2CAN019501, Monthly Operating Rept for Dec 1994 for ANO-2
| ML20077Q586 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/31/1994 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN019501, 2CAN19501, NUDOCS 9501190295 | |
| Download: ML20077Q586 (7) | |
Text
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j Entergy Operations, Inc.
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January 13,1995 2CAN019501 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Monthly Operating Report Gentlemen:
The Arkansas Nuclear One - Unit 2 Monthly Operating Report (MOR) for December 1994 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.
Very truly yours, I
S~gfbic-D);
Dwight C. Mims Director, Licensing DCM/jrh Attachment 1
1.COhbO 9501190295 941231 PDR ADOCK 05000368 k,I l
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U. S. NRC January 13,1995 2CAN019501 Page 2
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cc:
Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlingtan, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One 1448 S. R. 333 Russellville, AR 72801 Mr. George Kalman r
NRR Project Manager, Region IV/ANO-1 & 2 l
U. S. Nuclear Regulatory Commission i
NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 i
h i
1
OPERATING DATA REPORT DOCKET NO:
50-368
^
DATE:
January 3,1995 COMPLETED BY: M. S. Whitt TELEPHONE:
(50l) 858-5560 OPI' RATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 2 2.
Reporting Period:
December 1-31, 1994 3.
Licensed Thermal Power (MWt): 2,815 4.
Nameplate Rating (Gross MWe): 942.57 5.
Design Electrical Rating (Net MWe): 912 6.
Maximum Dependable Capacity (Gross MWe): 897 7.
Maximum Dependable Capacity (Net MWe): 858 8.
If Charges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9.
Power Level To Which Restricted. If Any (Net MWe): None 10.
Reasons For Restrictions. If Any:
None MONTH YR-TO-DATE CUMULATIVE I 1.
Ilours in Reporting Period..
744.0 8,760.0 129,456.0 12.
Number of Hours Reactor was Cntical.
744.0 7,739.6 100,561.3 13.
Reactor Reserve Shutdown Ifours.
0.0 0.0 0.0 14.
Hours Generator On-Line.
744.0 7,707.1 98,633.1 15.
Unit Reserve Shutdown Hours.
0.0 0.0 0.0 16.
Gross Thermal Energy Generated (MWII).
2,078,706 21,362.226 262,342,209 17.
Gross Electrical Energy Generated (MWII).
699,534 7,047,236 86,369,573 18.
Net Electrical Energy Generated (MWil).
669,350 6,724,880 82,197,788 19.
Unit Service Factor....
100.0 88.0 76.2 20.
Unit Availability Factor.
100.0 88.0 76.2 21.
Unit Capacity Factor (Using MDC Net).
104.9 89.5 74.0 22.
Unit Capacity Factor (Using DER Net).......
98.6 84.2 69.6 23.
Unit Forced Outage Rate.
0.0 0.0 10.4 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
t A mid-cycle steam generator inspection is scheduled to begin January 7,1995 and last ~12 days.
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 12/05n8 INITIAL ELECTRICITY 12/26n8 COMMERCIAL OPERATION 03/26/80
[
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AVERAGE DAILY UNIT POWER LEVEL t
DOCKET NO:
50-368 UNIT:
Two' t
DATE:
January 3,1995 COMPLETED BY: M. S. Whitt I
TELEPHONE:
(501) 858-5560 i
~ MONT11 Dmads 1994 i
i I
DAY AVERAGE DAILY POWER LEVEL j
(MWe-Net) 895 2
8%
3.............
894
-4..........
894 i
5....
893 6
894 7
897 8..
908 l
9 906 10.
909 l
1 1..........
909 12'................-..
910 13.......
907 I 4......
901 15...............
898 j
16..
897 l
17...
899
{
18.....
899 i
i 19...
899 i
20.......
898 l
2I...............
899 22....
899 23.
899 24.
899 25.
899 l
26..
899 27....
899 l
-28.
898 29...
899 30.
899 31.,
898 j
AVGS: 9(X)
INSTRUCTION On this format, list the average daily unit power level in MWe-Net for cach day in reporting month. Complete to the nearest whole megawatt.
I NRC MONTHLY OPERATING REPORT i
OPERATING
SUMMARY
DECEMBER 1994 UNIT TWO The unit began the month of December operating at 100% power.
At 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br /> on the fifth, the method for secondary calorimetric power measurement was changed from feedwater flow to steam flow. Reactor power was raised to reach 100% indicated. After a five day test to determine the effect of the power increase on Tw, was completed, power was reduced to 99% at 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br /> on the thirteenth so that Ts, could be maintained at 600i.5 F.
The unit operated at 99% power for the remainder of the month.
i l
l
UNIT SHUTDOWNS AND POWER REDUCrlONS REPORT FOR DECEMBER 1994 DOCKET NO.
50-368 UNIT NAME ANO Unit 2 DATE January 3,1995' COMPLETED BY M. S. %%tt TELEPHONE (501) 858-5560 METHOD OF LICENSEE DURATION SHUTTING DOWN EVFET SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO 8
B_Q DATE D'f1' fHOURS)
REASON 8 REACTOR 8 REPORT #
CODE' (ODE PREVENT RECURRENCE None 1
2 3
4 F: Forced Reason:
Method:
Exhibit G - Instructions S: Scheduled A - Equipement Failure (Explain) 1 - Manual for Preparation of Data B - Maintenance of Test 2 - Manual Scram Entry Sheets for Licensee C - Refineling 3 - Autosantic Scram Event Repost (LER) File (NUREG-8161)
D-Regulatory Restriction 4 - Continuation E - Operator Training & Licer.se Examination 5 - Load Reduction F-Admalaistratlee 9 - Other 5
G - Operational Error Exhibit I-Seine Source H - Other (Explain)
DATE: December 1994 REFUELING INFORMATION l.
Name of facility: Arkansas Nuclear One - U M 2.
Scheduled date for next refueling shutdown. Scotember 22.1995 3.
Scheduled date for restart following refueling. November 6.1995 t
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)?
Delete requirement for verification of position stops for the hiah orrssure safety injection thmitle valves. Revise Technip_al Specifications to account for the replacement of part-length control element assemblies with full-length control element assemblies. Revise the reference in the_ Administrative Controla section to allow use of the Modified Statistical Combination of UngcAainties for determining core operating limits. Relocate the value used to decrease the core power operating limit based on DNBR when neither CEAC is operable to the Core QpSrating Limits RepmL 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
March 1995.
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.
None plannest 7.
The number of fuel assemblies (a) in the core and (b) i:dhe spent fuel storage pool.
a) 177 b) 637 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 Q 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 offload capability)
_.