2CAN079405, Monthly Operating Rept for June 1994 for ANO Unit 2

Monthly Operating Rept for June 1994 for ANO Unit 2

ML20071H530
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/30/1994
From:	Mims D, Whitt M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN079405, 2CAN79405, NUDOCS 9407190293
Download: ML20071H530 (7)

Text

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-m 4 o,r :ay, July 15,1994 2CAN079405 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station Pl-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 June 1994 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.

Very truly yours, h

d ~f C7VM Dwight C. Mims Director, Licensing DCM/jrh Attachment 9407190293 940630 PDR ADOCK 05000368 R

PDR

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l U. S. NRC July 15,1994 2CAN079405 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 - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 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, Maryland 20852 l

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1 OPERATING DATA REPORT l.

DOCKET NO:

50-368 DATE:

July 6,1994 COMPLETED BY: M. S. Whitt TELEPHONE:

(501) 964 5560 OPERATING STATUS 1.

Unit Name: Arkansas Nuclear One - Unit 2 2.

Reporting Period:

June 1-30,1994 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): None 10.

Reasons For Restrictions. If Any:

None MONTH YR-TO-DATE CUMULATIVE 11.

Ilours in Reporting Period.

720.0 4,343.0 125,039.0 12.

Number of Hours Reactor was Critical.

720.0 3,322.6 96,144.3 13.

Reactor Reserve Shutdown flours.

0.0 0.0 0.0 14.

Hours Generator On-Line.

720.0 3,290.1 94,216.1 15.

Unit Reserve Shutdown Hours.

0.0 0.0 0.0 16.

Gross Thermal Energy Generated (MWH).

1,973,320 8,946,403 249,926,387 17.

Gross Electrical Energy Generated (MWH).

642,507 2,942,120 82,264,457 18.

Net Electrical Energy Generated (MWH).

613,130 2,800,682 78,273,591 19.

Unit Service Factor.

100.0 75.8 75.3 -

20 Unit Availability Factor.

100.0 75.8 75.3 21.

Unit Capacity Factor (Using MDC Net).

99.3 75.2 73.0 22.

Unit Capacity Factor (Using DEC Net).

93.4 70.7 68.6 23.

Unit Forced Outage Rate..

0.0 0.0 10.9 24.

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

25.

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

26.

Units in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 12/05n8 INITIAL ELECTRICITY 12/26/78 COMMERCIAL OPERATION 03/26/80

AVERAGE DAILY UNIT POWER LEVEL i

DOCKET NO:

50-368 UNIT:

Two I

DATE:

July 6,1994 COMPLETED BY: M. S. Whitt TELEPlIONE:

(501) 964-5560 h'ONTil June 1994 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 882 2

880 3

876 4

863 5

860 6

860 7

862 8

863 9

862 10.

863 11.

862 12.

859 13.

860 14.

858 15.

859 16.

856 17..

853 18, 859 19.

857 20.

857 21, 862 22.

876 23.

856 24.

877 25.

872 26.

870 27.

871 28.

527 29.

812 30.

875 31.

1. N/A AVGS: 852 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.

--mn.

NRC MONTIILY OPERATING REPORT OPERATING

SUMMARY

JUNE 1994 UNIT TWO The unit began the month of June at 100% power.

At 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on the third, power was decreased to 98% due to uncertainties in the feedwater flow indication. After resolution of the flow indication concern, power was increased to 100% on the twenty-first.

A power reduction to 60% was initiated on the twenty-eighth to find a condenser tube leak. The leaking tube was plugged and the unit returned to 100% power on the twenty-ninth.

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

l a

UNITSIIUTDOWNS AND POWER REDUCTIONS REPORT FOR JUNE 1994 DOCKET NO.

50-368

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UNIT NAME ANO Unit 2 DATE July 6,1994 i

COMPLETED BY M. S. Whitt I

TELEPilONE 50,1 964-5560 METilOD OF LICENSEE DURATION SHtTITING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO NO, DATE TYPE' OIOURS)

REASON 2 REACTOR 3 REPORT #

CODE' CODE 5 PREVENT RECURRENCE

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94-03 940628 S

0 II 5

N/A SG COND Power reduction to locate and plug

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leaking condenser tube.

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{

1 2

3 4

i 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 IJcensee C-Refueling 3 - Automatic Scram.

Event Report (LER) File (NURE(A'161)

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

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

-_o

a DATE: June 1994 REFUELING INFORMATION 1.

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

Scheduled date for next refueling shutdown. Ssptember 22.1995 3.

Scheduled date for restart following refueling. November 6.1995 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)?

Deletglequ!Lcment for verification of position stops for the high pressure safety injeglion throttle valves.

5.

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

Ma.r_qh 1991 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.

Nonc_ planned.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, a) 177 b)637 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 SL88 increase size by Q 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) l

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