2CAN129301, Monthly Operating Rept for Nov 1993 for ANO Unit 2

Monthly Operating Rept for Nov 1993 for ANO Unit 2

ML20058M634
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/30/1993
From:	Whitt M, Yelverton J ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN129301, NUDOCS 9312210056
Download: ML20058M634 (5)

Text

Entergy Operationo, Inc.

y, gg ENTERGY

"" 3 " " "

Rw,cEnllc. /J1 72801 Te!501-964 8308 Jerry W. Yelverton VbePra mt op,awt: ten December 15, 1993 2CAN129301 U. S. Nuclear Regu lat.ory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555

Subject:

Arkansas Nuclear

e - Unit 2 r

Docket No. 50-368 License No. NPF-6 Monthly Operating Report Gentlemen:

The Arkansas Nuclear One - linit 2 Monthly Operating Report (MOR) for November, 1993 is at.tached.

This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.

Very truly yours,

&U

/

VJWY/prg Attachment y

e n

. hk kDO K 00 8

g x

\\

U. S. NRC 1

December 15, 1993

~

2CAN129301 - Page 2 l

i cc:

Mr. James L. Milhoan Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arl.ington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellvil'.e, AR 72801 Mr. Roby Bevan

'l NPR Project Manager, Region IV/ANO-1

^

U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 4

One White Flint North l

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 6

7 1

5 2

a l

)

OPERATING DATA REPORT s

DOCKET NO:

50-368 j

DATE:

pecember 3,1993 COMPLETED BY: M. S. Whitt TELEPliONE:

(501) 964-5560 Q_P_ER_6 TING STATUS 1.

Unit Name: Arkansas Nuclear One - Unit 2 2.

Reporting Period:

November 1-30, 1993 3.

Licensed Thermal Power (MWt): 2,815

.i 4.

Nameplate Rating (Gross MWc): 942.57 5.

Design Electrical Rating (Net MWe): 912 6.

Maximum Dependable Capacity (G ross MWe): 897 7.

Maximum Dependable Capacity P%t MWe): 858 8.

If Changes Occur in Capacity lot ngs (Items Number 3 Through 7) Since Last Report, Give Reasons:

1 9.

Power Level To Which Restricted 'T Any (Net MWe): None 10.

Reasons For Restrictions. If Any:

Nonc i

MONTil YR-TO-DATE CUMULATIVE l

11.

Ilours in Reporting Period.

720.0 8,016.0 119,952.0 12.

Number of flours Reactor was Critical.

720.0 7,646.4 92,077.7 13.

Reactor Reserve Shutdown llours..

0.0 0.0 0.0 14.

Ilours Generator On-Line.

720.0 7,602.6 90,182.0 15.

Unit Reserve Shutdown llours.

0.0 0.0 0.0

)

16.

Gross Thermal Energy Generated (MW1I).

2,023,030 21,137,020 238,903,824 j

17.

Gross Electrical Energy l

Generated (MWil).

674,536 7,001,142 78,631,333 J

18.

Net Electrical Energy Generated (MWil).

644,993 6,684,041 74,812,160 19.

Unit Service Factor.

100.0 94.8' 75.2-

0.

Unit Availability Factor.,

100.0 94.8 -

75.2' 21.

Unit Capacity Factor

' (Using MDC Net). _

104.4 97.2 72.7 -

22.

Unit Capacity Factor (Using DEC Net)..

98.2 91.4 68.4 23, Unit Forced Outage Rate.

0.0 0.5 -

11.3 24.

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

I Refueling Outage 2R10 is scheduled for March 12,1994 through April 25,1994.

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

26.

Units in Test Status (Prior to Commercial Operation):

Forecast Achieved I

INITIAL CRITICALITY 12/05n8 INITIAL ELECTRICITY 12/26n8 COMMERCIAL OPERATION 03/26/80

AVERAGE DAILY UNIT POWER LEVEL

+

4 DOCKET NO:

50-X 8 UNIT:

50 l

DATE:

December 3,1993 COMPLETED BY: M. F. Whitt TELEPilONE:

I'Al) ?64-5 4G0 MONTil Nqrgnhgn_1993 DAY AVERAG8 DAILY POWER LEVEL (MWe-Net) i 1

899 2

899 3

899 4

897 5

898 6

900 7

899 8.

898 9

897 10 897 11.

897 12.

895 13.

889 14 894

.i 15.

898 16.

898 17.

897 18.

897 19.

890 20.

875 21.

896 22.

898 23.

896 24 896 k

25.

897 26.

897 27..

897

.]

28.

896 i

29.

896' 30, 896 31.

1. N/A l

AVGS: 896 I

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..

.~

.l NRC MONTIILY OPERATING REPORT i

OPER.ATING

SUMMARY

l NOVEMBER 1993 UNIT TWO The unit began the month of November operating at 100% power.

At 1957 hours0.0227 days <br />0.544 hours <br />0.00324 weeks <br />7.446385e-4 months <br /> on the nineteenth, a power reduction to.95% was commenced for Moderator Temperature Coefficient (MTC) testing. Following the completion of the MTC test at 1247 on the twentieth, the unit escalated in power and attained 100% at 1446 hours0.0167 days <br />0.402 hours <br />0.00239 weeks <br />5.50203e-4 months <br /> that same day.

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

i k

f i

UNIT SilUTDOWNS AND POWER REDUCTIONS REPORT FOR NOVEMHER.1993 DOCKET NO.

50-368 UNIT NAME ANO Unit 2 DATE December 3,1993 COMPLETED BY M. S. Whitt TELEPilONE 501-9M-5560 METilOD OF LICENSEE DURATION SilUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO M

DATE TYPE' (IIOURS)

REASON 2 REACTOR' REPORT #

CODE' CODES PREVENT RECURRENCE none 1

2 3

4 F: Forced Reason:

Method:

Exhibit G - Instructions 5: Scheduled A - Equipment Failure (Explain) 1 - Manual for Preparation of Data B - Maintenance of Test 2 - Manual Scram.

Entry Sheets for IJcensee C - Refueling 3 - Automatic Scram.

Ew nt Report (LER) File (NUREG-0161)

D-Regulatory Restriction 4 - Continuation E - Operator Training & License Examination 5 - Iead Reduction F-Administration 9 - Other 5

G - Operational Error Exhibit I-Same Source

' 11-Other (Explain)

4 DATE: November, 1993-1 REFUELING INFORMATION 1.

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

Scheduled date for next refueling shutdown. March 12,_1994 3.

Scheduled date for restart following refueling. April 25, 1995 4.

Will refueling or resumption of operation thereaf ter 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.

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

Information.

Changes submitted July 22, 1993.

6.

Important licensing considerations associated with refueling, e.g., new'orl 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) 565-8.

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.

DATE:

1997-(Loss of fu11 core offload capability)