ML20212C450

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Aug 1999 for LaSalle County Station,Units 1 & 2.With
ML20212C450
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 08/31/1999
From: Shaun Anderson, Jamie Benjamin
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9909210272
Download: ML20212C450 (9)
v • d • e


Text

,

(:ommonw calth I dison Comp.in)

I Atlle (icncr.iting St.ition l Rol North list Road {

+ \l.arseilles. ii. (il 3 4 l 9~5' i Tel H L 435 W61 September 15,1999 l

United States Nuclear Regulatory Commission l

Attention: Document Control Desk Washington, D.C. 20555 LaSalle County Station, Units 1 and 2

{

Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374

Subject:

Monthly Operating Report Enclosed is the LaSalle County Station Monthly Operating Report covering the period from August 1,1999 through August 31,1999. This report is submitted in accordance with Technical Specification 6.6.A.5.

Should you have any questions conceming this letter, please contact Mr. Frank A. Spangenberg Ill, Regulatory Assurance Manager, at (815) 357-6761, extension 2383.

Respectfully, xA- v ,

Jef rey A. Benjamin Site Vice President LaSalle County Station Enclosure 7

cc: Regional Administrator - NRC Region Ill J

NRC Senior Resident Inspector - LaSalle County Station 4/ 69%i \\

\

.. ~;j 99o9210272 990831 PDR ADOCK 05000373 R PDR A 1'nicom ( omp.m3

p-: ~

Ia l 1 I

LASALLE COUNTY STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT l COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 50-373 i NRC DOCKET NO. 50-374 i 1

l LICENSE NO. NPF-11 LICENSE NO. NPF-18 1

l i

i l i

]

T 1 TABLE OF CONTENTS iI

1. Monthly Report for LaSalle Unit One A. Operating Data Sumrnary B. Unit Shutdowns and Operating Summary

- C. Unique Reporting Requirements ll. Monthly Report for LaSalle Unit Two A. Operating Data Summary

. B. Unit Shutdowns and Operating Summary-C. Unique Reporting Requirements 1

l

1. Monthly Report for LaSalle County Station Unit One-August,1999 A. OPERATING DATA

SUMMARY

FOR UNIT ONE

. . j DOCKET NO.: 50-373 UNIT: LaSalle One i DATE: September 2,1999 I COMPLETED BY: S. Anderson '

TELEPHONE: (815) 357-6761 x2620

1. Reporting Period: August,1999 Gross Hours: 744
2. Currently Authorized Power Level: 3,323 (MWt)

Design Electrical Rating: 1,078 (MWe-net)

Max Dependable Capacity: 1,036 (MWe-net)

3. Power Level To Which Restricted (if Any): None
4. Reasons For Restriction (if Any): N/A THIS MONTH YEAR-TO-DATE CUMULATIVE
5. Reactor Critical Hours 744 5,831 87,954.9
6. Reactor Reserve 0.0 0.0 1,641.2 Shutdown Hours
7. Hours Generator On- 744 5,831 85,844.6 Line
8. Unit Reserve 0.0 0.0 1.0 Shutdown Hours
9. Gross Thermal 2,315,768 18,286,434 256,965,784 Energy (MWHt)
10. Omss Electric Energy 794,673 6,168,611 86,030,862 (MWHe)
11. Net Electrical Energy 768,571 5,989,423 82,995,549 (MWHe)
12. Reactor Service 100.0 100.0 64.0 Factor (%)
13. Reactor Availability 100.0 100.0 65.2 Factor (%)
14. Unit Service Factor 100.0 100.0 62.5

(%)

15. Unit Availability 100.0 100.0 62.5 Factor
16. Unit Capacity Factor 99.7 99.1 58.3 (MDC)
17. Unit Capacity Factor 95.8 95.3 56.1 (design MWe)
18. Unit Forced Outage 0.0 0.0 13.4 Factor (%)
19. Shutdowns Scheduled Over Next 6 Months: L1R08 - October 23,1999
20. If Shutdown at End of Report Period, Date of Startup: N/A

i B. UNIT SHUTDOWNS AND OPERATING

SUMMARY

i REPORT MONTH AUGUST 1999 NO DATE TYPE (1) DURATION REASON METHOD OF CORRECTIVE ACTIONS /

(HOURS)* (2) SHUTTING COMMENTS DOWN REACTOR (3)

None Year-to-date forced outage hours = 0.0 Cumulative forced outage hours = 13,227.8 TABLE KEY:

(1) (3)

F: Forced Method:

S: Scheduled 1. Manual

2. Manual Scram (2) 3. Automatic Scram Reason: 4. Continuation A Equipment Failure (Explain) 5. Other (Explain)

B Maintenance or Test (

C Refueling D Regulatory Restriction E Operator / Licensing Exam F Administrative G Operational Error (Explain) I H Other (Explain) l

SUMMARY

LaSalle Unit 1 operated at full power for much of the month of August. Unit coastdown began on August 9"'

Prior to coastdown, the unit operated at full power with the exception of the following:

o August 1,1999 0000 - Unit 1 began the month of August at reduced power in order to maintain condensate temperature below administrative limits associated with condensate polisher resins. The unit was operated at approximately 94% core thermal power until a load drop was taken at 0145.

o August 1,1999 0145 - A load drop was taken as requested by Bulk Power Operations. Due to a line loss in Virginia, an over-generation condition existed which necessitated a reduction in the load on LaSalle Unit 1. Scheduled control rod exercising and rod pattern adjustment were moved up and performed during this load drop. Rod pattern adjustment activities were completed at 0950, and the ramp back to full power began at 1018. The ramp back to full power was terminated at approximately 97% core thermal power at 1500 on August 1"in order to maintain condensate temperature below administrative limits associated with condensate polisher resins. The unit was operated at 97% core thermal power until decreasing inlet temperatures allowed the unit to be returned to 100% power at ,

approximately 1000 on August 2"". The originalload drop, including the ramp back to 97% power lasted approximately 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

u

~

l

SUMMARY

-(Continued) 1

)

o August 2,19991735 - A load drop was taken due to concerns with condensate temperature and condenser backpressure. In order to maintain condensate temperature below administrative limits associated with condensate polisher resins, reactor power was reduced approximately 80 MWt. The unit remained at reduced power for the next 8.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

e August 3,19991200 - Due to near end of cycle conditions, the unit began to coast down in power until a load drop could be taken to perform a final, all rods out, rod pattern adjustment on August 5*. Core thermal power coasted down to 98% before this load drop was taken. i e August 5,1990 0001 - A load drop was taken to support condenser waterbox flushing and a control rod pattern adjustment. These evolutions lasted approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Tne ramp back to full power lasted approximately 9.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The unit was returned to full power at 1530 ori August 5*,

o August 8,1999 0534 - A load drop was taken to support control rod exercising. This evolution lasted 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and the unit was returned to full power at approximatley 0730.

  • August 9,19991109 - End of cycle unit coastdown began when Reactor Recirculation Flow Control Valves were taken to the full open position with all control rods, with the exception of those inserted for suppression of a leaking fuel bundle, fully withdrawn. Core thermal power coasted down to 98.6%

before the next scheduled load drop was taken.

o August 15,1999 0330 - A load drop was taken to support scheduled surveillance testing. This load drop, including the subsequent ramp back to full power lasted approximately 5-6 hours, with the unit returning to maximum reactor recirculation flow by 0800. The unit then continued to coastdown, reaching 96.8% of rated core thermal power before the next scheduled load drop was taken, o August 21,19991947 - A load drop was taken to support weekly control rod exercising. This evolution, including the ramp back to full power, lasted roughly 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, with the unit returning to maximum reactor recirculation flow at 2330. The unit then continued to coastdown, reaching 95.2% of rated core thermal power before the next scheduled load drop was taken.

e August 29,1999 0300 - A load drop was taken to support weekly control rod exercising. This evolution, including the ramp back to full power, lasted roughly 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, with the unit returning to maximum reactor recirculation flow at 0534.

Following the load drop taken August 29*, the unit continued to coastdown, with reactor power reaching 94.3%

of rated core thermal power by the end of August.

C UNIQUE REPORTING REQUIREMENTS FOR UNIT ONE

1. Challenges other than routine surveillance testing to Safety / Relief Valve Operations--None
2. Major Changes to Radioactive Waste Treatment System--None

11 Monthly Report for LaSalle County Station Unit Two-August,1999 A. OPERATING DATA

SUMMARY

FOR UNIT TWO DOCKET NO.: 50-374 UNIT: LaSalle Two DATE: September 2,1999 COMPLETED BY: S. Anderson TELEPHONE: (815) 357-6761 x2620

1. Reporting Period: August,1999 Gross Hours: 744
2. Currently Authorized Power Level:~3,323 (MWt)

Design Electrical Rating: 1,078 (MWe-net)

Max Dependable Capacity: 1,036 (MWe-net)

3. Power Level To Which Restricted (if Any): None
4. Reasons For Restriction (if Any): N/A THIS MONTH YEAR-TO-DATE CUMULATIVE
5. Reactor Critical Hours 704.8 3,423.6 80,452
6. Reactor Reserve 0.0 0.0 1,716.9 Shutdown Hours
7. Hours Generator On- 688.9 3,365.5 79,335.7 Une
8. Unit Reserve 0.0 0.0 0.0 Shutdown Hours
9. Gross Thermal 2,168,334 10,696,800 241,219,487 Energy (MWHt)
10. Gross Electric Energy 726,644 3,615,900 80,791,824 (MWHe)
11. Net Electrical Energy 700,474 3,487,355 77,460,998 (MWHe) )
12. Reactor Service 94.7 58.7 61.7 .

Factor (%)

13. Reactor Availability 94.7 58.7 63.0 Factor (%)
14. Unit Service Factor . 92.6 57.7 60.9

(%)

15. Unit Availability 92.6 57.7 60.9 Factor
16. Unit Capacity Factor 90.9 57.7 57.4 (MDC)
17. Unit Capacity Factor 87.3 55.5 55.1 (design MWe) i
18. Unit Forced Outage 7.4 42.3 19.2 l Factor (%)
19. Shutdowns Scheduled Over Next 6 Months: None
20. If Shutdown at End of Report Period, Date of Startup: N/A

I B. _ UNIT SHUTDOWNS AND OPERATING

SUMMARY

(

REPORT MONTH AUGUST 1999 NO DATE TYPE (1) DURATION REASON METHOD OF CORRECTIVE ACTIONS /

(HOURS)* (2) SHUTTING COMMENTS DOWN

. REACTOR (3) 1 8/21/99 F 55.1 G, A 3 A loose mounting plate in the Feedwater Level Control system that contributed to the initiating reactor water level oscillations was repaired during startup.

Tuning of the Feedwater Level Control system was also performed during startup.

Additional training needs were identified to address the human performance issues in the Operations Department.

The operational error which contributed to this shutdown was as follows:

In response to reactor level oscillations, an operator failed to follow the established response procedure, which required that both reactor feed pumps be placed in manual control. The operator instead placed only one feed pump in manual control, which aggravated the situation, leading to the automatic scram on low level. 1 Year-to-date forced outage hours = 2,466.3 l Cumulative forced outage hours = 18,858.6  !

TABLE KEY:

(11 (3)

F: Forced Method:

S: Scheduled 1. Manual

2. Manual Scram (2) 3. Automatic Scram Reason: 4. Continuation A Equipment Failure (Explain) 5. Other (Explain)

B Maintenance or Test C Refueling D Regulatory Restriction E Operator / Licensing Exam F Administrative l G Operational Error (Explain)

H Other (Explain)

1

SUMMARY

LaSalle Unit 2 o'perated at full power throughout the month of August with the exception of the following:

e August 1,1999 0150 - A load drop was taken to support scheduled surveillance testing. This load drop lasted for approximately 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, with the unit returning to full power at 0717.

o August 8,1999 2324 - A 200 MWe load drop was taken at the request of the Load Dispatcher. This load drop, includin the ramp back full power, lasted 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />, with the unit returning to full power at 0820 on August 9' e August 15,1999 0019 - A 200 MWe load drop was taken at the request of the Load Dispatcher. This load drop, including the ramp back full power, lasted approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, with the unit returning to full power at 0957.

  • August 21,1999 2200 - A load drop was taken to support repairs to the potential transformer associated with the 'A' phase of the main generator. At approximately 2250, operations identified that Reactor Water Level was oscillating. Operators attempted to take manual control of one of the two turbine driven reactor feedwater pumps. This action was unsuccessfulin reducing or elitninating the level oscillations, and as the oscillations increased in amplitude, an automatic Scram occurred on low reactor water level at 2255.

A short forced outage schedule was performed following the scram, including rep 8 airs and tuning of the Feedwater Level Control system. Startup activities began at 0626 on August 23 . The reactor was taken critical at 1437 on August 23*, and the generator was placed on line at 0604 on August 24*.

The unit reached full power at 2239 on August 26*. The duration of the forced outage was 55.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and the ramp back to full power lasted 2 days and 18.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

o August 28,1999 0450 - A load drop was taken to support performance of a control rod pattern adjustment. Th!r activity was completed in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The ramp back to full power lasted another 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, with the L. nit returning to full power at approximately 1000. I e

C. UNIQUE REPORTING REQUIREMENTS FOR UNIT TWO

1. Challenges other than routine surveillance testing to Safety / Relief Valve Operations-None
2. Major Changes to Radioactive Waste Treatment Systems-None l l

1 l

Retrieved from "https://kanterella.com/w/index.php?title=ML20212C450&oldid=3246279"