NG-97-1452, Monthly Operating Rept for July 1997 for DAEC

Monthly Operating Rept for July 1997 for DAEC

ML20210K576
Person / Time
Site:	Duane Arnold
Issue date:	07/31/1997
From:	Van Middleswort, Woodward R IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	Beach A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NG-97-1452, NUDOCS 9708190306
Download: ML20210K576 (7)

Text

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Daa e A m ::: Energ. Cente-3:77 DAEc koao Pato. IA 52324

! Teoconone 319 8517611 Fax 319 8517611 UTILITIES August 15,1997 NG-97-1452 Mr. A. Bill Beach Regional Administrator Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle,IL 60532-4351

Subject:

Duane Arnold Energy Center Docket No: 50-331 Operating License: DPR-49 July 1997 Monthly Operating Report File: A-118d

Dear Mr. Beach:

Please find enclosed the Duane Arnold Energy Center Monthly Operating Report for July 1997. The report has been prepared in accordance with the guidelines of NRC GENERIC LETTER 97-02: REVISED CONTENTS OF THE MONTHLY OPERATING REPORT and distribution has been made in accordance with DAEC Technical Specifications, Section 6.11.1.c.

Very truly yours, an' '$ ,h c 6 c=6 Gary anMiddlesworth Plant Manager-Nuclear GDV/RBW l

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. ME.A.' Bill Beach -

- NG-97-1258 August 15,1997 Page 2 of 2 cc:

U.S. Nuclear Regulatory Conunission Ms. Lisa Stump

- Attn: Document Control Desk - Iowa State Utilities Board Mail Station PI-37 Lucas State Office Building Washington, DC 20555-0001 (Orig.) Des Moines,IA 50319

' Dr. William A. Jacobs, Jr.

- Ms. Barbara Lewis 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 -

CentralIowa Power Cooperative - Corn Belt Power Cooperative Box 2517 130013th Street North Cedar Rapids,IA 52406 Humboldt,IA 50548-

' Document Control Desk

- - Mr. Al Gutterman INPO Records Center Morgan, Lewis, Bockius ,

700 Galleria Parkway 1800 M St.NW Atlanta, GA 30339-5957 Washington, DC 20036-5859 Mr. Glenn Kelly DOCU Project Manager 1 Whiteflint North NRC Resident Inspector

' Mail Stop 13E21 11555 Rockville Pike -

Rockville, MD 20852 c-

OPERATING DATA REPORT DOCKET NO: 50-0331 DATE: 08/15/97 Unit: Duane Arnold Enerev Center COMPLETED BY: Richard Woodward TELEPHONE: (3191 851-7318 OPERATING STATUS Average Daily Power Level

1. Unit Name: Duane Arnold Enercy Center 500

2. Reporting Period: July 1997

3. LicensedThermalPower(MWth): 1658 $ 200 2 100 Nameplate Rating (Gross MW 0

4. e DER): 565.7 (Tinbine) '

1 6 11 16 21 26 31

5. Design Electrical Rating (Net MW e DER): !).I.

6. Maximum Dependable Capacity (Gross MW, MDC): !)._0 l

7. Maximum Dependable Capacity (Net "'U, MDC): SO

8. If Changes Occur in Capacity Rating %.6 cms Number 3 through 7) since the last report, Give Reasons: Not Annlicable

9. Power Level to Which Restricted,If A ny (Net Mwe ): N_%

10. Reasons for Restrictions,if Any: N!%

July-97 1997 Cumulative i1. Ilours in Reporting Period 744.0 5,087.0 197,207.0

12. Number of Hours Reactor Was Critical 744.0 4,79f,.3 151,292.4

13. Reactor Reserve Shutdown Hours 0.0 0.0 192.8

14. Hours Generator On-Line 744.n 4,686.9 147,708.0

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Hermal Energy Generated (MWH) 1,204,836.0 7,485,745.5 209,138,856.6

17. Gross Electrical Energy Generated (MWri) 398,792.0 2,524,008.0 70,113,054.6

18. Net Electrical Energy Generated (MWH) 376,236.1 2,381,613.4 65,797,172.4

19. Unit Service Factor 100.0 % 92.1 % 74.9 %

20. Unit Availability Factor 100.0 % 92.1 % 74.9 %

21. Unit Capacity Factor (Using MDC Net) 97.2 % 90.0 % 70.3 %

22. Unit Capacity Factor (Using DER Net) 94.0 % 87.0 % 67.3 %

23. Unit Forced Outage Rate 0.0% 0.0% 9.9%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of each): N/A

25. If Shutdown at End of R; -t Period, Estimated Date of Startup: N/A

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-0331 DATE: 08/15/97

- Unit: Duane Arnold Enerry Center

+

COMPLETED BY: Richard Woodward TELEPHONE: 0 19)851-7318 -

MONTH' July 1997 Day Average Daily PourIxvel (MWe-Ne0 1 516.2 2 524.7 3 .521.1 4 528.8 5 516.4 6 527.2 7 528.7 8 517.4 9 533 10 520.0 11 508.6 12 501.1 13 430.0 14 513.0 15 518.5 16- 517.5 17 490.7 18 502.7 19 5%.7 20 315.1 21 461.0 22 5203 23 518.4 24 517.8 25 512.4 26 510.5 27 513.7 28 519.1 29 524.2 30 524.4 31 525.1 i- - . - . . . . - -- .

REFUELING INFORMATION DOCKET NO: 50-0331

( DATE: 08/15/97 Unit: Duane Arnold Enercy Center COMPLETED BY: Richard Woodward TELEPHONE: (3191851-7318 1.- Name of facility. ,,

Duane Arnold Energy Center

2. Scheduled date for next refueling shutdown.

April 2,1998

3. Scheduled date for restert fallowing refueling.

May 1998

4. _Will refueling or resu~ stion of operation thereafter require a technical speelfication change or other license amen,N ut?

No. (Improved Technical Specifications (ITS) approval needed for refueling outage planning.)

5. Scheduled date(s) for submitting proposed licensing action and supporting information.

N/A. (ITS submitted October 30,1996.) _

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 and projected fuel assemblies inventory:

Number of Fuel Projected date oflast

' Assemblies refueling that can be discharged (after allowing margin for maintenance of continuous full-core discharge capability)

Installed in reactor core (following refueling)  ! 368 l n/a Discharged from core to Spent Fuel Storage Pool i 1528 n/a  ;

Installed Capacity of Spent Fuel Storage Pwl i 2411 2001 Licensed Capacity of Spent Fuel Storage Pool (with reracking) ! 2829 2006 Licensed Capacity of Spent Fuel Storage Pool and Cask Pool 3152 2010 (with reracking)

DOCKET NO: 50-0331 -

DATE: 08/15/97 Unit Duane Arnold Enerev Center '

COM;" TTED BY: Richard Woodward -

TELEPilONE: (3191851-7318

~

. l UNIT SilUTDOWNS AND POWER REDUCTIONS REPORT MONTil: July 1997 Cause No. Date Type Duration Reason Method of Licensee Event System Code Comp. Code Chutting Report # (4) (S)

(l) (flours) (2)

Down

- Reactor (3)

TA PCV fo perfonn control rod pattem sequence exchange and f 7 07/12/97 S 0 B 5 N/A Pressure turbine valve testing Main Turbine (4.9 full- Control Valve System power-

' hours equivalent)

N/A SN 1K To inspect, isolate, and repair ist Stage Moisture Separator 8 07/17/97 F 0 A 5 IIP Ileater and Tank Reheater (MSR) Drain Tank leaking manway cover (14.0 full-power- MSR Drains hours and Vents Sytems equivalent) 3 - Method: 4 - Exhibit G Instructions for 1 - F: Forced 2 - Reason 1-Manual Preparation of Data Entry ,

S: Scheduled A-Equipment Failure (Explain) l 2-Manual Scram Sheets for Licensee Event B-Maintenance or Test 3-Automatic Scram Report (LER) File (NUREG-C-Refueling 4-Continued 0161)

D-Regulatory Restriction E-Operator Training & License Examination 5-Reduced Load 9-Other (Explain) 5 - Exhibit I (Sam : Source)

F-Administrative G-Operational Error (Explain)

Il-Other (Explain) i l'

e

...,_a__

DOCKET NO.: 50-0331 DATE: 08/15/97 Unit: Duane Amold Energy Center COMPLETED BY: Richard Woodward TELEPHONE: (3191851-7318 Monthly Operational Overview for July 1997: -

The plant operated at licensed thetmal power throughout the month except:

• 07/04/97 2230 - 07/05/97 0700, because of reduced power demand on the grid, 0.4 Full Power-Hours equivalent (FPHy )

• 07/10/97 2245 - 07/11/97 2245, to change-out the plant process computer,0.8 FPHg.

• 07/11/97 2245 07/12/97 2200, to maintain margin to therme.1 limits,0.2 FPHy.

• 07/12/97 2200 - 07/14/97 0730, to perform control rod pattern sequence exchange and turbine valve testing,4.9 n%.

• 07/17/97 0100 - 07/21/97 2300, to inspect, isolate, and repair ist Stage Moisture Separator Reheater (MSR) Drain Tank leaking manway cover,14.0 FPHy.

• 07/22/97 0539 - 0616 and 07/23/97 0037 - 0118, to reduce recirculation flow for control rod withdrawals,0.1 FPHy .

• 07/29/97 2331 - 07/30/97 0309, to calibrate Feedwater Flow Transmitter,0.1 FPH y .

• 07/01/97 - 07/31/97, routine weather, capacity and efficiency losses 18.5 FPHy .

Allocation of Production & Losses: Electncal capacity Factor Full Power Output %of 565.7 MWe Equivalent MWe (Design Gross Hours Rating) -

Ac val Metered Net Electric Output 505.7 89.5 % 665.1 Attual Metered Plant Electric Loads 30.3 5.4% 39.9 5 eluded losses: July 5 - Lack of Grid Demand 0.3 0.1% 0.4 Off Line: 0.0 0.0% 0.0 Unplanned On-Line Capacity Losses: 7/10 Delay restoring PPC to service an3 to maintain margin to thermal limits, 7/17 & 7/20-21. Ist St MSR Drain Tank Repair 11.4 1.9% 15.0 I

Weather losses - condenser pressure >2.75 In Hg / Cire Water Temp > 74.5 *F 9.7 1.6% 122 Normal Capacity Losses ( Avg." Full Power" MWth < 1658) 0.4 0.1% 0.5 Other Planned On-Line Capacity Losses: 7/12 14 Seq Exhg, Turb Vive Testing Load-Line Adiustments: 7/30: Feed Flow Calibration 3.9 0.7% 5.1 Metering Losses (Avg indic MWe - Avg MWHe) 1.7 0.3% 2.2 Efficiency Losses (Weather-Norm-Full Power MWe > 565.7 Design) 2J 0.4% 1.0 Design Gross Electric Output is1lZ 100 0 % 744 0 On July 24,1997, it was discovered that the Surveillance Test Procedure (STP) used to functionally test the Reactor Water Cleanup (RWCU) Area Ventilation System does not adequately test the HIGH DIFFERENTIAL TEMPERATURE indication, as required by the Technical Specifications. (The STP for calibrating the differential temperature instrumentation does include adequate functional testing. This calibration had last been performed 12/12/96.) The plantimmediately entered a one-hour Limiting Condition of Operation (LCO) to isolate the RWCU system, and Instruments and Controls (l&C) technicians performed the calibration STP and verified operability. A Root Cause Evaluation is ongoing. (LER #97 08, pending).

Licensing Ac* ion Summary-Plant Availability: 100.0%_ Unpbnned Auto Scrams (while/ critical) this month: 0 Number of reportable eviInts: 1 " Unplanned Auto Scrams (while/ critical)last 12 months: 0

_