ML040210740

December 2003 Monthly Operating Report for Braidwood Station Units 1 and 2

ML040210740
Person / Time
Site:	Braidwood
Issue date:	01/13/2004
From:	Joyce T Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BW040005
Download: ML040210740 (5)

Text

intf ExelwE. S.

Exelon Generation Company, LLC Braidwood Station www.exeloncorp.com Nuclear 35100 South Rt 53, Suite 84 Braceville, IL60407-9619 Tel. 815-417-2000 January 13, 2004 BW040005 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, "Monthly Operating Reports," we are submitting the Monthly Operating Report for Braidwood Station, Units 1 and 2. This report covers the period of December 1, 2003 through December 31, 2003.

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

Respectfully, I.

T. P. Jo ce7 Plant Manager Braidwood Station Attachment DH/law cc: Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - Braidwood Station I

C--,--Iq

bcc: Project Manager, NRR - Braidwood Station Office of Nuclear Safety - Illinois Emergency Management Agency Manager of Energy Practice - Winston & Strawn Site Vice President - Braidwood Station Vice President - Licensing and Regulatory Affairs Regulatory Assurance Manager - Braidwood Station Director, Licensing and Regulatory Affairs Manager, Licensing - Braidwood, Byron and LaSalle County Stations Nuclear Licensing Administrator - Braidwood and Byron Stations Exelon Document Control Desk Licensing (Hard Copy)

Exelon Document Control Desk Licensing (Electronic Copy)

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: 01/0612004 Completed by. Don Hildebrant Telephone: (815)417-2173 Braidwood Unit 1 Reporting Period: December 2003 A. OPERATING DATA REPORT Design Electrical Rating (MWe Net) 1187 Maximum Dependable Capacity (MWe Net) - 1161 l I .. . I... ..

I Month I Year To Date I Cumulative I Hours Reactor Critical (Hours) 744.0 8,363.1 114,867.6 Hours Generator on Line (Hours) 744.0 8,352.0 113,894.8 Unit Reserve Shutdown (Hours) 0.0 0.0 0.0 Net Electrical Energ (MWh) 898,462 10,094.767 123,192.187 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 Hours Comments None

SUMMARY

The Unit performed normally at full load until 12/31/03 when load was reduced to 25% power to perform maintenance on valve 1FW009A. CR 192791 decribes this event.

C. SAFETY / RELIEF VALVE OPERATIONS Date Valves Actuated No. & Type Plant Condition Description of Event e Actuation NoneIII Data From: Production Data Bank and Operator Logs

Docket No: 50-457 Unit: Braidwood 2 Date:.01/06/2004 Completed by- Don Hildebrant Telephone: (815)417-2173 Braidwood Unit 2 Reporting Period: December 2003 A. OPERATING DATA REPORT Desiqn Electrical Rating (MWe Net) 1155 Maximum Dependable Capacity(MWe Net) l 1154 Month Year To Date Cumulative .'

Hours Reactor Critical (Hours) 719.8 8,377.8 118,433.3 Hours Generator on Line (Hours) 694.0 8,337.5 117,784.9 Unit Reserve Shutdown (Hours) 0.0 0.0 0.0 Net Electrical Energy (MWh) 804.786 9,932,165 127,138,800 B. UNIT SHUTDOWNS TYPE REASON METHOD F- Forced A - Equipment Failure (explain) 1 - 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 Dat Type Duration Reason Method Cause and Corrective Actions and Hours Comments 3 12/03/2003 F 50.62 A 3 A2F37 caused by old broken tie wrap

_. _______ _______ _______ blocking switch contacts.

SUMMARY

The Unit performed normally at full power except for a Unit trip on 12/03/03 caused by control problems on a Feed Pump Turbine during routine testing. Following Feed Pump Turbine repairs, returning the Unit to full power was delayed due to several FW Heater relief valve failures. CR 188874 and 189150 describe these issues.

C. SAFETY / RELIEF VALVE OPERATIONS Date Valves Actuated No. & Type Plant Condition Description of Event None Actuation l I NoneII Data From: Production Data Bank and Operator Logs