1CAN039706, Monthly Operating Rept for Feb 1997 for Arkansas Nuclear One,Unit 1

Monthly Operating Rept for Feb 1997 for Arkansas Nuclear One,Unit 1

ML20137C234
Person / Time
Site:	Arkansas Nuclear
Issue date:	02/28/1997
From:	Mims D, Whitt M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1CAN039706, 1CAN39706, NUDOCS 9703240189
Download: ML20137C234 (7)

Text

.. -m . .. m.. . _ . . . - . . _ . _ . _ . . .. _ . . - . , ,

i.

'~

l 3' Entergy operations,Inc. i

• (& ENTERGY m m 3n Rtm*A AR 72301

(- .

Td 501558 500 l

l I

I l March 17,1997 1CAN039706 l U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 l i Washington, DC 20555 j i

Subject:

Arkansas Nuclear One - Unit 1 Docket No, 50-313

! License No. DPR-51

! Monthly Operating Report Gentlemen:

l The Arkansas Nuclear One - Unit 1 Monthly Operating Report for Febniary 1997 is attached.

This report is submitted in accordance with ANO-1 Technical Specification 6.12.2.3.

Very truly yours, hf*$

Dwight C. Mims l

Director, Nuclear Safety DCM/eam )

\

3cpW \

l 1

9703240189 970228 i PDR ADOCK 05000313 R PDR 240074 mapspppppps i

_ __ _ . . _ . . . . _ .. .. _ ~ _ . _ . . . . .

U. S. NRC

- March 17,1997' 1CAN039706 Page 2 cc: Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 t

Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Mr. George Kalman NRR Project Manager Region IV/ANO-1 & 2 U. S. Nuclear . Regulatory Commission NRR Mail Stop 13 H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852

- . . .~ - -. - .- . .. .

\

• i OPERATING DATA REPORT i DOCKET NO: 50-313 DATE: March 17,1997 l COMPLETED BY: M. S. Whitt l

j OPERATING STATUS

\

1. Unit Name: Arkansas Nuclear One - Unit 1 l

2. Reporting Period: Feb.1-28 )

, 3. Licensed Thermal Power (MWt):  ;

4. NWMe Rating (Gross MWe):_ 903 2,568 +

. 5. Design ElectricalRating (Net MWe): 850 i 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 Repod, Give Reasons:

9. Power Level To Which Restricted. If Any (Net MWe): i

10. Reasons For Restrictions. If Any:  :

1 i

MONTH YR-TO-DATE CUMULATIVE ,

1 l 11. Hours in Reporting Period 672.0 1,416.0 194,587.0 .

12. Number of Hours Reactor Was Critical 672.0 1,416.0 145,911.6

. 13. Reactor Reserve Shutdown Hours 0.0 0.0 5,044.0

14. Hours Generator On Line 672.0 1,416.0 143,511.3 ,

15. Unit Reserve Shutdown Hours 0.0 0.0 817.5 l 16.' Gross Thermal Energy Generated (MWH) 1,721,401 3,627,808 335,155,598

17. Gross Electrical Energy Generated (MWH) 601,206 1,267,046 112,416,422-

18. Net Electrical Energy Generated (MWH) 577,154 1,216,314 107,001,546 i

19. Unit Service Factor 100.0 100.0 73.8 I

, 20. Unit AvailabilityFactor 100.0 100.0 74.2

21. Unit Capacity Factor (Using MDC Net) 102.7 102.7 65.8

22. . Unit Capacity Factor (Using DER Net) 101.0 101.I 64.7

23. Unit Forced Outage Rate 0.0 0.0 9.8 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 INITIAI, ELECTRICITY 08/1?n4 COMMERCIAL OPERATION 12/1904

. '. l 1

• i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-313 UNIT: One DATE: March 17,1997 COMPLETED BY: M. S. Whitt j TELEPHONE: (501) 858-5560 i MONTH February 1997 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 .. . .. .. 859 l 2........ .... 859  !

3........................ 860 i 4....... 860 5..... . . . . . . 860 6..................... 860 7.................... 836 8..................... 858 9 .. 861 i 10.. 861 l

11. 861 12= . . . 861 13 . . . . . . . .

861  ;

14 ... .. . . . . . . . . . . . .

861 15 . . . .. . . . . . . . . . .

860 16................ 859 17 .... .....

859 18.................. 859 19 .. .. ..

859 20 .... ..

859 21 . ... .. ... 860 22..................... 860 23 . ... . . . . . . . . . .

859 2 4 .. . ..... . .. . . . . . .

860 25.................. 859 26...................... 859 2 7 .. . .. . 860 28.... . . . . . . . . . .

860 AVGS: 859 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.

1 5

f I

i

~

UNIT SHUTDOWNS AND POWER REDUCTIONS -

REPORT FOR FEBRUARY 1997 -

DOCKET NO. 50-313 UNIT NAME ANO Unit 1 DATE March 17,1997 COMPLETED BY M. S. W1titt TELEPHONE 501-858-5560 METHOD OF LICENSEE DURATION SHUTIING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO E DATE M' GIOURS) REASON 8 REACTOR 8 REPORT # [ODi* CODES PREVENT RECURRENCE none 1 2 3 4 F: Forted Reason: Method. Exhibit G -Instructices S: Scheduled A - Equipment Failure (Explain) 1 - Manual for Pnparation of Data B - Maintenance of Test 2 - Manuel Scram Entry Sheets for Ucensee C - Refwiing 3 - Autontatic Scram Event Report (LER) File (NUREG-4161)

D- Regulatory Restriction 4 - Continuation E - Operator Training & Ucease Emannisation 5 -Imed Reduction F- Administration 9 - Other 5 G - Operational Error Exhibit I- Samme Source H - Other (Esplain)

~

NRC MONTIILY OPERATING REPORT OPERATING

SUMMARY

FEBRUARY 1997 UNIT ONE The month began with the unit operating at 100% power.

At i132 hours on the seventh, a power reduction to 85% was commenced for turbine governor and throttle valve stroke testing. Power was returned to 100% at 1645 hours0.019 days <br />0.457 hours <br />0.00272 weeks <br />6.259225e-4 months <br /> on the seventh at completion of the test. The unit operated the remainder of the month at 100%

power.

There were no challenges to the primary system code safeties nor automatic actuations of the electromatic relief valve (ERV) during this reporting period.

e

L 1

Reporting Period: February 1997 REFUELING INFORMATION i

1. Name of facility: Arkansas Nuclear One - Unit 1

2. Scheduled date for next refueling shutdown: March 20.1998

3. Scheduled date for restart following refueling: May 9.1998 l

4. .Will refueling or resumption of operation thereaAer 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.10CFR Section 50.59)?

No. No

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

l N/A l

i l 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, I new operating procedures.

l L ' None planned l

7. The number of fuel assemblies (a) in the core, (b) in the spent fuel storage pool and (c) dry cask l storage:

a) 1J71 b) 15.1 c) 48

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:

l Full core off-load capability no lonner available until a sufficient amount of spent fuel can be l claced in on-site dry storane.

4 Y

b

...m. ._