ML20096C808

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Monthly Operating Repts for Dec 1995 for LaSalle County Nuclear Power Station
ML20096C808
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 12/31/1995
From: Cialkowski M, Ray D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9601180299
Download: ML20096C808 (17)
v • d • e


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, .  ; Commonwealth Edium Company

. lasalle Generating Station 2601 North 21st Road

, Marvilkw IL 61311-9757

! Tcl HIS-35NC61 1

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January 11,1996 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Enclosed for your information is the monthly performance report covering l

LaSalle County Nuclear Power Station for December,1995.

D. J. Ray Station Manager LaSalle County Station DJR/mkl Enclosure cc: II. J. Miller, Regional Administrator - Region III NRC Senior Resident Inspector - LaSalle IL Department of Nuclear Safety - LaSalle IL Department of Nuclear Safety - Springfield, IL NRR Project Manager - Washington, D.C.

GE Representative - LaSalle Regulatory Assurance Supervisor - LaSalle Licensing Operations Director - Downers Grove Nuclear Fuel Services Manager - General Office Off-Site Safety Review Senior Participant - Downers Grove INPO Records Center Central File /fj 180072 9601180299 951231 6\\

PDR ADOCK 05000373 R PDR ,

A Unicom Company

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1 YmT.T.1e 350 CLEAR POWER STATICEt ,

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i SEBITELY PERFQgesugCE REPORT i

December 1995 J

I CCBGEgntEALTE EDIScet CC3dFAllY i

a'r 3ustC DOCERT 100. 050-373 LICENSE 300. NPF-11 w

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5 TABLE OF CONTENTS

! (UNIT 1) 1 4 I. INTRODUCTICII 1

1 j II. REP 00tf

) A. StBeautY OF OPERATING EXPERIENCE j E. ABSNDRENTS TO FACILITY LICENSE CEL TECENICAL SPSCIFICATIotts ,

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C. LICEttSEE EVENT REPoetTS  !

1 D. DATA ThacLATIcets

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! 1. Operating Data Report i 1 2. Averge Daily Unit Power Level

3. Unit Shutdowns and Power Reductions

! E. UttIQUE REPCELTING REQUIREbENTS 1

1. Main Steam Safety Relief Valve operations
2. Bonjor Changes to Radioactive Waste Treatment System
3. Static O-Ring Failures

! 4. Off-Site Dose Calculation Manual Changes i 4 i

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1 I. INTacDUCTIcet (tatIT 1) i The LaSalle County Nuclear Power Station is a two-Unit facility owned by Commmonwealth Edison Company and located near Marseilles, Illinois.

Each unit is a Boillag Water meactor with a designed not electrical output of 1078 Megawatts. Waste heat is zujected to a man-smade cooling pond using the Illinois river for make-up and blowdown. The architect-engineer was Sargent and Lundy and the contractor was Commannwealth Edison Cogeny.

Unit one was issued operating license ntamber NPF-11 on April 17, 1982. Initial criticality was achieved on June 21, 1982 and oosamercial power operation was - = M on January 1, 1984.

This report was compiled by Michael J. Cialkowski, telephone atauber (015)357-6761, eatension 2056.

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. i I II. 9000lTELY EIE708tT A. StBeemY OF OPERATIBOG EXPERIENCE (Unit 1) g Time Event 1 0000 menctor critical, Generator on-line at 970 Mwe, unit in coastdown for upconning refuel outage.

2 2300 Miaad power level to 690 news for perforsmance of a rod set.

3 2200 Increased power level to 945 Mwe.

9 1000 Increased power level to 970 tene.

17 2300 M==d power level to 800 Mwe for control rod drive accuumulator replacessant.

18 2400 h==d power level to 700 Mme for control rod drive accummiator replaceament.

19 0600 Increased power level to 850 Mwe.

1400 Increased power level to 915 newe. I 20 0000 ud==d power level to 700 tese for control rod drive maintenance.

0000 Increased power level to 900 Mwe.

21 0400 u d ==d power level to 730 Mwe for perforunance of scraan j time testing.  ;

0900 Increased power level to 900 Mwe.

31 2400 meactor critical, Generator on-line at 960 Mwe, unit in coastdown for upconning refuel outage.

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. . , D. N TO TER FACILITY OR TECENICAL CFECIFICATION f

(None) i C. SUEMITTED LICENEEE EVENT REPORTS (Unit 1) i ooourrence LER Mo. Date Description 95-018 11/28/95 Trip of the '13' Reactor Protection systema bus due to a failure of a Motor Generator set auxiliary relay.

D. DATA EnacLATIONs (Unit 1)

1. Operating Data Report (see Table 1)
2. Average Daily Unit Power Level (see Table 2)
3. Unit shutdowns and significant Power Reductions (see Table 3)

E. UNIQUE RESCRTING REQUIREbsENTS (UNIT 1)

)

1. safety melief valve operations (None)
2. Major Changes to Radioactive Waste Treatment systems (None)
3. Static O-Ring Failures l (None) J
4. Changes to the off-site Dose Calculation Manual (None) 1 I

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. 1 TABLE 1 0.1 OPERATING DATA REPORT DOCKET No. 050 373 UNIT LASALLE ONE DATE January 12, 1996 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 ,

OPERATlWG STATUS

1. REPORTING PERIOD: December 1995 GROSS NOURS IN REPORTING PERIOD 744
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe Net): 1,036 DESIGN ELECTRICAL RATING (MWe N 1,078
3. POWER LEVEL TO WHICH RESTRICTED (!F ANY) (MWe-Net):
6. REASONS FOR RESTRICTION (!F ANY):

REPORTING PERIOD DATA TH13 MONTH YEAR TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 744.0 8,302.1 74,942.0
6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2
7. GENERATOR ON LINE TIME (HOURS) 744.0 8,229.0 73,340.1
8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0
9. THERMAL ENERGY GENERATED (MWHt) 1,980,385 25,767,992 218,454,817
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 666,182 8,652,961 73,043,852
91. ELECTRICAL ENERGY GENERATED (MWHe Net) 641,459 8,369,284 70,138,428
12. REACTOR SERVICE FACTOR (%) 100.0 94.8 71.2
13. REACTOR AVAILABILITY FACTOR (%) 100.0 94.8 72.8
14. UNIT SERVICE FACTOR (%) 100.0 93.9 69.7
15. UNIT AVAILIBILITY FACTOR (%) 100.0 93.9 69.7 ,
16. UNIT CAPACITY FACTOR (USING MDC) (%) 83.2 92.2 64.3
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 80.0 88.6 61.8
18. UNIT FORCED OUTAGE FACTOR (%) 0.0 4.3 7.9
19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

REFUEL, 01/27/96, 9 WEEKS

20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A i

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DOCKET NO. 050-373 i TABLE 2 UNIT LASALLE ONE l D.2 AVERAGE DAILY UNIT POWER LEVEL (NWe-Net) DATE January 12, 1996 COMPLETED BY M.J. CIALK0WSKI l

1 TELEPHONE (815) 357 6761 '

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1 REPORT PERIOD: December 1995 DAY POWER DAY POWER 1 927 17 874 2 899 18 799 ,

3 816 19 821 4 892 20 827 5 880 21 841 6 878 22 845 7 875 23 843 8 869 24 840 9 899 25 836 10 918 26 832 11 917 27 828 12 916 28 823 13 912 29 819 14 906 30 815 15 893 31 811 16 880

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TABLE 3 -..-

D.3 UNIT SHUTDONNS AND POWER REDUCTIONS > 20%

(UNIT 1)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CCtedENTS E1QUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if NUMBER (YDOOD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable)

(None) l l

Cute 4TJtY OF OPERATION:

The unit r== mined on-line at high power throughout the month. Several minor power reductions were required due to rod pattern adjustments, maintenance and surveillance activities.

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4 v.mmar.r.m 300C12AR POWER S'EETION 1

UNIT 2 i

4 3EtfTELY PERPGsteGICE REPORT 4

Deceanbar 3995 J

4 CctemenEEALTH ELIS006 COMPA3ff i

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35tc DOCERT 300. 050-374

, LICENSE 300. NPF-18 4

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  • l TABLE OF CONTENTS (UNIT 2)

I. INTRODUCTION II. REPORT A. SEBASm! 0F OPERATING EEFERIEW 3 R. N TO FACILITY LICENSE OR TECENICAL SPECIFICATIONS C. LICENSEE EVENT REPORTS l

D. DATk Th3OLATICBf8 )

1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit shutdowns and Power Reductions 4 E. 12fIQUE REPORTING REQUIREBSNTS
1. Main Stama Safety Relief Valve operations
2. Major changes to Radioactive Waste Treatment System
3. Static O-Ring Failures
4. Off-site Dose calculation Manual Changes i l

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l I. INTRODUCTION (UNIT 2)

The Lasalle County Nuclear Power Station is a two-Unit facility owned by Commonwealth Edison Company and located near Marseilles, l Illinois. Each unit is a Boiling Water meactor with a designed not j electrical output of 1078 Megawatts. Waste heat is rejected to a man-made cooling pond using the I111acis river for make-up and blowdown. The architect-engineer was Sargent and Lundy and the contractor was Commnonwealth Edison Company.

Unit two was issued operating licenbe atumber NPF-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and

- ecial power operation was - a w on October 19, 1984. .

1 This report was compiled by Michael J. Cialkowski, telephone number (815)357-6751, extan=1on 2056.

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l II. De:mOTELY ItE700tT A. StBeeMt! OF OPE 3tATI35G EXPERIE3OCE (Unit 2) j Da Time Event 1- 0000 3teactor critical, a===rator on-line at 1130 Bewe. l 2 2000 w =aad power level to 850 Bere for surveillance l performance. l l

3 0000 Increased power level to 1130 newe.

5 0400 M iaad power level to 1040 Bere to swap the condensate i pumps.

1000 Increased power level to 1135 newe.

5 0200 madaaad power level to 1050 Bewe to swap the condensate pumps.

0800 Increased power level to 1140 Hue.

13 0100 e=dinaad power level to 730 Bewe for perfor- naa of a rod set.

0800 Increased power level to 1135 Dere.

18 0000 mad'=aad power ',evel to 1070 Mwe to swap the condensate p g s.

0700 Increased power level to 1140 Mwe.

20 2200 ==d==a-d power level to 850 Bewe for Beater Drain and Feedwater system p g main &= nance.

21 1300 Increased power level to 1000 Bewe.

22 2300 Increased power level to 1135 Mme.

30 2335 mad ==a-d power level to 990 Bewe due to system load.

31 0840 Increased power level to 1135 Mwe.

1 1245 staduced power level to 1075 Mwe to swap the condensate I p g s. i 1

1630 Increased power level to 1135 town. )

2400 Eleactor critica2, Generator on-line at 1135 Hwe.  ;

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,. D. JhbE3EEENTS TO TSE FSCILITY OR TECSNICAL CFECIFICATIC06 (Nons)

C. SUsMITTED LICENSEE EVENT REPORTS (Unit 2) ooourrence LER No. Date Description i 95-011 11/27/95 Inadvertent ESF actuation and Reactor Core l Isolation Cooling systeen isolation during l surveillance functional testing due to personnel i

error.

I D. DATE TABULETIONS (Unit 2)

1. Operating Data Report (see Table 1)
2. Average Daily Unit Power Level (see Table 2)
3. Unit shutdowns and significant Power moductions (see Table 3)

E. UNIQUE REPORTING REQUIREbSNTS (UNIT 2)

1. Safety Relief valve operations (Mone) l I
2. Major Changes to Radioactive Maste Trea h nt systeens I (None) l l
3. Static O-Ring Failures j (None)  !
4. Changes to the off-site Dose Calculation Manual (Mone) l i

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% - e --s. - A- ,--.,s TABLE 1 D.1 OPERATING DATA REPORT DOCKET NO. 050 374 UNIT LASALLE TWO DATE January 12, 1996 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357-6761 i OPERATING STATUS f

1. REPORTING PERIOD: December 1995 GROSS HOURS IN REPORTING PERIOD: 744 1
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt)
3,323 MAX DEPEND CAPACITY (MWe Met): 1,036 .

DESIGN ELECTRICAL RATING (MWe-Net): 1,078  ;

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): j
4. REASONS FOR RESTRICTION (IF ANY):

j REPORTING PERIOD DATA J

.............................................. j THIS MONTH YEAR To-DATE CLMILATIVE l

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5. REACTOR CRITICAL TIME (HOURS) 744.0 6,081.6 71,289.6  !

I j 6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 1

7. GENERATOR ON-LINE TIME (HOURS) 744.0 5,856.0 69,841.5
8. UNIT RESERVE SHUTDOWN TIME (HOUPS) 0.0 0.0 0.0
9. THERMAL ENERGY GENERATED (MWHt) 2,427,263 18,217,327 211,969,255 l
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 833,164 6,209,287 70,897,856
11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 804,502 5,967,910 68,152,672
12. REACTOR SERVICE FACTOR (%) 100.0 69.4 72.6  ;
13. REACTOR AVAILABILITY FACTOR (%) 100.0 69.4 74.3
14. UNIT SERVICE FACTOR (%) 100.0 66.8 71.1
15. UNIT AVAILIBILITY FACTOR (%) 100.0 66.8 71.1
16. UNIT CAPACITY FACTOR (USING MDC) (%) 104.4 65.8 67.0
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 100.3 63.2 64.4
18. UNIT FORCED OUTAGE FA:: TOR (%) 0.0 3.1 10.0 l

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19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): N/A
20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A I

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.e DOCKET N0. 050 374 TABLE 2 UNIT LASALLE TWO D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DATE January 12, 1996 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 REPORT PERIOD: December 1995 DAY POWER DAY POWER 1 1,100 17 1,099 2 1,064 18 1,087 3 1,047 .19 1,098 4 1,099 20 1,088 .

I 5 1,087 21 889 6 1,102 22 985 7 1,102 23 1,096 8 1,098 24 1,097 1 l

9 1,101 25 1,097 10 1,103 26 1,098 11 1,104 27 1,099 12 1,093 28 1,100 13 1,056 29 1,099 14 1,101 30 1,098 15 1,099 31 1,037 16 1,099 I

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TABLE 3 D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 2)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CobedENTS CEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if NUMBER (YDedDD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable)

(None)

StaeshRY OF OPERATION

  • The, unit remained on-line at high power throughout the month. Several minor power reductions were required during the month due to rod pattern adjustments, maintenance and surveillance activities.

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