1CAN119203, Monthly Operating Rept for Oct 1992 for Ano,Unit 1
| ML20116L936 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/31/1992 |
| From: | James Fisicaro, Hayes K ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1CAN119203, NUDOCS 9211190269 | |
| Download: ML20116L936 (7) | |
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November-13, 1992 1CAN119203 U. S. Nuclear Regulatory Commission Document Control Desk i
Mail Stop P1-137 Washington, D.C.
20555 SUBJECT Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Monthly: Operating Report Gentlement Monthly Operating Report statistics for Arkansas Nuclear One, Unit 1, for October,-1992 is attached.
This report is submitted in accordance with ANO-1 Technical Specification 6.12.2.3..
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JJF/JRH/sjf Attachment cci Mr. James L. Milhoan-
- Regional Administrator
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U.-S.
Nuclear Regulatory. Commission
- Region IV 611 Ryan Plaza:. Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior: Resident Inspector.
I Arkansas' Nuclear One - ANO-1 & 2-
-Number 1,t Nuclear Plant Road.
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Russellville, AR 72801
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O. S. NRC j
Novocb3r 13, 1992 l
ICAN119203 Page 2 Mr. Thomas W. Alexion HRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint' North 11555 Rockville Pike Rockville, Maryland 20052 Ms. Sheri Peterson NRR Project Manager, Region IV/ANO-2 U.
S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 1
11555_Rockville Pike i
Rockville, Maryland 20852 i
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OPERATING DATA REIORT DOCKET NO:-
50 313
~
DATE:
November 6,1992 COMPLETED 11Y; K. R.11 ayes TELEPilONE:
-(501) 964 5535 OPERATING STATUS 1
Unit Name: Arkansas Nuclear One. Unit i 2
Reporting Period:
October 1 31,1992 3
Licensed Therma! Powcr (MWt): 2,568 4.
Nameplate Rating (Gross MWe): 902.74 5.
Design Electrical Rating (Net MWe): 850 6.
Maximum Dependable Capacity (Gross MWe): 883 i
7.
Maximum Dependable Capacity (Net MWe): 816 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 MWc): Nonc 10.
Reasons For Restrictions. If Any:
None l
MONTil YBlO DATE~
CUMULATIVE 11.
Ifours in Reporting Period...
745.0 7320.0 156643.0 12.
Number ofIlours Reactor was Critical............
745.0
$C73.8 111535.0 '
13.
Reactor Resene Shutdown ilours..
0.0 0.0
-- $044.0 14.
Ilours Generator On Line...
745.0 5624.9 109357.7 i
15.
Unit Resenc Shutdown llours.,
00 0.0 817.5 16.
Gross Thermal Energy Generated (MWH),.
1912093_
14197764 249370 "
17.
Gross Electrical Energy Generated (MWH)...
650060 4809755 83L.
..s 18.
Net Electrical Energy Generated gMWil)...
622194 4588857
-78964105 19.
Unit Service Factor.......
100.0 76.8-
- 69.8 20.
Unit Availability Factor.
100.0 76.8.
70.3 21._
Unit Capacity Factor (Using MDC Net).......
99.9 75.0 ~
60.3:
22.
Unit Capacity Factor -
('Using DEC Net).
983; 73.8 59.3 23.
Unit Forced Outage Rate.,.....
0.0 0.1 11.9 t
24.
Shutdowns Scheduled Over Next 6 Months (1)pe, Date, and Duration of Each):
25.
If Shut Down At End of Report Period. Estimated Date of Stantup:
26.
Units in Test Status (Prior to Commercia! Operation):
i Forecast Achieved
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. INITIAL CRITICALITY 08/06n4 INITIAL ELECTRICITY 08/17/74' COMMERCIAL OPERATION 12/19n4
s 4
AVERAGE DAILY UNIT 19WER LEVEL
~
DOCKET NO.
50 313 UNIT:
One DATE:
Noumber 6,1992 COMPLETED 13Y: K. R. llaves TELEPilONE:
(501)9f64 5535 i
MONTil Ogtober.1992 i
DAY AVERAGE DAILY POWER LEVEL (MWc Net) l 1
832 833 2
3, 834 4
833 5
833 6
833 7
833 8
834 9
836 e
10.
835 11.
836 12.
835 13.
834 14...
831 15...
832 M..
827 17..
833 18...
834 19.......
834 20...,
837 21.
836 22...,
836-23..
817 24.,
339 25....
840 26..
838 2 7........
839 28..
838 2 9.....,,.
837 3 0.............
838-31.-.....,,....
842:
AVGS: 835 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for each day in reporting month Complete to the nearest whole megawatt.
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NItC MONTilIN OPI:llATING ltEPOltT Ol'l:llATING SilMMAltY OCTOllElt 1992
!! NIT ONE n=,=-=,=====
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Unit one began the mouth operating at 100% power. On the sixteenth at 19.01 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the unit load was decreased to 92% to perform scheduled testing of the turbine throttle / governor valves. The unit power was then returned to 100% at 21:20 hours on the same day. The unit operated at full power for the remainder of the month.
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UNIT SIIITTDOWNS AND POWER REDUCTIONS REPORTFOR OCTOBER.1992 DOCKET No.
50-313 UNIT NAME AS)Umt1 DATE Enmber 6,1*C COMPLETED BY K. R ILuves TELEPHONE
%I-wd-5.s35 1
MET 110D OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPENENT CAUSE & CORRECTIVE ACTION TO B_Q DATE TYPE' (IIOURS). REASON 2 REACTOR REPORT 8 CODE' CODES PREVEST RECIMENCE None 1
2 3
4
' F: Forced Reasoir 1 -Manual for Preparation of Data Methad:
- Exhibit G-Instructices S: Scheduled :
A-Equipment Failure (Explain)
' B - Maintenance of Test 2-Manual Scrant Entry Sheets for Ucensee C-Refueling 3 - Autcmatic Scrant Event Report (LER) F;le (NL1tEG-8161;
.l D-Regulatory Restrictica _
5 - 1med Reductice 4 - Contionatica 1
E - Operater Tralming & Ucrase Esamination F-Administraties 9 - Other 5
G - Cri --::_ - -I Error EthiW I-Same Source H -Other (Explais) r
l DATE:
October, 1992 REFUELI!JG llirORMATION 1.
flame of facility:
AIAan1AE_lLVglgar_One - Unit 1 2.
Scheduled date for next refueling shutdown.
Egnigtbgr 17. 1993 3.
Scheduled date for restart f ollowing ref ueling.11ovember 12, 1993 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendmnnt?
If answer is yes, what, in general, will there be?
If answer is no, has the reload fuel design and core cos. figuration been reviewed by your Plant safety Review Committee to determine whether any unroviewed safety questions are associated with the core reload (Ref. 10 Cr section 50.59)7 1Rg2 TechnLetLinctilltal. ion change to increase f uel eDrichment fIpm 1213 to 4.1%.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information. The.Tgchnical Sn22111GAkipn chanag_rpmttgt gag _gubmitted to the NRC on Jung_]7, 1991 f ICA1406910 0 ).
6.
Important licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unroviewed design or performance analysis methods, significant changes in fuel desin.1. new operating procedures.
None.
7.
The number af fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
a) 177 b) 625 8.
The present licensed spent fuel pool storage capacity and the size of sny increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.
present 968 increase nice 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: 1231__
( ?.oss of fullcore offload capability)
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