ML20115H410

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Monthly Operating Repts for June 1996 for LaSalle County Station
ML20115H410
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 06/30/1996
From: Cialkowski M, Ray D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9607230108
Download: ML20115H410 (17)
v • d • e


Text

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Commonw ealth lilkm Company

, .* 1.aSalle Generating Matson

., 2601 North list Rox!

Marseilkw. I1. 6I 3 41-9'57 Trl H15-357W61 July 8,1996 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk

Subject:

LaSalle County Station Units 1 and 2 Monthly Performance Report NRC Docket Numbers 50-373 and 50-374.

Enclosed is the LaSalle County Station Monthly Performance Report for the month of June,1996.

Respectfully, D.J. Ray Station Manager LaSalle County Station Enclosure cc: H. J. Miller, NRC Region lli Administrator M. P. Huber, NRC Senior Resident inspector - LaSalle B. Clayton - NRC Region ill Branch Chief D. M. Skay, Project Manager, NRR LaSalle C. H. Matthews, IDNS Resident inspector - LaSalle D. Deppa, IDNS Reactor Safety - Springfield P. Doverspike, GE Representative - LaSalle '

D. L. Farrar, Nuclear Regulatory Services Manager 1 i INPO - Records Center Central file L S[;

h6d7b OEO8 960630 '

PDR ADOCK 05000373 R PDR A i ?mcom company

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LASALLE NUCLEAR POWER STATION  !

e UNIT 1 ndONTELY PERFORMANCE REPORT ,

t June 19fr6 CQbedONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 i

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, . l TABLE OF CONTENTS (UNIT 1)  ;

I. INTRODUCTION II. REPORT A. SIBMARY OF OPERATING EXPERIENCE B. AMENDNENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. LICENSEE EVENT REPORTS D. DATA TABULATIONS

1. Operating Data Report
2. Average Daily Unit Power Level ,
3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS
1. Main Steam Safety Relief Valve Operations
2. Major Changes to Radioactive Waste Treatment System
3. Static O-Ring Failures i
4. Off-site Dose Calculation Manual Changes I

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I. INTRODUCTION (UNIT 1)

The LaSalle County Nuclear Power Station is a two-Unit facility owned by Comanonwealth Edison company and located near Marseilles, 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 l blowdown. The architect-engineer was Sargent and Lundy and the contractor was Comenonwealth Edison Company.  !

l 1 Unit one was issued operating license number NPF-11 on April 17, l

, _1982. Initial criticality was achieved on June 21, 1982 and  !

comunercial power operation was commenced on January 1,1984. 1 i l

! This report was compiled by Michael J. Cialkowski, telephone number (815) 357-6761, extension 2056.

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d II. MONTHLY REPORT

  • A. St2 MARY OF OPERATING EXPERIENCE (Unit 1) l y D Time Event 1 0000 Reactor critical, Generator on-line at 1130 Mwe.

2 0335 Reduced power level to 850 Mwe for performance of a 3

rod set and control rod scram time testing.

4 1900 Increased power level to 1130 Mwe.

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9 0100 Reduced power level to 850 Mwe for performance of +

control rod scram time testing. f i

1030 Increased power level to 1130 Mwe.

19 2317 Reduced power level to 840 Mwe due Service Water  ;

strainers high differential pressure.

20 0700 Increased power level to 1110 Mwe.

23 0623 Reduced power level to 950 Mwe for performance of Feedwater system testing. j 1830 Increased power level to 1110 Mwe.

24 1155 Reduced power to 850 Mwe due to low Service Water system header pressure.

1900 Increased power level to 1110 Mwe.

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26 2056 Automatic reactor scram due to Group 1 Main Steam )

isolation. l 28 1650 Reactor critical.

2315 Comunenced unit shutdown due to ECCS and CSCS equipment cooling systems being declared inoperable due to foreign material in the Service Water Tunnel.

2335 Manual Reactor scram.

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30 2400 Reactor sub-critical, Generator off-line. j i

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D. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION l ,

During the month of June, Amendment 113 was iccusd to licenso NPF-11 (Unit 1). This amendment deletes the requirement to place the reactor mode switch in the shutdown position if a stuck open safety / relief valve can not be closed within 2 minutes.

j C. SUBKITTED LICENSEE EVENT REPORTS (Unit 1)

Occurrence LER No. Date Description 96-006 05/12/96 Manual Reactor scram due to high vibration levels on the Main Turbine Generator Exciter.

D. DATA TABUIATIONS (Unit 1)

1. Operating Data Aeport (See Table 1) l 2. Average Daily Unit Power Level (See Table 2) l
3. Unit shutdowns and Significant Power Reductions (See Table 3)

E. UNIQUE REPORTING REQUIREMENTS (UNIT 1)

1. Safety Relief Valve Operations i Date of Type of Reason for Valve Actuation Actuation Actuation l 1B21F013C 06/26/96 Automatic Reactor scram (LER# 96-007) l j 1B21F013H 06/26/96 Automatic Reactor Scram (LER# 96-007) l l 1B21F013C 06/26/96 Automatic Reactor Scram (LER# 96-007) i 1B21F013H 06/26/96 Automatic Reactor Scram (LERf 96-007) l
2. Major Changes to Radioactive Waste Treatment Systems l

(None)

3. Static O-Ring Failures (None)
4. Changes to the off-site Dose calculation Manual (None) l l

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e TABLE 1 0.1 OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LASALLE ONE DATE July 10, 1996 COMPLETED BY M.J. CIALK0WSK!

TELEPHONE (815)-357-6761 OPERATING STATUS-

1. RFPORTING PERIOD: June 1996 GROSS HOURS IN REPORTING PERIOD 720
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 (IF ANY) (MWe-Net): N/A
6. REASONS FOR RESTRICTION (IF ANY): N/A REPORTING PERIOD DATA THIS MONTH YEAR-TO-DATE CUMJLATIVE
5. REACTOR CRITICAL TIME (HOURS) 627.7 2,077.9 75,527.5
6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2
7. GENERATOR ON-LINE TIME (HOURS) 620.9 1,674.9 75,015.1 8 UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0
9. THERMAL ENERGY GENERATED (MUHt) 2,026,012 4,835,856 223,290,673
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 687,334 1,569,965 74,613,817
11. ELECTRICAL ENERGY GENERATED (MWHe Net) 669,487 1,491,281 71,629,709
12. REACTOR SERVICE FACTOR (%) 87.2 47.6 68.9
13. REACTOR AVAILABILITY FACTOR (%) 87.2 47.6 70.4
16. UNIT SERVICE FACTOR (%) 86.2 38.4 68.5

, $5. UNIT AVAILIBILITY FACTOR (%) 86.2 38.4 68.5

16. UNIT CAPACITY FACTOR (USING MDC) (%) 89.8 33.0 63.1
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 86.3 31.7 60.6
18. UNIT FORCED OUTAGE FACTOR (%) 13.8 12.0 7.9
19. SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): N/A
20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 07/10/96

DOCKET NO. 050-373 TABLE 2 UNIT LASALLE ONE D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe Net) DATE July 10, 1996 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 REPORT PERIOD: June 1996 DAY POWER DAY POWER 1 1,073 17 1,093 2 1,018 18 1,094 3 1,101 19 1,076 4 1,105 20 1,042 5 1,107 21 1,082 6 1,105 22 1,077 7 1,103 23 1,013 8 1,099 24 1,049 9 1,017 25 1,084 10 1,101 26 944 11 1,101 27 -12 12 1,098 28 -12 13 1,094 29 -14 14 1,092 30 -12 15 1,087 31 16 1,090 i

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

(UNIT 1)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CCOGEENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if NUMBER (YYtedDD) 5: SCHEDULED (HOURS) REASON REDUCING POWER applicable) 04 960626 F 99.1 G 3 Automatic scram due to Group 1 Main Steam isolation (LERf 96-007).

Unit remained off-line due to ECCS and CSCS equipment cooling systems inoperable due to foreign material in the service Water system tunnel (LERf 96-008).

SUbetARY OF OPERATION: The unit started the month on line at high power. Several power reductions were required during the month due to Service Water system low pressure. The unit experience an automatic scram on 06/26/96 due to a Group 1 Main Steam isolation. The reactor was taken to criticality on 06/28/96 but due to foreign material in the Service Water system tunnel which required the ECCS and the CSCS equipment cooling systems to be declared inoperable the reactor was manually scramed on the same day. The unit remained shutdown for the remainder of the month.

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IAEALLE NUCLEAR POWER STATION  !

l UNIT 2 l 1

MONTHLY PERFORMANCE REPORT l l

June 1996 1

i CotMONWEALTH EDISON COMPANY I

l NRC DOCKET NO. 050-374 I

l LICENSE NO. NPF-18 2 1

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TABLE OF CONTENTS (UNIT 2)

I. INTRODUCTION II. REPORT A. StBGERY OF OPERATING EXPERIENCE B. AMENDBENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. LICENSEE EVENT REPORTS D. DATA TABUIATIONS

1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS
1. Main Steam 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

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I. INTRODUCTION (UNIT 2)

The LaSalle County Nuclear Power Station is a two-Unit facility owned by Cosumonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Nater 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 sargent and Lundy and the contractor was Conanonwealth Edison Company.

Unit two was issued operating license number NFF-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and comunercial power operation was consnenced on October 19, 1984 This report was compiled by Michael J. Cialkowski, telephone number (815) 357-6761, extension 2056.

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m II. MONTHLY REPORT l

A. St284ARY OF OPERATING EXPERIENCE (Unit 2) l l Day Time Event l

l 1 0000 Reactor critical, Generator on-line at 1120 Mwe.

S 0010 Reduced power level to 850 Mwe for performance of a rod set and to transfer the Condensate / Condensate Booster pumps.

0945 Increased power level to 1110 Mwe.

20 0100 Reduced power level to 840 Mwe due Service Water strainers high differential pressure.

23 0245 Reduced power level to 750 Mwe for performance of a rod set.

1900 Increased power level to 1110 Mwe.

l 24 1130 Reduced power level to 850 Mwe due to low Service Water system discharge pressure.

1900 Increased power level to 1110 Mwe.

28 2315 Commenced unit shutdown due to ECCS and CSCS equipment cooling systems being declared inoperable due to foreign material in the Service Water Tunnel.

29 0528 Manual Reactor scram.

30 2400 Reactor sub-critical, Generator off-line.

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l D. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION I

During tha month of Juns, Amendment 98 was losusd to licenso NPF-18 l (Unit 2) . This amendment deletes the requirement to place the reactor l mode switch in the shutdown position if a stuck open safety / relief valve can not be closed within 2 minutes.

l C. SUNITTED LICENSEE EVENT REPORTS (Unit 2)

(None)

D. DATA TABULATIONS (Unit 2)

1. Operating Data Report (See Table 1)
2. Average Daily Unit Power Level (See Table 2) j i
3. Unit shutdowns and Significant Power Reductions (see Table 3) l

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l E. UNIQUE REPORTING REQUIREMENTS (UNIT 2)  ;

1. Safety Relief Valve Operations (None)
2. Major Changes to Radioactive Waste Treatment Systems (None) ,
3. Static O-Ring Failures l (None) f 4.

Changes to the Off-Site Dose Calculation Manual (None) ,

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TABLE 1 D.1 OPERATING DATA REPORT DOCKET NO. 050-374 i UNIT LASALLE TWO l DATE July 10, 1996 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 l OPERATING STATUS i l

1. REPORTING PERIOD: June 1996 GROSS HOURS IN REPORTING PERIOD: 720 ,
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036 DESIGN ELECTRICAL RATING (MWe-Net): 1,078
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): N/A
6. REASONS FOR RESTRICTION (IF ANY): N/A REPORTING PERIOD DATA THIS MONTH YEAR-TO-1 ATE CUMULATIVE
5. REACTOR CRITICAL TIME (HOURS) 677.5 4,161.7 75,451.2

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

7. GENERATOR ON-LINE TIME (HOURS) 677.5 4, 0 75.6 73,917.0
8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0
9. THERMAL ENERGY GENERATED (MWHt) 2,196,485 12,615,951 224,585,206
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 742,136 4,306,415 75,2D4,271
11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 723,201 4,169,663 72,322,335
12. REACTOR SERVICE FACTOR (%) 94.1 95.3 73.6 [
13. REACTOR AVAILABILITY FACTOR (%) 94.1 95.3 75.2
14. UNIT SERVICE FACTOR (%) 94.1 93.3 72.1
15. sWIT AVAILIBILITY FACTOR (%) 94.1 93.3 72.1 l 16. UNIT CAPACITY FACTOR (USING MDC) (%) 97.0 92.2 68.1
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 93.2 88.6 65.4
18. UNIT FORCED DUTAGE FACTOR (%) 5.9 6.7 9.8
19. SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): Refuel, 09/07/96,10 Weeks
20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 07/14/96 l

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1 DOCKET No. 050-374 i TABLE 2 UNIT LASALLE TWO D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DATE July 10, 1996 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 REPORT PERIOD: June 1996 DAY POWER DAY POUER i

....... ......... ....... ......... 1 1 1,098 17 1,081 2 1,097 18 1,078 3 1,093 19 1,062 4 1,090 20 1,017 5 1,089 21 1,063 6 1,087 22 1,062 7 1,075 23 960 8 1,051 24 1,038 9 1,096 25 1,083 10 1,100 26 1,072 11 1,100 27 1,053 12 1,098 28 1,053 13 1,093 29 110 14 1,087 30 -12 15 1,081 31 16 1,081 l

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D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 2)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CODGEENTS SEQUENTIAL DATE F: EVRCED DURATION THE REACTOR OR (LER S if NUMBER (YYle4DD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable) 05 960629 F 42.5 H 2 Unit shutdown due to the ECCS and CSCS equipament cooling systeens being inoperable due to foreign material in the Service Water systesa tunnel (LERf 96-008).

SUte(ARY OF OPERATION: The unit remained on-line at high power throughout most of the month. The unit was taken off-line on 06/29/96 due to foreign material in the Service Water system tunnel which required the ECCS and the CSCS equipeent cooling systems to be declared inoperable. The unit remained shutdown for the remainder of the month.

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