2CAN059405, Monthly Operating Rept for Apr 1994 for ANO Unit 2

Monthly Operating Rept for Apr 1994 for ANO Unit 2

ML20065S352
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/30/1994
From:	Mims D, Whitt M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN059405, 2CAN59405, NUDOCS 9405180179
Download: ML20065S352 (7)

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Operations May 13,1994 2CAN059405 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station P1-137 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 April 1994 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.

Very truly yours,

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)wjgh '.Mims Direct r, Licensing i

DCM/jrh Attachment 9405100179 940430 i

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U. S. NRC May 13,1994 2CAN059405 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 13-11-3 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 i

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'4 OPER.ATING DATA REPORT DOCKET NO:

50-368 DATE:

May 5,1994 COMPLETED BY: M. S. Whitt TELEPilONE:

(501) 964-5560 QMRATING STATUS 1.

Unit Name: Arkansas Nuc8,:ar One - Um. 2 2.

Reporting Period:

April 1 30,1994 3.

Licensed Thermal Power (stWI): 2,815 4.

Nameplate Rating (Gross 14Wc); 942.57 5.

Design Electrical Rating (lict MWc): 912 6.

Maximum Dependable Capacity (Gross MWe): 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 Reasons For Restrictions. If Any:

None h10N111 YR-TO-DA'E CUMULATIVE I 1.

Ilour' a Reporting Period.

719.0 2,879.0 123,575.0 12.

Numbc ofIlours Reauar was Critical.

177.6 1,858.6 94,680.3 13.

Reactor Reserve Shutdown llours.

0.0 0.0 0.0 14.

Ilours Generator On-Linc.

145.1 1,826.1 92,752.1 15.

Unit Resenc Shutdown llours.

0.0 0.0 0.0 16.

Gross Thermal Energy Generated (MWH).,

270,443 4,913,206 245,893,190 17.

Gross Electrical Energy Generated (MWil).

84,550 1,619,785 80,942,122 18.

Net Electrical Energ" Generated (MWII).

73,245 1,538,009 77,010,918 19 Unit Service Factor.

20.2 63.4 75.1 20.

Unit Availability Factor.

20.2 63.4 75.1 21.

Unit Capacity Factor (Using MDC Net).

11.9 62.3 72.6 22.

Unit Capacity Factor (Using DEC Net).

I!.2 58 6 68.3 23.

Unit Forced Outage Rate.

0.0 00 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 12/05/78 INITIAL ELECTRICITY 12/2608 COMMERCIAL OPERATION 03/26/80

i AVERAGE DAILY UNIT POWER LEVEL i

DOCKET NO; 50-368 UNIT:

Two

. DATE:

May 5,1994 COMPLETED BY: M. S. Whitt TELEPHONE:

(501) 964-5560 MONTil April 1994 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) i 1

-2 2

-2 3

-2 4

-2 5

-2 6

-2 7

-2 8

-2 9

-2 10,

-2 11.

-2 12.

-3 13,

-4 14

-6 15.

-8 16,

-10 17 11 18

-11 19.

-25 20

-26 21.

-27 22,

-31 23.

30 24.

23 25.

81 26.

424 27 546 28..

630 29.

766 30 842 31.

1. N/A i

AVGS. 102 INSIRILCEION l

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.

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NRC MONTIILY OPERATING REPORT OPERATING

SUMMARY

APRIL 1991 UNIT TWO The unit began the month of April offline for 2R10 Refueling Outage.

At 1426 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.42593e-4 months <br /> on the twenty-third, the reactor attained criticality. On the following day, the twenty-fourth, the turbine was tied to the grid at 2125 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.085625e-4 months <br />. This marked the completion of 2R10. At 0139 hours0.00161 days <br />0.0386 hours <br />2.29828e-4 weeks <br />5.28895e-5 months <br /> on the twenty-fiflh, the turbine was taken back off line for the Main Turbine Overspeed Trip Test. After the test was completed, the turbine was placed on line at 0310 hours0.00359 days <br />0.0861 hours <br />5.125661e-4 weeks <br />1.17955e-4 months <br /> that same day.

Unit 2 continued normal start-up procedures and ended the month at 97% power.

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UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR APRIL,1994 DOCKET NO.

50-365 UNIT NAME ANO Umt 2 DATE May 5,1994 COMPLETED BY M. S. Whitt TELEPHONE 501-964-5560 METlfOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO M

DATE TYPE 2 11 TOURS)

REASON 2 REACTOR 2 REPORT #

CODE' CODE' PREVENT RECURRENCE 94-01 940401 S

762.3 C

4 N/A ZZ 77777.Z Unit offline for 2R10 Refueling Outage.

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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 Scram.

Event Report (LER) File (NUREG-0161)

D-Regulatory Restriction 4 - Continuation E - Operator Training & Ucense Examination S -lead Reduction F-Administration 9 - Other 5

G - Operational Errur Exhibit I-Same Source II-Other (Explain)

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DATE: April 1994 i

REFUELING INFORMATION 1.

Name of facility: ArkansnNugigar One - Unit _2 2.

Scheduled date for next refueling shutdown. S.cplember 22.1995 3.

Scheduled date for restart following refueling. November 6.1995 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)?

.Qnkpowittit this timc_

5.

Scheduled date(s) for submitting proposed licensing action and supporting information.

Unknown at Lhis time.

6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed desigt or performance analysis methods, significant changes in fuel design, new operating procedures.

b'one, 7.

The number of fuel sssemblics (a)in the core and (b)in the spent fuel storage pool.

a) 177 b) L31 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.

l present 98.8 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 cf full core off-load capability)

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