NG-93-4386, Monthly Operating Rept for Sept 1993 for DAEC
| ML20059A591 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 09/30/1993 |
| From: | Denise Wilson, Woodward R IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NG-93-4386, NUDOCS 9310260404 | |
| Download: ML20059A591 (6) | |
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l Iowa Electric Light and Power Company October 15,1993 NG-934386 Mr. John II. Martin Regional Administrator Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn,IL 60137
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Subject:
Duane Arnold Energy Center Docket No: 50-331
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Operating License DPR49 September 1993 Monthly Operating Report
Dear Mr. Martin:
1 Please find enclosed the Duane Amold Energy Center Monthly Operating Report for September 1993. The report has been prepared in accordance with the Fuidelines of NUREG4)020 and distnbution has been made in accordance with DAEC Tecimical Specifications, Section 6.11.1.c.
Very truly yours, David Wilson Plant Superintendent, Nuclear DLW/RBW/cc l
Enclosures Pile A-118d
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cc:
Dir. of Nuclear Reactor Regulation Mr. Dennis Murdock U.S Nuclear Regulatory Commission Central lowa Power Cooperative Mail Station Pl-137 Box 2517 Washington, D C. 20535 (Orig.)
Cedar Rapids,IA 52406 Mr. Robert Pulsifer Mr. William Loveless Project Manager U.S. NRC 1 Whitellint North I Whiteflint North Mail Stop 13E21 Mail Stop 11Cl4 11555 Rockville Pike 11555 Rockville Pike Rockville, MD 20852 Rockville, MD 20852 (2)
Document Control Desk Dr. William A. Jacobs, Jr.
INPO Records Center GDS Associates,Inc.
I100 Circle 75 Parkway Suite 720 Suite 1500 1850 Parkway Place Atlanta, GA 30339-3064 Marietta, GA 30068-8237 Mr. Steve Brown Mr. Dale Arends Iowa State Utilities lloard Corn Belt Power Cooperative Lucas State Office Buildmg 130013th Street North 4
Des Moines,IA 50319 Ihtmboldt,IA 50548 Mr Fred Yost DCRC Director, Research Services
/
I Utility Data Institute NRC Resident inspector
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j iX NW, Suite 4W 9310260404 930930 h
/j 2 7 @a.nington. DC 20006 i
PDR ADOCK 05000331 p f
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Uuane Arnold Energy Center
- 3277 UALC Itoad
- Palo, Iowa 52324
- 319 M17611 l
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- OPERATING DATA REPORT l
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I DOCKET NO:
50-0331 DATE:
10/15/93 Unit:
Duane Arnold Enercy Center COMPLETED BY:
Richard Woodward
't OPERATING STATUS 1.
Unit Name: Duane Arnold Enerny Center 2.
Reporting Period: September 1993 3.
Licensed Thermal Power (MWt): 1658 4.
Nameplate Rating (Gross MWe DER): 565.7 (Turbine)
-5.
Design Electrical Rating (Net MWe DER): 138 6.
Maximum Dependable Capacity (Gross MWe MDC): 545 7.
Maximum Dependable Capacity (Net MWe MDC): -115 i
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): 0 MWe 10.
Reasons for Restrictions, If Any: Refueline Outagq This Month Year-to-Date Cumulative 11.
Hours in Reporting Period 720.0 6,551.0 163,607.0 12.
Number ofIlours Reactor Was Ciitical 0.0 4,903.2 120,884.4 13.
Reactor Reserve Shutdown Hours 0.0 0.0 192.8 14.
Hours Generator On-Line 0.0 4,878.9 117,901.4 15.
Unit Resene Shutdon Hours 0.0 0.0 0.0 j
16.
Gross Hermal Energy Generated (MWH) 0.0 7,382,404.1 161,465,697.8 17.
Gross Electrical Energy Generated (MWH) 0.0 2,445,857.0 54,070,766.5-18.
Net Electrical Energy Generated (MWH)
-3,578.9 2,287,481.9 50,684,135.7 19.
Unit Senice Factor 0.0%
74.5 %
72.1 %
20.
Unit Availability Factor 0.0%
74.5 %
72.1 %
21.
Unit Capacity Factor (Using MDC Net) 0.0%
67.8 %
61.5 %
22.
Unit Capacity Factor (Using DER Net) 0.0%
64.9 %
58.9%
i 23.
Unit Forced Outage Rate 0.0%
0.0%
12.0 %
- 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of each): None Scheduled 25.
If Shutdown at End of Report Period, Est. Date of Startup: (Restarted October 13.1993)
AVERAGE DAILY UNIT POWER LEVEL
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DOCKET NO: 50-0331 DATE: 10/15/93.
Unit: Duane Arnold Enercy Center
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COMPLETED BY: Richard Woodward f
TELEPHONE: 0 19) 851-7318 MONT11 September 1993 Day Average Daily Day Average Daily Power Level Power Level (MWe-Net)
(MWe-Net)
I 1
-2.9 16
-4.1 2
-1.3_
17 M
3
-3.2 18
-4.3 4
-2.6 19
-4.1 l
5
-2.7 20
-4.2 6
-2 9 21
-4.4 7
-3.I 22
-5.0 8
-3 3 23 M
9
-3 J 24
-ld 10
-3.0 25
-7.0 11 djo 26
-10.3 12
-4.0 27
-6.0 13
-4.6 28
-9.5
)
14
-4_3 29
-11.2 15
-4.3 30
-9.4 i
(Station uses) l I
i l
l l
REFUELING INFORMATION l
DOCKET NO: 50-0331 DATE: 10/15/93 '
l Unit: Duane Arnold Encrcy Center COMPLETED BY: Bjchard Woodward '
TELEPHONE: (319)851-7318 I
1.
Name of facility.
' j Duane Arnold Energy Center i
2.
Scheduled date for next refueling shutdown.
February 1995
'i 3.
Scheduled date for restart following refueling.
I Has not been determined l
4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
i No 5.
Scheduled date(s) for submitting proposed licensing action and supporting I
information.
Not applicable 6.
Important licensing co9siderations associated with refueling, e.g., new or different '
i fuel design or supplic, unreviewed design or performance analysis methods, significant changes b fuel design, new operating procedures, s
No 7.
The number of fuel assemblies (a) in the core,(b) in the spent fuel storage pool a.
368 b.
1280 i
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 er Capacity or
.i b,
1898 une a e p esently installed storage rack capacity.
c.
3152 reque.. ' %/ RTS#252, submitted March 26,1993 9.
The projected date of the last refueling that can be discharged to the spent fuel pool e
assuming the present licensed capacity.
a.
2000 Licensed Capacity or b.
1998 under the presently installed storage rack capacity.
i
t DOCKET NO: 50433I r
DATE: 10/15/93 Unit: Duane Arnold Enerty Center COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318 UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTil: September 1993
?
i No.
Date Type Duration Reason Method of Licensee System Comp.
Cause (1)
(Hours)
(2)
Shutting Event Report Code Code Down (4)
(5)
Reactor (3) 1 9/l/93 S
720 C
4 N/A N/A N/A Refueling outage commenced 7/29/9313:05.
1 - F: Forced 2 - Reason:
3 - Method:
4 - Exhibit G.
1 S: Scheduled A-Equipment Failure (Explain) 1-Manual Instructions for Preparation of Data Entry B-Maintenance or Test 2-Manual Scram Shects for Licensee Event Report (LER) File C-Refueling 3-Automatic Scram (NUREG-0161)
D-Regulatory Restriction 4-Continued E-Operator Training & License 5-Reduced Load 5 - Exhibit 1 Examination 9-Other (Explain)
(Same Source) -
F-Administrative G-Operational Error (Explain) iI-Other (Explain i
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4 DOCKET NO.: 50-0331 DATE: 10/15/93 Unit: Duane Arnold Enerry Center COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318 Monthly Operational Oveniew for September 1993:
As of the first of September DAEC had entered Day 34 ofits scheduled 59 day maintenance and refueling outage.
Feedwater pump reassembly was in process. In-vessel inspections of the Core Shroud Welds and Core Spray Spargers had been completed. Divers had finished the Fecdwater Sparger repairs. Secondary Containment had been returned to senice, and the Main Turbine work was progressing well. All diaphragms were back in place, the inner casings were installed, and the hood was reinstalled. The control vahrs were reassembled, the bypass valve repair completed, and the EHC (E:cetro-Hydraulic Control) system work nearly completed.
During the second week of September Control Rod Drive (CRD) system repairs were completed and the CRD system restarted. The 'A' RHR (Residual Heat Removal) repairs were finishing up, and the system was made ready to go into 'A' side shutdown cooling. The Ce.rc reload began at 10:00 09/05/93 and finished on 09/11/93 at 24:00. The 'A' and 'D' Main Steam Isolation Valve (MSIV) repairs were in progress.
The reactor internals, reactor head, insulation head, and drywell head were all installed during the third week of September in preparation for performance of the Integrated Leak Rate Test (ILRT). Core Spray, RHR, RHR Senice Water, and Standby Diesel Generator maintenance were all completed.
The ILRT was performed September 19 - 22. "As-left" leakage was 0.25 Ydday or 0.1 L. After adjustments for a
Local Leak Rate Test improvements, the "as-found" containment leakage was 0.51 Ydday or 0.25 L. Following a
the ILRT, over-speed testing of the High Pressure Coolant injection (HPCI) and Reactor Core Isolation Cooling.
(RCIC) pumps was completed. The Class I Leak Rate Test (hydro) inspections were completed at approximately 1000 psig and revealed the necessity to perform a few funher repairs. The reactor was depressurized and vessel tempemture dropped below 212
- F, returning the vessel to a cold shutdown condition.
At the end of September repairs were continuing on the inboard Reactor Water Cleanup Isolation valve, a Main Steam Line Drain inboard isolation valve, the HPCI stop valve limit switch, and 4160 KV breakers. These repairs have delayed start-up beyond the originally planned September 26 start-up date.
On September 21,1993, the plant was in cold shutdown Ibr refueling when a partial Primary Containment Isolation System (PCIS) Group 4 isolation occurred ('A' shutdown cooling). This event occurred while transferring Reactor Protection System (RPS) power supply sources from the alternate source to the 'A' RPS motor generator.
Isolation valves were, per procedure, decnergized open during the transfer to prevent unwanted isolations.
Following the transfer, PCIS Divisions (I and 2) were reset and annunciators PCIS GROUPS (1 through 5)
ISOLATIONS were verified rescL The operator was then directed, by procedure, to recnergize the shutdown cooling suction and inject valves. Upon closing the breaker to the 'A' residual heat removal inboard inject valve, the valve went closed, isolating shutdown cooling. This occurred due to the isolation signal being locked in for this valve by design. There was no measurable increase in reactor vessel temperatures. The valve was reopened within nineteen seconds. The procedure was resised to give direction to reset the locked-in signal prior to recnergizing the valve. LER 93-07 On Septenmer 16,1993 the 'B' Standby Diesel Genemtor (SBDG) output breaker,1 A411, failed to close during the performance of the Loss of Offsite Power - Loss of Coolant Accident (LOOP-LOCA) surveillance test. The cause was an improper clearance between the breaker mechanism on the Standby Transformer feeder breaker, I A401, to essential bus 1 A4. This improper clearance disabled one of the closure permissives for 1 A411. The corrective actions included readjusting the gap between the breaker plunger and the stationary auxiliary switch to within the specifications intended by the breater vendor. LER 93-08 (pending)
Mggnsine Action Summam Plant Availability; 0.0%
Unplanned Auto Scrams (w/ Critical) this month:
0 Number of reportable events: 2 Unplanned Auto Scrams (w/ Critical)last 12 months:
1