1CAN079501, Monthly Operating Rept for June 1995 for ANO Unit 1

Monthly Operating Rept for June 1995 for ANO Unit 1

ML20086J996
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/30/1995
From:	Mims D, Whitt D ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1CAN079501, 1CAN79501, NUDOCS 9507190317
Download: ML20086J996 (7)

Text

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July 14,1995 1CAN079501 U. S. Nuclear Regulatory Commission g

Document Control Desk

!l Mail Station Pl-137 Washington, DC 20555

Subject:

Arkansas Nuclear One - Unit 1 Docket No. 50-313

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License N. OPR-51 Monthly Operating Report

,i Gentlemen.

The Arkemas Nuclear One - Unit 1 Monthly Operating Report for June 1995 is attached.

This report is submitted in accordance with ANO-1 Technical Specification 6.12.2.3.

Very truly yours, l

A$wft1LE t

Dwight C. Mims Director, Lcensing DCM/eas

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Attachments I

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9507190317 950630 PDR ADOCK 05000313 I{

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U.S.'NRC July 14,1995 ICAN079501 cc:

Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV j

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

4.

NRC Senior Resident Inspector Arkansas Nuclear One i

1448 S. R. 333 Russellville, AR72801 Mr. George Kalman NRR Project Manager Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-11-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 ii -

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OPERATING DATA REPORT DOCKET NO:

50 313 DATE:

July 14,1995 COMPLETED BY: M. S. Whitt TELEPHONE:

(501) 858-5560 OPERATING STATUS 1.

Unit Name: Arkansas Nuclear One - Unit i 1

2.

Reporting Period:

June 1-30 3.

Licensed Thermal Power (MWl): 2,568 4.

Nameplate Rating (Gross MWe): 902.74 5.

Design Electrical Rating (Net MWc): 850 6.

Maximum Dependable Capacity (Gross MWe): 883 7.

Maximum Dependrole Capacity (Net MWc): 836 I

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):

10.

Reasons For Restrictions. If Any:

MONTH YR TO-DATE CUMULATIVE j

11.

Ilours in Reporting Period.

720.0 4.343.0 179,970.0 12.

Number ofIlours Reactor uas Critical.

720.0 3,186.0 132,442.2 13.

Reactor Reserve Shutdown llours.

0.0 0.0 5,044.0 14.

ilours Generator On-Linc.

720 0 3,113.9 130,101.8 15.

Unit Reserve Shutdown llours.

0.0 0.0 817.5 16.

Gross Thermal Energy Generated (MWil).

1,846,474 7,108,924 301,262,813 17.

Gross Electrical Energy Generated (MWII).

629,950 2,424,690 100,736,610 i

18.

Net Electrical Energy Generated (MWH).

603,041 2.303.225 95,828,714 19.

Unit Service Factor.

100.0

1.7 72.3 20.

Unit Availabihty Factor.

100.0 7i.7 72.7 j

21.

Unit Capacity Factor (Using MDC Net).

100.2 63.4 63.7 22.

Unit Capacity Factor (Using DER Net).

98.5 62.4 62.6 23.

Unit Forced Outage Rate.

0.0 3.3 10.5 24.

Shutdow ns 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 Conuncreial Operation):

l Forecast Achieved INITI AL CRITICALITY 08/06/74 INITI AL ELECTRICITY 08/17/74 COMMERCIAL OPERATION 12/19/74

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-313 UNIT:

One DATE:

July 14.1995 COMPLETED BY: M. S. Whitt TELEPHONE:-

-(501) 858-5560 MONTH Igly 1995 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 4 i

=

1 842 2.

842 841 a..

4...

840

(

842 6.

840 7....

838 8

837 9.....

835 I

10..

876 11...

836 12.....

840 4

13...

841 14.............

840 i

15.

839 16..

838 17.......

833 18.

838 19.

838 20..

837 2 1..............

838 22..

834 23..

835 24..

837 25...........

836 2 6............

837 l

27....

837 2 8.....

836 29..

836 30.

837 31.

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AVGS: 838 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for eachday in reporting month. Complete to the nearest whole megawatt.

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NRC MONTIILY OPERATING REPORT OPERATING

SUMMARY

JUNE 1995 UNIT ONE i

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The unit began the month of June at 100% power.

At 1542 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.86731e-4 months <br /> on the tenth, a power reduction to 95% was required due to P-3D circulating water pump trip. After restarting P-3D, the unit was returned to 100% power at 0232 hours0.00269 days <br />0.0644 hours <br />3.835979e-4 weeks <br />8.8276e-5 months <br /> on the eleventh. The monthly main turbine governor valve test required a power reduction to 89.5% at 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br /> on the seventeenth. Following completion of the governor valve test, i

the unit was returned to 100% power at 1145 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.356725e-4 months <br /> that same day.

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

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UNrr SHUTDOWNS AND POWER REDUCTIONS REPORT FOR JUNE 1995 DOCKET NO.

50 313 UNIT NAME ANO Unit 1 DATE July 14,1995 COMPLETED BY M. S. Whitt TELEPHONE 501-858-5560 5tETi!OD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEst CO%tPOSJ5T CAUSE & CORRECTIVE ACTION TO E

DATE TYPE' OIOUR9 REAcON RFACTOR REPORT #

CODE' 2

3 CUDE PREVENT RFCURRENCE 1

2 3

4 F: Forced Reason:

Method:

Exhibit G -Instnactions S: Scheduled A - Equipinent Failure (Esplein) 1 - Manual for Preparation of Data B - Maintenance of Test 2 - Manual Scram Entry Sheets for Ucessee C-Refseling 3 - Antoinatic Scream.

Event Report (LER) File (NUREG-0161)

D-Regulatory Restriction 4 - Continuation E - Operator Training & Ucense Emannimation 5 -Imad Reduction e

F-Adailnistration 9 - Other 5

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

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Reporting Period: June 1995 REFUELING INFORMATION 1.

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

Scheduled date for next refueling shutdown: September 20.1996 3.

Scheduled date for restart following refueling: November 4. !996 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.10CFR Section 50.59)?

Unknown at this time 5.

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

N/A 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 olanned 7.

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

a) jl1 b) 241 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 2f63 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:

1996 (Loss of full core off load capability)

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