ML20149E254

Monthly Operating Repts for Apr 1994 for LaSalle County Nuclear Station Units 1 & 2

ML20149E254
Person / Time
Site:	LaSalle
Issue date:	04/30/1994
From:	Cialkowski M, Ray D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9405270187
Download: ML20149E254 (16)

Text

y 4[

Q Jf./

/

+.

. Ccmmonw:alth Edison LO

,LaSalle County Nuclear Station 2001 N. 21st. Rd.

Marsellies, Illinois 61341 Tolephone 815/357-6761 May 9,1994 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 April 1994.

p D. J. Ray Station Manager LaSalle County Station DJR/tmb Enclosure cc:

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 - Dowrars Grove Nuclear Fuel Services Manager - General Office QA/NS Off-Site Review - General Office INPO Records Center Station File I

/

/\\

l 9405270187 940430 PDR ADOCK 05000373 R

PDR

4 LABALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT APRIL 1994 COM40NWEALTH EDISON COMPANY NRC DOCKET No. 050-373 LICENSE NO. NPF-11 i

TABLE OF CONTENTS (UNIT 1)

I.

INTRODUCTION II.

REPORT A.

SUbHARY OF OPERATING EXPERIENCE B.

AMENDMENTS TO FACILITI LICENSE OR TECHNICAL DPECIFICATIONS 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 j

4, Off-Site Dose Calculation Manual Changes

~

i j

i l

1

'i l

4

I.

INTRODUCTION (UNIT 1)

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 1070 Nkgawatts. Waste heat is rejected to a man-made cooling pond using the Illinois river for make-up and blowdown. The architect-engineer was Margent 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 (015)357-6761, extension 2427.

I l

l s

s II.

MONTklLY REPCRT A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 1)

Day Time Event 1

0000 Reactor sub-critical, Generator off-line, refuel outage (LlR06) in progress.

30 2400 Reactor sub-critical, Generator off-line, refuel outage (LlR06) in progress.

C.

AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION Deletion of the containment isolation response time testing associated with the diesel generator response times.

Revision to allow the single unit operation while the

'O' diesel generator is out of service for planned maintenance, modifications or su rveillances.

C.

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) 1.

Safety Relief Valve Operations (None) 2.

Nbjor Changes to Radioactive Waste Treatment Systems (None) 3.

Static O-Ring Failures (None) 4.

Changes to the Off-Site Dose Calculation Manual l

(None) l

-~.

l TABLE 1 D.1 CPERATING DATA REPORT DOCKET NO. 050 373 UNIT LASALLE ONE DATE May 9, 1994 COMPLETED BY M.J. CIALK0WSK!

TELEPHONE (815)*357-6761 DPERATING STATUS 1.

REPORTING PERIDO:

April 1994 GROSS HOURS IN REPORTING PERIOD 719 2.

CURRENTLY AUTHORIZED POWER LEVEL (MWt):

3,323 MAX DEPEND CAPACITY (MWe-Net):

1,036 DES!CN 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 PERICO DATA THIS MONTH YEAR TO DATE CUMULATIVE

.5.

REACTOR CRITICAL TIME (HOURS) 0.0 958.3 62,285.2 6.

CEACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2 7.

CENERATOR ON LINE TIME (HOURS) 0.0 946.3 60,960.0 8.

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 1,00G.026 60,254,397

11. ELECTRICAL ENERGY CENERATED (MWHe+ Net) 8,216 943,324 57,792,078

12. REACTOR SERVICE FACTOR (%)

0.0 33.3 68.8-

13. REACTOR AVAILABILITY FACTOR (%)

0.0 33.3 70.6~

14. UNIT SERVICE FACTOR (%)

0.0 32.9 67.3 -

15. UNIT AVAILIBILITY FACTOR (%)

0.0 32.9 67.3 16, UNIT CAPACITY FACTOR (USING MDC) (%)

• 1.1 31.6 61.6'

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

+1.1 30.4 59.2

18. UNIT FORCED OUTAGE FACTOR (%)

0.0 41.4 8.3

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

20. IF SHUTDOWN AT END OF REPORT PER100, ESilMATED DATE OF STARTUP:

06/06/94 i

a

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

[:

a j.

DDCKET NO. 050 373 1

TABLE 2 UNIT LASALLE ONE F

D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe Net)

DATE May 9, 1994

(.

COMPLETED BY M.J. CIALK0WSK!

I TELEPHONE (815) 357-6761 1.

l 1

i REPORT PERIOD April 1994 e

DAY POWER DAY POWER j

1 11 17 12 2

11 18

-12

~

3

-11 19 12 i

f 4

-11 20

-12 5

11 21

-11 l.

6

-11 22

-12 l'

j 7

-11 23

-12 I

8

-11 24

-11 i.

I i

9

-12 25

-12

+

ID 12 26

-12 l.

11 12 27 12 i

12 12 28 11 4

11 13 11 29 i

11 14 '

12 30 i

15 12 31 l-16

-12 B

)

I i '

l l

l l

l?

s'.

4 t

1 r-

,m.

---..rv.

-~.m.

.emc.--...-r

..---nw..,

_..--.-m..we,.n.-w.,w,ou en se..- emer, y

c.,=

TABLE 3

~

D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(UNIT 1)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /CCH4ENTS -

SEQUENTIAL DATE F: FORCED C'JRATION THE REACTOR OR (LER # if WUMBER (YYM4DD)

S: SCHEDULED (HOURS)

REASON REDUCING POWER applicable) 4 040318 S

719.0 C

4-Refuel outage (LIR06).

SUM 4ARY. OF OPERATION:

The ur.it entered the month in a scheduled refuel outage. The units expected return to service is 06/06/94.

L..

.s m.

.,._..im.

.J.

m.

u

.m m

.a m

)

g 9

1 l

4 J

l

'.i LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT

' 1 APRIL 1994

.q COMt40NWEALTH EDISON COMPANY NRC DOCKET No. 050-374 LICENSE NO. NPF-18

..ij i

- l l

1 i

t*

P TABLE OF CONTENTS (UNIT 2)

I.

INTRODUCTION II.

REPORT A.

SUM 4ARY 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-Oite Dose Calculation Manual Changes i

1

)

1

t I.

INTRODUCTION (UNIT 2)

The LaSalle County Nuclear Power Station is a two-Unit facility owned by commonwealth Edison Corpany 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 (015)357-6761, extension 2427.

i

II.

MONTHLY REPORT

'A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 2)

Day Time Event 1

0000 Reactor critical, Generator on-line at 1137 Mwe.

3 0300 Reduced power level to 210 Mwe for main steam isolation valve limit switch testing.

4 1730 Increased power level to 1126 Mwe.

5 1800 Raduced power level to 1045 Mwe due to xenon buildup.

2300 Reduced power level to 780 NMe for performance of a rod set.

6 0400 Increased power level to 1130 Mwe.

7 0000 Reduced power level to 830 Hve due to 24B feedwater heater normal drain valve leakage.

0300 Increased powur level to 995 Mwe.

0530 Reduced power level to 800 Mwe due 21C feedwater heater high level.

8 1800 Increased power level to 1140 Mwe.

10 0100 Reduced power level to 960 Mwe to perform a rod set.

0500 Increased power level to 1140 Mwe.

16 2300 Reduced power level to 1075 Mwe for performance of feedwater system surveillance.

17 0500 Increased power level to 1140 Mwe.

24 2330 Reduced power level to 1070 Mwe, transferred the condensate / condensate booster pumps.

25 0700 Increased power level to 1140 Mwe.

28 1430 Reduced power level to 605 Nwe to take the 2B condensate pump off line due to high vibration levels.

29 0600 Increased power level to 860 Mwe.

30 2400 Reactor critical, Generator on-line at 850 Mwe.

w t '

'B.

AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION Deletion of the containment isolation response time testing associated with the diesel generator response times.

Revision to allow the single unit operation while the

'O', diesel generat<: is out of service for planned maintenance, modifications or surveillances.

C.

LICENSEE EVENT REPORTS (Unit 2)

(None)

D.

DATA TABULATIONS (Unit 2) 1.

Operating Data Report (See Table 1) 2.

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

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

UNIQUE REPORTING 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 (None) i I

i

TABLE 1 a

0.1 OPERATING DATA REPORT DOCKET No. 050 374 UNIT LASALLE TWO DATE May 9, 1994 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357 6761 DPERATING STATUS 1.

REPORIING PERIOD:

Apelt 1994 GROSS HOURS IN REPORTING PERIDO:,

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 RES1RICTED (IF AWf) (MWe Net):

N/A

' 6.

CEASONS FOR RESTRICTION (IF ANY):

REPORTING PERIOD DATA THis MONTH YEAR *TO-DATE CUMULATIVE 5.

REACTOR CRITICAL TIME (HOURS) 719.0 2,664.5 59,590.1 6.

REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 7.

GENERATOR DN LINE TIME (HOURS) 719.0 2,596.7 58,479.1 C.

UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0 9.

THERMAL ENERGY GENERATED (MWHt) 2,208,135 8,226,010 176,326,463

10. ELECTRICAL ENERGY GENERATED (MWHe Gross) 752,603 2,807,867 58,792,507 -

11. ELECTRICAL ENERGY GENEL4TED (MWHe Net) 734,758 2,723,420 56,479,311 12, REACTOR SERVICE FACTOR (%)

100.0 92.5 71.3

13. REACTOR AVAILABILITY FACTOR (%)

100.0 92.5 73.4

14. UNIT SERVICE FACTOR (%)

100.0 90.2 70,0'

15. UNIT AVAILI8ILITY FACTOR (%)

100.0 90.2

~70.0

16. UNIT CAPACITY FACTOR (USING MDC) (%)

98.6 91.3 65.2

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

94.8 87.8 62.7

18. UNIT FORCED OUTAGE FACTOR (%)

0.0 0.0 11.0'

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

l

20. If SHUTDOWN AT END OF REPORT PERIDO, ESilMATED DATE OF STARTUP:

i DOCKET N0'. 050-3F4 TABLE 2 UNii LASALLE TWO

' D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net)

DATE May 9, 1994 COMPLETED BY M.J. CIALK0WSK!

TELEPHONE (815) 357 6761 REPORT PERl00:

April 1994 DAf POWER DAY POWER 1

1,106 17 1,105 2

1,089 18 1,109 3

260 19 1,110 4

709 20 1,109 s

5 1,035 21 1,108 6

1,069 22 1,110 7

809 23 1,110 8

911 24 1,108 9

1,106 25 1,099 10 1,095 26 1,107 11 1,106 27 1,108 12 1,107 28 945 13 1,108 29 820 14 1,109 30 828 15 1,109 31 16 1,111 h

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

(UNIT 2)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / cot 4ENTS SEQUENTIAL DATE F: KRCED DURATION THE REACTOR OR (LER # if WJMBER (YYMMDD)

S: SCHEDULED (HOURS)

REASON REDUCING PCP4ER applicable) 2 940403 S

0.0 B

4 Power level reduction for main steam isolation valve limit switch testing.

3 940407 F

O.0 A

4 Power level reduction to perform maintenance on the 24B feedwater heater normal drain valve and 21C feedwater heater high level.

SL N. 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.

I t.

A