ML040490527

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January 2004 Monthly Operating Report for Braidwood Station, Units 1 and 2
ML040490527
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 02/12/2004
From: Joyce T
Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BW040019
Download: ML040490527 (4)


Text

ExekanM Exelon Generation Company, LLC www.exeloncorp.com Nuclear Braidwood Station 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 Tel. 815-417-2000 February 12, 2004 BWO40019 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457

Subject:

Monthly Operating Report In accordance with Technical Specification 5.6.4, " M onthly Operating Reports," we are submitting the Monthly Operating Report for Braidwood Station, Units 1 and 2. This report covers the period of January 1, 2004 through January 31, 2004.

If you have any questions regarding this letter, please contact Ms. Kelly Root, Regulatory Assurance Manager, at (815) 417-2800.

Respectfully, T. P. Jo Site Vice President Braidwood Station Attachment DH/Iaw cc: Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - Braidwood Station

>BY't

ATTACHMENT BRAIDWOOD STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT EXELON GENERATION COMPANY, LLC FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 NRC DOCKET NOS. STN 50-456 AND STN 50-457

Docket No: 50-456 Unit: Braidwood I Date: 02/04/2004 Completed by: Don Hildebrant Telephone: (815)417-2173 Braidwood Unit 1 Reporting Period: January 2004 A. OPERATING DATA REPORT IDesign Electrical Rating (MWe Net) 1187 l Maximum Dependable Capacity (MWe Net) 1161 l Month I Year To Date Cumulative Hours Reactor Critical (Hours) 744.0 744.0 115,611.6 Hours Generator on Line (Hours) 744.0 744.0 114,638.8 Unit Reserve Shutdown (Hours) 0.0 0.0 0.0 Net Electrical Energy (MWh) 868,918 868.918 124,061,105 B. UNIT SHUTDOWNS TYPE REASON METHOD F - Forced A - Equipment Failure (explain) I - Manual S - Scheduled B - Maintenance or Test 2 - Manual Trip / Scram C - Refueling 3 - Automatic Trip / Scram D - Regulatory Restriction 4 - Continuation E - Operator Training / Licensee Examination 5 - Other (explain)

F - Administrative G - Operator Error (explain)

H - Other (explain)

N Date Type Duration Reason Method Cause and Corrective Actions and Hours Comments None

SUMMARY

The Unit started the month at reduced power due to on going maintenance on valve I FW009A.

On 1/3/04 the Unit was returned to 100% power and operated normally for the remainder of the month.

C. SAFETY I RELIEF VALVE OPERATIONS Date Valves Actuated No. & Type Plant Condition Description of Event I Actuation l_

None I Data From: Production Data Bank and Operator Logs

Docket No: 50-457 Unit: Braidwood 2 Date: 02/04/2004 Completed by: Don Hildebrant Telephone: (815)417-2173 Braidwood Unit 2 Reporting Period: January 2004 A. OPERATING DATA REPORT IDesign Electrical Rating (MWe Net) 1155 lMaximum Dependable Capacty (MWe Net) l 1154 l Month Year To Date Cumulative Hours Reactor Critical (Hours) 744.0 744.0 119,177.3 Hours Generator on Line (Hours) 744.0 744.0 118,528.9 Unit Reserve Shutdown (Hours) 0.0 0.0 0.0 Net Electrical Energy (MWh) 869,782 869,782 128,008,582 B. UNIT SHUTDOWNS TYPE REASON METHOD F - Forced A - Equipment Failure (explain) I - Manual S - Scheduled B - Maintenance or Test 2 - Manual Trip / Scram C - Refueling 3 - Automatic Trip / Scram D - Regulatory Restriction 4 - Continuation E - Operator Training / Licensee Examination 5 - Other (explain)

F - Administrative G - Operator Error (explain)

H - Other (explain)

No Date Type Duration Reason Method Cause and Corrective Actions and None_________ Hours _ Comments

_ None ____ ==_ _ _ _ _ __ _ _ _ _ _ _ _

SLUMMARY The Unit operated normally at full power until 1/21/04 when a failure in the control circuit for 2MS009A-D resulted Ina minor power loss. On 1/26/04 power was manually reduced to enable the installation of a tracer injection port on the 27A FW Heater in support of FW Tracer flow testing scheduled in February.

C. SAFETY I RELIEF VALVE OPERATIONS Date lValves Actuated No. & Type Plant Condition Description of Event II

l. Actuation None l Data From: Production Data Bank and Operator Logs