2CAN119403, Monthly Operating Rept for Oct 1994 for ANO-Unit 2

Monthly Operating Rept for Oct 1994 for ANO-Unit 2

ML20080A815
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/31/1994
From:	Mims D, Whitt M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN119403, NUDOCS 9411210387
Download: ML20080A815 (7)

Text

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, smm3.m November 15,1994 2CANI19403 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:

i The Arkansas Nuclear One - Unit 2 Monthly Operating Report (MOR) for October 1994 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.

Very truly yours,

& & C.'71(n' Dwight C. Mims Director, Licensing DCM/jrh Attachment I

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9411210387 941031 1

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U. S. NRC November 15,1994 2CAN119403 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 1448 S. R. 333 Russellville, AR 72801 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, Maryland 20852

OPERATING DATA REPORT DOCKET NO:

50-368 DATE:

November 1,1994

]

COMPLETED BY: M. S. Whitt TELEPIIONE:

(501) 858-5560 OPERATING STATUS 1.

Unit Name: Arkansas Nuclear One - Unit 2 2.

Reporting Period:

October 1-31, 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 MWc): 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 MWc): None 10.

Reasons For Restrictions. If Any:

None MONT11 YR-TO-DATE CUMULATIVE I 1.

Ilours in Reporting Period.

745.0 7,296.0 127,992.0 12.

Number of flours Reactor was j

Critical.

745.0 6,275.6 99,097.3 13.

Reactor Reserve Shutdown ilours.

0.0 0.0 0.0 j

14.

IIours Generator On-Line.

745.0 6,243.1 97,169.1 i

15.

Unit Reserve Shutdown llours.

0.0 0.0 0.0 16.

Gross Thermal Energy Generated (MWil).

2,096,708 17,257.138 258,237,122 17.

Gross Electrical Energy Generated (MWH).

694,284 5,675,671 84,998,008 18.

Net Electrical Energy Generated (MWil).

663,867 5,412,934 80,885,843 19.

Unit Service Factor.

100.0 85.6 75.9 20.

Unit Availability Factor.

100.0 85.6 75.9 21.

Unit Capacity Factor (Using MDC Net),

103.9 86.5 73.7 22.

Unit Capacity Factor (Using DEC Net).

97.7 81.3 69.3 23.

Unit Forced Outage Rate.

0.0 0.0 10.6 24.

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

A mid-cycle steam generator inspection is scheduled for two weeks beginning January 6,1995.

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

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-368 UNIT:

Two DATE:

November 1,1994 COMPLETI!D BY: M. S. Whitt j

TELEPIIONE:

(501) 858-5560 MONTil October 1994 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 889 2

888 3

887 4

889 5

890 6

887 7

882 8

892 9

895 10.

894 11.

893 12.

892 13,

892 14.

890 15.

890 16.

891 17.

8W) 18.

888 19.

889 20.

890 21, 890 22.

889 23.

891 24.

893 25, 895 26.

8%

27.

896 28.

894 29.

895 30.

893 31.

894 AVGS: 891 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 MONTHLY OPERATING REPORT OPERATING

SUMMARY

OCTOBER 1994 UNIT TWO The unit operated the month of October at 100% power.

'l

UNIT SHUTDOWNS AND POWER REDUCTIONS

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REPORT FOR OCTOBER 1994 DOCKET NO.

50-368 UNIT NAME ANO Unit 2 -

DATE November 1,1994 COMPLETED BY M. S. Whitt TELEPHONE (501) 858-5560 METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO hjO DATE

_TM8 (HOURS)

REASON 2 REACTOR 8 REPORT #

CODE' CODE 8 PREVENT RECURRENCE 2

None 1

2 3

4 F: Forced Reason:

Method:

Exhibit G -Instructions S: Scheduled A - Equipment Failure (Esplein) 1 - Manual for Preparation of Data B - Maintenance of Test 2 - Manual Scrani.

Entry Sheets for Ucensee C - Refueling 3 - Automatic Scrant Event Report (LER) File (NLitEG-4161)

D-Regulatory Restriction 4 - Continuation E - Operator Training & License Examiination 5 -I. mad Reduction F-Administration 9 - Other 5

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

~

~

DATE: October 1994 4

REFUELING INFORMATION 1.

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

Scheduled date for next refueling shutdown. September 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 i

Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Section 50.59)?

D_clete requirement for verification of position stoos for the high pressure safety iniection throttle valves. Revise Technical Specifications to account for the reolacement of eart-kugth control element assemblies witii full-length control element assemblies.

1 I

5.

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

March 1995.

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 planned.

i 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 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 full core off-load capability)

..