ML20063G169

Monthly Operating Repts for Jan 1994 for LaSalle County Nuclear Power Station

ML20063G169
Person / Time
Site:	LaSalle
Issue date:	01/31/1994
From:	Cialkowski M, Ray D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9402150349
Download: ML20063G169 (19)

Text

[.-[.

. Commonw;alth Edison LaSalle County Nuclear Station 2001 N. 21st. Rd.

Marseilles, Illinois 61341 Telephone 815/357-6761 February 8,1994 U.S. Nuclear Regulatory Commission Docum:nt Control Desk Washington, D.C. 20555 Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for January 1994.

N Donald J. Ray

'W Station Manager LaSalle County Station DJR/tmb Enclosure cc: Regional Administrator - Region III NRC Senior Resident Inspector - LaSalle IL Department of Nuclear Safety - LaSalle NRR Project Manager - LaSalle GE Representative - LaSalle i Regulatory Assurance Supervisor - LaSalle Manager of Nuclear Licensing - Downers Grove Nuclear Fuel Services Manager - General Office t QA/NS Off-Site Review - General Office INPO Records Center Station File ICAO a .

l 9402150349 940131  ;

DR ADOCK0500g3 lll  !

t 1

P IASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT ,

JANUARY 1994 e

COMMONWEALTH EDISON COMPANY  !

NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 i

t i.

l i

I I

1 i

-. , e , m

TABLE OF CONTENTS (UNIT 1)

I. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE ,

B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. MAJOR CORRECTIVE MAINTENANCE TO SAFET'f-RELATED EQUIPMENT D. LICENSEE EVENT REPORTS E. DATA TABULATIONS

l. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions P. UNIQUE REPORTING REQUIREMENTS

1. Main Steam Safety Relief Valve Operations

2. ECCS System Outages

3. Off-site Dose Calculation Manual changes

4. Major Changes to Radioactive Naste Treatment System

5. Indications of Failed Fuel Elements l

1 1

4 l

l

1 I

I. INTRODUCTION (UNIT.1)  ;

I The LaSalle County Nuclear Power Station is a two-Unit facility owned  ;

by Commonwealth Edison company and located near Marsellies, Illinois. 1 Each unit is a Boiling Water Reactor with a designed net electrical output of'1078 Megawatts. Waste beat 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 compiled by Michael J. Cialkowski, telephone number (815)357-6761, extension 2427.

II. MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 1)

Day Ilme Event ,

1 0000 Reactor critical, Generator on-line at 1123 Mwe. .

22 0200 Commenced power reduction for maintenance outage (LlH05).

r 2059 Manual Reactor scram.

1 31 1740 Reactor critical.

1857 Generator on-line at 60 Mwe.

1948 Main turbine trip due to a moisture separator reheater pressure transmitter controller being out of service.

2400 Reacter arb-critical, Generator off-line.

t I

e

f B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION-(Noue)

C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT (including SOR differential pressure switch failure reports ).

(See Table 1)

D. LICENSEE EVENT REPORTS (Unit 1)

LER Number Date Description 94-001 01/17/94 Primary containment isolation and a 1/2 scram due to loss of the 'B' reactor protection system bus.94-002 01/22/94 Single rod scram during performance of main ,

steam isolation valve scram functional testing, i

E. DATA TABULATIONS (Unit 1)

1. Operating Data Report (See Table 2) l

2. Average Daily Unit Pcwer Level (See Table 3) l

3. Unit Shutdowns and Significant Power Reductions (See Table 4)

F. UNIQUE REPORTING REQUIREMENTS (UNIT 1)

1. Safety Relief Valve Operations (None) .

2. ECCS System Outages >

i Note: The year and unit data has been removed from the outage number.

OUTAGE NO. EQUIPMENT PURPOSE (U-0) 0003 ODG01K Calibrate Pressure gauge.

0012 ODG08CB Replace relief valve.

(U-1) 0052 1E12-N018 Replace instrument stop valve.

0091 1E12-F024B Cable repair.

I

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

4. Major Changes to Radioactive Waste Treatment Systems (None)

5. Indications of Failed Fuel Elements 1 (None)

M C. TABLE 1 (Unit 1) .

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT WORK RESULTS AND EFFECTS REOUEST COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L34893 Diesel Generator Pressure gauge Inaccurate indication Replaced gauge.

air supply L34974 Division II Post Recorder pen motor None Replaced recorder.

LOCA oxygen recorder LAIR-CM048 L75168 Main Steam leakage Packing leak None Repacked valve.

control valve 1E32-F008 L35842 Residual heat Differential pressure None Replaced switch.

removal shutdown switch 1E31-N012BA cooling high flow isolation L26536 Low pressure core Thermal overload None Replaced thermal spray pump room overload, cooling fan lvYO4C L36810 Reactor protection EPA circuit board Output breaker tripped Replaced circuit board.

system motor generator set 1C71-S001B L37027 Average power Alarm relay High alarm up Replaced alarm relay, range monitor high alarm

.(No SOR failures this month.)

V; }

4 TABLE 2 E.1 OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LASALLE ONE DATE February 10, 1994 I COMPLETED BY M.J. CIALKOWSK!

TELEPHONE (815)-357-6761 OPERATING STATUS i

1.~ REPORTING PERIOD: January 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

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): N/A 4 REASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA THIS MONTH YEAR-TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 531.3 531.3 61,858.2

4. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2

7. GENERATOR ON-LINE TIME (HOURS) 525.8 525.8 60,539.5~

{

8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0

0. THERMAL ENERGY GENERATED (MWHt) 1,636,666 1,636,666 178,962,303 ,

10. ELECTRICAL ENERGY GENERATED (MVHe-Gross) 561,354 561,354 59,815,725

11. ELECTRICAL ENERGY CENERATED (MWHe-Net) 538,655 538,655 57,387,409

12. REACTOR SERVICE FACTOR (':) 71.4 71.4 69.9

13. REACTOR AVAILABILITY FACTOR (%) 71.4 71.4 71.8

14. UNIT SERVICE FACTOR (%) 70.7 70.7 68.5

15. U:31T AVAILIBILITY FACTOR (%) 70.7 70.7 68.5 ,

16. UNIT CAPACITY FACTOR (USING MDC) (%) 69.9 69.9 62.6 ,

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 67.2 67.2 60.2

18. UNIT FORCED OUTAGE FACTOR (%) 0.8 0.8 7.5

19. EHUTOOWNS SCHEDULED DVER THE WEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

20. IF $NUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: )

02/01/94 l

u l

.J

i a

. .)'

DOCKET NO. 050-373 ' ]

TABLE 3 UNIT LASALLE ONE l E.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-ket) DATE February 10, 1994

.. .)

COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 l 3

I REPORT PERIOD:~ January 1994 DAY POWER DAY POWER

'l 1 1,078 17 1,030 .j i

2 1,076 18 1,032 <

3 1,074 19 1,028 l l

4 1,070 20 1,028 5 1,068 21 1,015 6 1,065 22 477 7 1,062 23 12 8 1,056 24 -12 9 1,057 25 -12 j 10 1,059 26 12 1

11 1,057 27 -12 12 1,051 28 12 13 1,047 29 -12 14 1,042 30 -12 15 1,041 31 -8 16 1,037 l

TABLE 4 E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 1) .

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED ' DURATION THE REACTOR OR (LER # if NUMBER (YYMMDD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable) 1 940122 S 214.0 B 2 Maintenance outage to replace the '1A' Reactor Recirculation s pump seals (L1MOS).

2 940131 F 4.2 A 4 Turbine trip due to a Moisture Separator Reheater pressure transmitter l high level controller out of service.

i l

SUMMARY

OF OPERATION:

l l Tha unit remained on-line at high power throughout most of the month. The unit commenced a scheduled-maintenance l outage which started on 01/22/94 and lasted 10 days. During the ramp to power the unit experienced a main turbine trip due to a Moisture Separator Reheater pressure transmitter controller being out of service. The unit is expected

to be returned to service on 02/01/94.

i i .-

I

, ., ~J ' -- _ _ _ _ _ _ _ _

E LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT JANUARY 1994 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPP-18

l l

I i

TABLE OF CONTENTS (UNIT 2)

I. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATINO EXPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT D. LICENSEE EVENT REPORTS E. DATA TABULATIONS

1. Operating Data Report '

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions F. UNIQUE REPORTING REQUIREMEh"IS

1. Main Steam Safety Relief Valve Operations

2. ECCS System Outages

3. Off-Site Dose Calculation Manual changes

4. Major Changes to Radioactive Waste Treatment System

5. Indications of Failed Fuel Elements 4

?

1

4 4

i

[

' I. INTRODUCTION (UNIT 2) j The LaSalle County Nuclear Power St'ation'is a two-Unit' facility l owned by Commonwealth Edison Company and located near Marseilles, t Illinois. Each unit is a Boiling Water Reactor with a designed not :i electrical output of-1078 Megawatts. Waste heat is rejected to a i 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, 'l 1983. Initial criticality was achieved on March 10,.1984 and <

commercial power operation was commenced'on October 19,.1984. .J r

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

'l R

I I

.i l

'l l

1

1 i

-i

- +

II. . MONTHLY REPORT A.

SUMMARY

~OF OPERATING EXPERIENCE (Unit 2)

D_ay 1 11me Event 1 0000 Reactor critical, Generator on-line at 840 Mwe.

3 0030 Reduced power level to 695 Mwe to perform rod set.

0700 Increased power level to 1000 Hwe.

4 1500 Increased power level to 1070 Mwe. t 7 2000 Commenced power reduction for maintenance outage (L2M09).

8 0740 Main Turbine tripped.

0805 Manual Reactor scram. l 16 0445 Reactor critical. ,

18 0133 Reactor scram. ,

19 0325 Reactor critical.

20 0200 Generator on-line at 60 Mwe. I 1130 Upshifted Reactor Recirculation Pumps, power level at 390 Mwe. l 1430 Power level at 1010 Mwe.

21 2230 Power level reduced to 835 Mwe to perform rod set.  ;

i 2330 Increased power level to 1000 Mws.

22 1130 Reduced power level to 835 Mwe, placed the 'A' Turbine ,

Driven Reactor Feed Pump on-line.

1800 Increased power level to 1140 Mwe.

23 0800 Reduced power level to 1065 Mwe to perform rod set.

1300 Increased power level to 1130 Mwe.

25 1100 Reduced power level to 1000 Mwe to place the 2nd stage ^

Moisture Separator Reheater off-line.

26 0900 Increased power level to 1135 Mwe.

31 2200 Reduced power level to 1070 Mwe to swap the condensate Booster pumps.

2330 Increased power level to 1130 Mwe.

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

I l

t l

B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION (None) {

C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT (including f SOR differential pressura switch failure reports ).  !

(See Table 1).

D. LICENSEE EVENT REPORTS (Unit 2) l LER Number Date Description 94-001 01/18/94 Reactor scram due to turbine stop valves i being in a closed state during plant -

startup. l E. DATA TABULATIONS (Unit 2) ,

1. Operating Data Report (See Table 2)

2. Average Daily Unit Power Level (See Table 3)

3. Unit Shutdowns and Significant Power Reductions (See Table 4) {

F. UNIQUE REPORTING REQUIREMENTS (UNIT 2)

1. Safety Relief Valve Operations  ;

(Hone)

2. ECCS System Outages Note: The year and unit data has been removed from the outage number.

OUTAGE NO. EQUIPMENT PURPOSE ,

f 0038 2E12-C300B Pump repair.  !

0040 _1

3. Changes'to the Off-Site Dose Calculation Manual ,

(None)

4. Major Changes to Radioactive Waste Treatment Systems (None)

5. Indications of Failed Fuel Elements  !

(None) e i

I i

i i

1

C. TABLE 1 (Unit 2) , ,

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT .

WORK RESULTS AND EFFECTS REQUEST COMPONENT CAUSE OF MALFUNCTION ON_ SAFE PLANT OPERATION CORRECTIVE ACTION LO9370 Low power range LPRM end of life None Replaced LPRM.

monitor 48-49 LO9381 Low power range LPRM end of life None . Replaced LPRM.

monitor 08-17 LO9382 Low power range LPRM end of life None Replaced LPRM.

monitor 40-25 LO9384 Low power range LPRM end of life None Replaced LPRM.

monitor 32-41 LO9386 Low power range LPRM end of life None Replaced LPRM.

monitor 24-57 L18038 Low power range LPRM end of life None Replaced LPRM.

monitor 56-33 L25848 Residual Heat Valve poppet Valve failed Replaced poppet, removal system excess flow check valve 2E12-F315 L26333 Main steam Limit switch Limit switch failed Replaced limit switch.

isolation valve 2B21-F022D L26489 Low power range Ion chamber power supply Power supply output Replaced power monitor 24-09A voltage drifting supply.

L26663 Residual heat Pump bearings None Replaced hearings.

removal system service water pump 2E12-C300B

-1: .

~

C. TABLE-1 (Unit 2)' ,  ;.

MAJOR CORGCTIVE MAINTENANCE TO SAFEIY-RELATED EQUIPMENT WORK RESULTS AND EFFECTS REQUEST COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L26779 Main steam Limit switch No full open indication Replaced limit switch.

isolation valve 2B21-F028B L26780 Main steam Limit switch Valve shows dual Replaced limit switches.

Isolation valve indication.

2B21-F022A (No SOR failures this month)

= c - su e-- +-e----e-- - are se -'+-erswe- a b i -inra-* eear - :+- e - , e e-e u+ me,vw c ev nea-- - ew . - - - -+- e w --- _ - - , - - w ua

I

. l TABLE 2  !

I E.1 OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LASALLE TWO DATE February 10, 1994 5

COMPLETED BY M.J. CIALK0WSK!

TELEPHONE (815) 357-6761~ l OPERATING STATUS-

1. REPORTING PERIOD: January 1994 GROSS HOURS IN REPORTING PERIOD: 744 l

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

I

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): N/A

4. REASONS FOR RESTRICTION (IF ANY): '

REPORTING PERIOD DATA THl3 MONTH YEAR TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS) 529.5 529.5 57,455.1 i

G. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 T'. GENERATOR ON-LINE TIME (HOURS) 461.7 461.7 56,344.1 r

8. UNIT RESERVE SHUTDOWN TIME (HOURS). 0.0 0.0 0.0 ,

i

9. THERMAL ENERGY GENERATED (MWHt) 1,377,826' 1,377,826 169,478,279

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 468,426 468,426 56,453,066

11. ELECTR! CAL ENERGY GENERATED (MWHe-Net) 448,584 448,584 54,204,475

12. REACTOR SERVICE FACTOR (%) 71.2 71.2 70.6 i

13. REACTOR AVAILABILITY FACTOR (%) 71.2 71.2 72.7 l

i

14. UNIT SERVICE FACTOR (%) 62.1 62.1 69.2 1

15. UNIT AVAILIBILITY FACTOR (%) 62.1 62.1 69.2-

16. UNIT CAPACITY FACTOR (USING MDC) (%) 58.2 58.2 64.3 l

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 55.9 55.9 61.7

~l

18. LOli FORCED OUTAGE FACTOR (%) 0.0 0.0 11.4

]

19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

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

1

-

• i DOCKE1 NO. 050-374 TABLE 3 ' UNIT LASALLE TWO E.2 AVERAGE DA!LY UNIT POWER LEVEL (HWe-Net) DATE February 10, 1994 COMPLETED BY H.J. CIALK0WSK!

TELEPHONE (815)-357-6761. >

j REPORT PERIOD: January 1994 DAY POWER DAY POWER 1 798 17 -12 2 785 18 -12 ,

3 918 19 -12 4 988 20 559 5 1,014 21 930 6 1,022 22 995 7 980 23 1,087 8 84 24 1,095 9 -12 25 1,026 10 -12 26 1,079 11 -12 27 1,096 12 -12 28 1,097 13 12 29 1,093 14 -12 30 1,092 1

15 12 31 1,086 j 16 -12 1

\

l l

I l

'4 -

a TABLE 4 .

E.3 UNIT' SHUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 2)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE Ft FORCED DURATION THE REACTOR OR (LER # if NUMBER _ (YYMMDD) St SCHEDULED fHOURS) REASON REDUCING POWER applicable) 1 940108 S 282.3 B 2 Maintenance outage for main steam isolation valve repair (L2M09).

SUMMARY

OF OPERATION:

The unit entered a scheduled maintenance outage. on 01/08/94. During the rarp to power to end the outage the unit experienced a scram due to the main turbine stop valves being in a closed state. The unit was returned to service on 01/20/94. Following the ramp to power the unit remained at high power for the remainder of thi month. Several minor power reductions were required during the month due to maintenance end surveillance activities.

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