ML19332G299

Monthly Operating Rept for Nov 1989 for Arkansas Nuclear One,Unit 1.W/891215 Ltr

ML19332G299
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/30/1989
From:	James Fisicaro, Schaubroeck D ARKANSAS POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1CAN128909, NUDOCS 8912210006
Download: ML19332G299 (6)

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i. December 15, 1989

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ICAN128909 U. S. Nuclear Regulatory Commission ,

' Document Control Desk

Mail Stop P1-137 Washington, D.C. 20555

SUBJECT:

Arkansas Nuclear One - Unit 1 ,

Docket No. 50-313 License No. DPR-51 Monthly Operating Report Gentlemen: i The Arkansas Nuclear One - Unit 1 Monthly Operating Report for November, 1989 is attached.

Very truly yours, -

=r- ykw J. J. Fisicato Manager, Licensing JJF/MCS/1w Attachment cc: Mr. Robert D. Martin Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 -

Arlington, TX 76011 l

l 8912210006 891130

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OPERATING DATA REPORT DOCKET NO: 50-313

DATE: November, 1989 COMPLETED BY: D. A. Schaubroeck  :

TELEPHONE: (501) 964-3743 OPERATING STATUS l 1. Unit Name: Arkansas Nuclear One - Unit 1 Reporting Period: November 1-30, 1989 2.

3. Licensed Thermal Power (MWt)

2,568 L 4. Nameplate Rating (Gross MWe): 902.74

! 5. Design Electrical Rating (Net MWe): 850-

6. Maximum Dependable Capacity (Gross MWe): 885

7. Maximum Dependable Capacity (Net MWe): 836

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since L Last Report, Give Reasons:

9. Power Level To Which Restricted. If Any (Net MWe): 80%

10. Reasons For Restrictions. If Any (Net MWe): A License Amendment was issued 1imiting o)eration to 80% due to a newly identified small break LOCA in the F101 Pressure Injection Line Piping.

MONTH YR-10 DATE CUMULATVE e

11. Hours in Reporting Period .... 720.0 8,016.0 131,059.0

12. Number of Hours Reactor was Critical ..................... 605.4 5,822.4 91,034.5

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

. 14. Hours Generator On-Line . . . . . . 541.9 5,713.4 89,139.4

15. Unit Reserve Shutdown Hours .. 0. 0 0. 0 817.5

16. Gross Thermal Energy Generated (MWH)........................ 1,008,386.0 10,533,246.0 201,812,176.0

17. Gross Electrical Energy Generated (MWH) .............. 340,010.0 3,525,455.0- 66,984,830.0-

18. Net Electrical Energy Generated (MWH) .............. 320,339.0 3,318,178.0 63,656,564.0

19. Unit Service Factor .......... 75.3 71.3 68.0

20. Unit Availability Factor ..... 75.3 71.3 68.6

21. Unit Capacity Factor (Using MDC Net) .............. 53.2 49.5 58.1

22. Unit Capacity Factor (Using DER Net) ............. 52.3 48.7 57.1

23. Unit Forced Outa e Rate ...... 12.7 27.8 13.9

24. Shutdowns Schedu ed Over Next 6 Months (Type, Date, and Duration of Each):

~A 19-day midcycle outage began November 26, 1989.

25. If Shut Down At End of Report Period. Estimated Date of Startup:

December 15, 1989. -

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

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% .:a s re .

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-313 UNIT: One DATE: November, 1989 COMPLETED BY: D.A. Schaubroeck iJ TELEPHONE: (501) 964-3743 MONTH ' November,1989 L DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

R -y 615 2 ............. 615 F

3 .........-.... 614 4 ............. 616 5 ............. 616-l- 6 ............. '619 i- 7 ............. 619 i 8 ............. 620 9 ............. S19 10 ............ 587 11 ............ -30 12 ............ -62 13 ............ 613 14 ............ 600 151 ............ -30 16 ............. 142 n

17 ............ 607

- 18 . . . . . . . . . . . .- 610 19 ............. 617

'20............. 618 b

21 ............ 617 22;............. 617 23 .......,.... 618 E 24'............ 618

25 ............ 617 26 ............ 373 o -27 ............ -26 l -28 ............ -16 29 ............ -11 30 ............- -6 F 31 ............ ,-

r AVGS: 445 INSTRUCTION l

On this format, list the average daily unit power level in MWe-Net for each  ;

-. day in reporting month. Compute to the nearest whole megawatt.

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NRC MONTHLY OPERATING REPORT  ;

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OPERATING

SUMMARY

v-I NOVEMBER 1989 UNIT ONE  ;

i l Unit One began the month at 74% power due to operation with only three reactor coolant pumps.

f On the . tenth at 2253 hours0.0261 days <br />0.626 hours <br />0.00373 weeks <br />8.572665e-4 months <br />, there was a reactor trip which resulted from worker error during calibration of the Reactor Protection System. The unit  ;

was placed back on line at 1605 hours0.0186 days <br />0.446 hours <br />0.00265 weeks <br />6.107025e-4 months <br /> on the twelfth and attained 74% power at 0156 hours0.00181 days <br />0.0433 hours <br />2.579365e-4 weeks <br />5.9358e-5 months <br /> on the thirteenth.  ;

Power was held at 74% until 2322 hours0.0269 days <br />0.645 hours <br />0.00384 weeks <br />8.83521e-4 months <br /> on the fourteenth. At that time,  !

there was a reactor trip on high reactor coolant system pressure due to a main feedwater pump trip resulting from operator error. The unit was ,

placed back on line at 1254 hours0.0145 days <br />0.348 hours <br />0.00207 weeks <br />4.77147e-4 months <br /> on the sixteenth and attained 74% power 3 at 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> that same day. ,

The unit remained at 74% power until 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> on the twenty-sixth at .

which time a power reduction was connenced for a midcycle maintenance outage. At 2038 hours0.0236 days <br />0.566 hours <br />0.00337 weeks <br />7.75459e-4 months <br /> _on the twenty-sixth, there was a turbine trip .

resulting from a low condenser vacuum switch alarm. The unit remained off ,

Lline through the end of the month for the midcycle outage.

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UNIT SHUTDOWNS AND POWER' REDUCTIONS REPORT FOR NOVEMBER, 1989 DOCKET NO S0-313 UNIT MAME. ANO Unit 1 DATE November, 1989 COMPLETED BY D. A. Schaubroeck TELEPHONE -(501)964-3743 Method of Licensee Cause & Corrective-Duration Shutting Event System Component Action To No. Date _ Type t

(Hours) Reason 2 Down Reactor 3 Report # Code 4 Code 5 Prevent Recurrence 89-06 11/10/89 F 41.2 H 3 1-89-037 JC ZZZZZZ Reactor trip resulting from worker error.

89-07 11/14/89 F 37.5 G 3 1-89-038 SJ ZZZZZZ Reactor trip resulting from operator error.

89-08 11/26/89 5 99.4 H 1 N/A ZZ . ZZZZZZ Power reduction and unit off line for a scheduled maintenance outage.

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 or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Continuation 1022)

E-Operator Training & 5-Load Reduction 9-Other 5 License Examination F-Administrative ' Exhibit I - Same Source G-Operational Error (Explain)

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i g DATE: November, 1989 REFUELING INFORMATION 1.' Name of facility: Arkansas Nuclear One - Unit 1

2. Scheduled date for next refueling shutdown. September, 1990

3. Scheduled date for restart following refueling.' December, 1990

4. Will-refueling or resumption of operation thereafter 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)?

Normal Technical Specification changes associated with submission of Ifie ANO-1 Cycle 10 Relnd Report.

5. Scheduled date(s) for submitting proposed licensing action and supporting-information. June, 1990

6. Important licensing considerations associated with refueling, e.g. , new or different fuel design or sup? lier, unreviewed design or performance analysis methods, significant'c1anges in fuel design, new operating procedures.

A debris resistant, extended solid end cap desian fuel rod will be used in the reload fuel batch.

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel

. storage pool, a) 177 __ b) 508

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: 1994 (Loss of fu11 core offload capability) l