1CAN058504, Monthly Operating Rept for Apr 1985
| ML20129G312 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/30/1985 |
| From: | Enos J, Morton K ARKANSAS POWER & LIGHT CO. |
| To: | Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 1CAN058504, 1CAN58504, NUDOCS 8507180019 | |
| Download: ML20129G312 (6) | |
Text
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OPERATING DATA REPORT DOCKET NO:
50-313 DATE:
April 1985 COMPLETED 8Y:K. L. Morton TELEPHONE:
501-964-3115 OPERATING STATUS 1.
Unit Name:
Arkansas Nuclear One - Unit 1 2.
Reporting Period:
April 1-30, 1985 3.
Licensed Thermal Power (MWt):
2568 4.
Nameplate Rating (Gross MWe):
902.74 5.
Design Electrical Rating (Net MWe):
850 6.
Maximum Dependable Capacity (Gross MWe):
883 7.
Maximum Dependable Capacity (Net MWe):
836 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9.
Power Level To Which Restricted.
If Any (Net MWe):
None 10.
Reasons For Restrictions.
If Any:
None MONTH YR-TO-DATE CUMULATVE 11.
Hours in Reporting Period....
719.0 2,879.0 90,858.0 12.
Number of Hours Reactor was Critical.....................
561.5 1,710.5 60,368.4 13.
Reactor Reserve Shutdown Hours........................
0.0 0.0 5,044.0 14.
Hours Generator On-Line......
555.1 1,618.2 59,021.7 15.
Unit Reserve Shutdown Hours..
0.0 0.0 817.5
- 16. Gross Thermal Energy Generated (MWH)........................
1,382,363.0 3,842,815.0 140,195,631.0
- 17. Gross Electrical Energy Generated (MWH)..............
468,035.0 1,293,594.0 46,255,865.0 18.
Net Electrical Energy Generated (MWH)..............
443,934.0 1,214,936.0 44,077,459.0
- 19. Unit Service Factor..........
77.2 56.2 65.0 20.
Unit Availability Factor.....
77.2 56.2 65.9 21.
Unit Capacity Factor (Using MDC Net)..............
73.9 50.5 58.0 22.
Unit Capacity Factor l
(Using DER Net)..............
72.6 49.6 57.1 23.
Unit Forced Outage Rate......
22.8 29.1 15.1 l
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
None 25.
If Shut Down At End of Report Period.
Estimated Date of Startup:
26.
Units in Test Status (Prior to Commercial Operation):
Forecast Achieved l
INITIAL CRITICALITY l
INITIAL ELECTRICITY COMMERCIAL OPERATION l
i 0507180019 850430 7
DR ADOCK 0500 3
g L
o AVERAGE DAILY UNIT POWER LEVEL DOCKET N0:
50-313 UNIT:
One DATE:
April, 1986 COMPLETED BY: K. L. Morton TELEPHONE:
501-964-3115 MONTH April 1985 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.............
830 2.............
830 3.............
828
'4.............
826 5.............
830 6.............
831 7.............
831 8.............
830 9.............
657 10............
-29 11............
-10 12............
-8 13............
-21 14............
-32 15............
-32 16............
17 17............
560 18............
787 19............
837 20............
846 21............
834 22............
832 23............
834 24............
833 25............
831 26............
833 27............
833 28............
832 29............
831 30............
830 31............
AVGS:
617 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for each day in reporting month.
Compute to the nearest whole megawatt.
NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
APRIL 1985 UNIT ONE The unit started the month at 100% full power.
At 1914 hours0.0222 days <br />0.532 hours <br />0.00316 weeks <br />7.28277e-4 months <br /> on the 9th, the unit tripped because of a reactor trip on high RCS pressure.
The initiating event was the loss of a main feedwater pump.
A high resistance contact on the auxiliary relay in the "A" main feedwater pump control caused the demand signal to be limited, even in manual control.
This prevented the pump from responding correctly to the flow demand signal, which was being affected by a failed static analog memory for the AT cold control module.
This AT cold control circuit provides steam generator heat load ratio control.
The pump subsequently tripped on low suction pressure, causing the reactor trip.
The unit was taken to cold shutdown to repair a failed bleeder trip valve on a high pressure turbine extraction line and to perform an inspection on some snubbers.
A plant heatup was begun at 0546 hours0.00632 days <br />0.152 hours <br />9.027778e-4 weeks <br />2.07753e-4 months <br /> on the 13th with the reactor going critical at 0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br /> on the 16th and the unit placed on line at 1508 hours0.0175 days <br />0.419 hours <br />0.00249 weeks <br />5.73794e-4 months <br /> the same day.
The unit attained 100% full power operation at 1110 hours0.0128 days <br />0.308 hours <br />0.00184 weeks <br />4.22355e-4 months <br /> on the 18th and remained there through the end of the month.
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR APRIL 1985 DOCKET NO 50-313 UNIT NAME ANO Unit One DATE May 6, 1985 COMPLETED BY K. L. Morton TELEPHONE (501) 964-3115 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to 2
No.
Date Type (Hours)
Reason 2 Down Reactor 3 Report #
Code 4 Codes Prevent Recurrence 85-02 850409 F
163.9 A
2 ILER-85-003 5J P
Unit trip on high RCS pressure due to main feedwater pump trip.
Returned plant to power after correcting "A" MFWP control problem.
1 2
3 4
F:
Forced Reason:
Method:
Exhibit G - Instructions 5:
Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Continuation 1022)
E-Operator Training &
5-Load Reduction License Examination 9-Other s
F-Administrative Exhibit I - Same Source G-Operational Error (Explain)
H-Other (Explain)
O a
i y.
DATE:
April 1985 REFUELING INFORMATION 1.
Name of facility:
Arkansas Nuclear One - Unit 1 2.
Scheduled date for next refueling shutdown.
August, 1986 3.
Scheduled date for restart following refueling.
October, 1986 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
If answer is yes, what, in general, will there be?
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?
Yes.
Reload Report and associated proposed Technical Specification change request.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
May 1, 1986 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.
None 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, a) 177 b) 456 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.
present 988 increase size by 0 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
DATE:
1998
[g ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK, ARKANSAS 72203 (501)371-4000 May 15, 1985 1 Call 058504 Mr. Harold S. Bassett, Director Division of Data Automation and Management Information i
Office of Resource Management U. S. Nuclear Regulatory Commission Washington, D. C.
20555
SUBJECT:
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Monthly Operating Report Gentlemen:
The Arkansas Nuclear One - Unit 1 Monthly Operating Report for April 1985 is attached.
Ve truly
- urs, J. Ted Enos Manager, Licensing JTE:MCS:ds Attachment cc:
Mr. Robert D. Martin Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Mr. Richard C. DeYoung Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555
((\\
MEMBEA MiDOLE SOUTH UTIUTIES SYSTEM