ML20083L347

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Apr 1995 for Lasalle County Nuclear Power Station
ML20083L347
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 04/30/1995
From: Cialkowski M, Ray D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9505180279
Download: ML20083L347 (17)
v • d • e


Text

.- Q>mmonwcalth Edison Company 7# f _f. '

. '- 1.aSalle Generating station

  • /'

2(d)I North 2Ist Road

.. Marseilles, 11. 613 4 l-9757 ~

Tcl HI 5-357476I May 12,1995 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for April,1995, t, .

.s D. J. Ray Station Manager LaSalle County Station DJR/mkl Enclosure cc: John B. Martin, Regional Administrator - Region Ill 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 9505180279 950430 PDR ADOCK 05000373 R PDR A i:naum oimiun> l v

pc e

~+ - . .,

v ._

z..... ,

4

)

)

1 l

l LASALLE NUCLEAR POWER STATION UNIT 1

)

NONTELY PERFORMANCE' REPORT April 1995 C004dONNEALTH EDISON COMPANY -

NRC DOCKET NO. 050-373 LICENSE No. NPF-11 L

i-

.i I

?

1 J

l l

l 1

l l

1 l

l 1

J

l TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION II. REPORT A. SISe4ARY 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 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 e

j i

1 1

i l

4

?

. i

.. 1 I. INTRODUCTION (UNIT 1)

~

The LaSalle County Nuclear Power Station is a two-Unit facility owned by Conunonwealth Edison company and located near Marseilles, Illinois.

Each unit is a Boiling Water Reactor with a designed ret 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 Conunonwealth Edison Company.

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

,_' 1982. Initial criticality was achieved on June 21, 1982 and l consnercial power operation was consnenced on January 1, 1984.

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

l

~

. II. MONTHLY REPORT A. Sthe4ARY OF OPERATING EXPERIENCE (Unit 1)

Day Time Event 1 0000 Reactor' critical, Generator on-line at 1140 NWo.

0010 Reduced power level to 1040 NWe to transfer the Heater Drain pumps.

0400 Increased power level to 1140 NWo.

6 2330 Reduced power level to 1050 Nke to transfer the Heater Drain and Condensate pumps.

7 0500 Increased power level to 1140 MWo.

12 2300 Reduced power level to 850 NWe to perform Mkin Steam Isolation valve limit switch testing.

13 0700 Increased power level to 1130 NWo.

21 1300 Reduced power level to 1025 MWe to take the 2nd stage Moisture Seperator Reheater off-line and for the performance of a rod set.

22 0800 Increased power level to 1140 Nke.

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

l I

l

-D. AMENDMENTS TO THE FACILITY OR TECHNICAL CPECIFICATION  !

On April 13, 1995, Anunendment 103 was issued to License NPF-11 (Unit 1). This amendment implemented the General Electric Average Power Range Monitor scram / rod block Technical Specifications (ARTS) analysis for thermal limits monitoring.

C. SUBMITTED LICENSEE EVENT REPORTS (Unit 1)

Occurence LER No. Date Description 95-009 03/15/95 Discrepancies were identified between the Updated Final Safety Analysis Report (UFSAR) description of flood protection features and the actual plant design.

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)

1. Safety Relief Valve Operations (None)
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)

I I

l

..... l

r. TABLE 1 i D.1 OPERATING DATA REPORT--' DOCKET NO. 050-373 UNIT LASALLE ONE l DATE May 11, 1995 I COMPLETED BY M.J. CIALK0WSK!

TELEPHONE (815)-357-6761

' OPERATING STATUS

1. REPORTING PERIOD: April 1995 GROSS HOURS IN REPORTING PERIOD 719 2.' CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036 DESIGN ELECTRICAL RATING (MWe-N 1,0 78
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe Net):
6. REASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA THIS MONTH YEAR-TO-DATE CUMULATIVE  ;

5. REACTOR CRITICAL TIME (HOURS) 719.0 2,748.7 69,388.6
6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 . 1,641.2
7. GENERATOR DN LINE TIME (HOURS) 719.0 2,738.7 67,849.9 ,
8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0
9. VHERMAL ENERGY GENERATED (MWHt) 2,376,301 8,913,066 201,599,891
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 809,583 3,033,977 67,424,868
11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 788,528 2,947,590 64,716,734
12. REACTOR SERVICE FACTOR (%) 100.0 95.5 69.9

?

13. REACTOR AVAILABILITY FACTOR (%) 100.0 95.5 71.5
14. UNIT SERVICE FACTOR (%) 100.0 95.1 68.3
15. UNIT AVAILIBILITY FACTOR (%) 100.0 95.1 68.3
16. UNIT CAPACITY FACTOR (USING MDC) (%) 105.9 98.8 62.9
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 101.7 95.0 60.4
18. UNIT FORCED OUTAGE FACTOR (%) 0.0 4.9 8.1
19. SHUTDOWNS $CHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
20. IF SHUTDOWN AT END OF REPORT PERIDO, ESTIMATED DATE OF STARTUP:

)

l

7_. .

.."H 4 DOCKET NO. 050-373 1ABLE 2 UNIT LASALLE ONE D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DATE May 11, 1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 REPORT PERIOD: April 1995 DAY POWER DAY POWER 1 1,099 17 1,100 2 1,055 lb 1,101 3 1,102 19 1,101 4 1,101 20 1,100 5 1,101 21 1,066 6 1,099 22 1,103 7 1,095 23 1,103 8 1,099 24 1,101 9 1,100 25 1,104 10 1,104 26 1,099 11 1,101 27 1,096 12 1,101 28 1,094 13 1,050 29 1,091 14 1,100 30 1,089 15 1,101 31 16 1,101 i

l l

t_* .;- ' n '_ ,

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

(UNIT 1)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CC0 GENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if NUMBER (YYPe4DD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable)-

(None) t SUM 4ARY OF OPERATION:

l The unit remained on-line at high power throughout the month. Several minor power reductions were required due to maintenance and surveillance activities.

I i

1

r ;.'

ow J

t i

LASALLE NUCLEAR POWER STATION UNIT 2 l HONTELY PERFORMANCE REPORT- I April 1995 CCte40NNEALTH EDISON COMPANY  ;

I t

NRC DOCKET No. 050-374 i

LICENSE No NPF-19 1

l l

l 4

e .-

  • TABLE OF CONTENTS

.(UNIT 2)

I. INTRODUCTION II. REPORT A. S15edhRY OF OPERATING EXPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. LICENSEE EVENT REPORTS D. DATA TABULATIONS t

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 Naste Treatment System
3. Static O-Ring Failures '
4. Off-Site Dose Calculation Manual Changes I

l

1 I

a

-I. INTRODUCTION (UNIT 2)

The LaSalle County Nuclear Power Station is a two-Unit facility owned by Commonwealth 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 blowdown. The architect-engineer was-Sargent and Lundy and the contractor was Commonwealth Edison Company.

Unit two was issued operating license number NPF-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and commercial power operation was commenced on October 19, 1984.

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

1 j

= ~ .

,.. . . =

4 .

]

. *r

  • j L *; II. MONTELY' REPORT )

A. StaemRY JOF OPERATING EXPERIENCE '(Unit 2)

.g Time Event l' 0000 Reactor sub-critical, Generator off-line. Refuel outage  !

(L2R06) in progress. )

30. 2400 Reactor sub-critical, Generator off-line. Refuel outage (L2R06) in progress. l

.j

'B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION- .)

on April 13,.1995, Asumendment 88 was issued to License NPF-18 (Unit 2).

This amendment implemented the General Electric Average Power Range .

Monitor scram / rod block Technical Specifications (ARTS) analysis for '

thermal limits monitoring.'

~

on April 25, 1995, Amendment 89 was issued to license NPF-18 (Unit 2).

This Technical Specification change revised the Safety Relief Valve upper setpoint tolerance from +1% to +3%. i C. SUBMITTED LICENSEE EVENT REPORTS (Unit 2)

Occurence LER No. Date Description j 95-006 03/20/95 During the performance of.the local leak rate testing on the 2RE024 and 2RE025 valves it was '

found that the leakage rate of the valves was 1 too excessive to quantify.

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)

1. Safety Relief Valve Operations (See Atachment A)
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)

l

=

TABLE 1 D.1 OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LASALLE TWO DATE May 11, 1995 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357-6761 OPE 2ATING STATUS

1. REPORTING F.'a100: April 1995 GROSS HOURS IN REPORTING PERIOD: 719
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):
4. REASONS FCR RESTRICTION (!F ANY):

REPORTING PERIOD DATA THIS MONTH YEAR-TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 0.0 1,152.6 66,360.6
6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 F. GENERATOR ON LINE TIME (HOURS) 0.0 1,152.3 65,137.8
8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0
9. THERMAL ENERGY GENERATED (MWHt) 0 3,731,007 197,482,935
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 0 1,281,127 65,969,696
11. ELECTRICAL ENERGY GENERATED (MWHe-Net) -8,016 1,222,866 63,407,628
12. REACTOR SERVICE FACTOR (%) 0.0 40.0 71.9
13. REACTOR AVAILABILITY FACTOR (%) 0.0 40.0 73.7
16. UNIT SERVICE FACTOR (%) 0.0 40.0 70.6
95. UNIT AVAILIBILITY FACTOR (%) 0.0 40.0 70.6 >
16. UNIT CAPACITY FACTOR (USING MDC) (%) *1.1 41.0 66.3
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) -1.0 39.4 63.7
18. UNIT FORCED OUTAGE FACTOR (%) 0.0 0.0 10.4
19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND Dtma;;ON OF EACH):
20. IF SHUTDOWN AT END OF REPORT PERIOD, ESilMATED DATE OF STARTUP:

05/15/95

i DOCKET NO.. 050-374 TABLE 2 UNIT LASALLE TWO D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DATE May 11, 1995 COMPLETED BY M.J. CIALKDWSK!

TELEPHONE (815) 357-6761 REPORT PERIOD: April 1995 DAY POWER DAY POWER 1 -11 17 -11 2 -11 18 11 3 -11 19 -11 4 -11 20 -11 5 11 21 11 6 11 22 -11 7 -11 23 -11 8 11 24 -11 i

9 -11 25 -11 10 -11 26 -11 l

11 11 27 -12 l 12 11 28 12 13 -11 29 12

)

i 14 11 30 12 i 15 -11 31 16 -11

u gn __ * ' ; q . . +

,i ..

TABLE 3 l .

D.3 UNIT SHUTDOWNS AN9 POWER REDUCTIONS > 20%

(UNIT 2) i METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CCteENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER #'if-NUMBER (YDeOD) 3: SCHEDULED (HOURS) REASON REDUCING POWER applicable)

! 1 950218 S 719.0 C 2 Refuel outage (L2R06) 5 i

~i St.DOOLRY OF OPERATION:

The unit was in a scheduled refuel outage for the entire month.

i l

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

Att:chment A l

'. Safety Relief Valve operations l

l The following operations took place with the unit shutdown and with the reactor depressurized as part of routine intentional operability testing.

Date of Type of Reason for Valve Actuation Actuation Actuation 2B21F013A 04/06/95 Manual operability testing 2B21F013B 04/06/95 Manual operability Testing 2B21F013C 04/06/95 Manual operability Testing 2B21F013D 04/06/95 Manual operability Testing 2B21F013E 04/06/95 Manual operability Testing 2B21F013F 04/06/95 Manual operability Testing 2B21F013G 04/06/95 Manual operability Testing 2B21F013H 04/06/95 Manual operability Testing 2B21F013J 04/06/95 Manual operability Testing l 2B21F013K 04/06/95 Manual operability Testing 1 l 2B21F013L 04/06/95 Manual operability Tusting j l 2B21F013N 04/06/95 Manual operability Testing l l 2B21F013P 04/06/95 Manual operability Testing )

2B21F013R 04/06/95 Manual operability Testing )

2B21F013s 04/06/95 Manual operability Testing 2B21F013U 04/06/95 Manual operability Testing 2B21F013V 04/06/95 Manual operability Testing 2B21F013C 04/07/95 Nknual operability Testing 2B21F013D 04/07/95 Manual operability Testing -;

! 2B21F013E 04/07/95 Manual operability Testing 04/07/95 2B21F013R Manual operability Testing i 2B21F013S 04/07/95 Manual operability Testing 2B21F013U 04/07/95 Manual operability Testing 2B21F013V 04/07/95 Manual operability Testing 2B21F013A 04/12/95 Manual operability Testing 2B21F013C 04/12/95 Manual operability Testing 2B21F0130 04/12/95 Manual operability Testing (

2B21F0130 04/12/95 Manual operability Testing -

2B21F013M 04/26/95 Manual operability Testing

- - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ - _ _ _ . _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ - _ - -

Retrieved from "https://kanterella.com/w/index.php?title=ML20083L347&oldid=2746169"