ML20050B736
| ML20050B736 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear |
| Issue date: | 11/14/1980 |
| From: | Bramlett L ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20050B733 | List: |
| References | |
| NUDOCS 8204070301 | |
| Download: ML20050B736 (7) | |
Text
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-313 UNIT ANO-l DATE 11/14/80 COMPLETED BY L. S. Bramlett TELEPHONE (5011968-2519 MONm _0ctober 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe Net)
I 723 37 563 720 2
723 is 3
727 39 741 4
722 20 740 5
776 21 7dU 6
723 740 22 7
326 23 739 8
277 24 737 9
374 25 737 10 6R3 26 737 735 11 731 27 12 723 28 734 13 731 29 732 14 716 30 734 15 735 3
736 16 485 INSTRUCTIONS On this format, list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/771 r204070301 901114 PDR ADOCK 05000313 R
e, AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-313 UNIT ANO-l DATE 11/14/80 COMPLETED By L. S. Bramlett TELEPilONE (5011968-2519 MONm October 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(ywe. Net) i 723 37 563 2
723 720
,g 3
727 39 741 4
722 20 740 5
796 21 740 6
723 740 22 7
326 23 739 8
277 24 737 9
374 25 737 10 6R3 26 737 11 731 735 27 12 723 28 734 13 731 29 732 14 716 30 734 15 735 736 3
16 485 INSTRUCTIONS On this format. list the average daily unit power levelin MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77)
OPERATING DATA REPORT DOCKET NO.
50-313 DATE 11/14/Rn COMPLETED BY L.' S. Bramlett
~
TELEPHONE (5011968-2519 OPERATING STATUS Notes
- 1. Unit Name:
Arkansas Nuclear One-Unit 1
- 2. Reporting Period: _0ctober 1-31; lorn
- 3. Licensed Thermal Power (MWI):
256R
- 4. Nameplate Rating (Grrss MWe):
902.74
$. Design Electrical Rating (Net MWe):
850 883
- 6. Maximum Dependable Capacity (Gross MWe):
836
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons:
None
- 9. Power Level To Which Restricted. If Any (Net MWe):
None
- 10. Reasons For Restrictions. If Any:
N/A This Month Yr. to.Dat e Cumulative 745.0 7.320.0 61 4s1 n i1. Hours In Reporting Period
- 12. Number Of Hours Reactor Was Critical 742.0 4.199.1 34.337.6
- 13. Reactor Reserve Shutdown Hours 0.0 647.6 4.R95_n
- 14. Ilours Generator On.Line 738.9 4.130.7 33.601.2
- 15. Unit Rewrve Shutdown Hours 0.0 2n A t:17 5
- 16. Gross Thermal Energy Generated (MWH) 1.734.256.0 9.R25.000.0 R1 nR6 nda n
- 17. Gross Electrical Energy Generated (MWil) 531.799.0 3.025.419.0 26.746.676 n
- 18. Net Electrical Energy Generated (MWHi 504.847.0 MZ6J14.0 26 61n R61 n 99.2 56.4 65.3
- 19. Unit Senice Factor M
56.7 fi6_ q
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (U>ing MDC Net)
D I.I 3 47.0 L59.D F
46.2 6R 3
- 22. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate C 0.87 31.1 (g
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each):
January 2.1981 to March 15.19d,Refnplinn
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status (Prior o Commercial Operation):
Forecast Achiesed INITI A L CRITICALITY INITIAL ELECTRICITY CO\\lMERCIA L OPER ATION (9/77 )
N '-
UNITSilUI' DOWNS AND POWER REDUCTIONS DOCKET NO.
50-313 UNIT NASIE _ ANO Unit I DATE 11-14-80 REPORT ?.f 0NTil October COhtPLETED l!Y L. S. Bramlett TEl.EPilONE (5011 968-2510
~.
E c
.53 3
$.5i licensee j-r, Cause & Corrective
=
N...
D.ne i
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is&
Event
- ?
el Atilon to yE
~djj Report :
cE C 5'
Prevent Recurrence H
U C
80-10 801007 F
-6.08 G
3 None ZZ ZZZZZZ The "A" main feed pump was accident-ally tripped when a mechanic, who was cleaning up oil around the pump, slipped and hit the. trip mechanism.
80-11 801007 F
0.0 B
4 None Cll HECFUN Power was limited because of maint-enance on the "A" main feed pump gov-ernor control mechanism. The cause was determined to be trash in the control oil system.
80-12 801016 F
0.0 B
4 None CH MECFUN Power was limited because of maint-enance on the "A" main feed pump gov-ernor control mechanism. The cause was determined to be trash in the control oil system.
I 2
1 4
F: Forced Reason:
htethod:
Exhibit G Instructions S. Scheduled A. Equipment Failure (Explain) 1-Alanual for Prepar.ition of Data U.htaintensnee of Test T htanual Scram.
Entry Sheets for Licensee C Refueling 1 Automatie Saam.
Eveni Repose (I.FR) File iNUREG-D. Regulatory Restriction 4 Oiher (thplain) 0161)
I. Opes.itor Tr::ining& Licen:.e Eumination F Adminisisative 5
G Operational I..ror (l' pl.iial Eshibii 1 5.une Somee P8/77 ll Other (lisplain)
e ovember. 1980 REFUELING INFORMATION 1.
Name of facility. _ Arkansas Nuclear One - Unit 1 2.
Scheduled date for next refueling shutdown.
1/2/81 3.
' Scheduled date for restart following refueling.
3/15/81 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 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 C7R Section 50.59)7 Yes.
Reload rannrt and associated nr_consed Technical Soecification chances.
Also. the safety analysis of four demonstration high burn-up assemblies will be provided.
4 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
Partial submittal 10/31/80.
Complete submittal by 2/1/81.
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.
Will reload 68 fresh fuel assemblies and operate for approximately 16 months.
Four of which will be high burn-up test assemblies.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
a) 177 b) 176 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 590 increase size by 0
9.
The projected date of the last' refueling that can be discharged to the spent fuel pool casuming the present licensed capacity.
DATE:
1986
4, f
NRC MONTELY OPERATING REPORT OPERATING
SUMMARY
- OCTOBER 1980 UNIT I The unit began the month at 100% power with normal operation.
On October 7 the unit tripped o's high RCS pressure following a main feed pump trip. The unit was returned to power later that day and power was held to about 45% for maintenance on main feed pump control problems.
The unit returned to 93% power on October 11.
On October 16 power was reduced to about 50% for more maintenance on "A" main feed pump. The unit was returned to 98% power on October 19 and continued operation there through the end of the month.
4 i
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I ARKANSAS NUCLEAR ONE - UNIT 1 PERIODIC CORE P0k'ER DISTRIBUTION COMPARISON The radial power distribution comparison was performed at 259.9 EFPD.
The RMS (root :nean square) value of the difference between measured and predicted power at the 52 instrumented fuel assembly 1ccation was calculated. The RMS value was 0.026 at 259.9 EFPD. The value was within the acceptance criteria of 0.073.
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