ML20064J512
| ML20064J512 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/28/1994 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN03404, 2CAN3404, NUDOCS 9403210271 | |
| Download: ML20064J512 (7) | |
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l March 15,1994 l
l 2CAN039304 l
U. S. Nuclear Regulatory Commission Document Control Desk Mail Station Pl-137 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unii 2 Docket No. 50-368 License No. NPF-6 Monthly Operating Report Gentlemen:
l'he Arkansas Nuclear One - Unit 2 Monthly Operating Report (MOR) fbr February,1994 l
is attached This report is submitted in accordance with ANO-2 Technical Specification 6 9.1.6 l
l Very truly yours, l
I l
b>9YC'. 71),,'
Dwight C. Mims Director, Licensmg l
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1 DCM/jrh Attachment 210111 t
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'l U.S.NRC March 15,1994 2CANO39404 Page 2 cc:
Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansaa Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road r
Russellville, AR 72801 Mr. George Kalman NRR 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 20852 Mr. Thomas W. Alexion NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-11-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 1
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l l-OPERATING DATA REPORT DOCKET NO:
50-368 DATE:
March 2,1994 COMPLETED BY; M. S. Whitt TELEPIIONE:
(501) 964 5560 OffilMILN_D..SIAIUS 1.
Unit Name: Arkansas Nucleac One - Unit 2 2.
Reporting Period:
February 1 28.1994 3.
Licensed Thermal Power (MWt): 2.815 4.
Narneplate Rating (Gross MWe): 942.57 5.
Design Electrical Rating (Net MWc):. 912 6.
Maximum Dependable Capacity (Gross MWc): 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): Nonc 10.
Peasons For Restrictions. If Any:
None MONTH Xil-T_O-DATE CMMULATIVE I 1.
Ifours in Reporting Period.
672.0 1,416.0 122,112.0 12.
Number ofIlours Reactor was Critical.
672.0 1,416.0 94,237.7 13.
Reactor Reserve Shutdown llours.
0.0 0.0 0.0 14.
Ilours Generator On-Line.
672.0 1,416,0 92,342.0 15.
Unit Reserve Shutdown llours.
0.0 0.0 0.0 16.
Gross Thermal Energy Generated (MWIf).
1,890,714 3,951,301 244,931,284 17.
Gross Electrical Energy Generated (MWil).
623,625 1,305,529 80,627,866 18 Net Electrical Energy Generated (MWII).
596,140 1,247,909 76,720,818 19, Unit Service Factor.
100.0 100.0 75.6 20.
Unit Availability Factor.
100.0 100.0 75.6 21 Unit Capacity Factor (Using MDC Nel).
103.4 102.7 73.2 22.
Unit Capacity Factor (Using DEC Net).
97.3 96.6 68.9 23.
Unit Forced Outage Rate.
0.0 0.0 11.1 24.
Shutdowns Scheduled Oser Next 6 Months (Type, Date, and Duration of Each):
Refochng Outage 2RIO is scheduled for March 11.1994 through April 24,1994.
25 if Shut Down At End of Report Period. Estimated Date of Startup.
26.
Units in Test S;atus (Prior to Commercial Operation). _.
Forecast Achieved INITI AL CRrflCALITY 12/05/78 INITIAL ELECTRICITY 12/26/78 COMMERCIAL OPERATION 03/26/80
l j
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:-
50 368 UNIT:
Two DATE:
Afarch 2,1994 COMPLETED BY: M. S. Whitt TELEPflONE:
(501) 964 5560 MONTil Est maDJ>M a
DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 1
884 2
884 3
884 4
883 5
884 6
883 7
88n 8
882 9
884 10,
883 11.
885 12.
890 13, 890 14.
890 15.
889 16.
889 17.
889 18..
889 19.
885 j
20 889 21.
890 22.
891
- 23.,
890 24.
891 25.
SW) 26.
891 27.
891 28, 889 29.
- N/A 30.
- N/A 31.
- N/A AVGS: 887
[NETR1LCIl0M On this format, list the ascwe daily unit power level in MWe-Net for each day in reporting month. Complete to the nearest whole megawatt.
l
4 NitC MONTIILY OPEllATING REPORT OPEllATING SUS 151ARY FEllltUARY 1994 UNIT TWO The unit began the month of February operating at 100% power.
At 1201 hours0.0139 days <br />0.334 hours <br />0.00199 weeks <br />4.569805e-4 months <br /> on the twenty-eighth, the unit began a power coastdown in preparation for the upcoming 2R10 Refueling and Maintenance Outage. The unit ended the month at 99.5% power.
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u to UNIT Sl!UTDOWNS AND POWER REDUCTIONS REPORT FOR FEBRUARY,1994 DOCKET NO.
50-M S
'i UNIT NAME ANO Umt 2 DATE Abrch 2.1994 COMPLETED BY M. S Wlutt TELEPilONE 501-9M-5560 METliOD OF LICENSEE DURATION SIlUTTINC DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO M
DATE TYP E' (IIOURS)
R E ASON2 REACTOR REPORT #
CODE' CODE 5 PREVENT RECURRENCE 8
none j
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i 1
i 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 of Test 2 - Manual Scram.
Entry Snects for Urensee C - Refueling 3 - Automatic Scram.
Esent Report (LER) File (NUREG-0161)
D-Regulatory Restriction 4 - Continuation E - Operator Training & Ucense Examination 5 - Losd Redaction F-Administration 9 - Other 5
G - Operational Errur Exhibit I-Same Source Il-Other (Explain)
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DATE: February,1994 REFUELING INFORMATION 1.
Name of facility: & kansas Nuclear One - UniL2 2.
Scheduled date for next refueling shutdown. bfarch 11.1994 a
3.
Scheduled date for restart following refueling. April 24.1994 4.
Will refueling or resumpticn of operation thereafler require a technical specification change 1
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 connguration 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)?
Le3mTechnical Sgtg.ificatipa_ charges to reignate cyclp_Speci6c parametenjo a Core Operat.ingjjmits_Renort J
5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
Changn.sithiri!Ltmlh!!y11993m 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.
Nont 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.-
a) 177 b) SM 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 9 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
DATE 1997 (Loss of full core oft-load capability)
..