ML20100F769

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Jan 1996 for LaSalle County Nuclear Power Station
ML20100F769
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 01/31/1996
From: Cialkowski M, Ray D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9602220135
Download: ML20100F769 (16)
v • d • e


Text

_ _ _

e 1

_, Commonwealth Edison Compan)

,q laSalle Generating Station

(' Rd)I North 21st Road

    • 1 hl'.trseilles, iL 613 i 1-975" Tel H j 5 35' 6761

)

1 February 12,1996 l

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

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for January,1996.

J. Ray

[b VA

/ tation Manager LaSalle County Station DJR/mkl l Enclosure l 1

cc: H. J. Miller, Regional Administrator - Region III I NRC Senior Resident Inspector - LaSalle j IL Department of Nuclear Safety - LaSalle i IL Department of Nuclear Safety - Springfield, IL NRR Project Manager - Washington, D.C. l 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 9602220135 960131 PDR ADOCK 05000373 R pyg A tinicom Company 16%

If q

i .

l

. 1 l

i J

IA5ALLE NUCLEAR POWER STATION UNIT 1 MONTELY PERIORMANCE REPORT January 1996 Cate00NNEALTH EDISON C MPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11

TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION II. REPORT A. SCtedhRY OF OPERATING EXPERIENCE

)

5. n n N NTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATI0 TIS l I

C. LICENSEE EVENT REPORTS l

D. DATA TABUIATIORIS ,

1. Operating Data Report I
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 Systesa
3. Static O-Ring Failures
4. Off-site Dose calculation Manual Changes l

l

I. INTRODUCTIcel (UNIT 1)

The LaSalle County Nuclear Power Station is a two-Unit facility owned by commonwealth Edison Company and located near Marseilles, 1111acis. 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 contractor was cessnonwealth Edison Company.

Unit one was issued operating license number NPF-11 on April 17, 1982. Initial criticality was achieved on June 21, 1982 and acammercial power operation was ocumenced on January 1,1984.

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

- . . - x-

s j- ,II . ,MONTELY REPORT A. StBe(ARY OF OPERATING EXPERIENCE (Unit 1) l D E Time Event

.i 1 0000 Reactor critical, Generator on-line at 060 Mwe,

, unit in coastdown for upocaing refuel outage.

, 12 1300 Reduced power level to 790 Mwe for performance of a rod set.

{

1600 Increased power level to 840 Mwe.

i 23 0100 Reduced power level to 750 Mwe to take the Condensate / Condensate Booster Pump off-line. )

i 0200 Increased power level to 800 Mwe.

J l 25 0617 Main Turbine trip, cosnenced refuel outage (L1R07).

i 0932 Manual reactor scram.

31 2400 Reactor sub-oritical, Generator off-line, refuel cuatge in progress.

1

3. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION On January 3, 1996, Amendment 100 was issued to license NPF-11 (Unit 1). This amendment revised the Safety Relief Valve setpoint tolerance from +3,-04 to +36.

C. SUBMITTED LICENSEE EVENT REPORTS (Unit 1)

(None)

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) 4

1. Safety Relief Valve Operations (None) 1
2. Major Changes to Radioactive Waste Treatment Systems (None)
3. Static O-Ring Failures (None)
4. Changes to the Off-Site Dose Calculation Manual

, (None)

s TABLE 1 0.1 OPERATING DATA REPORT DOCKET NO. 050 373 UNIT LASALLE ONE DATE February 9, 1996 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 OPERATING STATUS

1. REPORTING PERIOD: January 1996 GROSS HOURS 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 e
3. POWE2 LEVEL TO WHICH RESTRICTED (IF ANY) (MWe Net):
4. REASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA

, THIS MONTH YEAR TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 585.5 585.5 75,527.5
6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2 4
7. GENERATOR ON LINE TIME (HOURS) 582.3 582.3 73,922.4
8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0

, 9. THERMAL ENERGY GENERATED (MWHt) 1,411,768 1,411,768 219,866,585

10. ELECTRICAL ENERGY GENERATED (MWHe Gross) 470,404 470,404 73,514,256
11. ELECTRICAL ENERGY GENERATED (MWHe Net) 449,263 449,263 70,587,691
12. REACTOR SERVICE FACTOR (%) 78.7 78.7 71.3 4
13. REACTOR AVAILABILITY FACTOR (%) 78.7 78.7 72.8
16. UNIT SERVICE FACTOR (%) 78.3 78.3 69.8 1 15. UNIT AVAILIBILITY FACTOR (%) 78.3 78.3 69.8
16. UNIT CAPACITY FACTOR (USING MDC) (%) 58.3 58.3 64.3
97. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 56.0 56.0 61.8
18. UNIT FORCED OUTAGE FACTOR (%) 0.0 0.0 7.8
19. $ HUT 00WNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): REFUEL, 01/25/96, 9 WEEKS
30. IF SHUTDOWN AT END OF REPORT PERl00, ESTIMATED DATE OF STARTUP: 03/29/96 i

1

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

DOCKET NO. 050-373 TABLE 2 UNIT LASALLE ONE D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe Net) DATE February 9, 1996 COMPLETED BY M.J. CIALK0WSK(

TELEPHONE (815) 357 6761 REPORT PERIOD: January 1996 DAY POWER DAY POWER 1 807 17 784 2 803 18 779 3 800 19 774 4 796 20 769 5 795 21 766 6 792 22 761 7 789 23 758 8 785 24 728 9 781 25 50 10 776 26 12 11 775 27 12 12 782 28 -12 13 787 29 12 14 780 30 -12 15 787 31 12 16 787 i

m .___ ._. --

TABLE 3 .

D.3 UNIT SHUTDONNS AND POWER REDUCTIONS > 200 c (UNIT 1)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /COBSENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if NUMBER (YYtetDD) 5: SCHEDULED (HOURS) REASON REDUCING POWER applicable) 01 960125 S 161.7 C 2 Refuel outage (L1R07)

SIDE (ARY OF OPERATION: The unit started the month in a coastdown condition for the pending refuel outage.

The Main Turbine was A w ved from service and the Reactor was manually scramed on 01/25/96 to start refuel outage L1RO7.

f 1

I 1

IJUELLE NUCLEAR POWER STATION UNIT 2 MONTELY PERPORMhMCE REPORT January 1996 CCBMOMMEALTE EDISON CCMPANY MRC DOCKET NO. 050-374 ,

l LICENSE NO. NPF-18 t

i 1

s i

TABLE OF CONTENTS (UNIT 2) l l

I. INTRODUCTION II. REPORT i

l A. St3 MARY OF OPERATING EXPE3 FENCE B. W N N NTS TO FACILITY LICENSE OR TECENICAL SPECIFICATIONS C. LICENSEE EVENT REPORTS  ;

l 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 4

I. INTRODUCTICM (UNIT 2)

The LaSalle County Nuclear Power station is a two-Unit facility owned by commnonwealth Edison Company and located near Marseiller, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste heat is rejected to a j man-made cooling pond using the Illinois river for make-up and blowdown. The architect-engineer was Sargent and Lundy and the contractor was ccannonwealth Edison Company.

I Unit two was issued operating license number NPF-18 on Der ==har 16, 1983. Initial criticality was achieved on March 10, 1984 and commercial power operation was ocamnenced on October 19, 1984.

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

I 1

I 1

1 1

1 1

l l

l l

l l

,,II . MONTELY REPORT A. StBMARY OF OPERATING EXPERIENCE (Unit 2) g Time Event l 1 0000 Reactor critical, Generator on-line at 1130 Mwe.

0255 Reduced power level to 1035 Mwe due to system load.

1000 Increased power level to 1130 Mwe.

5 0130 Reduced power level to 1075 Mwe to swap the Condensate pumps.

0430 Increased power level to 1130 Mwe.

2200 Reduced power level to 815 Mwe for repair of a ,

l

'22A' Feedwater Beater valvs and performance of scram time testing.

6 1030 Increased power level to 1130 Mwe.

13 2000 Reduced power level to 750 Mwe for repair of a

'22A' Feedwater Beater valve and a Turbine Control Valve.

14 2000 Increased power level to 1030 Mwe.

15 1800 Ir. creased power level to 1130 Mwe.

20 1300 Reduced power level to 1065 Mwe to swap the Condensate pumps.

2200 Increased power level to 1130 Mwe.

22 2140 Reduced power level to 750 Mwe for testing to identify a possible fuel failure.

25 1330 Increased power level to 950 Mwe.

26 2330 Reduced power level to 900 Mwe to place the Turbine-Driven Reactor Feed Puep on-line.

28 0200 Increased power level to 1130 Mwe.

31 2400 Reactor critical, Generator on-line at 1130 Mwe.

D. M W58NTS TO THE FACILITY OR TECHNICAL SPECIFICATION

, ., (None)

C. SU M TTED LICENSEE EVENT REPORTS (Unit 2)

(None)

D. DATA TABU 1ATIONS (Unit 2)

1. Operating Data Report (See Ts.ble 1)
2. Average Daily Unit Power Level (See Table 2)
3. Unit Shutdowns and Significant Power Reductions (See Table 3)

E. UNIQUE REPORTING REQUIR M 1TS (UNIT 2)

1. Safety Relief Valve Operations (None)
2. Major Changes to Radioactive Naste Treatment Systeens (None)
3. Static O-Ring Failures (None)
4. Changes to the Off-Site Dose calculation Manual (None)

.. ~.

TABLE 1 D.1 OPERATING DATA REPORT DOCKET Wo. C50-374 UNIT LASALLE TWO DATE February 9, 1996 COMPLETED BY M.J. CIALK0WSKI ,

TELEPHONE (815) 357-6761 l DPERATING STATUS 1

1. REPORTING PERIOD: January 1996 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 Net): 1,078
3. POWER LEVEL TO WHICH RESTRICTED (!F ANY) (MWe-Net):
6. REASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA THIS MONTH YEAR TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 744.0 744.0 72,033.6
6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9
7. GENERATOR ON LINE TIME (HOURS) 744.0 744.0 70,585.5
8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0
9. THERMAL ENERGY GENERATED (MWHt) 2,341,473 2,341,473 214,310,728
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 801,419 801,419 71,699,275
11. ELECTRICAL ENERGY GENERATED (MWHe Net) 772,818 772,818 68,925,490
13. REACTOR SERVICE FACTOR (%) 100.0 100.0 72.8
13. REACTOR AVAILABILITY FACTOR (%) 100.0 100.0 74.5
10. UNIT SERVICE FACTOR (%) 100.0 100.0 71.3
15. UNIT AVAILIBILITY FACTOR (%) 100.0 100.0 71.3
16. UNIT CAPACITY FACTOR (USING MDC) (%) 100.3 100.3 67.2
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 96.4 96.4 64.6
18. UNIT FORCED OUTAGE FACTOR (%) 0.0 0.0 9.9
19. SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURAT!DN OF EACH): N/A 1 I
20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A I

1 1

l I

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

4 l

)

1

. ~.

1 DOCKET NO. 050 374 )

TABLE 2 UNIT LASALLE TWO '

D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe Net) DATE February 9, 1996 COMPLETED BY M.J. CIALK0W$K!

TELEPHONE (815)-357-6761

REPORT PERIOD
January 1996 DAY POWER DAY POWER 1 1,082 17 1,096 2 1,096 18 1,094 3 1,096 19 1,095 4 1,091 20 1,081 5 1,085 21 1,096 6 1,009 22 1,069 7 1,095 23 616 8 1,097 24 710 9 1,096 25 871 10 1,099 26 927 11 1,098 ?T 993 12 1,098 28 1,098 13 1,061 29 1,100 14 882 30 1,101 15 1,071 31 1,100 1

16 1,096 i

j i

l i

TABLE 3 D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 204 (UNIT 2)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CCBedENTS SEQUENTIAL DATE F: FURCED DURATION THE REACTOR OR (LER # if NIABER (YY M D) S: SCHEDUIED (HOURS) REASON REDUCING POWER applicable) 01 960123 F 0.0 B 4 Power reduction for testing to identify a possible fuel failure.

l SIEGERY OF OPERATION: The unit remained on-line at high power throughout the month. Several minor power reductions were required during the month due to amaintenance, surveillance and testing activities.

_ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ - - _ - _ --- _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ . . - - ______ - ________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _

Retrieved from "https://kanterella.com/w/index.php?title=ML20100F769&oldid=2777820"