ML20093E623

Monthly Operating Repts for Sept 1995 for LaSalle County Nuclear Power Station

ML20093E623
Person / Time
Site:	LaSalle
Issue date:	09/30/1995
From:	Cialkowski M, Ray D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9510170004
Download: ML20093E623 (18)

Text

Commonwealth I.dium Company

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• IMalle Generating Station 2601 North 21st Road Marwilles. II. 61.i il 9757 Tel 141,5.457 #*6 I

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October 13,1995 I

l U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 i

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for September,1995.

I D. J. Ray l Station Manager  !

LaSalle County Station I

DJR/mkl Enclosure cc: H. J. Miller, Regional Administrator - Regien III  !

NRC Senior Resident Inspector - LaSalle l IL Department of Nuclear Safety - LaSalle l IL Department of Nuclear Safety - Springfield, IL j NRR Project Manager - Washington, D.C.

GE Representative - LaSalle l Regulatory Assurance Supervisor - LaSalle  !

Licensing Operations Director - Downers Grove l i Nuclear Fuel Services Manager - General Office l Off-Site Safety Review Senior Participant - Downers Grove INPO Records Center Central File i

1 9510170004 950930 PDR 7

R ADOCK 05000373 PDR L/ j 4

A linicom Company i

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LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERF0PtNhNCE REPORT September 1995 CcteONNEALTE EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 4

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TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION II. REPORT l

A. SISe4ARY OF OPERATING EXPERIENCE i

B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS l

C. LICENSEt, 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

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 Commonwealth Edison Company and located near Marseilles, Illinoia.

Each unit is a Boiling Water Reactor with a designed net electrical output of 1079 Nhgawatts. 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 Commonwealth Edison Cospany.

Unit one was issued operating license number NPF-11 on April 17, 1992. Initial criticality was achieved on June 21, 1982 and commercial power operation was commenced on January 1, 1994.

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

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II. MONTHLY REPORT A. SINedARY OF OPERATING EXPERIENCE (Unit 1) y D Time Event 1 0000 Reactor critical, Generator on-line at 1090 Mwe.

11 0200 Reduced power level to 900 Mwe for performance of a rod set and inspection of the Motor Driven Reactor Feed Pump mixing flow valve.

1000 Increased power level to 1128 Mwe.

16 1015 Reduced power level to 1075 Mwe to swap the Beater Drain and condensate / condensate Booster Puups.

1400 Increased power level to 1110 Mwe.

24 0408 Manual Peactor scram due to loss of the '1B' Turbine Driven Reactor Feed Pung during surveillance performance.

27 2029 Reactor critical.

28 1017 Generator on-line at 60 Mwe.

29 1738 Generator at 350 Mwe, upshifted Reactor Recirculation Pungs .

29 2400 Power level at 1000 Mwe. ,

1 30 2400 Reactor critical, Generator on-line at 1000 Mwe. l 1

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3. AMENDNENTS TO THE FACILITY OR TECHNICAL SPECIFICATION 1

On' september 27, 1995, Amendment 106 was issued to license NPF-11 (Unit 1). This amendment allowed the extension of surveillance test ,

intervals to accommodate the start date change of the L1R07 outage from l September 30, 1995 to January 27, 1996.

I C. SUEMITTED LICENSEE EVENT REPORTS (Unit 1)

Occurence LER No. Date Description 95-012 07/11/95 Two Fire Protection system valves were identified as not being verified to be in the correct position within the time frame as required by the Technical specifications.95-014 08/17/95 An automatic Reactor scram occurred due to the

'1D' Reactor Protection System trip which caused a group 1 isolation.95-015 08/24/95 Fire Protection isolation valve 1FP228 was not included in the monthly fire protection system valve surveillance and inturn was not inspected as required by the Technical specifications.

D. DATA TABULATIONS (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 REPORTING REQUIREMENTS (UNIT 1)  !

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1. safety Relief Valve Operations (None)

2. Major Changes to Radioactive Waste Treatment Systems j (None)

3. Static O-Ring Failures (See Attachment A, Note: The attached Static O-Ring Failure was

inadvertantly omitted from the July 1995 Nbnthly Performance 4 Report) i 4

4. Changes to the Off-site Dose Calculation Manual (None) i

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TA8LE 1 0.1 OPERATING DATA REPORT DOCKET Wo. 050 373 UNIT LASALLE ONE DATE October 11, 1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 OPERATING STATUS

1. REPORTING PERIOD: September 1995 GROSS NOURS IN REPORTING PERIOD 720

2. CURRENTLY AUTNORIZED 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):

4. REASONS FOR RESTRICTION (IF ANY):

• REPORTING PERIOD DATA THIS MONTH YEAR TO-DATE CUNULATIVE

5. REACTOR CRITICAL TIME (NOURS) 631.7 6,093.1 72,733.0

6. REACTOR RESERVE SNUTDOWN TIME (NOURS) 0.0 0.0 1,641.2

7. GENERATOR ON LINE TIME (NOURS) 617.9 6,020.0 71,131.1

8. UNIT RESERVE SHUTDOWN TIME (NOURS) 0.0 0.0 1.0 j

9. THERMAL ENERGY GENERATED (MWNt) 1,925,935 19,333,424 212,020,249

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 642,011 6,480,125 70,871,016

11. ELECTRICAL ENERGY GENERATED (MWHe Net) 617,973 6,270,096 68,039,240

12. REACTOR SERVICE FACTOR (%) 87.7 93.0 70.6

13. REACTOR AVAILABILITY FACTOR (%) 87.7 93.0 72.2 j 14. UNIT SERVICE FACTOR (%) 85.8 91.9 69.1

15. UNIT AVAILIBILITY FACTOR (%) 85.8 91.9 69.1

16. UNIT CAPACITY FACTOR (USING MDC) (%) 82.8 92.4 63.8

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (1) 79.6 88.8 61.3

18. UNIT FORCED OUTAGE FACTOR (1) 14.2 5.8 8.1 J

19. SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURAfl0N OF EACH): 01/27/96

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

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t0 *ET No. 050 373 TABLE 2 UNIT LASALLE ONE D.2 AVERA0E DAILY UWlf POWER LEVEL (NWe Net) DATE October 11, 1995 i COMPLETED BY M.J. CIALK0WSKI TELEPN0NE (415) 357 6761 1

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, REPORT PERIOD: September 1995

, DAY POER DAY POWER

< 1 1,050 17 1,069 2 1,044 18 1,072 j 3 1,047 19 1,070 l 4 1,039 20 1,065 l 5 1,044 21 1,064 1

6 1,037 22 1,057

7 1,035 23 1,054 8 1,038 24 167 l

l 9 1.035 25 -13

• 10 1,028 26 12 11 1,040 27 12 12 1,075 28 75 13 1,071 29 350

14 1,069 30 954 1

i 15 1,071 31 i

j 16 1,065 j

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

(UNIT 1)

• METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CC29 DENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if NUMBER (YYledDD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable) 5 950924 F 102.1 A 2 Manual Reactor Scram due to loss of the '1B' Turbine Driven Reactor Feed pump during surveillance testing.

SIBedARY OF OPEILATION:

The unit mined on-line at high power throughout amost of the month. The unit exp.erienced a forced outage on 09/24/95 Cnd was returned to service on 09/28/95. Minor power reductions were required due to rod pattern adjustaments, maintenance end surveillance testing.

ATTACHMENT A

. SOR dp SWITCH FAILURE DATA SHEET Equipment Piece Number: 1PDS-E12N010AA Model Number: 103AS-B202-NX-JJTTX6 serial Number: 92-3-7256 a

Application: 81A' Residual Heat Removal flow pressure differential switch

] Date and Time of Discovery: 07/17/95 1544 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.87492e-4 months <br /> 1

Reactor Mode: 1 (Run) Power Level: 904 i

Calibration Tolerance: 23.6 -

24.4 " w.C.

Nominal setpoint: 23.0 " W.C.

i Action Limits: 3 17.7 or 3 28.3 " W.C.

Reject Limits: 3 15.4 or 3 30.6 " W.C.

Technical specification Limits: 5.9 a W.C.

As Found Setpoint: N/A " W.C.

Date and Time of Return to Service: 07/18/95 1245 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.737225e-4 months <br /> i

Model Number of Replacement switch: 103AS-B202-NX-JJTTX6 i

serial Number of Replacement Switch: 92-5-7835 PIF Number: 373-201-95-01420PIF Cause: switch failed diaphragm integrity test.

Corrective Action: The switch was taken out of service and replaced.

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i LASALLE NUCLEAR POWER STATION j

UNIT 2 l

M NTHLY PERFORMANCE REPORT September 1995 CCDMONNEALTE EDISON CCNPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 i

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TABLE OF CONTENTS (UNIT 2)

I. INTRODUCTION i II. REPORT A. SJteGRY OF OPERATING EXPERIENCE B. AMENDMENTS 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 Steant 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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.c I. INTRODUCTION (UNIT 2)  !

l The Lasalle County Nuclear Power Station is a two-Unit facility owned by Comenonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a @ signed 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 contractor was Comunonwealth Edison Company.

Unit two was issued operating license number NPF-18 on December 16,

1993. Initial criticality was achieved on March 10, 1984 and comunercial power operation was commenced on October 19, 1994.

This report was compiled by Michael J. Cialkowski, telephone number 3

(815)357-6761, extension 2056.

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II. MONTRLY REPORT j A, SUD64kRY OF OPERATING EXPERIENCE (Unit 2) l y D Time Event 1 0000 Reactor critical, Generator on-line at 1030 Mwe. Power j level held due to Main condenser back pressure.

4 0500 Reduced power level to 900 Mwe to take the Circulating Water Pump off-line due to traveling screen repairs.

l 15 1500 Commenced rang down in power for maintenace outage for repairs of the '2A' Reactor Recirculation Flow Control I Valve.

! 16 0750 Manual Reactor scram.

23 1655 Reactor Critical.

, 24 0523 Generator on-line at 60 Mwe.

4 q 26 0434 Generator at 390 Mwe, upshif ted Reactor Recirculation

, Pumps.

d j 0000 Increased power level to 770 Mwe.

j 1030 Increased power level to 930 Mwe.

1900 Reduced power level to 880 Mwe for performance of a rod

, set.

2000 Increased power level to 1000 Mwe.

29 0100 Reduced power level to 740 Mwe for performance of a rod set.

0700 Increased power level to 1130 Mwe.

t j 30 2400 Reactor critical, Generator on-line at 1130 Mwe.

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B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION j

1 Drr September 27, 1995, Amendment 92 was issued to license NPF-lO (Unit 2). This amendment allowed the extension of surveillance test intervals to accommodate the start date change of the LlR07 outage from September 30, 1995 to January 27, 1996.

C. SIG MTfED LICENSEE EVENT REPORTS (Unit 2)

(h'ene)

D. DATA TABULATIONS (Unit 2)

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 REPORTING REQUIREMENTS (UNIT 2)

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1. Safety Relief Valve Operations (None)

2. Major Changes to Radioactive Waste Treatment Systems (None) 1 3. Static O-Ring Failures (None)

4. Changes to the off-Site Dose calculation Manual (None) l 4

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. TABLE 1

' . D.1 OPERATING DATA REPORT DOCKET Wo. 050 374  ;

.* UNIT LASALLE TW i DATE october 11, 1995 COMPLETED SY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 OPERATING STATUS

1. REPORTING PERIOD: Septesber 1995 GROSS NOURS IN REPORTING PERIOD: 720

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe Net): 1,036 DESIGN ELECTRICAL RATING (MWe Met): 1,078

3. POWER LEVEL TO WICH RESTRICTED (IF ANY) (MWe-Net):

4. REASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA THIS MONTH YEAR TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (NOURS) 542.9 3,872.6 69,080.6

6. REACTOR RESERVE SNUTDOWN TIME (NOURS) 0.0 0.0 1,716.9

7. GENERATOR ON LINE TIME (NOURS) 530.5 3,647.0 67,632.5

8. UNIT RESERVE SNUTDOWN TIME (NOURS) 0.0 0.0 0.0

9. THERMAL E M AGY SENERATED (MWHt) 1,393,378 10,939,041 204,690,969

10. ELECTRICAL ENERGY GENERATED (MWHe Gross) 466,474 3,715,124 68,403,693

11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 446,327 3,554,336 65,739,098

12. REACTOR SERVICE FACTOR (%) 75.4 59.1 72.0

13. REACTOR AVAILABILITY FACTOR (%) 75.4 59.1 73.7

14. UNIT SERVICE FACTOR (%) 73.7 55.7 70.5

15. UNIT AVAILISILITY FACTOR (1) 73.7 55.7 70.5

16. UNIT CAPACITY FACTOR (USING MDC) (1) 59.8 52.4 66.1

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 57.5 50.3 63.5

18. UNIT FORCED OUTAGE FACTOR (X) 26.3 4.9 10.3

19. SNUTDOWNS SCHEDULQ OVER THE NEXT 6 MONTNS (TYPE, DATE, AND DURATION OF EACN): N/A

20. IF SNUTDOWN AT END OF REPORT PERIOD, ESilMATED DATE OF STARTUP: N/A

DOCKET No. 050 374 TABLE 2 UNIT LASALLE TWO l

D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe Net) DATE October 11, 1995 i COMPLETED BY M.J. CIALK0WSEI TELEPHONE (815) 357 6761 l

l REPORT PER100: September 1995 DAY POER DAY POWER 1 1,002 17 12 2 1,001 18 12 3 1,003 19 12 4 893 20 -12 5 876 21 -12 6 880 22 12 7 884 23 -12 1 8 890 24 17 l

9 890 25 141 to 887 26 728 l 11 888 27 1,041 l

12 887 28 999 l 13 887 29 1,041 14 883 30 1,092 15 834 31 16 72 1

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"N 3 D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20% *

(UNIT 2)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /COteENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if NUMBER (YDefDD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable) 3 950916 F 189.5 A 2 Nanual Reactor scram for maintenance of the

'2A' Reactor Recirculation flow control valve.

SUbedARY CF OPERATION:

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l Tho unit remained on-line at high power throughout most of the month. The unit experienced a forced outage on l

09/16/95 and was returned to service en 09/24/95. Several minor power reductions were required during the month duo to rod pattern adjustments.

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