NG-96-2447, Monthly Operating Rept for Oct 1996 for Duane Arnold Energy Center

Monthly Operating Rept for Oct 1996 for Duane Arnold Energy Center

ML20134N177
Person / Time
Site:	Duane Arnold
Issue date:	10/31/1996
From:	Vanmiddlesworth, Woodward R IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	Beach A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NG-96-2447, NUDOCS 9611260202
Download: ML20134N177 (8)

Text

__s Duane Amold Energy Center 3277 DAEC Road

. Palo, IA 52324 Telephone 319 6517611 Fax 319 8517611 UTILITIES

, November 15,1996 NG-96-2447 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 October 1996 Monthly Operating Report File: A-118d

Dear Mr. Beach:

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

Very truly yours, rf, <

Gary VanMiddlesworth Plant Manager-Nuclear GDV/RBW Enclosures /

9611260202 961031 PDR ADOCK 05000331 R PDR An IES Industnes Company

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Mr. A. Bill Beach l

., NG-96-2447 j November 15,1996 Page 2 of 2 i

i cc:

'U.S. Nuclear Regulatory Commission Ms. Lisa Stump Attn: Document Control Desk lowa State Utilities Board l Mail Station PI-37 Lucas State Office Building Washington, DC 20555-0001 (Orig.) Des Moines,IA 50319 ,

I Mr. Fred Yost Dr. William A. Jacobs, Jr.

Director, Research Services GDS Associates,Inc.

Utility Data Institute Suite 720 j .1700 K St. NW, Suite 400 1850 Parkway Place

Washington, DC 20006 Marietta, GA 30068-8237 Mr. Dennis Murdock Mr. Dale Arends CentralIowa Power Cooperative Corn Belt Power Cooperative j Box 2517 130013th Street North Cedar Rapids,IA 52406 Humboldt,IA 50548 j Document Control Desk Mr. Al Gutterman

?

INPO Records Center Morgan, Lewis, Bockius 700 Galleria Parkway 1800 M St. N W -I Atlanta, GA 30339-5957 Washington, DC 20036-5859 i Mr. Glenn Kelly DOCU i Project Manager l 1 Whiteflint North NRC Resident Inspector Mail Stop 13E21 11555 Rockville Pike '

Rockville, MD 20852

OPERATING DATA REPORT DOCKET NO: 50-0331 DATE: 11/15/96 Unit: Duane Arnold Enerev Center COMPLETED BY: Richard Woodward

TELEPHONE

(119) 851-7318 OPERATING STATUS

1. Unit Name: Quane Arnold Energy Center

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2. Reporting Period: October 1996 l l l l 400

3. Licensed Thermal Power (Mwth) E l i

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4. Nameplate Rating (Gross MW e DER): 565.7 (Turbine) $ l l  !  !

2 , ,

5. Design Electrical Rating (Net MWe DER): 118 l l l 100

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6. Maximum Dependable Capacity (Gross MW e MDC): 150 o  ;

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~. Maximum Dependable Capacity (Net MW e MDC): 520 6 11 gy 21 26 31 1

8. If Changes Occur in Capacity Ratings (ltems Number 3 through 7) since the last report, Give Reasons: Not Aeolicable

9. Power Level to Which Restricted, if Any (Net Mwe): Coast down from 97% (October 1) to 93% (October 10)

10. Reasons for Restrictions, if Any: End of fuel cycle reduction in full thermal oower canability October-96 1996 Cummulative

11. Hours in Reporting Period 745.0 7,320.0 190,656.0

12. Number ofliours Reactor Was Critical 258.4 6,833.4 145,359.2

13. Reactor Reserve Shutdown liours 0.0 0.0 192.8

14. Hours Generator On-Line 248.7 6,823.7 141,937.5

15. Unit Reserve Shutdown 11ours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWil) 379,411.7 10,819,084.1 200,080,298.5

17. Gross Electrical Energy Generated (MWii) 127,320.0 3,644,889.0 67,056,859.6

18. Net Electrical Energy Generated (MWii) 119,585.5 3,437,653.0 62,914,667.6 j

19. Unit Service Factor 33.4 % 93.2 % 74.4 %  !

20. Unit Availability Factor 33.4 % 93.2 % 74.4 %

21. Unit Capacity Factor (Using MDC Net) 30.9% 90.3 % 69.6 %

22. Unit Capacity Factor (Using DER Net) 29.8% 87.3 % 66.6 %

23. Unit Forced Outage Rate 0.0% 0.0% 10.3 % j I

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of each): Refueling Outage 14.

commenced 10/11/96. olanned duration: 36 days

25. If Shutdown at End of Report Period, Estimated Date of Startup: November 16.1996

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, AVERAGE DAILY UNIT POWER LEVEL 1 1 . .

' DOCKET NO: 50-0331 j DATE: 11/15/96 ~

Unit: Duane Arnold Enernv Center COMPLETED BY: Richard Woodward l TELEPHONE: (319) 851-7318 '

l MONTH October 1996 Day Avemge Daily PowerIxvel (MWe-Ne0

' l 1 510.4 2 511.5 l 3 513.4 4 510.0 j

, 5 503.6 l 6 497.2 7 500.1  ;

4 8 494.6 9 501.8 10 429.8 11 0.3 12 0.0 13 0.0 14 0.0 1 0.0

, 15 16 0.0 17 0.0 18 0.0 )

19 0.0 20 0.0 l 21 0.0 l 22 0.0 l 23 0.0 i 24 0.0 25 0.0 26 0.0 27 0.0 28 0.0 29 0.0 I 30 0.0 31 0.0

, REFUELING INFORMATION

• / DOCKET NO: 50-0331 DATE: 11/15/96 Unit: Duane Arnold Enercy Center t

COMPLETED BY: Richard Woodward TELEPHONE: (319)851-7318

1. Name of facility.

Duane Arnold Energy Center 4

2. Scheduled date for next refueling shutdown.

Refuel Outage 14 (began) October 11,1996.

3. Scheduled date for restart following refueling.

November 16,1996

4. Will refueling or resumption of operation thereafter require a technical specification change

or other license amendment?

N/A l S. 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 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 n/a  ;

Discharged from core to Spent Fuel Storage Pool 1528 n/a l Installed Capacity of Spent Fuel Storage Pool 2il1 2001 Licensed Capacity of Spent Fuel Storage Pool (with reracking) 2829 2006 Licensed Capacity of Spent Fuel Storage Pool and Cask Pool 3152 2010 i (with reracking)

DOCKET NO: 50-0331 DATE: 11/15M6 .

Unit: Duane Arnold Enerev Center .,

COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318 UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: October 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) 12 October S 496.3 C 2 n/a n/a n/a Refueling Outage 11- 31 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 Report (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 (Same Source)

G-Operational Error (Explain) 1I-Other (Explain)

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DOCKET NO.: 50-0331 DATE: 11/15/96 Unit: Duane Arnold Energy Center COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318 Monthly Operational Overview for October 1996:

At the beginning of the month, the DAEC was operating at 97% of rated thermal power, six days into its end-of-cycle coast-down. Apart from the coast-down, the DAEC operated at its maximum available power until commencing a controlled shutdown October 10 from 94% power. DAEC began Refueling Outage 14 on Friday, October 11 at 084I when the turbine generator was taken offline. All rods had been inserted by 1426 on the same day.

At the end of Cycle 14 the Duane Arnold Energy Center had operated 493 consecutive days, its best-ever continuous operating run and fourth best ever among all Boiling Water Reactors.

Allocanon of Production & Losses: Liectrical Lapac.ty Factor Full Power Output  % of 565.7 MWe Equivaleni MWe (Design Gross llours Rating)

Actual Metered Net Electric Output 157.2 27.9% 207.0 Actual Metered Plant Electric Loads 13.7 2.4% 18.0 Excluded losses: (Load Following or Coast Down): 10/1 10/11-Coast down 8.4 1.5'A 11.0 OtT-Line 10/11/96 0841 - end of month 376.9 66.6 % 496.4 Weather losses, ie., condenser pressure >2.75 in lig / Circ Water Temp > 74.5 *F 0.2 0.0% 0.3 Planned Capacity Losses: Ramp-down 10/10- 11 7.9 1.4% 10A Unplanned Capacity Losses 0.0 0.0% 0.0 Nonnal Capacity Lesses (Avg MWth < 1658) 0.1 0.0% 0.2 Metering Losses (Avg indic MWe - Avg MWile) 0.6 0.1% 0.8 Efficiency Losses (Weather-Norm-Full-Power-MWe < 565.7) 01 Q,.1% Q2 Design Gross Electrie Output 565 7 10n n% 7450 Refueling Outage 14 will end in mid-November. As of November 1, core reload (120 new fuel assemblies) and replacement of six Local Power Range Monitor strings had been completed, as well as an enhanced visual inspection (IVVI) of Core Spray piping in the reactor vessel, and ultrasonic and visuti exams of reactor vessel welds. Corrective and preventive maintenance on "B" side safety systems had also been finished, with work on the "A" side systems in progress. A number of modification packages were nearing completion, involving items such as increased 11ydrogen injection, Noble Metals Chemical Addition, improved feedwater control, and 10 CFR 50 App. R enhancements.

On October 8,1996, with the plant operating at 93% power, two technicians inadvertently caused a Primary Containment Isolation System (PCIS) closure of the High Pressure Coolant Injection (IIPCI) outboard steam supply isolation valve. The valve closure resulted from a misplaced relay contact block which would have prevented the isolation during the calibration of a HPCI Steam Flow Indicating Switch. In response to this event, the front of the relays were labeled to indicate contact locations. Management conducted meetings with all plant maintenance

, personnel reinforcing the expectations for self-checking, independent verification, and dual verification. Plant I&C l personnel received additional briefings that included practical exercises on the simulator. (LER #96-004)

On October 20,1996, two spurious PCIS isolations occurred. They resulted in a secondary containment isolation, loss of drywell ventilation, isolation of various containment and reactor coolant sample valves, and isolation of the Reactor Water Cleanup system. The cause of the isolations is believed to be a voltage transient on a temporary power connection supplying Instrument AC. The transient resulted in a brief voltage drop that caused a momentary

{ loss of power to the Reactor Building Exhaust Radiation Monitor, the Reactor Water Cleanup instrument panel and various other instruments. All automatic actions occurred as designed on equipment that was not removed from

': l service for maintenance. In response to this event, a temporary power cart that was connected to the breaker was removed. (LER #96-005 -- pending) 1 1

On October 26,1996, six inoperable Local Power Range Monitor (LPRM) strings were discovered in a configuration which caused the Average Power Range Monitor (APRM) circuit to include the inoperable LPRMs into its averaging ofinputs. The final effect of this configuration is to cause the indicated APRM neutron power ,

level to be less than actual neutron power level (i.e., non-conservative). The condition of having indicated power l less than actual impaired the APRM 15% liigh Flux Scram function and would have caused the scram function to occur later than required.

The plant was in the Refuel Mode with fuel shuffling in progress. Technical Specifications require the APRM 15%

High Flux Scram function to be operable whenever the reactor is in REFUEL or STARTUP and IlOT STANDBY l Mode. Technical Specifications also require suspension of all operations involving CORE ALTERATION and insertion of all insertable control rods within one hour of the APRM 15% Neutron liigh Flux Trip becoming inoperable. The requirements were not met because fuel shuffling had begun at 0558 on October 25 (the prior day).

Upon discovery, the Operations Shift Supervisor immediately stopped the fuel shuffling and verified that all control rods were fully inserted. Finally, at 0020 on October 27,1996, it was discovered that at least one inoperable APRM I channel had not been placed in the tripped condition within one hour as required by Technical Specifications. All l six .APRM channels were discovered to be inoperable, but none had been placed in the tripped condition. When the i disconnected LPRMs were later bypassed, all six APRMs were found to be operable. j Following the event, an engineering evaluation was performed to quantify the plant effects ofleaving the APRM select switches in " Operate" for inoperative LPRMs. Operations placed the affected twenty-four LPRM switches in

" Bypass" with " CAUTION" tags on them. The Prerequisite Checklist of the Core Alteration procedure was performed again to ensure all other requirements were met. All other LPRMs were determined to be operable since no maintenance was performed on them. Longer term corrective actions will include revising the procedures and work control documents to ensure the LPRM mode selector switch is placed in " Bypass" prior to disconnecting the LPRMs. (LER # 96-006 -- pending)

Licensing Action Summerv:

Plant Availability: 33.4 % Unplanned Auto Scrams (while/ critical) this month: 0 Number of reportable events: 3 Unplanned Auto Scrams (while/ critical)last 12 months: 0 i

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