ML20065G468

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Mar 1994 for LaSalle County Nuclear Power Station Units 1 & 2
ML20065G468
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 03/31/1994
From: Cialkowski M, Ray D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9404120289
Download: ML20065G468 (16)


Text

V I '

j. ..

Ccmm:nw: lth Edizon LaSalle County Nuclear Station

. 2601 N 21st. Rd.

Marseilles, lllinois 61341 Telephone 815/357-6761 April 8,1994 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 March 1994.

D. . Ray <rt)

Station Manager LaSalle County Station DJR/tmb Enclosure cc: Mr. John B. Martin - Regional Administrator - Region III NRC Senior Resident Inspector - LaSalle IL Department of Nuclear Safety - LaSalle NRR Project Manager - LaSalle GE Representative - LaSalle Regulatory Assurance Supervisor - LaSalle Manager of Nuclear Licensing - Downers Grove Nuclear Fuel Services Manager - General Office QA/NS Off-Site Review - General Office INPO Records Center Station File

// h ,

9404120289 940331 -i PDR ADOCK 05000373 R PDR

, , . . . _m . . _ . .. . _ . -.

m. l .

5

.. '1

. * .s

. . g.

, l

-1

'l ,

1 i

.J LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT ~

MARCH 1994-COMMONWEALTH EDISON COMPANY -7

'NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 s

k i

.t

+

?

r a

.'i 4

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

i TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION II. REPORT A. .

SUMMARY

OF OPERATING EXPERIENCE B. AMENDHENTS 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 j 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 3

9

'i a

e -

i I. . INTRODUCTION (UNIT-1).

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

Each unit is a Boiling Water Reactor with a designed not electrical.

output of.1078 Negawatts. 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 one was issued operating license number.NPF-11 on. April 17, 1982. Initial-criticality was achieved on June 21, 1982 and commercial power operation was commenced on January 1,' 1984.

This report was complied by Nichael J. Cialkowski, telephone number (815)357-6761, extension.2427.

,j

-l I

I i

R l

i

'i .

i 5 F -

.~

1

~

+

II. MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 1) p_ar ' Ilse Event i 0000 Reactor sub-critical, Generator off-line, forced outage in progress.

18 1100 Commenced refuel outage (L1R06).

31 2400 Reactor sub-critical, Generator off-line, refuel outage (L1R06) in progress.

B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION Increased the Emergency Core Cooling System response times in the Technical Specification based on accident analysis.

Revised the Diesel Generator fuel oil sampling requirements.

C. LICENSEE E7UNT REPORTS (Unit 1)

LER Number Date Description 94-005 03/09/94 Bypassed the upper limit of the auxiliary hoist to provide for the removal of control blades from the reactor vessel.94-006 03/30/94 Component support for the 'B' loop of the Residual Heat Removal system was not completely installed.

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) a
2. Major Changes to Radioactive Waste Treatment Systems (None)
3. Static O-Ring Failures (None) l
4. Changes to the Off-Site Dose Calculation Manual ,

(None) j 1

1

t l

~

-TABLE 1 i D.1 OPERATING DATA REPORT DOCKET NO. 050 373

. UNIT LASALLE ONE DATE April 8,1994' COMPLETED BY M.J. C ALK0WSKI TELEPHONE (815)-357 6761 l OPERATING STATUS

1. ' REPORTING PERIODI March 1994 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 4
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe Net):

4 SEASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA THIS MONTH YEAR TO-DATE CUMULATIVE.

5. DEACTOR CRITICAL TIME (HOURS) 0.0 958.3 62,285.2-
6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2
7. GENERATOR ON-LINE TIME (HOURS) 0.0 946.3 60,960.0 Q. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0
9. THERMAL ENERGY GENERATED (MWHt) 0 2,959,412 180,285,049
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 0 1,000,026 . 60,254,397
11. ELECTRICAL ENERGY GENERATED (MWHe Net) 8,365 951,540 57,800,294
12. REACTOR SERVICE FACTOR (%) 0.0 44.4 69.3

'13. REACTOR AVAILABILITY FACTOR (%) 0.0 44.4 71.1

14. UNIT SERVICE FACTOR (%) 0.0 43.8 67.8

-15.' UNIT AVAILIBILITY FACTOR (%) 0.0 .43.8 67.8

.16. UNIT CAPACITY FACTOR (USING MDC).(%) -1.1 42.5 62.1

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) -1.0 40.9 59.7
18. UNIT FORCED OUTAGE FACTOR (%) 100.0 41.4 8.3
19. SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

Refuel, 03/18/94, 11 Weeks

' 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 06/06/94 "yv-

DOCKET CO.' 050 3F3 TABLE 2 UNIT LASALLE ONE

, D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe Net) DATE April 8,1994 COMPLETED BY M.J. CIALK0WSKI ,

l TELEPHONE (815) 357-6761

.1 REPORT PERIOD: March 1994 j DAY r0WER DAY POWER 1 -12 17 11 2 -12 18 11 3 -11 19 -11 1

1 4 -11 20 11

.l 5 -11 21 -11 6 -11 22 -11 7 -11 23 -11 8 12 24 -11 9 -11 25 -11 10 12 26 11 11 12 27 11

.q 12 11 28 11 l

13 -12 29 11 14 -11 30 -11 15 -11 31 -11 16 -11 .)

1 h .i

-I

TABLE 3 D.3 UNIT SHUTDOWNS AND POWER ? EDUCTIONS > 20%

(UNIT 1)

NETHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER # if NUMBER (YYNMDD) St SCHEDULED (HOURS) REASON REDUCING POWER applicable) 3 940218 F 419.0 A 2 Unit shutdown to repair a main condenser boot. seal leak.

4 940318 S 325.0 C 4 Refuel outage (L1R06).

The unit exited the forced outage and entered into a scheduled refuel outage.

SUMMARY

OF OPERATION:

Tha unit entered the month in a forced outage due to a main condenser boot seal leak. The unit entered a scheduled rsfuel outage on 03/18/94. The month ended with the unit off-line.

i x

L LASALLE NUCLEAR POWER STATION UNIT 2 l

MONTHLY PERFORMANCE REPORT MARCH 1994 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18

?

I 1

'j

4 TABLE OF CONTENTS (UNIT 2)

I. INTRODUCTION II. REPORT A.-

SUMMARY

OF OPERATINO EXPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. LICENSEE EVENT REPORTS D. DATA TA.BULATIONS

1. Operating Data Report j
2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions )

I E. UNIQlfE REPORTINO 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

J

r- ..

lU .

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. Nater Reactor with a designed not electrical output of 1078 Megawatts.LNaste 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.0ctober 19,.1984.~

This report was compiled by Michael J. Cialkowski, telephone number, (815)357-6761,' extension 2427.

l:

t l'

I L,

s D

II. MONTHLY REPORT A.

SUMMARY

OF OPERATING EIPERIENCE (Unit 2) par Time Event 1 0000 Reactor critical, Generator on-line at 1130 Mwe.

0130 Reduced power level to 1070 Mwe, swapped the Condensate / Condensate Booster pumps.

0300 Increased power level to 1136 Mwe.

4 1800 Reduced power level to 1075 Mwe due to control rod drive accumulator failure.

2000 Increased power level to 1128 Mwe.

6 0010 Reduced power level to 1050 Mwe, swapped the condensate / Condensate Booster pumps.

0800 Increased power level to 1126 Mwe.

7 1200 Reduced power level to 1050 Mwe due to control rod drive accumulator problems.

1300 Increased power level to 1100 Mwo.

8 0200 Reduced power level to 885 Mwe to perform a rod set.

0500 Increased power level to 1131 Mwe.

13 0000 Reduced power level to 750 Mwe, 2nd stage feedwater heater taken off-line.

1200 Increased power level to 1116 Mwe, placed the 2nd stage feedwater heater on-line.

15 1600 Reduced power level to 1042 Mwe, 2nd stage feedwater heater taken off-line.

2000 Increased power level to 1121 Mwe.

20 0000 Reduced power level to 1080 Mwe for performance of a feedwater system surveillance.

20 0600 Increased power level to 1130 Mwe.

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

1

m i

. l i

  • j B. AMENDHENTS TO THE FACILITY OR TECHNICAL SPECIFICATION Increased the Emergency Core Cooling System response times in the Technical Specification based on accident analysis, i Revised the Diesel Oenerator fuel oil sampling requirements.

C. 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)
3. Unit Shutdowns and Significant Power Reductions (See Table 3)

E. UNIQUE REPORTINO REQUIREMENTS (UNIT 2)

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 (Hono) l I

l 1

'E:

A l .

TABLE 1 L. D.1 OPERATING DATA REPORT DOCKET NO. 050 374

. . UNIT LASALLE TWO

- DATE April 8,1994 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357 6761 L. OPERATING STATUS

1. REPORTING PER100: Merch 1994 GROSS HOURS IN REPORTING PERIDO: 744
2. CURRENTLY AUTHORIZED POWFP 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. REASON 3 FOR RESTRICTION (if ANY):

REPORTING PERIOD DATA THIS MONTH YEAR-TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 744.0 1,945.5 58,871.1 6.' REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 ~
7. GENERATOR ON LINE TIME (HOURS) 744.0 1,877.7 57,760.1 G. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0
9. THERMAL ENERGY GENERATED (MWHt) 2,424,776 6,017,875 174,118,328
10. ELECTRICAL ENERGY GENERATED (MWHe cross) 829,026 2,055,264 58,039,904
11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 805,869 1,988,662' 55,744,553
12. REACTOR SERVICE FACTOR (%) 100.0 90.1 71.1
13. REACTOR AVAILABILITY FACTOR (%) 100.0 90.1 73.1
16. UNIT SERVICE FACTOR (%) 100.0 86.9 69.7'
15. UNIT AVAILIBILITY FACTOR (%) 100.0 'B6.9 69.7
16. UNIT CAPACITY FACTOR (USING MDC) (%) 104.6 88.9 64.9
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 100.5 85.4 62.4
18. UNIT FORCED OUTAGE FACTOR (%) 0.0 0.0 11.1
19. SHUTDOWNS SCNEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

-I

. 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

a

's

.g ,

DOCKET NO. 050 374 TABLE 2 UNIT LASALLE TWO

. D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DATE April 8,1994 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357-6761 REPORT PERIOD: March 1994 DAY POWER DAY POWER 1 1,097 17 1,090 a 2 1,101 18 1,091 3 1,102 19 1,091 4 1,096 20 1,092 ,

5 1,091 21 1,098 6 1,073 22 1,095 7 1,079 23 1,099 8 1,061 24 1,103 9 1,099 25 1,104 10 1,041 26 1,105 11 1,009 27 1,*06 12 1,043 28 1,106 13 920 29 1,106 14 1,094 30 1,106 15 1,083 31 1,105 s 16 1,092 5

t

?

L I

~

v.

~

TABLE 3 . .

D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 201 (UNIT 2)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DCWN ACTIONS / COMMENTS CEQUENTIAL DATE F FORCED DURATION THE REACTOR OR (LER # if NUMBER (YYMMDD) St SCHEDULED (HOURS) REASON REDUCING POWER applicable)

(None)

SUMMARY

OF OPERATION:

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

_ _ _ _ _ _ _ _ _ _ __ - . _ _ _ _ _ _ _