1CAN038506, Monthly Operating Rept for Feb 1985
| ML20115F634 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear |
| Issue date: | 02/28/1985 |
| From: | Enos J, Morton K ARKANSAS POWER & LIGHT CO. |
| To: | Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 1CAN038506, 1CAN38506, NUDOCS 8504190605 | |
| Download: ML20115F634 (6) | |
Text
.
1 OPERATING DATA REPORT DOCKET N0:
50-313 DATE:
February 1985 COMPLETED BY:K. L. Morton TELEPHONE:
501-964-3115 OPERATING STATUS 1.
Unit Name:
Arkansas Nuclear One - Unit 1 2.
Reporting Period:
February 1-28, 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....
672.0 1,416.0 89,395.0 12.
Number of Hours Reactor was Critical.....................
242.0 405.0 39,062.9 13.
Reactor Reserve Shutdown Hours........................
0.0 0.0 5,044.0 14.
Hours Generator On-Line......
230.6 319.1 57,722.6 15.
Unit Reserve Shutdown Hours..
0.0 0.0 817.5
'16.
Gross Thermal Energy Generated (MWH)........................
489,530.0 558,607.0 136,911,423.0 17.
Gross Electrical Energy Generated (MWH)..............
163,900.0 182, 899.0 45,145,170.0 18.
Net Electrical Energy Generated (MWH)..............
151,120.0 155,413.0 43,017,936.0 19.
Unit Service Factor..........
34.3 22.5 64.6 20.
Unit Availability Factor.....
34.3 22.5 65.5 21.
Unit Capacity Factor (Using MDC Net)..............
26.9 13.1 57.6 22.
Unit Capacity Factor (Us'ing DER Net)..............
26.5 12.9 56.6 23.
Unit Forced Outage Rate......
65.7 61.0 15.1 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Nor.e 25.
If Shut Down At End of Report Period.
Estimated Date of Startup:
26.
Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8504190605 850228 PDR ADOCK 05000313.
R PDR _
[hv [
l
1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-313 UNIT:
One DATE:
February, 1985 COMPLETED BY: K. L. Morton TELEPHONE:
501-964-3115 MONTH February 1985 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
~l.............
-8 2..............
-8 3.............
-8 4.............
-7 S.............
-5 6.............
-5 7.............
-8 8.............
-8 9.............
-15 10............
-25 11............
-9 12............
-8 13............
-8 14............
-8 15............
-8 16............
~.8 17............
-10 18............
-30 19............
90 20............
372 21............
611 22~............
622 23............
669 24............
806 25............
828 26~............
827 27............
828 28............
829 l'
29............
30............
31.............
Avg.
225 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.
-i NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
FEBRUARY 1984 UNIT ONE The unit started the month in cold shutdown mode for repair of the control
. rod drive stator coil on Group 4, Rod 8, and to repair the failed seal on the "C" Reactor Coolant Pump (RCP).
The unit began heatup at 1359 hours0.0157 days <br />0.378 hours <br />0.00225 weeks <br />5.170995e-4 months <br /> on February 9th; however, heatup was terminated at 2127 hours0.0246 days <br />0.591 hours <br />0.00352 weeks <br />8.093235e-4 months <br /> on February 10th due to a RCP seal failure.
The unit was then taken to cold shutdown for repair of the "A" RCP seal.
At 1946 hours0.0225 days <br />0.541 hours <br />0.00322 weeks <br />7.40453e-4 months <br /> on February 17th, Heatup began with the reactor taken critical at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on February 18th; the unit was placed on line at 0922 hours0.0107 days <br />0.256 hours <br />0.00152 weeks <br />3.50821e-4 months <br /> on February 19th.
The unit reached 30% power at-2200 hours on February 19th and was held there for core physics testing.
Testing was completed at 0652 hours0.00755 days <br />0.181 hours <br />0.00108 weeks <br />2.48086e-4 months <br /> on February 20th and a power escalation begun.
After two holds at 75%
and 90% for physics testing and to achieve Xenon equilibrium respectively, the unit attained 100% full power operation at 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br /> on February 24th.
The unit remained at 100% full power through the end of the month.
l
e UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR FEBRUARY 1985 DOCKET NO 50-313 UNIT NAME ANO - Unit 1 DATE March 5, 1985 COMPLETED BY K. L. Morton
' TELEPHONE (501) 964-3115
. Method of Licensee Cause & Corrective Duration Shutting Event.
System Component Action to l
No.
Date Tyge (Hours)
Reason 2 Down Reactor 3 Report #
Code 4 Codes Prevent Recurrence 85-01 850129 F
441.4 G
3 85-002 JB LT Unit tripped on high RCS pressure due to steam generator level problems.
Unit remained shutdown to repair failed reactor coolant pump seals.
1 2
3 4
F:
Forced Reason:
Method:
Exhibit G - Instructions S:
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 5
F-Administrative Exhibit I - Same Source G-Operational Error (Explain)
H-Other (Explain)
g,. 9 *,
DATE:
February 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 4
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
O
.o ARKANSAS POWER & LIGHT COMPANY POST OFRCE BOX 551 LITTLE ROCK, ARKANSAS 72203 (501)371-4000 March 15, 1985 ICAN038506 Mr. Harold S. Bassett, Director Division of Data Automation and Management Information 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 February 1985 is attached.
Very truly yours,
. Ted Enos anager, Licensing JTE:SAB: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 rGrci 8lg uwsca uime sour-uriures systm