ML20249B517
| ML20249B517 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 05/31/1998 |
| From: | Woodward R IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | |
| Shared Package | |
| ML20249B514 | List: |
| References | |
| NUDOCS 9806230252 | |
| Download: ML20249B517 (6) | |
Text
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i 1
OPERATING DATA REPORT DOCKET NO:
10-0331 DATE:
06/15/98 Unit:
Duane Arnold Energy Center COMPLETED BY:
Richard Woodward TELEPHONE:
(319) 851-7318
{
OPERATING STATUS 1
1.
Unit Name: Duane Arnold Enerav Center i
2.
Reporting Period: May 1998 Average Daily Power Level 3.
LicensedThermalPower(MW ): 1658 500
[g th g
Z 400
)
4.
Nameplate Rating (Gross MW DER): 565.7 (Turbine)
- 300 e
- g 200 E 100 5.
Design Electrical Rating (Net MW DER): 538 3
e O
6.
Maximum Dependable Capacity (Gross MW MDC): 559 1
6 11 16 21 26 31 5
e 7,
Maximum Dependable Capacity (Net MW MDC): 229 Y
e 8.
If Changes Occur in Capacity Ratings (Items Number 3 through 7) since the last report, Give Reasons: Not Annlicable
{
9.
Power Level to Which Restricted, If Any (Net Mw ): May 1-22. oft-line e
10.
Reasons for Restrictions, If Any: Refuel Outane 1
l May-98 1998 Cumulative 11.
Hours in Reporting Period 744.0 3,623.0 204,503.0 12.
Number of Hours Reactor Was Critical 330.2 2,543.8 157,310.3 13.
Reactor Reserve Shutdown Hours 0.0 0.0 192.8 14.
Hours Generator On-Line 246.3 2,458.2 153,607.3 15.
Unit Reserve Shutdown Hours 0.0 0.0 0.0 16.
Gross Thermal Energy Generated (MWH) 292,411.2 3,903,132.0 218,609,174.2 17.
Gross Electrical Energy Generated (MWH) 87,543.0 1,318,302.0 73,310,988.6 I 8.
Net Electrical Energy Generated (MWH) 81,814.3 1,243,324.3 68,814,412.5 19 Unit Service Factor 33.1 %
67.9 %
75.1 %
20.
Unit Availability Factor 33.1 %
67.9 %
75.1 %
21.
Unit Capacity Factor (Using MDC Net) 21.1%
66.0 %
70.8 %
22.
Unit Capcity Factor (Using DER Net) 20.4 %
63.8 %
67.8 %
23.
Unit Forced Outage Rate 0.0%
0.0%
9.7%
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of each): NL%
1 25.
If Shutdown at End of Report Period, Estimated Date of Startup: NL%
1 9806230252 900615 PDR ADOCK 05000331 R
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-0331 DATE: _06/I5/98 Unit: Duane Amold Enerev Center j
COMPLETED BY: Richard Woodward TELEPHONE: (319)851-7318 MONTH May 1998 j
Day Average Daily Power Level (MWe-Net) 1 0.0 2
0.0 3
0.0 4
0.0 5
0.0 6
0.0 7
0.0 8
0.0 9
0.0 10.
0.0 11 0.0 12 0.0 13 0.0 14 0.0 15 0.0 16 0.0 17 0.0 18 0.0 19 0.0 20 0.0 21 0.5 22 117.3 23 119.8 24 250.1 25 383.3 26 503.8 27 413.5 28 264.7 29 334.3 30 491.8 31 515.6]
t REFUELING INFORMATION l
DOCKET NO: 50-0331 DATE: 06/15/98 Unit: Duane Arnold Enercy Center COMPLETED BY: Richard Woodward TELEPilONE: (319) 851-7318 1.
Name of facility. Duane Arnold Enercy Center 2.
Scheduled date for next refueling shutdown. October 8.1999
(
3.
Scheduled date for restart following refueling. November 13.1999
[
4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? N_O l
I 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
N/A 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. N/A l
l 7.
Current and projected fuel assemblies inventory:
Number of Projected date oflast Fuel refueling that can be discharged i
Assemblies (after allowing margin for I
maintenance of continuous full-core discharge capability)
Installed in reactor core 368 n/a l
Previously discharged from core to Spent Fuel Storage Pool 1648 n/a Installed Capacity of Spent Fuel Storage Pool 2411 2001 j
Licensed Capacity of Spent Fuel Storage Poc,1 (with reracking) 2829 2006 Licensed Capacity of Spent Fuel Storage Pool and Cask Pool (with 3152 2010 t
reracking)
(
--m.___________-_m_-
1.
- DOCKET NO: 50-0331 DATE: 06/15/98 Unit: Duane Arnold Enercy Center COMPLETED BY: Richard Woodward TELEPHONE: (319)851-73,18 UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: May 1998 No.
Date Type Duration Reason Method of Licensee Cause (1)
(Hours)
(2)
Shutting Event Down Reactor Report #
(3) 2 05/01/98 S
497.4 C
2 Refueling outage 3
05/27/97 F
0 A
5 Repair oilleak on 'A' (27.0 full-feedwater pump power hours equivalent) 1 - F: Forced 2 - Reason 3 - Method:
)
S: Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continued E-Operator Training & License Examination 5-Reduced Load F-Administrative 9-Other (Explain)
G-Operational Error (Explain)
H-Other (Explain) l l
l L______________________________..___________
b DOCKET NO.:
50-0331 DATE:
06/15/98 Unit: Duane Arnold Energy Center COMPLETED BY:
Richard Woodward TELEP110NE: (3191 851-7318 Monthly Operational Overview for May 1998 At the beginning of the month, the DAEC was 28 days in to its scheduled 45-day refuel outage (RFO-15). During the refuel outage,120 thrice-burned fuel assemblies were replaced with fresh fuel. Outage workscope included 270 surveillance tests,157 in-service inspections, and 1623 separate maintenance actions, two torus suction strainer /
Emergency Core Cooling System (ECCS) modifications, overhaul of the high pressure turbine, and rewind of the generator stator.
In the startup sequence, the reactor was taken critical May 18 at 05:49. The generator was first connected to the giid for the turbine roll May 21 at 15:26, then taken off-line to balance the turbine at 22:10. After 48 days,19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br />,29 minutes, Refuel Outage 15 officially ended with the final synchronization of the generator to the grid at 00:24 hours on May 22.
At 13:59 on May 27, repair of an oil leak on the 'A' feedwater pump motor required power to be reduced to 50%. At 15:30 on May 29, the 'A' Feed Pump was returned to service, and ascension to full-power completed at 18:00 on May 30.
Following is a chronology of the startup and operation through the month.
From To Event Generation Losses (Full-Power-Hours.
Equivalent) 04/03/97 03:55 05/01/98 00:00 Cycle 15 Shutdown until May 1 05/01/98 00:00 05/18/98 05:49 May I until Reactor Critical 413.8 (Off-Line) 05/18/98 05:49 05/21/98 15:26 Reactor Critical Until Turbine Roll 81.7 (Off-Line) 05/21/98 15:26 05/21/98 22:10 Turbine Over-Speed Testing 6.0 05/2I/98 22:10 05/22/98 00:24 Turbine Trip until Generator On-line 2.2 (oft-Line) 05/22/98 00:24 05/26/98 15:42 Ramp-up to full-power
$5.4 05/26/98 15:42 05/27/98 13:59 Full Power 05/27/98 13:59 05/29/98 00:00 Repair 'A' Feed Pump Oil Leak 15.5 05/29/98 00:00 06/01/98 00:00 Full Power, Rod Pulls 11.5 Ef11ciency Losses 1:3 Total Losses
$89.1 (497.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Off-Line)
Allocation of Production & Losses:
Electncal Capacity Factor Full Power Output
% of 565.7 MWe Equivalent MWe (Design Rating) llours (FPil,)
l Actual Metered Net Electric Output 109.5 19.4 %
144.0 i
l Actual Metered Plant Electric leads (while on-line) 8.2 1.4%
10.8 Off-I ine Capacity Losses:
378.4 66.9 %
497.7 On-Line Unplanned Capacity Losses:
20.7 3.7%
27.2 l --
Vormal Capacity Losses (Avg?FallPowr" MWth < 1658) 0.0 0.0%
0.(1 l
On-1 ine planned Capacity Losses 47.7 8.4%
62.6 (neg.) Weather losses - condenser pressure <2.75 in lig / Circ Water Temp < 74.5 'r 0.2 0.0%
0]
Unplanned Et11ciency lasses (Weather-Norm-Full-Power-MWe > 565.7 Design) 08 02%
1.1 Metering (Avg indicated power MWe - Avg metered energy MWile) 0.2 0.0%
0J Excluded losses (coast-down, lack of grid demand. etc.)
00 00%
00 Design Gross Electric Output 3
M 24,;}JQ L___-____-___________
T
. A DOCKET NO.:
50-0331 DATE: 06/15/98 Unit:
Duane Arnold Enerav Center COMPLETED BY: Richard Woodward TELEPHONE: (319) 851-7318 On April 29,1998, while the plant was in Cold Shutdown for Refueling Outage 15, a review of a previously performed operability evaluGa determined that Containment Atmosphere Control System Hydrogen and Oxygen Monitors were technically inoperable in the past. Specifically it was determined that a significant inaccuracy in indicated readings above post-accident conditions could have occurred as a result of steam condensing in the sample lines due to insufficient heat tracing and insulation. As a result the accuracy requirements of NUREG 0737 were not met and operation in a condition prohibited by Technical Specifications existed.
L The cause of this event was less than adequate implementation of original design requirements. Interim actions include implementation of a correction factor chart which was later converted into a calculation and implemented into an operating procedure. A modification is in progress to upgrade the heat tracing and insulation. His sample error could have resulted in excessively conservative indication of containment combustibility under certain accident conditions, but had no actual or potential consequences on safe operations of the plant. (LER 98-05).
While in cold shutdown for Refueling Outage 15 all the Main Steam Relief Valves (MSRVs) and Main Steam Safety Valves (MSSVs) were removed and as-found setpoint testing was completed on May 2,1998, at NWS (Nederostek-Williams-Schulte) Technologies. Five of the eight valves failed to meet the setpoint requirements of the Technical
)
l Specification (TS) Limiting Safety System Setting. The cause of the MSRVs' failure was inadequate corrective actions and the cause of the MSSV failure is unknown. All MSRV pilots and the MSSVs have been replaced with valves that were previously set pressure tested. He out of tolerance valves will be restored to within their TS Limiting Safety System Settings prior to reinstallation. He actual and potential safety consequences associated with this condition were minimal. Improvements previously made to the setpoint methodology for the MSSVs will be evaluated for effectiveness.
Additional actions required to further expand the tolerances to the full range of *3% will be completed. (LER 98-04)
On May 19,1998, while the plant was starting up from the refuel outage with the reactor operating at 8% power, it was
- discovered that a visual examination (VT-2) had not been performed on the Standby Liquid Control (SBLC) system explosive valves prior to returning them to service. He SBLC system was declared inoperable and a 24-hour limiting l
i condition for operation (LCO) per the Technical Specification was entered. The cause of the event was a failure to recognize the addition of the SBLC system to the Inservice Inspection (ISI) Program during the ISI maintenance planning. A VT-2 examination was subsequently performed satisfactorily on the explosive valves and completed well within the LCO time frame. This event has been discussed with the ISI maintenance planning personnel. As a long term corrective action to aid in not missing the VT-2 examination for the explosive valves in the future, the SBLC system test procedure (STP 44A002-CY, SBLC System Manual Initiation, Explosion Valve Test, and Relief Valve Test) will be revised to specify that a VT-2 examination is required. Here were no actual safety consequences associated with this event as the explosive valves were operable (or leak tight) throughout the period of the event, proven by the subsequent VT-2 examination. (LER 98-06, pending)
'Licensine Action Summary:
1 Plant Availability:
33.1 %
Unplanned Auto Scrams (while/ critical) this month:
0 l
- Number of reportable events:
3 Unplanned Auto Scrams (while/ critical) last 12 months:
0 Safety Relief Valve Challenges:
0
)
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l l
l L.____.______________________._______