2CAN019703, Monthly Operating Rept for Dec 1996 for Arkansas Nuclear One Unit 2

Monthly Operating Rept for Dec 1996 for Arkansas Nuclear One Unit 2

ML20133M176
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/31/1996
From:	Mims D, Whitt M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN019703, 2CAN19703, NUDOCS 9701220290
Download: ML20133M176 (7)

Text

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4 Entergy operations, Inc.

• ~~ENTERGY' m asa 333 R efS A,AR /2801 i

l Tel 501658 5000

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4 January 15,1997 2CAN019703 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 for December 1996 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.

Very truly yours, Dwight C. Mims Director, Nuclear Safety

, DCM/ead attachment i

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9701220290 961231 "'

PDR ADOCK 05000368 R PDR Q

U. S. NRC January 15,1997 2CAN019703 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 P.O. Box 310 i

London, AR 72847 Mr. George Kalman 4 NRR Project Manager Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 4 One White Flint North

! 11555 Rockville Pike Rockville, MD 20852 4

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.i OPERATING DATA REPORT.

DOCKET NO: 50-368 )

DATE: January 15,1997 i COMPLETED BY: M. S. Whitt  ;

TELEPHONE: (501) 858-5560 }

QiNRATING STATUS  ;

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1. Unit Name: Arkansas Nuclear One-Unit 2

2. Reporting Ponod . Dec.1-31 3, Licensed ThermalPower(MWt); 2,815 f

4. I'-- ;' ^: Rating (Gross MWe): 942.57 .

5. ' Design Electncal Rating (Net MWe): 912  !

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6. Maximum Dependable Capacity (Gross MWe): 897

7. . Maximum t; -- ' ' ': Capacity (Not MWe): 858

8. If Changes Occur in Capacity Ratings (Items Number 3 This egh 7) Since Last Report, Give Reasons N/A l i

9. Power level To Which Restncted. If.Any (Net MWe): 884 i

10. Reasons For Restrictions. If Any: Selfimposed power restriction to ~ 97.0% power based on  !

T-hot limitations in combination with steam generator plugging and fouling levels. l t

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4- MQ]S)) YR-TO-DATE CUMULATIVE I

b 11. Hours in Reporting Period 744.0 8,78 Q l47,000.0 '

j- 12. Number of Hours Reactor Was Critical 361.5 8,063.5 115,534.3

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0 ]

! 14. Hours Generator On-Line 347.9 8,049.9 113,327.9 i

' 0.0 0.0 0.0

'15. Unit Reserve Shutdown Hours l 16. Gross Thermal Energy Generated (MWH) 863,486 22,072,932 302,335,417 i 17. Gross Electrical Energy Generated (MWH) 290,032 7,401,642 99,751,245 j 18. Not Electncal Energy Generated (MWH) 271,188 7,063,898 94,944,564

. 19. UMt Service Factor 46.8 91.6 77.1

} 20. Unit AvailabilityFactor 46.8 91.6 77.i

21. Unit Capacity Factor (Using MDC Net) 42.5 93.7 75.3 j- 22. Unit Capacity Factor (Using DER Net) 40.0 88.2 70.8 1 23. Unit Forced Outage Rate 53.2 8.4 10.I

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

j Refueling Outage 2R12 scheduled to begin April 25,1997 with an expected duration of 47 days  !

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25, if Shut Down At End of Report Period. Estimated Date of Startup: N/A

26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved l INITIAL CRITICALITY 12/05n8

INITIAL ELECTRICITY 12/26n8 COMMERCIAL OPERATION 03/26/80 l

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. e AVERAGE DAILY UNIT POWER LEVEL ,

DOCKET NO: 50-368 UNIT: Two 1 DA*IE: January 15,1997 COMPLETED BY: M. S. Whitt .

i TELEPHONE: (501) 858-5560

- MONITI D%l., c 1996 3

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DAY AVERAGE DAILY POWERLEVEL (MWe-Net) 1............................ -5

, 2........... -5 ,

3........................... 5  ;

4............. .. -5 i 5............................. -5 ' -

6........................... -9 7............................ -12 8....-. . -12 }

9.............................. -12

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10.......................... -1I  !

11 . .... -11 l-12............................. _

-ii t 13 .. ..... -12 i 16 l 14 . .......

1....................... -28 16........................ -31 I

17............................. 28 1 18........................... 205 19............................ 684

. 20............................ 873

, 21.. ........

878 22............................. 879

23. 879 24.......................... 883 25........................ 883 26..................... 884 27........................... 883 28......................... 882 29........................... 882 30...........................

31 ....... 882 AVGS: 365 INSTRUCTION i On this fonnat, list the average daily unit power level in MWe-Net for each day in reporting month. Complete to the nearest whole megawatt.

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UNrr SHUTDOWNS AND POWER REDUCTIONS .

REPORT FOR DECEMBER 1996 DOCKET NO. 50-368 UNIT NAME ANO Unit 2 DATE January 15,1997 COMPIETED BY M. S. Whitt TEI2 PHONE 501-858-5560 METHOD OF IJCLMSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO JEL DATE HPf IHOURS) REASON 8 REACTOR' REPORT # CODE' CODE' PREVENT RECURRENCE 96-41 961291 F 396.2 A 4 AB SG Unit tatem off Hee due to increased prinsary to secondary leakage la "A" -

Steam Generator.

1 2 3 4 F: Forced Reason: Method. Exhibit G -Instructices 5: Scheduled A- Equipment Failure (Explain) 1 - Manual for Preparaties of Data B - Maintenance of Test 2 - Manual Scram. Entry Sheets for Ucensee C- Refineling 3 - Automatic Scram. Event Report (LER) File (NUREG-4161)

D- Regulatory Restriction 4 - Continuation ,

E - Operator Training & Ucense Examination 5 -Imed Reduction F- Administration 9 - Other 5 G - Operational Error Exhibit I- Same Source H - Other (Explain)

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NRC MONTIILY OPERATING REPORT OPERATING

SUMMARY

l DECEMBER 1996

, UNIT TWO l

The unit began the month of December off-line for forced outage 2F96-1.

Following the completion of steam generator work, the unit commenced plant startup and at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br /> on the sixteenth the reactor achieved criticality. At 1209 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.600245e-4 months <br /> on the seventeenth, the unit was placed back on-line and proceeded with its normal power escalation following an outage. l The unit reached its maximum achievable power level at 0015 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> on the twentieth.

The unit operated the remainder of the month at 97% power.

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Reporting Period: December 1996 i

REFUELING INFORMATION .  ;

1. - Name of facility: Arkansas Nuclear One - Unit 2

2. Scheduled date for next refueling shutdown: April 25.1997 i

3. Scheduled date for restart following refueling: June 13.1997 f

Will refueling or resumption of operation thercaAer require a technical specification change or other  !

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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 i determine whether any unreviewed safety questions are associated with the core reload (Ref.10CFR l Section 50.59)?

Yes. increase fuel enrichment limit from 4.1 weinht percent to 5.0 weiaht ocreent. revisc reactor t enaba* system (RCS) flow limit. revise RCS volume. add methodoloav references to the Core r Oper=*iaa Limits Report m4=la!ony list. and chanac tolerance for when core protection calculator power indications must be adjusted to calorimetric results.

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

Fuel enrichment channe submitted Aunust 1996: RCS volume. methodoloav references. and power I adjustment tolerance submitted in December 1996.

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

Fuel enrich acnt change discussed under auestion 4. ,

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7. The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool:  ;

I a) Ul b)2H

8. 'Ihe 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 fuct assemblies:  ;

present 238!8 increase size by 0

9. '!he 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 off-load capability)

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