2CAN088405, Monthly Operating Rept for Jul 1984
| ML20097A468 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/31/1984 |
| From: | Bramlett L, John Marshall ARKANSAS POWER & LIGHT CO. |
| To: | Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 2CAN088405, 2CAN88405, NUDOCS 8409130279 | |
| Download: ML20097A468 (6) | |
Text
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4.
OPERATING DATA REPORT DOCKET N0:
50-368 DATE:
--August 1984 COMPLETED ~BY: L.S. Bramlett TELEPHONE:
501-964-3145 0PERATING STATUS 1.
Unit Name:
Arkansas Nuclear One - Unit 2 2.
Reporting Period: July 1-31, 1984 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....
144.0 5,111.0 38,135.0 12.
Number of Hours Reactor was Critical.....................
550.8 4,220.3 25,847.4 13.
Reactor Reserve Shutdown Hours........................
0.0 0.0 1,430.1 14.
Hours Generator On-Line......
548.3 4,058.6 25,008.9 15.
Unit Reserve Shutdown Hours..
0.0 0.0 75.0-16.
Gross Thermal Energy Generated (MWH)........................
1,372,786.0 10,320,126.0 62,869,666.0 17.
Gross Electrical Energy Generated (MWH)..............
453,432.0 3,435.752.0 20,452,703.0 18.
Net Electrical Energy Generated (MWH) 431,843.0 3,276,589.0 19,482,929.0 19.
Unit Service Factor..........
73.7 79.4 65.6 20.
Unit Availability Factor.....
73.7 79.4 65.8 21.
Unit Capacity Factor (Using MDC Net)..............
67.6 74.7 59.5 22.
Unit Capacity Factor (Using DER Net)..............
63.6 70.3 56.0 23.
Unit Forced Outaga Rate......
26.3 6.9 18.5 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 e
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8409130279'B40731 1
PDR ADOCK 05000368
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-368 UNIT:
Two DATE:
August 1984 COMPLETED 8Y: L.S. Bramlett.
TELEPHONE:
501-964-3145 MONTH July 1984
~ DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
=1.............
899 2.............
895 3.............
891 4.............
892 5.............
893 6.............
891 7.............
893 8.............
891 9.............
887 10............
887 11............
888 12............
890 13............
889 14............
885 15............
887 16............
891 17............
894 18............
896 19............
897 20............
49 21............
0 22............
0 23............
0 24............
0 25............
0 26............
0 27............
0 28............
137 29............
217 30............
222 31............
434 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.
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-NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
JULY 1984
' UNIT 2 The unit began the month at-100%. full power.
On July 20, the reactor was manually tripped because of indications received following a spurious
. inverter transfer.
The unit was then brought to Mode 5 to perform maintenance on startup channels 1 and 2 of the excore detectors, the reactor coolant system cold leg. temperature element and the reactor coolant pump seals. On July 28,-the unit was tied on line; power was brought to 30%.
The unit was maintained at 30% until July 31 in order to perform steam generator chemistry and secondary side boric acid addition.
Later that day, power was escalated to 80% and remained there throughout the month holding for stabilization of the axial shape index and nuclear instrumentation calibration.
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UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR JULY 1984 DOCKET NO.
50-368 UNIT NAME.
ANO-2 DATE
. 8/2/84 COMPLETED BY-
.L.S. Bramlett-TELEPHONE
'501-964-3145 Method of Licensee Cause & Corrective.
Duration Shutting Event System Component Action to l
(Hours)
Reason 2 Down Reactor 3 Report #
Code 4 Code 5 Prevent-Recurrence i
No.
Date-Type 84-07 840720 F
195.7 H
2 84-19-00 ZZ ZZZZZZ The unit'was manually.
tripped due to i
indications received when an ~ inverter was l
' inadvertently transferred.
The unit remained shutdown i
for equipment maintenancei (excore detectors, RCS temperature elements, and RCP seals).
7 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 0161)
E-Operator Training &
5-Load Reduction
-License Examination 9-Other 5
F-Administrative Exhibit 1 - Same Source
.G-Operational Error (Explain)
G-Other (Explain) e
+
- 4*
.e
-q E.;
DATE: July 1984 REFUELING INFORMATION 1.
-Name of facility: Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown..May 1985 3.
SchedUleddateforrestartfollowingrefueling.
July 1985
~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? fIf 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, some proposed software changes to'the Core Protection Calculators are being considered.
5.
Scheduled date(s) for submitting proposed licensing-action and supporting information.
February 1985 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.
Burnable poison rods will be used in reload fuel.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel' storage pool.
a) 177 b) 168 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
O o
ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK, ARKANSAS 72203 (501) 371-4000 August 15, 1984 2CAN088405 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 (File:
2-0520.1 Gentlemen:
Attached is the NRC Monthly Operating Report for July 1984 for Arkansas Nuclear One - Unit 2.
Very truly yours, l
/ h&
John R. Marshall
( W Manager, Licensing JRM:SAB:ac i
l l
Attachment cc:
Mr. John T. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 l
Arlington, TX 76011 Mr. Richard C. DeYoung Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 d
p i
MEMDEF4 MIDDLE SCOTH UTILITIES SYSTEM