NG-94-0504, Monthly Operating Rept for Jan 1994 for DAEC
| ML20067B079 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold |
| Issue date: | 01/31/1994 |
| From: | Denise Wilson, Woodward R IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NG-94-0504, NG-94-504, NUDOCS 9402220300 | |
| Download: ML20067B079 (6) | |
Text
.
Iowa Electric Light and Power Company February 15,1994 NGA4-0504 Mr. John IL Martin Regional Administrator Region 111 U.S Nuclear Regulatory Commi.ssion 801 Warrenville Road
- 1. isle. II,60532-4 351
Subject:
Duane Arnold linergy Center Dmket No: 50-331 Operating License DPR-49 January 1994 Monthly Operating Report
Dear Mr. Martin:
I' lease find enclosed the Duane Arnold Energy Center Monthly Operating Report for January 1994. The report has been prepared in accordance with the guidelines of NUREG-0020 and distribution has been made in accordance with DAl:C Technical Specifications, Section 6.11.1.e.
Very truly yours.
David Wilson Plant Superintendent, Nuclear DI.W/RilW/ce Enclosures l'ile A-118d cc:
Dir. of Nuclear Reactor Regulation Mr. Dennis Murdock U.S. Nuclear Regulatory Conunission Central low a Pow er Cooperative Mail Station PI-137 llox 2517 Washington, D C. 20555 (Orig )
Cedar Rapids, IA 52406 Mr. Robert Pulsifer Mr. William Loveless l'rojett Manager U.S. NRC 1 Whitellint North I Whitellint North Mail Stop 131121 Mail Stop IICl4 11555 Rocksille hke i1555 Rockville Pike Retk s ille, MD 20X52 Rocksille, MD 20852 (2)
Document Control Desk Dr. William A. Jacobs, Jr.
INI'O Records Center GDS Associates,Inc.
i100 Cirtle 75 Parkway Suite 720 Smte 1500 1850 Parkwa) Place Atlanta, GA 30339 3064 Marietta, GA 30063-8237 Mr. Stes e ltrown Mr. Dale Arends town State Utihties lloard Corn R:lt Power Cooperative I ucas State Otlice fluilding 130013th Street North Des Moines, I A 50319 IlumbolJt, IA 50548 Mr. Fred Yost DCRC Director, Research Sen ices Utihty Data Institute NRC Resident inspector 1700 K St. NW, Suite 400 9402220300 940131
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Washington, DC 20006 PDR ADOCK 05000331 k R
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I Qy ; Qg vaane Arnohl Energy Center
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OPl! RATING DATA REPORT j
l DOCKET NO:
1()-0331 DATE:
Q2/15/94 _
Unit:
Duane Arnold Energy Center I
COMPLETED BY:
Richard Woodward OPEllATING STATUS 1.
Unit Name: Ihlanc_ Arnold.lincIgy_Cnller 2.
Reporting Period: January 1994 3.
1.icensed Thermal Power (MWth): MdB 4.
Nameplate Rating (Gross MWe DI!R): 5b5.7 ( futhinc) i 5.
Design Electrical Rating (Net MWe DER): 518 6.
Maximum Dependable Capacity (Gross MWe MDC): 515 7.
Maximum Dependable Capacity (Net MWe MDC):
515 8.
If Changes Occur in Capacity Ratings (items Number 3 through 7) since the last report, Give Reasons: N!%
9.
Power 1.evel to Which Restricted,if Any (Net MWe): MutApplientlk 10.
Reasons for Restrictions, if Any: No1Applicahk This Month Year-to-Date Cumulative 11.
Ilours in Reporting Perio 744.0 744.0 166,560.0 12.
. Number of flours Reactor Was Critical 744.0 744.0 123,688.6 13.
Reactor Reserve Shutdown llours 0.0 0.0 192.8 14.
Ifours Generator On-l.ine 744.0 744.0 120,522.7 15.
Unit Reserve Shutdown llours 0.0 0.0 0.0 16.
Gross Thermal linergy Generated (M WII) 1,224,863.2 1,224,863.2 165,683,427.4 17.
Gross Electrical Energy Generated (MWil) 415,081.0 415,081.0 55,495,466.5 18.
Net Electrical Energy Generated (MWIi) 391,497.0 391,497.0 52,023,159.9 19.
Unit Service Factor 100.0 %
100.0 %
72.4 %
20.
Unit Availability Factor 100.0 %
100.0 %
72.4 %
21.
Unit Capacity Factor (Using MDC Net) 102.2 %
102.2 %
62.0 %
22.
Unit Capacity Factor (Using DER Net) 97.8 %
97.8 %
59.3 %
23.
Unit Forced Outage Rate 0.0%
0.0%
i 1.8%
24.
Shutdowns Scheduled Os er Next 6 Months (Type, Date, and Duration of each): NoncJicheduled 25, if Shutdown at End of Report Period, Est. Date of Startup: (Not Applicabic)
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AVERAGE DAll.Y UNIT POWER LEVEL 3
DOCKET NO: 50-0331 DATE: 02/15/94 Unit: D,gane Arnold Energy Centet COMPLETED BY: Richard Woodward 1-TEl.EPilONE: (319)851-7313 MONTil January 1994 4
Average Daily Average Daily Power Level Power Level Day (NIWe-Net)
Day (MWe-Net)
I
$28.3 16 528.0 2
5 I 8.9 17 494.1 3
53 5 18 526.9 4
531.1 19 526.8 5
529.8 20 527.3 6
535.2 21 528.7 7
530.I 22 529.3 8
528.8 23 529.0 9
528.2 24 529.5 10 528.8 25 529.3 11 531.2 26 530.7 12 528.8 27 527.7 13 530.8 28 529.7 14 529.3 29 529A I5 528.5 30 482.4 31 529.1 i
e d
REFUELING INFORMATION
^
DOCKET NO: 10-0331 DATE: Q2!!5/94 Unit: Ilma. Arnold Energy Center COMPl.ETED BY: Itishard woodward TEl.EPIIONE: 0 19)851-7318 1.
Name of facility.
Duane Arnold Energy Center 2.
Scheduled date for next refueling shutdown.
February 23,1995 3.
Scheduled date for restart following refueling.
April 14 - 19,1995 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
No 4
5.
Scheduled date(s) for sulunitting proposed licensing action and supporting information.
Not applicable j
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.
The number of fuel assemblies (a)in the core,(b)in the spent fuel storage pool a.
368 b.
1280 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned,in number of fuel assemblies.
a.
2050 - Licensed Capacity or b.
I 898 under the presently installed storage rack capacity.
3152 requested by RTS#252, submitted March 26,1993 c.
9.
The projected date of the last refueling that can he discharged to the spent fuel pool assuming the present licensed capacity.
a.
2000 Licensed Capacity or b.
1998 under the presently installed storage rack capacity.
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l DOCKET NO.: 1Q-0111 DATE: 02/15/94
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Unit: _Duane Arnold Energy Centet COMPLETED BY: Richard Woodward TELEPilONE: (3191851-731R Monthly Operational Overview for January 1994:
The only downpowers during January were brief periods to perfonn turbine valve testiag on January 2 and to perform turbine valve testing. heater bay inspections, and a control rod sequence exchange on January 30. On January 17 a power reduction was performed as a conservative measure (anticipating potential consequences) as a result of a frozen pipe causing flow disruption in the offgas system. Forgone production during these downpower: totaled approximately the equivalent of four hours' generation. Elliciency losses have gradually increased by 4 5 MWe since the October 26-28 outage. Fouling of the Feedwater flow noales is suspected. Fouled nozzles would cause the heat balance calculation to indicate more reactor pow er than is actually being produced.
Production and Loss Statistics for the January:
Electric Capacity Clock Output Factor Hours
% of 565.7 # of 744 MWe h1We Hours Actual Electric Output 557.9 98.6 %
733.7 Weather (gains)/ losses
-2.8
-0.5%
-3.7 Control Rod Movements 1.8 03%
2.4 Other Capacity Losses (Avg MWth < 1658) 0.9 0.2%
1.2 Efficiency 1.osses (Weather Normalized Full Power MWe < 565.7) 23 1d%
10A Design Electric Output 1612 JDO,0%
744.0 On January 7,1994 while the plant was operating at 100% power, it was determined that the surveillance test of the Averuge Power Range Monitor (APRM) high flux scram trip setpoint was inadequate. The test had not been performed at a recirculation How greater than 100% to ensure that the scram setpoint did not exceed 120% rated power, as required by the Technical Specifications. The APRMs were considered to be inoperable and a six hour to Startup mode Limiting Condition for Operation (LCO) was entered. The test was revised and performed with satisfactory results and the LCO was exited. This condition was caused by a lack of awareness of the requirement to test the " clamping" function on the scram trip setpoint. The test results verified that the " clamping" function had been and is set properly at 120% rated power. There was no effect on safe operation of the plant. (LER 94-01)
On January 12.1994, during routine surveillance of the Reactor Core Isolation Cooling (RCIC) system, three of the four low steam supply pressure isolation switches were found to have drifted below their allowed values (in the non-conservative direction). These four switches generate Primary Containment Isolation System (PCIS) signals to the RCIC inboard and outboard steam supply valves. The plant was operating at 100% power at the time of the surveillance with no existing limiting conditions for operation (LCOs)in effect. All three pressure switches were recalibrated and returned to service within the allowed out-of-ser ice-times. Increased surveillance frequency, procedure revisions, insto
.nt Trending Program enhancements, and Engineering evaluations of the Barksdale model 112T-M12SS pressure switches are in progress to preclude the recurrence of this and similar events. There was no effect on continued safe operation of the plant or personnel safety as a result of this event. (LER 94-02 pending)
On January 19,1994 out-of-service maintenance was performed on Off Gas vent radiation monitors without operation of the Standby Gas Treatment Systen to establish Secondary Containment integrity within one hour as required by Technical Specifications. The Oft Gas vent radiation monitors were successfully returned to service and verified operable on January 2 L 1994. A separate Off Gas stack ernuent radiation monitor was operable during the maintenance, and no abnormal trends were inJicated. There was no effect on the safe operation of the plant.
(LER 94-03 pending)
Licensing Ardienjiummntyl Plant Availability:
100.0 %
Unplanned Auto Scrams (while/ Critical) this month:
0 Number of reportable events: 3 Unplanned Auto Scrams (w hile/ Critical) last 12 months:
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