2CAN019401, Monthly Operating Rept for Dec 1993 for ANO Unit 2

Monthly Operating Rept for Dec 1993 for ANO Unit 2

ML20059G569
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/31/1993
From:	Whitt M, Yelverton J ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN019401, 2CAN19401, NUDOCS 9401240273
Download: ML20059G569 (7)

Text

Entergy opercuona,Inc.

==~ ENTERGY E"ifMim Tel50 F/ A 8888 Jerry W. Yelverton VC0 PrCMif.1 0 vaurc Ato January 14,1994 2CAN019401 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 December, 1993 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.

Very truly yours,

/4) 2 JWY/jrh Attachment 210074 i

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U.S.NRC January 14, 1994 2CAN019401 Page 2 cc:

Mr. James L. Milhoan Regional Administrator

. U. S. Nuclear Regulatory Commission

)

Region IV

-l 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 i

NRC Senior Resident inspector

-l Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 1

Mr. Roby Bevan 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 j

NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint Nonh 11555 Rockville Pike Rockville, Maryland 20852

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}

OPERATING DATA REPORT DOCKET NO:

50-368 i

. DATE:

January 3,1994 COMPLETED BY: M. S. Whitt

{

TELEPilONE:

(501) 964-5560 i

OPERATING STATUS

]

.j 1.

Unit Name: Arkansas Nuclear One - Unit 2

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2.

Reporting Period:

December 1-31,1993

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3.

Licensed Thermal Power (MWt): 2,815

.Ij 4.

Nameplate Rating (Gross MWe): 942.57 5.

Design Electrical Rating (Net MWe): 912

-l 6.

Maximum Dependable Capacity (Gross MWe): 897

.j 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 MWc): None j

10.

Reasons For Restrictions. If Any:

None l

.i MONTil YR-TO-DATE CUMULATIVF

l 11.

Hours in Reporting Period.

744.0 8,760.0 120,696.0 '

12.

Number ofIlours Reactor was i

Critical.

744.0 8.390.4 92,821.7 13.

Reactor Reserve Shutdown Ilours.

0.0 0.0 0.0 14.

Ilours Generator On-Line.

744.0 8,346.6 90,926.0-i 15.

Unit Reserve Shutdown Ilours.

0.0 0.0 0.0 l

16.

Gross Thermal Energy Generated i

(MWII).

2,076,159 23,213,180 240,979,983 j

17.

. Gross Electrical Energy q

Generated (MWil).

691,004 7,692,146 79,322,337 4

18.

Net Electrical Energy Generated (MWII)...

660,749 7,344,790-75,472,909 19<

Unit Scnice Factor....

100.0 95.3 75.3 4

20.

Unit Availability Factor.

100.0 95.3 75.3 l

21.

Unit Capacity Factor (Using MDC Net) 103.5 97.7 72.9.

22.

Unit Capacity Factor (Using DEC Net)...

I 97.4 91.9 68.6 23.

Unit Forced Outage Rate.

0.0

.0.4 I1.2

.]

24.

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

~

Refueling Outare 2R10 is scheduled for March 11,1994 through April 24,1994.

25.

If Shut Down At End of Report Period. Estimated Date of -

Startup:

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26.

Units in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 12/05n8 INITIAL ELECTRICITY 12/26n8 COMMERCIAL OitRATION 03/26/80

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s.-.-

i AVERAGE DAILY UNIT POWER LEVEL 1

DOCKET NO:

50-368 UNIT:

Two DATE:

January 3,1994 COMPLETED BY: M. S. Whitt TELEPHONE:

(501) 964 5560 l

MONTH Decem.bgr.1993 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 896 2

895 3.

894 4

895 5.

895 6

896

[

7 896 8

895 9

893 10.

891 11.

895

+

12.

894 13.

895 14 894 l

15.

895 l

16.

895 l

17..

895 18.

896

19...

896

'20.

897 21.

871

~1 22.

728 23.

871 24.

897

j 25.

896 26.

895 27.

894 l

896 I

28._

29.

897 i

30.

896 31.

894 i

~I AVGS: 888 I

INSTRUCTION 1

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.

i

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NRC MONTIILY OPERATING REPORT OPERATING

SUMMARY

DECEMBER 1993 UNIT TWO The unit began the month of December operating at 100% power.

At 2137 hours0.0247 days <br />0.594 hours <br />0.00353 weeks <br />8.131285e-4 months <br /> on the twenty-first, a power reduction was commenced due to a condenser tube leak. Following the plugging of the leaking condenser tube,100%

power was attained at 1434 hours0.0166 days <br />0.398 hours <br />0.00237 weeks <br />5.45637e-4 months <br /> on the twenty-third.

The unit operated at 100% power for the remainder of the month.

UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT FOR DECEMBEIL 1993 DOCKET NO.

50-368 UNIT NAME ANO Unit 2 DATE Januarv 3,1994 COMPLETED BY M. S Whitt TELEPIIONE 501-964-5560 METIIOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO B'O DATE TYPE 8 (I!OURS)

REASON 2 REACTOR REPORT #

CODE 4 CODES PREVENT RECURRENCE 3

m none 1

2 3

4 F: Forced Reason:

Method:

Exhibit G - Instruct;ons 5: 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 (NURELM!61)

D-Regulatory Restriction.

4 - Continuation E - Operator Training & Ucense Examination 5 -I;>ad Reduction

' F-Administration 9 - Other 5

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

-+

I

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DATE: December,1993 r

REFUELING INFORMATION 1.

Name offacility: Arkansas Nuclear One - Unit 2 2.

Scheduled date for next refueling shutdown. March 11 1994 3.

Scheduled date for restart following refueling. April 24.1994 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)?

Yes. Technical Specification changes to relocate cycle specific parameters-to a Core Operating Limits Report.

5.

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

Changes 19bmitted July 22.1993.

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.

7.

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

a) 177 b)16J 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 0

)

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

q DATE: 1997 (Loss of full core off-load capability)

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