.-

0645 Ir. creased load to 960 MWE, holding for high Hydrogen tempetature in generator.

29 2100 keduced load to 800 MWE for System load.

30 0245 Reduced load to 700 MWE for generator hydrogen cooler I repairs.

1325 Increased load to 920 MWE 31 2140 Reduced load to 850 MWE for System load and scheduled surveillances 2400 Reactor critical, generator on-line at 850 MWE 4

]

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i B.- PLANT OR PROCEDURE CNANGESo TESTS, EXPERIMENTS AND SAFETY RELATED l

, MAINTENANCE. (Unit 1) I

1. Amen &ments to the Facility License or Technical Specification.  !

)

4 Amend the load profile currently listed in the battery Tech. ]

Specs. to account for the Alternate Rod Insertion Modification. '

f

2. Changes.to procedures which are described in the Safety Analysis Report. i (None.)
3. Tests and Experiments not described in t.he Safety. Analysis f Report.

(None)

4. Major corrective maintenance to Safety-Related Equipment, including any SOR switch failure reports.

(None.) i l

S. Completed Safety-Related Modifications.

(See Table 2)

C. LICENSEE EVENT REPORTS (Unit 1)

LER Number DAtt D.itScrip11pn __,

(None)

D. DATA TABULATIONS (Unit 1) J

1. Operating Data RLport (See Table 3)
2. Average Daily Unit Power Level (See Table 4)
3. Unit Shutdowns and Significant Power Reductions'(See Table 5) 1 l

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B.5 TABLE 2 (Unit 1)

COMPLETED SAFETY-RELATED MODITICATIONS EUMBER DESCRIPTION

'M01-1-87-031 Replaced the control room lighting "eggerates" and support runner with an off-white shade. The new ceiling will replace ~

the existing diffusers in both the "at controls" and back-panel areas, in conjunction with the new fixtures and' reflectors.

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, ?3: i . :D.1 OPERATING DATA REPORTi .'DOCKETN01050-3i3i ,

W 49 'T ,

UNIT LASALLE ONE:

54 s ibATE Asmst to,1990 l

.a cf C mPLETED BY!J.W. THUNSTEDT fi[. c7 i- TELEPHONE t815)-357 6761:

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H ;9 OPERATING STATUS . ..

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-11 1.? REPORTING PERIOD: fJULT 1990 ' GROSS HOURS IN REPORTING PERIOD: 1 744" b n12 : ', .

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' 13 2.'iCURRENTLY AUTHDRIZED FtWER LEVEL' Wt)f ,3,323- >

MAXDEPCNDCAPACIT7(Me-Net)( . 1C1,0361

-14L ' , .

DESIGN ELECTRICAL RATING (Me-Neth / . 1,078 "

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3- i s

p l16u . . .

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l17 3. . POWER LEVEL TO WICH RESTRICTED (if ANY);(Me-Neth . (None):: 1a

18 i _. .. . . . . i' . . . . 2 y :19;4. .REASDNS FOR;RESTRICilDN (IF ANY) L >

'(N/A): _.

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$ ~ 21

' 20 '

< r gc dEPORTINGPERIODDATAJ ( ~

22 c ^,THISMONTHE IYEAR-TO-DATC)'(CUMULATIVE:

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+ . 245. REACTOR CRii! CAL TI N (HOURS) s ' 744.0: ~ 4,802.3 { L36,936.4:

25 J ..

26 6.1 REACTOR RESERVE SHUIDOW ilME (HOURS) .

L 6.0 ? '6.0 - l 1,64i.2 a

275 .

, _ 4 28 7. GENERATOR OH-LINE ilME (HOURO

' 727.4 !4,657.5:

336,075.8~~

29 . s ,

' l 30 0. UNif RESERVE SHUIDOW TIME (HOURS) 0.0! 6.0 1.0-31 s 329.~THERMALENERGTGENERATEDiMHi) -2,116N8BD L14',619,097.4J Ith2,451345 33 3410. ELECTRICAL ENERGY GENERATED ,(MHe-Gross)1 _'698,752- 3 4,969,029L 34,037,570 35 s -

0J411.ELECTRICALENERGYGENERATED.(MHe-Net) ?673,1861 ' _

4,805,560- 32,538,2621 13T :

3B 12. REACTDR SERVICE FACTOR (%) - 100.0 I ' -94.4: f 64.0.

! 39 i -

40 13. REACTOR AVAILABILITT FACTOR (%) 100.0 ?  ! 94.4-l 46.8/ 4 41 .

.42 14i' UNIT SERVICE FAC10R (!) 97,0.1 4 91.6 L '62.5

- 43 44 15. UNIT AVAILIPillif FACTOR (%) 97,8: 91.6N 62.5

' 45:.

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'4616.UNITCAPACITYFACTOR(USINGHDC)(1)- 187.3 91.23 54.4'

4T .

i48 17.' UNIT CAPACITY FACTOR (USING DESIGN M e) (%) ' S3.9. 587.6S ' 52.3 -

49 50 18. UNIT FORCED 001 AGE FACTOR (%)- t 0.es ~ 2i9 9.3

. $p a ; 52;

> 53 '

n5419. SHUTDOWS SCHEDULED DVER H T' E NEXT.6 MONTHS (TYPE, DATE, AND DURATION OF: EACW)-

'55 (None)

, -;$p .

i57 29. IF. SHUTDOWN At END OF REPORT PERIOD, ESTIMATED DATE OF.STARTUP:

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TA"LE 5 D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(Unit 1)

METHOD OF CORRECTIVE YEARLY TIPE SHUTTING DONT ACTIONS / CODE (ENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR S if NUMBER (YDGEDD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable)

C%ne) t SID#(ARY OF OPERATION:

The Unit returned to service following main condenser tube plugging. Most load' reductions were due to System load cenditions. Fouling of the main generator hydrogen cooler has reduced output due to excessive hydrogen temperatures;-

on-line chemical cleaning is in-progress.

ZCADTS/5

- - . = _ . = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ . - _ _ _ - . _ . _ . ~ _ _ _ _ _ _ _ _ _ _ _ _ . __ . _ . . . _ _ _. - -. .. . , - -- = _ _ _ _ _ . _ _ - . , . . _ , . . .

_ _...._n.

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E. UNIQUE REPORTING REQUIREMENTS (Unit 1)

1. Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIPTION DAIE ACWAIED ACWATION CONDITION OF EVENT I

(None)

2. ECCS System Outages (See Table 6)
3. Changes to the Off-Site Dose Calculation Manual (None).
4. Major changes to Radioactive Waste Treatment Systems.

(None)

5. Indications of Failed Fuel Elements.

(Hone)-

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(U21t:1) l

.. Tablo 6- ]

l ECCS System Outages {

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

QUIAGEEh - 50u12tlEtiT EERROSE' ,

I (U-0) l

. .l 194 ODG01P. Lubricate coupling j (Cooling water i Pump) .!

i (U-1)  !

5 326 1A D/G Inspect fuel-oli pressure sensing j

.line- 4 351 1E12-C003 (RH) Lubricato coupling f l

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LASALLE NUCLEAR POWER STATION t UNIT 2 MONTHLY PERFORMANCE REPORT JULY, 1990 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 i

LICENSE NO. NPT-18 I

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ZCADTS/7 L-

b TABLE OF CCNTENTS (Unit 2)

I. INTRODUCTION g; i

II. REPORT i J

A.

SUMMARY

OF OPERATING EXPERIENCE  ;

B. PLANT OR PROCEDURE' CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED  ;

MAINTth ANCE

1. Amendments to Tacility. License or Technical Specifications
2. Changes to procedures which are described in the Safety  ;

Analysis Report.

3. Teste:and Experiments not covered in the Safety Analysis Report.
4. Corrective Maintenance of Safety-Related Equipment ~  !
5. Completed Safety Related Modifications i
C. LICENSEE EVENT REPORTS 1 D. DATA TABULATIONS j 1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions l E. UNIQUE REPORTING REQUIREMENTS
1. Safety / Relief Valve Operations
2. ECCS System Outages
3. l Off-Site Dose Calculation Manual Changes l
4. Major Changes to Radioactive Naste Treatment System
5. Indications of Failed Fuel Elements '

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1. INTRODUCTION (Unit 2)

J The LaSalle County Nuclear Power Station is a two-unit f acility owned by Commonwealth Edison Company and located near Marsellies, Illinois. Each  ;

unit is a Boiling Water Reactor with a designed not electrical output of 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 and the primary construction contractor was Commonwealth Edison Corpany.

Unit Two was issued operating license number NPF-18 on December 16,. l 1983.. Initial critic '.ity was achieved on March 10, 1984 and commercial  !

power operation was cc 1menced on June 19, 1984.

This report was compiled by John W. Thunstedt, telephone number ,

(815)357-6761 extension 2463.

{

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ZCADTS/7 ,

f II. MONTHLY REPORT a I

I A.

SUMMARY

OF OPERATING' EKPERIENCE (Unit 2) i DAY 111tti Event i 1 0000 Reactor critical, generator on-line at 1110 MWE.

4 '0300 Reduced load to 1000 MWE for scheduled surveillances.

1 0800 Increased load to 1110 MWE. i l

l-11 0200 Reduced load to 900 MWE for'CRD exercising 1 l

1300 Increased load to 1110 MWE. l l

13 0200 Reduced load to 720 MWE for scram-time testing CRD 26-55.  ;

14 0200 Reduced load to 120 MWE to adjust MSIV limit switches.

l 15 2200 Increased load to 850 MWE. j i

16 0700 Increased load to 985 MWE. l 2000 Reduced load to 720 MWE for Heater-bay' work. j 17 1700 Increased load to 1000 MWE.

19 0200 Reduced load to 625 MWE for rod-set.

1800 Increased load to 1110 MWE. 1 20 0200 Reduced load to 850 MWE for System'1oad" l

1300 Increased load to 1110 MWE. j I

22 0200 Reduced load to 850 MWE for System load 1200 Increased load to 1110 MWE. l I

26 0300 Reduced load to 850 MWE for System load.

0900 Increased load to 1110 MWE.

31 2400 Reactor critical, generator on-line at 1110 MWE.

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B.' PLANT OR PROCEDURE CHANGESo tTESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE. (Unit 2) t

1. Amendments to the Facility License or Technica'. Specification.

'('

Amend the load profile currently listed in the battery Tech.  !

Specs. to account for the Alternate Rod Insertion Modification.

.v ,

2. Changes to procedures which are describedLin the Safety Analysis Report. . .  !
a. LaSalle Special Procedure, LLP-90-045, "MSIV Scram Functional Test." The purpose of t.his test was to outline l the steps necessary to verify proper operation of the  !

inboard / outboard MSIV RPS limit switches with isome partial

channel trips present. This procedure was required to prevent a unit scram due to MSIV combination trip !!ogic.

The procedure was maintained within the bounds of the i existing TechnicaliSpecifications.

i

). Tests and Experiments not' described in the Safety Analysis Report.

(None) i

4. Major corrective maintenance'to Safety-Related Equipment, including any'SOR switch failures. .

(None) l

5. Completed Safety-Related Modifications.

(See Table 2)  ;

.t C. LICENSEE EVENT REPORTS (Unit 2)-

LER Number Date Qascript1 0n , )

(None) U

\l l

D.. DATA TABULATIONS (Unit 2)

1. Operating Data Report.

(See Table 3) i

'n

2. Average Daily Unit Power Level.  ;

(See Table 4) l

3. Unit Shutdowns and Significant Power Raductions.

(See Table 5) li ZCADTS/7 l l

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s.5 TABLE 2 (Uait 2)

COMPLETED SAFETY-RELATED MODIFICATIONS NUMBER _. DESCRIPTION M01-2-87-002 Installed an annunciator pushbutton station.on the 2PM03J Panel in the control room per Detailed Control Room Design Review (DCRDR) pregram.

M01-2-87-026 Replaced the key operated control switches for the MSIV Leakage Control System with non-key operated type switches. Replaced the scale range indicator for the RCIC turbine exhaust pressure indicator and RCIC pump suction pressure Indicator per Detailed Control Room Design Review (DCRDR) program.

M01-2-87-028 Rearranged the recorders on the P602 control room panel to allow c'Tslatency in right to left and top to bottom arrangement per Detalled Control Room Review (DCRDR). program.

M01-2-87-031 Rearranged the Vent and Purge damper controls located on the=

{- control room panel 2PM06J in a logical configuration per g

L Detailed Control Room Review (DCRDR).

M01-2-87-033 Installed a PA override capability for control room' inputs into

( the PA system, installed permanent telephones on the N62-P600 and P601 control room panels, and deleted the tripping hasards .;

prosented by overly long handset cords on the radiophones per  ;

Detailed Control Room Review (DCRDR).

M01-2-88-004 Replaced the existing 125 Volt, Division 1 battery and rack and I revised the current monitoring instrumentation for the battery and it's associated charger.

. M01-2-89-001 Replaced the double disc configuration for the Reactor Recirc 2B33-F067A/B valves with a single, flexible wedge disc.

Installed new packing assembl l conslsting of a single set of '

packing, eliminating the need for a stem leak-off line.

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. 41 .

j 1 m: ' '

UNITLASALLETWO'

13 2. CURREtilf AUTHORIZED POWER LEVEL (Mt): 3,323 MAX DEftND CAPACITY (We-Net): .t 036- 4 7 14 : ' -"

l1 1

DESIGN ELECTRICAL RAi!NG (Me-Nat h , , jl,078; f M (g$7 ,

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,mm

  • 1< 16' zi7 3.5 POWER LEVELLTO WHICH RESTRICTED (If ANY) ( We-Net):

(None)

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, J i9,4 3 REASONS FDR REETRICTION'(!T ANT)i f(N/Ah i

' 20 / ' <

LREPORTING FTRIOD MTA

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21 , "  % LTHISMONTHf  ; YEAR-104ATEL i CUNOLATIVE; 23 '.

W  : a .Q _,

6 33,110.25 24 5. REACTOR CRliltAL TIME (HOURS) - , ,  : 744.0j , ?2,963.1:~

x 25 ,

1

26t : REACTOR RESERVE -SHU1DOWN -i!ME (HOURS) ' ,

' 0.9 ) !0.01 ,i1,716.9/u 27 , .

.c 28 7. GENERATOR ON-LINE TIME (HOUR 3) . ,

744.0 - 2,845.2 e32,528.3g i 291 .

'1 .308. UNIT RESERVE SHUTDOWN TIME-(HOURS) o - 0.0 l

^

0.0 '_ ^ i 0.0:'

'31 '

32 9. THERMAL ENERGY GENERATED (NWHt) 4 2,262,9841 i8,563,207.2l. - -

94,883,255.2 33

34.10.~ ELECTRICAL ENER.Y GENERATED (MHe-Grossi .  : 748,72f L  ! U B77 d66 y !31,328,23
e 35 ..

p ' 36 it(ELECTRICAL ENERGY GENERATED (WHe-Net) 722,104 / E ;2,749,fje- f29,984,9t$;

37L
3812. REAC(DR SNVICE fAC10R (%)-  : 100.0 ' L 58.2 ! ' 65.35 -

' 39 ' . .. . .

{ ' 4013. REACTOR AVAILMILITY FACTOR (%)

f00.0 58.2; f 6'8'.7)

" ' 41, i

_ 1 6 42 14. UNIT SERVICE FACTOR (%) 100.0.= < 55.9-- '64.11

- : 43 ; ,

q 44.15. UNIT AVAILIBilliY FACTOR (%F 100j ; $5,9 64.1 :

45 L -r 14616. UNIT CAPACITY FACTOR (USING MDC) (%) , 93.7 -- 52.2 ' 37.1!

. s 147 74817. UNil CAPACITY FACTOR (USING DESIGN Me)-(%) 90.0 - 50.1 t 54.9 d '

7 49. , ,

H 50 18. UNIT FORCED OUTAGE FACTOR (%) 0'.0 4.3 "15.4 5

, 51 c 525 i 53- s 15419.- SHUTDOWNS SCHEDULED DVER THE NEXT 4 MONTHS (TYPE. MTE, AND DURATION OF EACH): r  !

l' ' 33f -(None);

la 56 .,

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  • . E. UNIQUE REPORTIIG REQUIREMENTS (Unit 2)
1. Safety / Relief Valve Operations VALVES NO & TYPE PLANT DESCRIPTION DATE ACHIATED h*illATIONS 1% EDITION OF EVENT (None)
2. ECCS System Outhges (See Table 6)
3. Changes to the Off-Site Dose Calculation Manual.

(None).

4. Major changes to Radioactive Waste Treatment Systems.

(None) '

5. Indications of railed Fuel Elements.

(None) i l

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i ZCADTS/7

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(Unit 2)  !

. T;blo 6 ,

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

QUIA M EQLIIDG2LT Pl!EEDSE i

1527 2B D/G Replace oil.f11ters 1528 2B D/G Remove and'm3asure fusi pressure- ,

sensing line 1556 2A D/G Troubleshoot and repair Cylinder 110 thermocour.e ,

1583 2A D/G Calibrate Cylinder 110 thermocouple  :

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