ML022960342
| ML022960342 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/15/2002 |
| From: | Tulon T Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GL-97-002, SVP-02-087 | |
| Download: ML022960342 (8) | |
Text
"Exelkn.
Exelon Generation Company, LLC wwwexeloncorp com Nuclear Quad Cities Nuclear Power Station 22710 206" Avenue North Cordova, I L 61242-9740 October 15, 2002 SVP-02-087 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Quad Cities Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
Subject:
Monthly Operating Report for September 2002 In accordance with Technical Specifications, Section 5.6.4, "Monthly Operating Reports," we are submitting this Monthly Operating Report for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2.
Additionally, QCNPS has implemented the relaxation designated in NRC Generic Letter 97-02, "Revised Contents of the Monthly Operating Report," which allowed a reduction in information that was being submitted in the Monthly Operating Report.
These changes are and will be reflected in this and future reports.
Should you have any questions concerning this letter, please contact Mr. Wally Beck at (309) 227-2800.
Respectfully, Timothy J. Tulon Site Vice President Quad Cities Nuclear Power Station Attachment cc:
Regional Administrator-- NRC Region Ill NRC Senior Resident Inspector -
Quad Cities Nuclear Power Station
ATTACHMENT QUAD CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT FOR SEPTEMBER 2002 EXELON NUCLEAR AND MIDAMERICAN ENERGY COMPANY FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 NRC DOCKET NOS. 50-254 AND 50-265 Page 1 of 7
TABLE OF CONTENTS I.
Introduction II.
Summary of Operating Experience A.
Unit One B.
Unit Two Ill.
Operating Data Statistics A.
Operating Data Report - Quad Cities Unit One B.
Operating Data Report - Quad Cities Unit Two IV.
Unit Shutdowns A.
Unit One Shutdowns B.
Unit Two Shutdowns V.
Challenges to Safety and Relief Valves Page 2 of 7
- 1. INTRODUCTION Quad Cities Nuclear Power Station is composed of two Boiling Water Reactors and Steam Turbine/Generators located in Cordova, Illinois. Unit One has a Maximum Dependable Capacity of 769 MWe Net, and Unit Two has a Maximum Dependable Capacity of 855 MWe Net. The Station is jointly owned by Exelon Nuclear and MidAmerican Energy Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The Architect/ Engineer was Sargent &
Lundy, Incorporated, and the primary construction contractor was United Engineers &
Constructors. The Mississippi River is the condenser cooling water source. The plant is subject to license numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, respectively, pursuant to Docket Numbers 50-254 and 50-265. The dates of initial Reactor criticality for Units One and Two were October 18, 1971, and April 26, 1972, respectively. Commercial generation of power began on February 18, 1973, for Unit One and March 10, 1973, for Unit Two.
Page 3 of 7
II.'
SUMMARY
OF OPERATING EXPERIENCE A. Unit One Unit One operated the month of September at full power except for a planned load drop to approximately 500 MWe from September 07, 2300 until September 10, 0100 for scram timing and rod pattern adjustment. Another planned load drop to approximately 555 MWe occurred from September 21, 2300 until September 22, 1553 for a planned control rod shuffle. Another planned load drop to approximately 605 MWe occurred from September 28, 0109 until September 28, 2200 for a planned feedwater heater repair.
B. Unit Two Unit Two operated the month of September at full power with the exception of a planned load drop to approximately 550 MWe on September 14, 2300 until September 15, 1903 for control rod pattern adjustment and control rod scram timing.
Page 4 of 7
Jlb 1
III.
OPERATING DATA STATISTICS A.
Quad Cities Unit One Operating Data Report for September 2002 DOCKET NO.:
50-254 DATE:
October 15, 2002 COMPLETED BY: Tom Petersen TELEPHONE:
(309) 227-2825 OPERATING STATUS REPORTING PERIOD: September 2002 GROSS HOURS IN REPORTING PERIOD: 720 CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511
- 1.
DESIGN ELECTRICAL RATING (MWe-Net): 789
- 2.
MAX. DEPEND. CAPACITY (MWe-Net): 769 UNIT 1 OPERATING STATUS PARAMETER THIS MONTH YTD CUMULATIVE
- 3.
NUMBER OF HOURS THE REACTOR WAS CRITICAL 720.00 5916.50 207949.30
- 4.
HOURS GENERATOR ON-LINE 720.00 5874.00 202612.60
- 5.
UNIT RESERVE SHUTDOWN HOURS 0.00 677.00 1655.20
- 6.
NET ELECTRICAL ENERGY GENERATED (MWH) 540557.00 4405619.00 132920008.00 Page 5 of 7
III.
OPERATING DATA STATISTICS B.
Quad Cities Unit Two Operating Data Report for September 2002 DOCKET NO.:
DATE:
COMPLETED BY:
TELEPHONE:
50-265 October 15, 2002 Tom Petersen (309) 227-2825 OPERATING STATUS REPORTING PERIOD: September 2002 GROSS HOURS IN REPORTING PERIOD: 720 CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2957 DESIGN ELECTRICAL RATING (MWe-Net): 867 MAX. DEPEND. CAPACITY (MWe-Net): 855
- 1.
2.
UNIT 2 OPERATING STATUS PARMETER THIS MONTH YTD CUMULATIVE
- 3.
NUMBER OF HOURS THE REACTOR WAS CRITICAL 720.00 5741.80 200286.10
- 4.
HOURS GENERATOR ON-LINE 720.00 5643.00 195462.15
- 5.
UNIT RESERVE SHUTDOWN HOURS 0.00 908.00 2312.90
- 16.
NET ELECTRICAL ENERGY GENERATED (MWH) 634073.00 14604905.00 133463075.00 Page 6 of 7 t
IV. UNIT SHUTDOWNS A. Unit ONE Shutdowns for September 2002 NO.
DATE TYPE DURATION REASON (2)
METHOD CORRECTIVE (1)
(HOURS)
OF ACTIONS/COMMENTS SHUTTING DOWN (3)
None B. Unit TWO Shutdowns for September 2002 NO.
DATE TYPE DURATION REASON (2)
METHOD CORRECTIVE FOR (1)
(HOURS)
OF ACTIONS/COMMENTS YEAR SHUTTING DOWN (3)
None Legend (1) TYPE (2) REASON (3) 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. OperatorTraining/License
- 5. Other (Explain)
Examination F. Administrative G. Operational Error (Explain)
I H. Other (Explain)
Page 7 of 7 V. CHALLENGES TO SAFETY AND RELIEF VALVES