1CAN029602, Monthly Operating Rept for Jan 1996 for ANO-Unit 1

Monthly Operating Rept for Jan 1996 for ANO-Unit 1

ML20149K709
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/31/1996
From:	Mims D, Whitt M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1CAN029602, 1CAN29602, NUDOCS 9602220092
Download: ML20149K709 (8)

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gl Entergy Operations, Inc.

EINTERGY-

' m sn 333 Ra;xN#, AR 72301 id 50185PA000 February 15,1996

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lCAN029602 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 -

. Washington, DC 20555

Subject:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51

- Monthly Operating Report Gentlemen:

The Arkansas Nuclear One - Unit 1 Monthly Operating Report for January 1996 is attached.

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

accordance with ANO-1 Technical Specification 6.12.2.4 and NUREG-0737, Item II.K.3.3, attached is the 1995 Annual Report of Failures and Challenges to Pressurizer Safety Valves.

.Very truly yours,

$+mh'M7A i

Dwight C. Mims Director, Nuclear Safety 4

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U. S. NRC

. February 15,1996 j

1CAN029602 Page 2 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 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Mr. George Kalman NRR Project Manager Region IWANO-1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H 3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 i

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I OPERATING DATA REPORT DOCKET NO:

50-313 DATE:

February 15,1996_

COMPLETED BY: M. S. Whitt TELEPilONE:

(50l) 858-5560 QPERATING STATUS 1.

Unit Name: Arkansas Nuclear One - Unit 1 2.

Reporting Period:

January 1-31 j

3.

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

Nameplate Rating (Gross MWe): 903 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: N/A 9.

Power Level To Which Restricted. If Any (Net MWe): N/A 10.

Reasons For Restrictions. If Any:

N/A MONTH YR-TO-DATE CUMULATIVE I 1.

Hours in Reporting Period.

744.0 744.0 185,131.0 12.

Number of Hours Reactor was Critical...

744.0 744.0 137,576.0 13.

Reactor Reserve Shutdown Hours..

0.0 0.0 5,044.0 14.

Hours Generator On-Line..

744.0 744.0 135,225.9 15.

Unit Reserve Shutdown Hours..

0.0 0.0 817.5 16.

Gross Thermal Energy Generated (MWH).....

1,836,819 1,836,819 314,310,735 17.

Gross Electrical Energy J

Generated (MWH).

638,582 638,582 105,208,627 18.

Net Electrical Energy Generated (MWH)......

611,580 611,580 100,109,794 19.

Unit Scryice Factor.

100.0 100.0 73.0 20.

Unit Availability Factor........

100.0 100.0 73.5 21.

Unit Capacity Factor (Using MDC Net)......

98.3 98.3 64.7 i.

22.

Unit Capacity Factor (Using DER Net)...............

96.7 96.7 63.6 23.

Unit Forced Outage Rate...

0.0 0.0 10.1 24.

Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of F.ach):

None 25.

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

N/A 26.

Units in Test Status (Prior to Commercial Operation):

1 None J

Forecast Achieved INITIAL CRITICALITY 08/06/74 INITIAL 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:

February 15,1996 COMPLETED BY: M. S. Whitt TELEPHONE:

(501) 858-5560 i

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3 MONTH January 19%

DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.....

855 2...

855 i

3...............................

855 4.......

854 5..............

855 6................

854 7.

854 8...................

854 9..........................

854 10............................

855 11...............................

854 12..............................

849 13..........

853 14.,

854 15......

855 16....

855 17.........................

854 18....

854 19...........................

855

20...............

854 21......

855 22..

851 23.

852 2 4.......

853 25.............................

854 2 6..............

644 27........................

516 2 8...........

539 29................

854 30...

855 31.

730 AVGS: 822 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.

UNITSHUTDOWNS AND POWER REDUCTIONS REPORT FOR JANUARY 1996 DOCKET NO.

50-313 UNIT NAME ANO Umt i DATE February 15,1996 COMPLETED BY M. S. Whitt TELEPHONE 501-858-5560 l

METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO M

DATE TYPE 8 GIOURS)

REASON 2 REACTORS REPORT #

CODE

• CODE 5 PREVENT RECURRENCE 96-41 960126 F

0 A

5 N/A SG TBG Power reductions to locate and plug leaking condenser tubes.

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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 C - Refueling 3 - Automatic Scram.

Event Report (LER) File (NUREG-0161)

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

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

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I NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

JANUARY 1996 l

UNIT ONE The month began with the unit operating at 100% power.

Power was reduced to 86% on the twelfth to perform turbine governor and throttle valve stroke testing. Following completion of the testing on the thirteenth, the unit was returned to 100%

power. Unit power was reduced to 80% on the twenty-sixth due to a tube leak in condenser waterbox E-11B. Additional condenser tube leaks were discovered and power was further reduced to 60% to allow for plugging of the tube leaks and cleaning of the waterboxes. The condenser tube leaks were plugged and a power escalation commenced on the twenty-eighth at 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br />; at 2205 hours0.0255 days <br />0.613 hours <br />0.00365 weeks <br />8.390025e-4 months <br /> main turbine governor and throttle valve stroke testing began. Power was restored to 100% following completion of the testing on the wenty-ninth. Power was decreased to 80% on the thirty-first due to a condenser tube leak in the E-11B north waterbox.

The condenser tube leak was plugged and power was returned to 100% on the thirty-first. A power reduction to 90% was initiated the same day due to problems in high pressure feedwater heater E-1B.

The unit operated the remainder of the month at 90% power.

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Reporting Period: January 1996 REFUELING INFORMATION 1.

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

Scheduled date for next refueling shutdown: Sentember 20.1996 3.

Scheduled date for restart following refueling: November 4.1996 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)?

No.No 5.

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

Nlb 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, sij ;nificant changes in fuel design, new J

operating procedures.

None olanned 7.

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

a) jl1 b)241 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 2f68 increase size by 0 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the l

present licensed capacity:

DATE:

1996 (Loss of full core off-load capability)

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ATTACIIMENT ANNUAL REPORT OF PRESSURIZER SAFETY VALVE FAILURES AND CHALLENGES J

This annual report is submitted in the January Monthly Operating Report in response to requirements implemented as a result of NUREG-0737, Item II.K.3.3 and to fulfill technical specification reporting requirements (TS 6.12.2.4).

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For ANO-1, there were no failures or challenges to the primary system code safeties or automatic actuations of the electromatic relief valve (ERV) during 1995.

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