1CAN069302, Monthly Operating Rept for May 1993 for Ano,Unit 1

Monthly Operating Rept for May 1993 for Ano,Unit 1

ML20045C119
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/31/1993
From:	James Fisicaro, Hayes K ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1CAN069302, 1CAN69302, NUDOCS 9306220100
Download: ML20045C119 (7)

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m un.w :mo June 15, 1993 1CAN069302 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station P1-137 Washington, DC 20555

Subject:

Arkansas Nuclear One - Unit 1 1

Docket No. 50-313 License No. DPR-51 Monthly Operating Report Gentlemen:

The Arkansas Nuclear One - Unit 1 Monthly Operating Report (MOR) for May, 1993 is attached.

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

Very truly yours, fp,u,i :skOn James

. Fisicaro Director, Licensing JJF/JRil/prg Attachment d 0 \\)'$ $

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June 15,~1993 1CAN069302 Page 2

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Mr.' James L. Milhoan 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

.i 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 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 Rockville, Maryland 20852 i

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'I OPERATING DATA REPORT

. DOCKET NO:

50-313 DATE:

June 3,1993 COMPLETED BY: K. R. Hayes TELEPIIONE:

(501) 964-5535 OPERATING STATUS 1.

Unit Name: Arkansas Nuclear One - Unit 1 2.

Reporting Period:

May 1-31.1943 3.

Licensed Thermal Power (MWI): 2.568 4.

Nameplate Rating (Gross MWe): 902.74 5.

Design Electrical Rating (Net MWe): 850 6.

Maximum Dependable Capacity (Gross MWe): 883 7.

Maximum Dependable Capacity (Net MWe): 836 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 i

MONTH YR-TO-DAT_E CUMULATIVE I 1.

Ilours in Reporting Period.

744.0 3623.0 161730.0 12.

Number of Hours Reactor was Critical.

744.0 3581.8 116580.8 13.

Reactor Reserve Shutdown ilours.

0.0 0.0 5044.0 14 Hours Generator On-Line.

744.0 3561.5 114383.2 15.

Unit Reserve Shutdown Hours.

0.0 0.0 817.5 16.

Gross Thermal Energy Generated (MWH).

1906751 8950444 262087598 17.

Gross Electrical Energy Generated (MWH).

649025 3063200 87441070 18.

Net Electrical Energy Generated (MWH).

621444 2932620 83133221 19 Unit Service Factor.

100.0 98.3 70.7 20.

Unit Availability Factor.

100.0 98.3 71.2 21.

Unit Capacity Factor (Using MDC Net).

99.9 96.8 61.5 22.

Unit Capacity Factor (Using DEC Net).

98 3 95.2 60.5 23.

Unit Forced Outage Rate.

0.0 1.7 11.5 24.

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

Refueling Outage 1RI1 is scheduled to begin September 5,1993 and startup is scheduled for November 1,1993.

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 08/06n4 -

INITIAL ELECTRICITY 08/17n4 COMMERCIAL OPERATION 12/19n4 rs-

..m,

-. =

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' AVERAGE DAILY UNIT POWER LEVEL r

DOCKET NO:

50-313 UNIT:

One DATE:

June 3,1993 COMPLETED BY: K. R. Hayes TELEPHONE:

(501) 964-5535 l

MONTH hiav.1993 5

DAY AVERAGE DAILY POWER LEVEL -

(MWe-Net)

)

1 838 2

837 3

838 4

839 5

838 6

837 7

836 8

835 835 9

10.

836 11.

837 s

12.

838 13.

838 14.

838 15, 838 16.,

837 17.

838 18..

837 19.

797 20, 833 21.

838 22.

837 23.

837 24.

836 25, 836 26.

836 2 7 ~.

837 28.

835 29.

833 30.

834 31.

835 AVGS: 835 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for cach day in reporting month. Complete to the nearest whcie megawatt.

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NRC MONTIILY OPERAT'hG REPORT OPER ATING

SUMMARY

MAY 1993 UNIT ONE Unit one began the month operating at 100% power. On the nineteenth at 17:04 hours, the B Heater Drain Pump tripped. Following the pump trip, a power decrease to 85% was initiated to stabilize levelin the Heater Drain Tank which supplied the suction source for the tripped pump. A pressure switch was replaced and the unit ramped to 95% power to perform the turbine throttle / governor valve monthly surveillance at 00:55 hours on the twentieth. The unit returned to full power at 01:55 hours on the same day. The unit operated at full power for the remainder of the month.

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UNIT SilUTDOWNS AND POWER REDUCTIONS REPORT FOR MAY,1993 DOCKET NO.

50-313 UNIT NAME ANO Unit I DATE June 2,1993 COMPLETED BY K. R_ Ilayes TELEPIIONE 501-964-5535 METIIO3 OF LICENSEE Dl1 RATION SIIUTTING DOWN EVENT SYSTEM COMPENENT CAUSE & CORRECTIVE ACTION TO M

DATE TYPE' filOURS)

REASON:

REACTOR 8 REPORT #

CODE' CODE 8 PREVENT RECURRENCE NONE 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 Licensee i

C - Refueling 3 - Automatic Scram.

Event Report (LER) File (NUREG-0161)

D - Regulatory Restriction 4 - Continuation i

E - Operator Training & License Examination 5 - Load Reduction F-Administration 9 - Other 5

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

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DATE:

May, 1993.

t REFUELING INFORMATION 1.

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

Scheduled date for next refueling shutdown.

September 5, 1993 3.

Scheduled date for restart following refueling.-November 1, 1993 l

4.

Will refue1Jng or resumption of operation thereafter require a technical specjfication 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)?

Yes, Technical Specification change to increase fuel enrichment from 3.5% to 4.1% and to reference B&W Topical Report BAW-10179P for the Core Operating Limits Report.

i 5.

Scheduled date(s) for submitting proposed licensing action and supporting information. The fuel enrichment Technical-Specification change request was submitted to the NRC on June 27, 1991 (ICAN069108).

A Technical Specification change request to reference B&W Topical Report BAW-10179P was-submitted on May 7, 1993.

i 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) 625 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 pinnned, in number of fuel assemblies.

present 968 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:

1995 (Loss of fu11 core offload capability) a..

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