2CAN078604, Monthly Operating Rept for June 1986
| ML20214L898 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/30/1986 |
| From: | Enos J, Harrison D ARKANSAS POWER & LIGHT CO. |
| To: | Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 2CAN078604, 2CAN78604, NUDOCS 8609100437 | |
| Download: ML20214L898 (8) | |
Text
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OPERATING DATA REPORT DOCKET NO:
50-368 DATE:
June, 1986 COMPLETED BY:D. F. Harrison TELEPHONE:
(501)964-3743 OPERATING STATUS 1.
Unit Name:
Arkansas Nuclear One - Unit 2 2.
Reporting Period: June 1-30, 1986 3.
Licensed Thermal Power (MWt):
2,815 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....
720.0 4,343.0 54,911.0 12.
Number of Hours Reactor was Critical.....................
310.3 3,853.3 39,490.0 13.
Reactor Reserve Shutdown Hours........................
0.0 0.0 1,430.1 14.
Hours Generator On-Line......
310.3 3,831.8 38,267.5 15.
Unit Reserve Shutdown Hours..
0.0 0.0 75.0 16.
Gross Thermal Energy Generated (MWH)........................
861,936.0 10,664,834.0 97,702,185.0 17.
Gross Electrical Energy Generated (MWH)..............
283,390.0 3,545,089.0 32,034,331.0 18.
Net Electrical Energy Generated (MWH)..............
268,785.0 3,384,491.0 30,494,025.0 19.
Unit Service Factor..........
43.1 88.2 69.7 20.
Unit Availability Factor.....
43.1 88.2 69.8 21.
Unit Capacity Factor (Using MDC Net)..............
43.5 90.8 64.7 22.
Unit Capacity Factor (Using DER Net)..............
40.9 85.4 60.9 23.
Unit Forced Outage Rate......
0.0 2.6 15.6 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25.
If Shut Down At End of Report Period.
Estimated Date of Startup:
August 1, 1986 26.
Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION hg
\\
8609100437 860630
/
PDR ADOCK 05000368~
R PDRa
4 AVERAGE DAILY UNIT POWER LEVEL DOCKET N0:
50-368 UNIT:
Two DATE:
June, 1986 COMPLETED BY: D. F. Harrison TELEPHONE:
(501)964-3743 MONTH June DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.............
887 2.............
885 3.............
885 4.............
884 5.............
884 6.............
883 7.............
883 8.............
883 9.............
882 10............
880 11............
884 12............
884 13............
675 14............
-16 15............
-5 16............
-5 17.
-5 18............
-5 19............
-5 20............
-4 21............
-4 22............
-4 23............
-4 24...........
-4 25............
-4 26............
-3 27............
-2 28............
-4 29............
-1 30............
-2 31............
AVGS:
373 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
JUNE 1986 UNIT TWO The Unit began the month at 100% power.
At 1456 hours0.0169 days <br />0.404 hours <br />0.00241 weeks <br />5.54008e-4 months <br /> on June thirteenth, CEA-26 dropped while CEDM part length traces were being obtained.
At 1457 hours0.0169 days <br />0.405 hours <br />0.00241 weeks <br />5.543885e-4 months <br />, a power reduction to 70%
commenced for rod recovery.
The rod was recovered to the upper electrical limit.
The power reduction was continued to go into refueling outage 2RS.
At 2218 hours0.0257 days <br />0.616 hours <br />0.00367 weeks <br />8.43949e-4 months <br />, the reactor tripped on low DNBR/high LPD due to CPC calculated axial shape index. The unit went to cold shutdown to begin the refueling outage.
J l
1
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UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR JUNE,1986 DOCKET NO 50-368 UNIT NAME ANO Unit 2 DATE June, 1986 COMPLETED BY D. F. Harrison TELEPHONE (501)964-3743 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to No.
Date Type (Hours)
Reason 2 Down Reactor 3 Report #
Code 4 Codes Prevent Recurrence l
8605 19860613 F 0
A NA NA AA R0D CEA-26 dropped while CEDM part length traces were being obtained.
Power was reduced to
~70% for rod recovery.
Rod was recovered to the upper electrical limit.
8606 19860613 F 0
H 3
2LER-86-009 JC ZZZZZZZ Reactor trip on low DNBR/high LPD during power reduction due to CPC calculated axial shape index.
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)
Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to No.
Date Tyge (Hours)
Reason 2 Down Reactor 3 Report #
Code 4 Code 5 Prevent Recurrence l
8607 19860613 S 409.7 C
4 NA XX ZZZZZZZ Refueling outage 2RS.
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-l 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) i H-Other (Explain) 9 9
DATE:
June, 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.
A Technical Specification change on negative moderator temperature coefficient has been submitted.
Included in the change request are changes in shutdown margin and in Refueling Water Tank temperature.
Earlier Technical Specification changes submitted and still under review dealt with CPC addressable constants and an improved CPC program 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
The Technical Specification change request on moderator temperature coefficient was submitted in April; and two others:before that.
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 change 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 prior to Cycle 6 startup.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
a) 177 b) 289 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 e
1
C o
ARKANSAS POWER & LIGHT COMPANY PCST OFFICE BOX 551 UTTLE ROCK. ARKANSAS 72203 (5011371-4MB July 15, 1986 2CAN078604 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 ?
Docket No. 50-368 License No. NPF-6 Monthly Operating Report
Dear Mr. Bassett:
The Arkansas Nuclear One - Unit 2 Monthly Operating Report for June 1986 is, attached.
1 Very truly yo rs, J. Ted Enos, Manager Nuclear Engineering and Licensing JTE:MCS:sg Attachment j
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 J
Washington, DC 20555 k
MEMBER MCOLE SOUTH UTiUTIES SYSTEM