ML19339C462
| ML19339C462 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/14/1980 |
| From: | Pendergraft R ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19339C460 | List: |
| References | |
| NUDOCS 8011180420 | |
| Download: ML19339C462 (5) | |
Text
.
AVERAGE DAILY UNIT POWER LEVEL.
DOCKET NO. _50-368 UNIT 2
DATE 11/14/80 CC.'.iPLETEL' BY Rox Penderaraft TELEPHONE (501) 968-2519 MONT1; October. 1980 DAY AVERAGE DAILY PCWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe Net) 1 53 873
,7
-879 2
436 ig 3
R71 19 882 4
872 881
,o 5
876 879 21 880 6
876
,2 7
874 879 23 8
874 883
,4 9
871
'S 884 883 10 874 26 11 879 2;
882 12 881 885
,g 13 881 885
,9 220 884 14 30 15 207 883 3,
16 844 INSTRUCTIONS On this format. list the average daily unit power lesel in MWe-Net for each day in the reporting inonth. Compute to 1
the nearest whole megawatt.
W/771 h
OPERATING DATA REPORT 50-368 DOCKET NO.
DATE 11/1 af on COMPLETED BY Rav Pontiargraft TELEPHONE f601) %A-2519 OPERATING STATUS N'
Arkansas Nuclear One linh ?
- 1. Unit Name:
October 1-31. 1980
- 2. Reporting Period:
2815
- 3. Licensed Thermal Power IMWt):
959
- 4. Nameplate Rating (Gross MWe):
912
- 5. Design Electrical Rating (Net MWe):
897
- 6. Maximum Dependable Capacity (Gross MWe):
- 7. Maximum Dependable Capacity (Net MWe):
8"
- 8. If Changes Occur in Capacity Ratings (Irems Number 3 Through 7) Since Last Report.Gise Reasons:
- 9. Power Level To Which Restricted. lf Any (Net MWe):
- 10. Reasons For Restrictiom.!f Any:
N/A This Month Yr..to.Date Cumulatise 745.0 5.280.0 5.280.0
- 11. Hours In Reporting Period 703.6 3,942.1 3,942.1
- 12. Number Of Hours Reactor Was Critical 26_6 7R1.1 7R1_1
- 13. Reactor Rewrve Shutdown Hours 700.~ 3 3.877.8 3.877.8
- 14. Hours Generator On.Line 0.0 75.0 75.0
- 15. Unit Rewrie Shutdown Hours 1,899,722.0 9,877,702.0 9,877,702.0
- 16. Gross Thermal Energy Generated (MWH) 618,173.0 3.207.523.0 3.207.523.0
- 17. Gross Electrical Energy Generated (MWH) 591,465.0 3,058,832.0 3,058,832.0
- 18. Net Electrical Energy Generated (MWH) 94.0 73.4 73.4
- 19. Unit Service Factor 94.0 74.9 74.9
- 20. Unit Asailability Factor 92.5 67.5 67.5
- 21. Unit Capacity Factor (Using MDC Net) 87.1 63.5 63.5
- 22. Unit Capacity Factor (Using DER Net).
6.0 26.6 26.6
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Ne.st 6.4f.ns (Type. Date, and Duration of Each):
March 15,1981 to May 15,1981. Refuelina
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status tPrior io Commercial Operation):
Forecast Achiesed INITIAL CRITICALITY INTIAL ELECTRICITY COMMERCIAL OPER ATION (4/771
L e
DATE: November, 1980 REFUELING INFORMATIO*.2 1.
Name of facility.
Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown.
3/15/81 3.
Scheduled date for restart following refueling. 5/15/81 4.
h*ill re.'ueling or resumption of operation thereaf ter require a technical specification change or other license amendment?
If answer is yes, what, in general, will these 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. Description of effects of new core loading 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
1/15/81 6.
Important licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or performance enalysis methods, significant changes in fuel design, new operating procedures.
As part of a research and development effort, two fuel assemblies will be loaded possessing design characteristics related to extended burnuo.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 58,(New) 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, 0
present 486 increase size by 9.
The projected date of the last* refueling that can be discharged to the spent fuel pool assuaing the present licensed capacity.
t l
DATE:
1989
DOCKET NO.
53:368 UNIT SilUIDOWNS AND POWER REDUCTIONS UNIT NAME.AN0_- Unit 2 DATE 41/14/R0 COMPLETED BY Rav Pandarornft REPORT MONTil October TELEPHONE 501-968-2519 "t.
E
'Cause & Corrective j7 3
Licensee
, t, g",,
No.
Date g
3g i;
,y5 Event m7 93 Action to
$E 5
j@g Report se
- i O O
Prevent Recustence c5 1
80-22 10-1-80
.F 16.4 A
1 None CB PUMPXX Lost "B" RCP while at approximately 27% power.
Past,
- rip was probably due to maintenaam: In the pump breaker cabinet.
80-23 10-14-80 F
28.3 A
3 None Cll INSTRU Square root extractor in the "A"
loop 1N control system failed causing an overfeed situation. The Rx tripped on high "A" S/G 1evel.
Instrument was replaced.
t i
2 3
4 F: Forsed Reason:
Method:
Exhibit G - Instructions S: Scheduleil A. Equipment Failure (Explain) 1-Manual for Pieparation of Data ll-Maintenance of Test 2 Manual Scram.
Entry Sheets for Liecusee 3-Automatic Scram.
Event Reposi(LER) File (NURLG-C-Hefueling D. Regulatory Restriction 4.Other (Explain) 0161) 1 -Operator Tsaining A thense Examination 5
F Administrative Exhibit I - Same Source G-Operational 1:nor (Explain)
(9/77)
Il Other (Explain) 4
NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
- OCTOBER 1980 UNIT 2 The. Unit was operating at approximately 27% fall power during the beginning of this reporting period when a reactor trip was experienced due to losing the "B" Reactor Coolant Pump (10-1-80). The reactor was manually tripped approximately one minute following the loss of the "B" Reactor Coolant Pump. An automatic CPC generated trip would nor-mally have tripped the reactor at a higher power level. The Unit was returned to power operation the next day (10-2-RO) and escalated tc 100% full power.
Full power operation was tenninated on (10-14-80) when a reactor trip occurred due to high "A" Steam Generator Level.
The Steam Generator Level problem was caused by a failed instrument (Square Root Extractor) in the Feedwater Control System cabinets.
The Square Root Extractor was replaced and Power Operation was then achieved on (10-15-80). The Unit has operated at full power for the remainder of this reporting period without interruption.
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