ML20069M036
| ML20069M036 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/31/1994 |
| From: | Hayes K, Mims D ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9406210079 | |
| Download: ML20069M036 (7) | |
Text
.
s Entergy faianoa atloa
'ac-Operations
+
June 15,1994 ICAN069403 U. S. Nuclear Regulatory Commission Document Control Desk hiall Station PI-137 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Monthly Operating Report Gentlemen:
The Arkansas Nuclear One - Unit 1 Monthly Operating Report (MOR) for hiay 1994 is attached. This report is submitted in accordance with ANO-1 Technical Specification 6.I2.2.3.
Very truly yours, 4
Dwight.Mims Director, Licensing DCM/jrh j
Attachment I l 9406210079 940531 F
PDR ADOCK 05000313 i
PDR l
~Rmv.v
i U. S. NRC June 15,1994 1CAN069403 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 Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road 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-H-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 l
OPERATING DATA REPORT DOCKET NO:
50-313 DATE:
June 3,1994 COMPLETED BY: K. R. Hayes TELEPilONE:
(501) 964-5535 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 1 2.
Reporting Period:
May 1-31,1994 l
3.
Licensed Thermal Power (MWt):- 2,568 4.
Nameplate Rating (Gross MWe): 902.74 5.
Design Electrical Rating (Net MWe): 850 6.
Maximum Dependable Capacity (Gross MWe): 883 7
Maximum Dependable Capacity (Net MWe): 836 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.
Reasons For Restrictions. If Any:
None MONTH YR TO-DATE CUMULATIVE 11, Ifours in Reporting Period.,
744.0 3623.0 170490.0 12.
Number of Hours Reactor was Critical.
744.0 3520.8 124119.2 13.
Reactor Reserve Shutdown Hours..
0.0 0.0 5044.0 14.
Ilours Generator On Line.
744.0 3507.4 121851.0 15.
Unit Reserve Shutdown Hours.
0.0 0.0 817.5 16.
Gross Thermal Energy Generated (MWH).
1909739 8973872 281024434 17.
Gross Electrical Energy Generated (MWH).
652485 3071545 93864580 18.
Net Electrical Energy Generated (MWH),
624847 2940832 89267968 19.
Umt Service Factor.
100.0 96.8 71.5 20.
Unit Availability Factor,,
100.0 96.8 72.0 21.
Unit Capacity Factor (Using MDC Net).
100.5 97.1 62.6 22.
Unit Capacity Factor (Using DEC Net).
98.8 95.5 61.6 23.
Unit Forced Outage Rate.
0.0 3.2 11.0 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25.
If Shut Down At End of Report Period. Estimated Date of Startup:
26.
Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY 08/06n4 INITIAL ELECTRICITY 08/17/74 COMMERCI AL OPERATION 12/19/74 l
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-313 UNIT:
One j
DATE:
June 3.1994 COMPLETED BY: K. R. Hayes
)
TELEPIIONE:
(501) 964 5535 MONTil May 1994 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 840 2
841 3
841 4
841 5
842 6
841 7
840 8
841 9
841 10.
843 11.
843 12.
842 13.
839 14.
843 15.
841 16..
841 17.
839 18.
840 19,
840 20 840 21.
839 22.
840 23..
839 24, 838 25.
836 26.
836 27.
837 28..
838 29..
837 30.
838 31.
836 AVGS: 840 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for each day in reponing month. Complete to the nearest whole megawatt.
l.
t i
NRC MONTIILY OPERATING REPORT OPERATING
SUMMARY
MAY 1994 UNIT ONE Arkansas Nuclear One, Unit One, began the month operating at 100% power. On the thirteenth at 20:05 hours, the unit load was decreased to 96% to perform planned testing of the turbine throttle / governor valves. The unit was retumed to full power at 22:06 hours the same day.
Unit 1 operated at full power for the remainder of the month.
.~
UNIT SilUTDOWNS AND POWER REDUCTIONS REPORT FOR MAY 1994 DOCKET NO.
50-313 UNIT NAME ANO Umt 1 DATE May 6,1994 COMPLETED BY K. R. llaves TELEPilONE 501-9M-5535 METIIOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO p'O DATE TYPE 1 (IIOURS)
REASON 2 REACTOR' REPORT #
CODE' CODES PREVENT RECURRENCE NONE I
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 Sheets for Ucensee C-Refueling 3 - Automatic Scrum.
Event Report (LER) File (NUREG-0161)
D - Regulatory Restriction 4 - Continuation E - Operator Training & Ucense Examination 5 -lead Reduction F-Administration 9 - Other 5
G - Operational Error Exhibit 1 - Same Source II-Other (Explain)
DATE: May 1994 REFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear One - Unit 1 2.
Scheduled date for next refueling shutdown. February 14.1995 3.
Scheduled date for restart following refueling. April 7.1995 4.
Will refueling or resumption of operation thereafler require a technical specification change 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 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)7 Technical Speci6 cation change to relocate additional cycle specific parameters to the Core Operating Limits Regort (COLR).
5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
August 1994.
6.
Imponant 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.
Nonc planned.
7.
The number of fuel assemblies (a)in the core and (b) in the spent fuel storage pool.
a) 177 b) 6._8.5 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 968 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: 1996 (Loss of full core off-load capability)
-