NG-96-1713, Monthly Operating Rept for Jul 1996 for DAEC

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Monthly Operating Rept for Jul 1996 for DAEC
ML20129E574
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 07/31/1996
From: Middlesworth G, Woodward R
IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To: Beach A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NG-96-1713, NUDOCS 9610280096
Download: ML20129E574 (8)


Text

i Duane Amotd Energy Centsr 3277 DAEC Road Pato. IA 52324 Telechone 319 8517611 Fax 319 8517611 UTILITIES August 15,1996 NG-96-1713 1

i Mr. A. Bill Beach Regional Administrator Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road l Lisle, IL 60532-4351

Subject:

Duane Arnold Energy Center I

Docket No: 50-331 Operating License: DPR-49 l July 1996 Monthly Operating Report File: A-118d i

Dear Mr. Beach:

l Please find enclosed the Duane Arnold Energy Center Monthly Operating Report for July 1996. The report has been prepared in accordance with the guidelines of NUREG-0020 and distribution has been made in accordance with DAEC Technical Specificat:ons, Section 6.11.1.c.

Very truly yours,

.rll / Edb c9 Gary Van Middlesworth Plant Manager-Nuclear l

GDV/RBW j Enclosures

/

T<z)f 9610280096 960731 PDR ADOCK 05000331 R PDR t

280030 An IEs Industnes Company

- .- . _ - , - . . -_ - . __- -_ -- -. - - ~ -.

Mr. A. Bill Beach NG-96-1713 August 15,1996 Page 2 of 2 cc:

U.S. Nuclear Regulatory Commission Mr. Dennis Murdock Attn: Document Control Desk Central Iowa Power Cooperative l Mail Station PI-37 Box 2517 i Washington, DC 20555-0001 (Orig.) Cedar Rapids,IA 52406 i

Mr. Glenn Kelly Dr. William A. Jacobs, Jr. '

Project Manager GDS Associates,Inc.

1 Whiteflint North - Suite 720 Mail Stop 13E21 1850 Parkway Place 11555 Rockville Pike Marietta, GA 30068-8237  !

Rockville, MD 20852 Document Control Desk Mr. Dale Arends INPO Records Center Corn Belt Power Cooperative 700 Galleria Parkway 130013th Street North Atlanta, GA 30339-5957 Humboldt,IA 50548 j Ms. Lisa Stump DOCU j Iowa State Utilities Board Lucas State Office Building NRC Resident Inspector Des Moines,IA 50319 Mr. Fred Yost Mr. Al Gutterman Director, Research Services Morgan, Lewis, Bockius Utility Data Institute 1800 M St. N W 1700 K St. NW, Suite 400 Washington, DC 20036-5859 Washington, DC 20006

OPERATING DATA REPORT DOCKET NO: 50-0331 DATE: 08/15/96 Unit: Duane Arnold Enerev Cenigt COMPLETED BY: Richard Woodward TELEPHONE: (3191 851-7318 OPERATING STATUS Average Daily Power Level

1. Unit Name: Duane Arnold Enerev Center -

500

2. Reporting Period: Juiv 1096 499 t;
3. Licensed Thermal Power (Mwth): Iflig }300
4. Nameplate Rating (Gross MWe DER): 565.7 (Turbine) 100
5. Design Electrical Rating (Net MWe DER): 518 0

I 6 11 16 21 26 31

6. Maximum Dependable Capacity (Gross MW e MDC): 55H Day
7. Maximum Dependable Capacity (Net MW e MDC): 520
8. If Changes Occur in Capcity Ratings (Items Number 3 through 7) since the last report, Give Reasons: Het Aeolicable
9. Power Level to Which Restricted,If Any (Net Mwe ): Nel Acolicable
10. Reasons for Restrictions,If Any: Mal Acolicable July-96 1996 Cummulative
11. Hours in Reporting Period 744.0 5,111.0 188,447.0
12. Number of Hours Reactor Was Critical 744.0 5,111.0 143,636.8
13. Reactor Reserve Shutdown Hours 0.0 0.0 192.8
14. Hours Generator On Line 744.0 5,111.0 140,224.8
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1,227,449.0 8,030,063.7 197,291,278.0
17. Gross Electrical Energy Generated (MWH) 409,100.0 2,711,846.0 66,123,816.6
18. Net Electrical Energy Generated (MWH) 386,194.3 2,557,739.6 62,034,754.2
19. Unit Service Factor 100.0 % 100.0 % 74.4 %
20. Unit Availability Factor 100.0 % 100.0 % 74.4 %
21. Unit Capacity Factor (Using MDC Net) 99.8 % 96.2 % 69.4 %
22. Unit Capacity Factor (Using DER Net) 96.5 % 93.0 % 66.5 %
23. Unit Forced Outage Rate 0.0% 0.0% 10.4%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of each): Refueline. 10/11/96.30 dayJi

{

25. If Shutdown at End of Repon Period, Estimated Date of Stanup: N/A

. -. ._ __ _ . _. _ _. . _ _ . . . - - . . _ . _ _ _ _ _ . _ . _ . _ _ _ _ _ _ _ . . _ . _ . = _ _ _ _ _ _ _ _ . _ _ _ _ . . .

l l

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-0331 1

  • DATE: 08/15/96 Unit: Duane Arnold Energy Center COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318 MONTH July 1996 Day i Average Daily PowerLevel 1 (MWe-Ne0 ,

1 520.1  !

2 518.4 l 3 521.9 1 4 523.4 l 5 524.4

)

6 520.2 7 519.3 8 521.9 9 523.9 10 534.8 11 516.1  !

12 520.6

)

13 521.7 14 461.7 15 515.4 16 520.5 17 511.9 18 507.8 19 516.2 20 522.1 21 522.1 22 520.7 23 520.1

-- 24 520.5 25 525.4 26 524.6 27 524.0 28 521.9 29 521.7 3

30 524.7

, 31 523.6 s

REFUELING INFORMATION DOCKST NO: 50 0331 DATE: 08/15/96 Unit: Duane Arnold Enerev Center COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318

1. Name of facility.

Duane Arnold Energy Center

2. Scheduled date for next refueling shutdown.

Refuel Outage XIV to begin October 11,1996.

l

3. Scheduled date for restart following refueling.
November 11,1996
4. Will refueling or resumption of operation thereafter require a technical specification change l or other license amendment?

l Yes l RTS 269, T.S. 3.7, " Plant Containment Systems" l RTS 288, T.S. 2.1, 3.2, " Reactor Water Clean-up Systems Vessel Level Isolation Set-Point Change" l

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

RTS 269, submitted December 22,1995

  • RTS 288, submitted January 18,1996 l
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.

No

7. Current and projected fuel assemblics inventory:

Number of Projected date oflast

, Fuel refueling that can be i Assemblies discharged l

Installed in reactor core (following refueling) 368 n/a Previously discharged from core to Spent Fuel Storage 1408 n/a Pool (following refueling)

Under present physical capacity of Spent Fuel Storage 2411 2007 Pool Under Licensed Capacity of Spent Fuel Storage Pool 3152 2014 l

r l

l r . . .

DOCKET NO: 50-0331 DATE: 08/15/96 .

Unit: Duane Amold Enerev Center .

COMPLETED BY: Richard Woodward -

TELEPHONE: (3191 851-7318 I

UNIT SHUTDOWNS AND POWER REDUC 110NS REPORT MONTII: July 1996 No. Date Type Duration Reason Method of Licensee Event System Code Comp. Code Cause (1) (Hours) (2) Shutting Report # (4) (5)

Down Reactor (3) 9 July 14 S 0 B 5 n/a n/a n/a Turbine Control Valve testing (3.9 full- Controi Rod Sequence Exercises  ;

power-hours equivalent) 1 - F: Forced 2 - Reason 3 - Method: 4 - Exhibit G-Instructions for S: Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data Entry B-Maintenance or Test 2-Manual Scram Sheets for Licensee Event C-Refueling 3-Automatic Scram Repoit (LER) File (NUREG-D-Regulatory Restriction 4-Continued 0161)

E-Operator Training & License Examination 5-Reduced Load F-Administrative 9-Other(Explain) 5 - Exhibit I (Sune Source)

G-Operational Error (Explain)

II-Other(Explain)

DOCKET NO.: 50-0331 DATE: 08/15/96 Unit: Duane Arnold Enercy Center COMPLETED BY: Richard Woodward TELEPHONE: (319)851-7318 Monthly Operational Overview for July 1996:

The DAEC operated at full thermal power throughout the month except:

on July 2, to perform feedwater flow measurement calibration.

on July 13-16, to perform scheduled Scram Time Testing, Turbine Control Valve Testing, and Control Rod Drive manipulations: 3.9 full-power-hours (equivalent) lost.

+

on July 17-18, to clear a high condenser back-pressure alarm due to high ambient wet-bulb temperatures.

on July 4,19,24 and 29, to reduce recirculation flow to withdraw a control rod.

Total forgone production was the equivalent of 20.8 full-power hours of operation.

At the end of the month the Duane Arnold Energy Center had operated 422 consecutive days, its best-ever continuous operating run.

Allocation of Production & Losses: Electrical Capacity Factor Full Power Output  % of 565.7 MWe Equivaleni MWe (Design Gross 11ours Rating)

Actual Metered Net Electric Output 519.1 91.8 % 682.7 Actual Metered Plant Electric Loads 30.8 5.4% 40.5 Load Following 0.0 0.0% 0.0 Off-Line 0.0 0.0% 0.0 Weather losses, ie., condenser pressure >2.75 in Hg / Circ Water Temp > 74.5 'F 6.4 1.1% 8.5 Planned Capacity Losses: July 2,4,13 16,24, & 29 3.5 0.6% 4.6 Unplanned Capacity Losses: July 17 18 0.4 0.0% 0.5 Normal Capacity 14sses (Avg MWth < 1658) 0.9 0.2% 1.2 Metering Losses (Avg indic MWe - Avg MWHe) 2.0 0.4% 2.6 Emelency Losses (Weather Norm-Full-Power-MWe < 565.7) 2.fi Q.M's 33 Design Grou Electric Output M,5,7 100 0 % 744 0 3

On July 16,1996 en Electrical Protection Assembly (EPA) breaker tripped on undervoltage, de-energizing the "A" Reactor Protection Sys'em (RPS) bus which powers the "A" side sensors for the Primary Containment Isolation System (PCIS).

PCIS Groups 1 5 isolations then occurred (except main steam isolation valves). All automatic actions were completed satisfactorily, ar.d all systems functioned as required. Extensive troubleshooting following the event did not conclusively determine a root cause for the EPA breaker undervoltage trip, but some sub-components in one of the "A" Average Power Range Monitor (APRM) power supplies were found degraded and replaced. Monitoring equipment was installed on the "A" RPS MG set and on the "A" APRM to obtain operational data to support future troubleshooting. The event had no effect on the safe operation of the plant. (LER #96-003)

Licensine Action Summary:

Plant Availability: 100.0 % Unplanned Auto Scrams (while/ critical) this month: 0 Number of reportable events: 1 Unplanned Auto Scrams (while/ critical)last 12 months: 0

'Iherm11~& EIectric Power '

_____________________________________________________________________________._____________-~~~~---'.C179

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650 1600. _ _ _ _ _ ._ _____________________j_________

_ _ _l ._____._______  ! ___ _______________ ___ _____________

________ .V _!..G0 l l l l 557.3 l t

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___________1______________________

600 1500._________l_______________________l_________l_ . . .

550 1400 g ,pa % ' s _ __ _ _

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500 1300._________l______________________.;_________ .

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450 1200 .

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400 1100__________;_______________________l__________ ___________;______________________ _______________________;.

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. . l 350 1000_ _ _ _ _ _ _ _ _ _ ..

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. I 300 900_ _ _ _ _ _ _ _ _ _ ..______________________;______________________1.______________________

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250 800__________l_____ ________________.j______________________!______________________ _____________________l.

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200 700 7/1796 00:00 00 AM 31.00 Day (s) 87179F00 00:00 Ah

.NSSSI CORE TIIERMAL POWER . GEN GROSS WATTS

_ _ _ _ . _ _ _ . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ . - _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _