NG-03-0272, March 2003 Monthly Operating Report for Duane Arnold Energy Center

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March 2003 Monthly Operating Report for Duane Arnold Energy Center
ML031130137
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 04/15/2003
From: Peifer M
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GL-97-002, NG-03-0272
Download: ML031130137 (8)


Text

NIii Committed to Nuclear Excellence Duane Arnold Energy Center Operated by Nuclear Management Company, LLC April 15, 2003 NG-03-0272 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station O-P1-17 Washington, DC 20555-0001

Subject:

Duane Arnold Energy Center Docket No: 50-331 Operating License: DPR-49 March 2003 Monthly Operating Report File: A-118d Please find enclosed the Duane Arnold Energy Center Monthly Operating Report. The report has been prepared in accordance with the guidelines of NRC Generic Letter 97-02: Rev!sePd Contents Of The Monthly Operating Report, and distribution has been made in accordance with DAEC Technical Specifications, Section 5.6.4.

Very truly yours, Site Vice-President MAP/RBW Enclosures 1/2 I - I,

- I . .... I.....

I . I . .

I'" ~'I - -, ,'-..r 'r'g-> - '-*

I ; , I ; r ,

3277 DAEC Road

  • Palo, Iowa 52324-9785 Telephone 319 851.7611

April 15, 2003 NG-03-0272 Page 2 of 2 cc:

Mr. James E. Dyer Ms. Parveen Baig Regional Administrator, Region m _ Iowa State Utilities Board __

U.S. clear igulatory Commission Lucas State Office Building 801 Warrenville Road Des Moines, IA 50319 Lisle, IL 60532-4351 Ms. Barbara Lewis Dr. William A. Jacobs, Jr.

McGraw-Hill, Inc. GDS Associates, Inc.

1200 G Street NW, Suite 1100 1850 Parkway Place, Suite 720 Washington, DC 20005 Marietta, GA 30068-8237 Mr. Dennis Murdock Mr. Dale Arends Central Iowa Power Cooperative Corn Belt Power Cooperative Box 2517 1300 13th Street North Cedar Rapids, IA 52406 Humboldt, IA 50548 Document Control Desk IRMS INPO Records Center 700 Galleria Parkway NRC Resident Inspector Atlanta, GA 30339-5957 CTS Project Mr. Darl Hood 1 White Flint North Mail Stop 8H4A 11555 Rockville Pike Rockville, MD 20852

OPERATING DATA REPORT DOCKET NO: 50-331 DATE: 04-15-2003 Unit: Duane Arnold Energy Center COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318 OPERATING STATUS

1. Unit Name: Duane Arnold Energy Center Avemge Daily Net Power Level
2. Reporting Period: March 2003 600
3. Licensed Thermal Power (MWth): 1912 Tech Spec Amendments 243andTSCR for exterdedpowertuprate was implemented November 7, 2001. Currentoperating thermal 500 power, as limited by balance-of-plant equipment, is 1790 400
4. Nameplate Rating (Gross MWe DER): 676 425 Currentrated output, adjustedfor as-built balance-of-plant 300 conditions is 614 0.

200

5. Design Electrical Rating (Net MWe DER): 581.4 100
6. Maximum Dependable Capacity (Gross MWe MDC): 593.1
7. Maximum Dependable Capacity (Net MWe MDC): 565 5 01 08 15 22 29
8. If Changes Occur in Capacity Ratings (Items Number 3 through 7) since the last report, give reasons: N/A
9. Power Level to Which Restricted, If Any (Net MWe): N/A
10. Reasons for Restrictions, If Any: N/A M ar-03 2003 Cumulative
11. Hours in Reporting Penod - 1 744.0 2,160 0 246,864.0
12. Number of Hours Reactor Was Critical 553.5 1,649.0 195,894.8
13. Reactor Reserve Shutdown Hours l 0.0 0.0 192.8
14. Hours Generator On-Line 551.9 1,620.4 191,693.7
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) l 974,578.3 2,840,716.1 281,578,142.2
17. Gross Electrical Energy Generated (MWH) l 334,164.0 972,004.0 94,546,816.6
18. Net Electrical Energy Generated (MWH) 316,193.2 919,462.0 88,876,164.3
19. Unit Service Factor 74.2% 75 0% 77.7%
20. Unit Availability Factor 74.2% 75 0% 77.7%
21. Unit Capacity Factor (Using MDC Net) 75.2% 75.3% 70.8%
22. Unit Capacity Factor (Using DER Net) 73.1% 73.2% 68 6%
23. Unit Forced Outage Rate 0.0% 17.7% 8.4%

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-331 DATE: 04-15-2003 Unit: Duane Arnold Energv Center COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318 MONTH March 2003 Day Average Daily Power Level (MWe-Net) 03/01 586 03/02 587 03/03 585 03/04 586

-03/05 - -587 03/06 585 03/07 584 03/08 587 03/09 584 03/10 585 03/11 583 03/12 583 03/13 584 03/14 581 03/15 578 03/16 572 03/17 571 03/18 575 03/19 578 03/20 577 03/21 574 03/22 575 03/23 390 03/24 0 03/25 0 03/26 0 03/27 0 03/28 0 03/29 0 03/30 0 03/31 0

REFUELING INFORMATION DOCKET NO: 50-331 DATE: 04-15-2003 Unit: Duane Arnold Energy Center COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318

1. Name of facility. Duane Arnold Energy Center
2. Scheduled date for next refueling shutdown. March 2003
3. Scheduled date for restart following refueling. April 2003
4. Will refueling or resumption of operation thereafter require a technical specification change __

= or otherilicense-amendinent? Not-

5. Scheduled date(s) for submitting proposed licensing action and supporting information. N/A
6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures. N/A
7. Current fuel assemblies inventory Number of Projected date of last Fuel refueling that can be Assemblies discharged (after allowing margin for maintenance of continuous full-core discharge capabilty In receiving for Reload 18 152 Installed into reactor core 368 Discharged from core to Spent Fuel Storage Pool 1912 Scheduled for transfer to Dry Fuel Storage November 2003 610 Installed capacity of Spent Fuel Storage

... ..Pool .... ......

....... . ............. ..2411

........ - ..... 2008 Licensed capacity of Spent Fuel Storage Pool (with re-racking) 2829 2014 Licensed capacity of Spent Fuel Storage Pool and Cask Pool (with 3152 reracking)__ _ _ _ _ _ _ _ _ _ _ _ _

DOCKET NO: 50-331 DATE: 04-15-2003 Unit: Duane Arnold Energy Center COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318 UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: March 2003 No. Date Type Duration Reason Method of Licensee Cause (1) (Hours) (2) Shutting Event Down Reactor Report #

(3) 3 03/23/2003 S 192.1 C 1 Refueling Outage

- - - ~- _ -_ - -(199.7 Effective-- --- - -- _-- - - - -

full-power hours) 1 - F: Forced 2 - Reason 3 - Method:

S: Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continued E-Operator Training & License Examination 5-Reduced Load F-Administrative 9-Other (Explain)

G-Operational Error (Explain)

H-Other (Explain)

DOCKET NO.: 50-331 DATE. 04-15-2003

-Unit: Duane Arnold Energy Center COMPLETED BY: Richard Woodward TELEPHONE. (319) 851-7318 Monthly Operational Overview for March 2003 At the beginning of March, the unit had operated fourteen days since its most recent shutdown for repairs to the main condenser. Just twenty-three days from the end of Operating Cycle 18, the fuel core was nearing end-of-full-power capability.

During the month, six brief, shallow departures from full power would be required to perform control rod adjustments in order to maintain loadline. On March 7 at 11:00, power was reduced 10 MWth for approximately three hours to perform a HPCI (High Pressure Coolant Injection) system surveillance.

On March21 at 20:15, the "A" COOLING TOWER BASIN HI/LO LEVEL annunciator activated, and at 20:35 the CIRC WATER PIT LO LEVEL annunciator also activated. At 20:36, a line break in the circulating (circ) water supply to the north temporary cooling tower was identified. At 20:39, as reactor power was being reduced in response, circ water pit level momentarily dropped for 54 seconds to less than 13 feet 6 inches (Normallevelis 22 feet. Had level dropped to less-than13 feet, the shift manager had determined t perform a fast power reduction and trip one circ pump ) By 20:43, the supply line to the temporary cooling tower had been isolated, and circ pit level had risen to greater than 15 feet. The power level reduction (70 MWth) was halted at 1720 MWth.

At 22:40, power was increased to 1740 MWth and held at that level to perform control rod exercises. The control rod exercises were completed satisfactorily at 01:33 on March 22, and at 02:13 reactor power level was restored to 1790 MWth.

At 12:01 on March 23, DAEC began reducing power to commence Refueling Outage 18. The mam turbine was tripped at 23:52, and a manual scram was inserted from 7% power at 01:39 on March 24. Key activities during this outage will be replacement of 152 fuel assemblies, replacement of six sets of drywell coolers, refurbishment of a low-pressure main turbine, refurbishment of the 'B' cooling tower, replacement of the 250 VDC station batteries, and replacement of all scram solenoid pilot valves.

On February 11, 2003 at 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br />, with the plant in Cold Shutdown (MODE 4), Control Rod Drive (CRD) exercises commenced utilizing Special Operations Technical Specification (TS) 3.10.4, "Single Control Rod Withdrawal - Cold Shutdown." TS 3.10.4 invokes TS 3.9.2, "Refuel Position One-Rod-Out Interlock" as a sub-tiered requirement. Surveillance Requirement (SR) 3.9.2.1 requires that the Reactor Mode Switch be locked in the Refuel position. The TS Bases for SR 3.9.2.1 defines "locking" as removing the key from the switch. When the key was discovered in the switch at 2041 hours0.0236 days <br />0.567 hours <br />0.00337 weeks <br />7.766005e-4 months <br />, 23 CRDs had been exercised. While the Reactor Mode Switch remained locked in the Refuel position during the CRD exercises, the key was not removed as required by SR 3.9.2.1. This is considered to be a TS violation, as control rod withdrawal took place with TS 3.9.2 and 3.10.4 not met. The cause of the event was inadequate procedures that did not include a step to remove the key from the switch, coupled with unfamiliarity by the on-shift Operations crew of the Bases requirement to remove the key Corrective Actions are to add steps to the appropriate plant procedures to remove the key as part of "locking" the Mode Switch. Also, an Operations Department "Hot Item" was prepared to make licensed Operations personnel aware of the incident There was no safety significance to this event, as the Mode Switch remained in the Refuel position when Control Rods were exercised. (This was identified as a reportable event on March 14. LER 2003-002).

DOCKET NO.: 50-331 DATE: 04-15-2003 Unit: Duane Arnold Energy Center COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318 Following is the allocation of production and losses: Electrical Output j Capacity Factor Full Power MWe  % of 614 MWe Hours (Target Output) Equivalent

__ .__ _ (FPHeq)

Net Electric Output -  :'425.01 s 69.22% 514.97 Plant House Loads (while on-line) +24.13 +3.93% 29.21 Subtotal: Gross Electric Output 449.08 73.14% 544.18 I

Capacity Losses (departures from full thermal ___ -- ---------

power):

6.26 1.02% 7.59 Ramp Down: 03/23 12:0 1 - 23:52 Loadline-Adjustments:--03/05- 0100-01 :47,-03/09 00.12 - I--- 0.09- - 01°- 0 11 01:03, 03/12 01 01.50, 03/14 23:10 - 03/15 00.10, 03/17 23.10 - 23:53. 03/20 01:33 - 02:30 Unplanned powerreduction: 03/21 20:39-22:40 0.09 0.01% 0.10 Control rod exercises: 03/21 22:40 - 03/22 02:13 0.09 0.02% 0.12 HPCI Surveillance: 03/07 11:00 - 14:00 0.02 0 00% 0.02 Maintain Margin to 1790 Administrative MWth Limit 0.24 0.04% 0.29 Efficiency Losse hich occureven at full thermal power): 0.03 0.01% 0.00

-/+ Seasonal Effects ( i.e., cold weather increase) (0.43) 1 (0.07%) ( 54)

Subtotal: On-line Losses (Capacity, Efficiency, and 6.39 [ 1.04% l 7.69 WYeathier): - _ _ _ _ _ _ _ I _ _ _ _ _ ___ _ _ _ _ _

Off-Line Losses '- , 158.53 25.82% 1 92.13 Total: Tlarget Flectric Output, % # of clock-hours 'A -Q0.00% j 744.00 Licensing Action Summary:

l Plant Availability: l 74.2% 1 Unplanned Auto Scrams (while critical) this month: I0 Number of reportable events: I0 1 Unplanned Auto Scrams (while critical) last 12 months: I0

Text

NIii Committed to Nuclear Excellence Duane Arnold Energy Center Operated by Nuclear Management Company, LLC April 15, 2003 NG-03-0272 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station O-P1-17 Washington, DC 20555-0001

Subject:

Duane Arnold Energy Center Docket No: 50-331 Operating License: DPR-49 March 2003 Monthly Operating Report File: A-118d Please find enclosed the Duane Arnold Energy Center Monthly Operating Report. The report has been prepared in accordance with the guidelines of NRC Generic Letter 97-02: Rev!sePd Contents Of The Monthly Operating Report, and distribution has been made in accordance with DAEC Technical Specifications, Section 5.6.4.

Very truly yours, Site Vice-President MAP/RBW Enclosures 1/2 I - I,

- I . .... I.....

I . I . .

I'" ~'I - -, ,'-..r 'r'g-> - '-*

I ; , I ; r ,

3277 DAEC Road

  • Palo, Iowa 52324-9785 Telephone 319 851.7611

April 15, 2003 NG-03-0272 Page 2 of 2 cc:

Mr. James E. Dyer Ms. Parveen Baig Regional Administrator, Region m _ Iowa State Utilities Board __

U.S. clear igulatory Commission Lucas State Office Building 801 Warrenville Road Des Moines, IA 50319 Lisle, IL 60532-4351 Ms. Barbara Lewis Dr. William A. Jacobs, Jr.

McGraw-Hill, Inc. GDS Associates, Inc.

1200 G Street NW, Suite 1100 1850 Parkway Place, Suite 720 Washington, DC 20005 Marietta, GA 30068-8237 Mr. Dennis Murdock Mr. Dale Arends Central Iowa Power Cooperative Corn Belt Power Cooperative Box 2517 1300 13th Street North Cedar Rapids, IA 52406 Humboldt, IA 50548 Document Control Desk IRMS INPO Records Center 700 Galleria Parkway NRC Resident Inspector Atlanta, GA 30339-5957 CTS Project Mr. Darl Hood 1 White Flint North Mail Stop 8H4A 11555 Rockville Pike Rockville, MD 20852

OPERATING DATA REPORT DOCKET NO: 50-331 DATE: 04-15-2003 Unit: Duane Arnold Energy Center COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318 OPERATING STATUS

1. Unit Name: Duane Arnold Energy Center Avemge Daily Net Power Level
2. Reporting Period: March 2003 600
3. Licensed Thermal Power (MWth): 1912 Tech Spec Amendments 243andTSCR for exterdedpowertuprate was implemented November 7, 2001. Currentoperating thermal 500 power, as limited by balance-of-plant equipment, is 1790 400
4. Nameplate Rating (Gross MWe DER): 676 425 Currentrated output, adjustedfor as-built balance-of-plant 300 conditions is 614 0.

200

5. Design Electrical Rating (Net MWe DER): 581.4 100
6. Maximum Dependable Capacity (Gross MWe MDC): 593.1
7. Maximum Dependable Capacity (Net MWe MDC): 565 5 01 08 15 22 29
8. If Changes Occur in Capacity Ratings (Items Number 3 through 7) since the last report, give reasons: N/A
9. Power Level to Which Restricted, If Any (Net MWe): N/A
10. Reasons for Restrictions, If Any: N/A M ar-03 2003 Cumulative
11. Hours in Reporting Penod - 1 744.0 2,160 0 246,864.0
12. Number of Hours Reactor Was Critical 553.5 1,649.0 195,894.8
13. Reactor Reserve Shutdown Hours l 0.0 0.0 192.8
14. Hours Generator On-Line 551.9 1,620.4 191,693.7
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) l 974,578.3 2,840,716.1 281,578,142.2
17. Gross Electrical Energy Generated (MWH) l 334,164.0 972,004.0 94,546,816.6
18. Net Electrical Energy Generated (MWH) 316,193.2 919,462.0 88,876,164.3
19. Unit Service Factor 74.2% 75 0% 77.7%
20. Unit Availability Factor 74.2% 75 0% 77.7%
21. Unit Capacity Factor (Using MDC Net) 75.2% 75.3% 70.8%
22. Unit Capacity Factor (Using DER Net) 73.1% 73.2% 68 6%
23. Unit Forced Outage Rate 0.0% 17.7% 8.4%

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-331 DATE: 04-15-2003 Unit: Duane Arnold Energv Center COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318 MONTH March 2003 Day Average Daily Power Level (MWe-Net) 03/01 586 03/02 587 03/03 585 03/04 586

-03/05 - -587 03/06 585 03/07 584 03/08 587 03/09 584 03/10 585 03/11 583 03/12 583 03/13 584 03/14 581 03/15 578 03/16 572 03/17 571 03/18 575 03/19 578 03/20 577 03/21 574 03/22 575 03/23 390 03/24 0 03/25 0 03/26 0 03/27 0 03/28 0 03/29 0 03/30 0 03/31 0

REFUELING INFORMATION DOCKET NO: 50-331 DATE: 04-15-2003 Unit: Duane Arnold Energy Center COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318

1. Name of facility. Duane Arnold Energy Center
2. Scheduled date for next refueling shutdown. March 2003
3. Scheduled date for restart following refueling. April 2003
4. Will refueling or resumption of operation thereafter require a technical specification change __

= or otherilicense-amendinent? Not-

5. Scheduled date(s) for submitting proposed licensing action and supporting information. N/A
6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures. N/A
7. Current fuel assemblies inventory Number of Projected date of last Fuel refueling that can be Assemblies discharged (after allowing margin for maintenance of continuous full-core discharge capabilty In receiving for Reload 18 152 Installed into reactor core 368 Discharged from core to Spent Fuel Storage Pool 1912 Scheduled for transfer to Dry Fuel Storage November 2003 610 Installed capacity of Spent Fuel Storage

... ..Pool .... ......

....... . ............. ..2411

........ - ..... 2008 Licensed capacity of Spent Fuel Storage Pool (with re-racking) 2829 2014 Licensed capacity of Spent Fuel Storage Pool and Cask Pool (with 3152 reracking)__ _ _ _ _ _ _ _ _ _ _ _ _

DOCKET NO: 50-331 DATE: 04-15-2003 Unit: Duane Arnold Energy Center COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318 UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: March 2003 No. Date Type Duration Reason Method of Licensee Cause (1) (Hours) (2) Shutting Event Down Reactor Report #

(3) 3 03/23/2003 S 192.1 C 1 Refueling Outage

- - - ~- _ -_ - -(199.7 Effective-- --- - -- _-- - - - -

full-power hours) 1 - F: Forced 2 - Reason 3 - Method:

S: Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continued E-Operator Training & License Examination 5-Reduced Load F-Administrative 9-Other (Explain)

G-Operational Error (Explain)

H-Other (Explain)

DOCKET NO.: 50-331 DATE. 04-15-2003

-Unit: Duane Arnold Energy Center COMPLETED BY: Richard Woodward TELEPHONE. (319) 851-7318 Monthly Operational Overview for March 2003 At the beginning of March, the unit had operated fourteen days since its most recent shutdown for repairs to the main condenser. Just twenty-three days from the end of Operating Cycle 18, the fuel core was nearing end-of-full-power capability.

During the month, six brief, shallow departures from full power would be required to perform control rod adjustments in order to maintain loadline. On March 7 at 11:00, power was reduced 10 MWth for approximately three hours to perform a HPCI (High Pressure Coolant Injection) system surveillance.

On March21 at 20:15, the "A" COOLING TOWER BASIN HI/LO LEVEL annunciator activated, and at 20:35 the CIRC WATER PIT LO LEVEL annunciator also activated. At 20:36, a line break in the circulating (circ) water supply to the north temporary cooling tower was identified. At 20:39, as reactor power was being reduced in response, circ water pit level momentarily dropped for 54 seconds to less than 13 feet 6 inches (Normallevelis 22 feet. Had level dropped to less-than13 feet, the shift manager had determined t perform a fast power reduction and trip one circ pump ) By 20:43, the supply line to the temporary cooling tower had been isolated, and circ pit level had risen to greater than 15 feet. The power level reduction (70 MWth) was halted at 1720 MWth.

At 22:40, power was increased to 1740 MWth and held at that level to perform control rod exercises. The control rod exercises were completed satisfactorily at 01:33 on March 22, and at 02:13 reactor power level was restored to 1790 MWth.

At 12:01 on March 23, DAEC began reducing power to commence Refueling Outage 18. The mam turbine was tripped at 23:52, and a manual scram was inserted from 7% power at 01:39 on March 24. Key activities during this outage will be replacement of 152 fuel assemblies, replacement of six sets of drywell coolers, refurbishment of a low-pressure main turbine, refurbishment of the 'B' cooling tower, replacement of the 250 VDC station batteries, and replacement of all scram solenoid pilot valves.

On February 11, 2003 at 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br />, with the plant in Cold Shutdown (MODE 4), Control Rod Drive (CRD) exercises commenced utilizing Special Operations Technical Specification (TS) 3.10.4, "Single Control Rod Withdrawal - Cold Shutdown." TS 3.10.4 invokes TS 3.9.2, "Refuel Position One-Rod-Out Interlock" as a sub-tiered requirement. Surveillance Requirement (SR) 3.9.2.1 requires that the Reactor Mode Switch be locked in the Refuel position. The TS Bases for SR 3.9.2.1 defines "locking" as removing the key from the switch. When the key was discovered in the switch at 2041 hours0.0236 days <br />0.567 hours <br />0.00337 weeks <br />7.766005e-4 months <br />, 23 CRDs had been exercised. While the Reactor Mode Switch remained locked in the Refuel position during the CRD exercises, the key was not removed as required by SR 3.9.2.1. This is considered to be a TS violation, as control rod withdrawal took place with TS 3.9.2 and 3.10.4 not met. The cause of the event was inadequate procedures that did not include a step to remove the key from the switch, coupled with unfamiliarity by the on-shift Operations crew of the Bases requirement to remove the key Corrective Actions are to add steps to the appropriate plant procedures to remove the key as part of "locking" the Mode Switch. Also, an Operations Department "Hot Item" was prepared to make licensed Operations personnel aware of the incident There was no safety significance to this event, as the Mode Switch remained in the Refuel position when Control Rods were exercised. (This was identified as a reportable event on March 14. LER 2003-002).

DOCKET NO.: 50-331 DATE: 04-15-2003 Unit: Duane Arnold Energy Center COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318 Following is the allocation of production and losses: Electrical Output j Capacity Factor Full Power MWe  % of 614 MWe Hours (Target Output) Equivalent

__ .__ _ (FPHeq)

Net Electric Output -  :'425.01 s 69.22% 514.97 Plant House Loads (while on-line) +24.13 +3.93% 29.21 Subtotal: Gross Electric Output 449.08 73.14% 544.18 I

Capacity Losses (departures from full thermal ___ -- ---------

power):

6.26 1.02% 7.59 Ramp Down: 03/23 12:0 1 - 23:52 Loadline-Adjustments:--03/05- 0100-01 :47,-03/09 00.12 - I--- 0.09- - 01°- 0 11 01:03, 03/12 01 01.50, 03/14 23:10 - 03/15 00.10, 03/17 23.10 - 23:53. 03/20 01:33 - 02:30 Unplanned powerreduction: 03/21 20:39-22:40 0.09 0.01% 0.10 Control rod exercises: 03/21 22:40 - 03/22 02:13 0.09 0.02% 0.12 HPCI Surveillance: 03/07 11:00 - 14:00 0.02 0 00% 0.02 Maintain Margin to 1790 Administrative MWth Limit 0.24 0.04% 0.29 Efficiency Losse hich occureven at full thermal power): 0.03 0.01% 0.00

-/+ Seasonal Effects ( i.e., cold weather increase) (0.43) 1 (0.07%) ( 54)

Subtotal: On-line Losses (Capacity, Efficiency, and 6.39 [ 1.04% l 7.69 WYeathier): - _ _ _ _ _ _ _ I _ _ _ _ _ ___ _ _ _ _ _

Off-Line Losses '- , 158.53 25.82% 1 92.13 Total: Tlarget Flectric Output, % # of clock-hours 'A -Q0.00% j 744.00 Licensing Action Summary:

l Plant Availability: l 74.2% 1 Unplanned Auto Scrams (while critical) this month: I0 Number of reportable events: I0 1 Unplanned Auto Scrams (while critical) last 12 months: I0