2CAN059603, Monthly Operating Rept for April 1996 for Ano,Unit 2

Monthly Operating Rept for April 1996 for Ano,Unit 2

ML20112A187
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/30/1996
From:	Mims D, Whitt M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN059603, 2CAN59603, NUDOCS 9605200327
Download: ML20112A187 (7)

Text

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-~ - ENTERGY ma a m FkscMc AR 7230i Tel 501858 '500 May 15,1996 2CAN059603 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555

Subject:

Arkansas Nuclear One - Unit 2 Docket No. 50-363 License No. NPF-6 Monthly Operating Report Gentlemen:

The Arkansas Nuclear One - Unit 2 Monthly Operating Report for April 1996 is attached.

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

Very truly yours, kwfC.1}W Dwight C. Mims Director, Nuclear Safety DCM/eas attachment 200133 9605200327 960430 t/,

PDR ADOCK 05000368 i

R PDR

U. S. NRC i

May 15,19%

2CAN059603 Page 2 cc:

Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission RegionIV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR72847 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 1

I

1 L

OPERATING DATA REPORT DOCKET NO:

50-368 DATE:

May 15,1996 COMPLETED BY: M. S. Whitt TELEPHONE:

(50l) 858-5560 OPERATING STATUS 1.

Unit Name: Arkansas Nuclear One - Unit 2 2.

Reporting Period:

April 1-30 3.

Licensed Thermal Power (MWt): 2,815 4.

Nameplate Rating (Gross MWe): 942.57

)

5.

Design Electrical Rating (Net MWe): 912 6.

Maximum Dependable Capacity (Gross MWe): 897 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 MWe): 890 10.

Reasons For Restrictions. If Any:

Selfimposed power restriction to - 97.9% power based on T-hot limitations in combination with current steam generator plugging and fouling levels.

MONTH YR-TO-DATE CUMULATIVE 11.

Hours in Reporting Period.

719.0 2,903.0 141,119.0 12.

Number of Hours Reactor was Critical.

719.0 2,903.0 110,373.8 13.

Reactor Reserve Shutdown i

l Hours...

0.0 0.0 0.0 14.

Hours Generator On-Line.

719.0 2,903.0 108,181.1 15.

Unit Reserve Shutdown Hours..

0.0 0.0 0.0 16.

Gross Thermal Energy Generated (MWH).

1,980,858 7,997,504 288,259,989 17.

Gross Electrical Energy Generated (MWH).

666,344 2,693,772 95,043,375 18.

Net Electrical Energy Generated (MWH).

636,896 2,575,103 90,455,769 19.

Unit Service Factor....

100.0 100.0 76.7 20.

Unit AvailabilityFactor.

100.0 100.0 76.7 21.

Unit Capacity Factor (Using MDC Net).

103.2 103.4 74.7 22.

Unit Capacity Factor (Using DER Net).

97.1 97.3 70.3 23.

Unit Forced Outage Rate...

0.0 0.0 10.0 24.

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

None 25.

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

N/A 26.

Units in Test Status (Prior to Commercial Operation):

None Forecast Achieved INITIAL CRITICALITY 12/05n8 l

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

l t

o AVERAGE DAILY UNIT POWER LEVEL t

DOCKET NO:

50-368 UNIT:

Two DATE:

May 15,1996 l

COMPLETED BY: M. S. Whitt TELEPHONE:

(501) 858-5560 i

MONTH Anril19%

DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 888 2..

887 3.

886 4.

888 5.

889 6..........

888 7....

887 8.....

888 9

887 10.................

887

11...

884 12..

884 13.............

886 14...

884

15...............

888 16.

887 17..

886 18......

882 19....

880 2 0...........

886 21.......

884 22......

884 23....

887 24............................

885 25...

884 26..

886 27................

886 2 8.........

882

29..

888 30..........................

.R38 j

AVGS: 886 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.

A

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR APRIL 1996 DOCKET NO.

50-368 UNIT NAME ANO Unit 2 DATE May 15,1996 COMPLETED BY M. S. Whitt TELEPHONE 501-858-5560 METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO M

DATE E'

OfOURS)

REASON 8 REACTORS REPORT #

CODE

• CODES PREVENT RECURRENCE l

none l

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 of Test 2 - Manual Scram.

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

Event Report (LER) File (NUREG-0161)

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

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

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

l APRIL 1996 UNIT TWO The unit operated the entire month of April at 97.9% power.

4 l

1 l

[~

Reporting Period: April 1996 l

REFUELING 1NFORMATION 1.

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

Scheduled date for next refueling shutdown: March 21.1997 3.

Scheduled date for restart following refueling: May 5.1997 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 deternune whether any unreviewed safety questions are associated with the core reload (Ref.10CFR Section 50.59)?

Yss. increase fuel enrichment limit from 4.1 weinht nercent to 5.0 weinht oeregit. relocate reactor coolant system (RCS) flow limit to Core Operatina Limits Report. and revise RCS volume in the desian features section.

I 5.

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

lune 1996 j

6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or perfonnance analysis methods, significant changes in fuel design, new operating procedures.

None olanned 7.

He number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool:

)

a) 171 b) 221

)

8.

He 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 188 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 full core off-load capability)

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