2CAN038606, Monthly Operating Rept for Feb 1986
| ML20210Q495 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear |
| Issue date: | 02/28/1986 |
| From: | Enos J, Harrison D ARKANSAS POWER & LIGHT CO. |
| To: | Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 2CAN038606, 2CAN38606, NUDOCS 8605140104 | |
| Download: ML20210Q495 (6) | |
Text
T OPERATING DATA REPORT DOCKET N0:
50-368 DATE:
February, 1986 COMPLETED BY:D. F. Harrison TELEPHONE:
(501)964-3743 OPERATING STATUS 1.
Unit Name:
Arkansas Nuclear One - Unit 2 2.
Reporting Period:
February 1-28, 1986 3.
Licensed Thermal Power (MWt):
2815 4.
Nameplate Rating (Gross MWe):
942.57 5.
Design Electrical Rating (Net MWe):
912 6.
Maximum Dependable Capacity (Gross MWe):
897 7.
Maximum Dependable Capacity (Net MWe):
858 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 51,984.0 12.
Number of Hours Reactor was Critical.....................
627.7 1,371.7 37,008.4 13.
Reactor Reserve Shutdown Hours........................
0.0 0.0 1,430.1 14.
Hours Generator On-Line......
626.2 1,370.2 35,805.9 15.
Unit Reserve Shutdown Hours..
0.0
- 0. 0 75.0
- 16. Gross Thermal Energy Generated (MWH)........................
1,745,079.0 3,836,038.0 90,873,389.0 17.
Gross Electrical Energy Generated (MWH)..............
582,420.0 1,282,239.0 29,771,431.0 18.
Net Electrical Energy Generated (MWH)..............
555,757.0 1,225,353.0 28,334,887.0 19.
Unit Service Factor..........
93.2 96.8 68.9 20.
Unit Availability Factor.....
93.2 96.8 69.0 21.
Unit Capacity Factor (Using MDC Net)..............
96.4 100.9 63.5 22.
Unit Capacity Factor (Using DER Net)..............
90.7 94.9 59.8 23.
Unit Forced Outage Rate......
6.8 3.2 16.3 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): A 7 week refueling outage is scheduled to begin June 13, 1986.
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 8605140104 860228 PDR ADOCK 05000368 R
AVERAGE DAILY UNIT POWER LEVEL DOCKET N0:
50-368-UNIT:
Two DATE:
February, 1986 COMPLETED BY: D. F. Harrison TELEPHONE:
(501)964-3743 MONTH Feburary, 1986 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.............
895 2.............
895 3.............
895 4.............
896 5.............
899 6.............
901 7.............
901 8.............
902 9.............
902 10............
902 11............
481 12............
-27 13............
259 14............
897 15............
899 16............
893 17............
892 18............
895 19............
895 20............
896 21............
899 22............
899 23............
899 24............
899 25............
900 26............
897 27............
899 28............
900 29............
30............
31............
AVGS:
827 i
INSTRUCTICN 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.
1 I
NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
FEBRUARY 1986 UNIT TWO The unit began the month at 100% power.
At 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br /> on the eleventh of February, the unit tripped on low DNBR following the inadvertent closure of an MSIV.
The closure was apparently caused by a failure of a motor driven relay.
The unit was placed back on line at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on February the thirteenth.
The unit attained 100% power at 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br /> on the thirteenth and remained there through the end of the month.
l
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR FEBRUARY, 1986 DOCKET NO 50-368 UNIT NAME ANO Unit 2 DATE February, 1986 COMPLETED BY D. F. Harrison TELEPHONE (501)964-3743 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 8601 860211 F
45.8 A
3 2-LER-86-01 SB ISV The unit tripped on low DNBR following the-inadvertent closure of an MSIV.
The closure was apparently caused by the failure of a motor driven relay.
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 s
F-Administrative Exhibit I - Same Source G-Operational Error (Explain)
H-Other (Explain) e
DATE:
February, 1986 REFUELING INFORMATION 1.
Name of facility:
Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown.
Cycle 5 was initiated in May 1985.
The next refueling shutdown is scheduled for June 1986.
3.
Scheduled date for restart following refueling.
August 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.
Two technical specification changes on shutdown boron concentration and moderator temperature coefficient are in preparation 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
April, 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.
The fresh fuel will have a modification to the CEA guide tube wear sleeves which has been reviewed.
(Ref. SER dated September 7, 1984 for C-E Report LD-84-043). A longer cycle and a thange in in-core fuel management from out-in-in to in-in-out are also planned.
When pending Technical Specification changes are approved, we expect to install a revised CPC program during Cycle S.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
a) 177 b) 229 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:
2003
~
ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 (501) 371-4000 March 14, 1986 2CAN038606 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 2 Docket No. 50-368 License No. NPF-6 Monthly Operating Report
Dear Mr. Bassett:
The Arkansas Nuclear One - Unit 2 Monthly Operating Report for February 1986 is attached.
Very truly yourc, J. Ted Enos, Manager Nuclear Engineering and Licensing JTE:MCS: sg 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. James M. Taylor, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 MEMBEA MIDOLE SOUTH UTIUTIES SYSTEM