2CAN049304, Monthly Operating Rept for Mar 1993 for Ano,Unit 2

Monthly Operating Rept for Mar 1993 for Ano,Unit 2

ML20035E702
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/31/1993
From:	James Fisicaro, Whitt M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN049304, 2CAN49304, NUDOCS 9304190119
Download: ML20035E702 (7)

Text

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w Kn.w: :noo April 15, 1993 2CAN049304 U. S. Nuclear Regulatory Commission i

Document Control Desk Mail Station F1-137 Washington, DC 20555

Subject:

Arkansas Nuclear One - Unit 2 i

Docket No. 50-368 4

License No. NPF-6 Monthly Operating Report Gentlemen:

Monthly Operating Report statistics for Arkansas Nuclear One, Unit-2, j

l for March, 1993 is attached. This report is submitted in accordance t

with ANO-2 Technical Specification 6.9.1.6.

i Very truly yours,

/ '1&*

James J. Fisicaro Director, Licensing JJF/JRil/prg l

Attachment I

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i U. S. NRC April 15, 1993 2CAN049304 - Page 2 cc:

Mr. James L. Milhoan Regional Administrator U. S. Nuclear Regulatory Commission Region IV j

611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 i

Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. Roby Bevan NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 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 l

Rockville, Maryland 20852 l

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. ~.

OPERATING DATA REPORT DOCKETNO:

50-368 DATE:

pril 2,1993 COMPLETED BY: M. S. Whitt TELEPHONE:

j501) 964-5560 OPERATING STATUS 1.

Unit Name: Arkansas Nuclear Ont Unit 2 2.

Reporting Period:

March 1-31,1993 3.

Licensed Thermal Power (MWI): 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 l

t MONTH YR-TO-DATE CUMULATIVE f

11.

Hours in Reponing Period...

744.0 2,160.0 114,096.0 12.

Number of Hours Reactor wa; Critical 744.0 2,160.0 86,591.3 13.

Reactor Reserve Shutdown Hours.

0.0 0.0 -

0.0 14.

Hours Generator On-Line..

744.0 2,160.0 84,739.4 15.

Unit Reserve Shutdown Hots..

0.0 0.0 0.0 16.

Gross Thermal Energy Generated (MWH).

2,073,261 6,043,549 223,810,352 17.

Gross Electrical Energy Generated (MWH) 688,850 2,008,860 73,639,051 18.

Net ElectricalEnergy Generated (MWH).

658,506 1,920,720 70,048,839 19.

Unit Senice Factor. _

100.0 100.0 74.3 20.

Unit Availability Factor -

100.0 100.0 74.3 21.

Unit Capacity Factor (Using MDC Net).

103.2 103.6 71.6 22.

Unit Capacity Factor (Using DEC Net)._

97.0 97.5 67.3 23.

Unit Forced Outage Rat -

0.0 0.0 11.9 24.

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

25.

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

26.

Units in Test Status (Prior to Commercial Operation):

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

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-368 UNIT:

Two I

DATE:

April 2.1993 COMPLETED BY: M. S. Whitt TELEPHONE:

(501) 964-5560 MONTH March.1993 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1..

892 i

2 891 3

893 4

893 5

893 6

887 7.

893 i

8 891 9

892 10 -

895 11..

895 l

12.. _.....

894 13 -

896 14 896 15 8%

16:

893 17.

895 18-895 19 816 20...

894 21-895

[

22 --

895 l

23 -

896 24.

895 7

i

25..

893 26 -

892 27.

891 28.

890 29.

888

30.....

889 7

31..

722 AVGS: 885 I

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.

P L

)

NRC MONTHLY OPERATING REPORT.

OPERATING

SUMMARY

MARCH 1993 UNIT TWO The unit began the month ofMarch at 100% power.

At 1043 hours0.0121 days <br />0.29 hours <br />0.00172 weeks <br />3.968615e-4 months <br /> on the nineteenth, a power reduction to 80% was initiated due to fire water-intrusion into a Feedwater Turbine cabinet, generating an inadvertent Turbine Generator setback signal. After infonning the System Dispatcher of the load reduction and cause, the dispatcher ordered a further derate to 75% at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br />. - The unit was released by the dispatcher at 1818 hours0.021 days <br />0.505 hours <br />0.00301 weeks <br />6.91749e-4 months <br /> on the nineteenth and the unit attained 100% at 2132 hours0.0247 days <br />0.592 hours <br />0.00353 weeks <br />8.11226e-4 months <br /> that same day. The System Dispatcher requested a power reduction to 75% on the thirty-first and a power reduction was commenced at 0047 hours5.439815e-4 days <br />0.0131 hours <br />7.771164e-5 weeks <br />1.78835e-5 months <br />. The unit attained 75% at 0345 hours0.00399 days <br />0.0958 hours <br />5.704365e-4 weeks <br />1.312725e-4 months <br /> and while at reduced power a condenser tube leak was located and plugged.

The unit was held at 75% per the dispatcher for the remainder of the month.

UNITSilUTDOWNS AND POWER REDUCTIONS REPORT FOR MARClf 1993 DOCKET NO.

50-368 UNIT NAME ANO Unit 2 DATE April 2,1993 COMPLETED BY M. S. Whitt TELEPIIONE 501-%t-5560 METIIOD OF LICENSEE DURATION SilUTTING DOWN EVENT SYSTEM COMPENENT CAUSE & CORRECTIVE ACTION TO liO DATE TYPE' filOURS)

REASON' REACTOR 2 REPORT #

CODE' CODE 8 PREVENT RECURRENCE 2

none 1

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 Scram.

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

Event Report (LER) File (NUREG-0161)

D-Regulatory Restrictior.

1 - Continuation E - Operator Training & Liccese Examination 5 - load Reduction F-Administration 9 - Other 5

G - Operational Ermr Exhibit 1 - Same Source j

II-Other (Explain)

{

DATE ': March, 1993 REFUELING INFORMATION 1.

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

Scheduled date for next refueling shutdown. March 25, 1994 i

3.

Scheduled date for restart following refueling. May 16, 1994 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 ans.wer 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 co:re reload (Ref. 10 CFR Section 50.59)?

Yes. Technical Specification changes to relocate cycle specific parameters to a Core Operating Limits Report and to make the Technical Specification requirements for Azimuthal Power Tilt consistent with accident analyses.

5.

Scheduled date(s) for submitting proposed licensing action and supporting information. August, 1993 l

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.

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 l

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)