2CAN058605, Monthly Operating Rept for Apr 1986

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Monthly Operating Rept for Apr 1986
ML20207C247
Person / Time
Site: Arkansas Nuclear 
Issue date: 04/30/1986
From: Enos J, Harrison D
ARKANSAS POWER & LIGHT CO.
To: Bassett H
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
2CAN058605, 2CAN58605, NUDOCS 8607210309
Download: ML20207C247 (6)


Text

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OPERATING DATA REPORT DOCKET N0:

50-368 DATE:

April, 1986 COMPLETED BY:D. F. Harrison TELEPHONE:

(501)964-3743 OPERATING STATUS 1.

Unit Name:

Arkansas Nuclear One - Unit 2 2.

Reporting Period:

April 1-30, 1986 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 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 MONTH YR-T0-DATE CUMULATVE 11.

Hours in Reporting Period...

7I9 0 2,879.0 53,447.0 12.

Number of Hours Reactor was Critical.....................

683.3 2,799.0 38,435.7 13.

Reactor Reserve Shutdown Hours........................

0.0 0.0 1,430.1 14.

Hours Generator On-Line......

663.3 2,777.5 37,213.2 15.

Unit Reserve Shutdown Hours..

0.0 0.0 75.0 16.

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

1,810,739.0 7,711,679.0 94,749,030.0 17.

Gross Electrical Energy Generated (MWH)..............

601,385.0 2,571,809.0 31,061,051.0 18.

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

572,640.0 2,456,111.0 29,565,645.0 19.

Unit Service Factor...

92.3 96.5 69.6 20.

Unit Availability Factor.....

92.3 96.5 69.8 21.

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

92.8 99.4 64.5 22.

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

87.3 93.5 60.7 23.

Unit Forced Outage Rate......

7.7 3.5 15.9 24.

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

A 7 week refueling outage is scheduled to begin June 13, 1986.

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 INITIAL ELECTRICITY COMMERCIAL OPERATION

~

TEcW 8607210309 860430 2DR ADOCK 0500 8

/

l

AVERAGE DAILY UNIT POWER LEVEL DOCKET N0:

50-368 UNIT:

Two DATE:

April, 1986 COMPLETED BY: D. F. Harrison TELEPHONE:

(501)964-3743 MONTH April DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.............

894 2.............

895 3............

892 4.............

890 5.............

870 6.............

893 7............

890 8.............

896 9............

900 10............

898 11............

897 12............

896 13...........

894 14...........

896 15...........

897 16............

897 17..........

894 18............

891 19............

890 20............

895 21............

183 22............

36 23............

765 24...........

891 25............

890 26...........

605 27............

57 28............

798 29............

888 30............

886 31............

AVGS:

796 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for each day in reporting month.

Compute to the nearest whole megawatt.

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

APRIL 1986 UNIT TWO The unit began the month at 100% power.

At 0532 hours0.00616 days <br />0.148 hours <br />8.796296e-4 weeks <br />2.02426e-4 months <br /> on the twenty-first, the unit tripped following the loss of "D" reactor coolant pump due to an electrical short while replacing a light 1

bulb at the remote shutdown panel.

The unit was placed back on line at 1426 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.42593e-4 months <br /> on the twenty-second and reached 100% power on the twenty-third at 1325 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.041625e-4 months <br />.

At 1628 hours0.0188 days <br />0.452 hours <br />0.00269 weeks <br />6.19454e-4 months <br /> on the twenty-sixth, the unit tripped following the loss of "D" reactor coolant pump due to a failed starting surge capacitor.

The unit was placed back on line at 1616 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.14888e-4 months <br /> on the twenty-seventh and reached 100%

power at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on the twenty eighth, where it remained through the end of the month.

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR APRIL, 1986 DOCKET N0 50-368 UNIT NAME ANO Unit 2 DATE April, 1986 COMPLETED BY D. F. Harrison TELEPHONE T501)964-3743 i

Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to No.

Date Type (Hours)

Reason 2 Down Reactor 3 Report #

Code 4 Code 5 Prevent Recurrence l

8603 860421 F

32.9 A

3 2-LER-86-04 AB IL Unit trip following loss of "D" reactor coolant pump.

The pump tripped due to an electrical short while replacing a light bulb at the remote shutdown panel.

8604 860426 F

22.8 A

3 2-LER-86-07 AB CAP Unit trip following loss of "D" RCP due to a faile.

starting surge capacitor.

The capacitor was replace.

and the unit returned to power.

1 2

3 4

F:

Forced Reason:

Method:

Exhibit G - Instructions 5:

Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram.

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

Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Continuation 1022)

E-Operator Trainir.g &

5-Load Reduction License Examination 9-0ther 5

F-Administrative Exhibit I - Same Source G-Operational Error (Explain)

H-Other (Explain) 4 1

e

DATE:

April, 1986 REFUELING INFORMATION 1.

Name of facility:

Arkansas Nuclear One - Unit 2 2.

Scheduled date for next refueling shutdown.

Cycle 5 was initiated in May 1985.

The next refueling shutdown is scheduled for June 1986.

3.

Scheduled date for restart following refueling.

August 1986 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 t

questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

Yes.

A Tachnical Specification change on negative moderator l

temperature coefficient has been submitted.

Included in the change j

request are changes in shutdown margin and in Refueling Water Tank

{

temperature.

5.

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

The Technical Specification change request was submitted in April.

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.

The fresh fuel will have a modification to the CEA guide tube wear sleeves which has been reviewed.

(Ref. SER dated September 7, 1984 for C-E Report LD-84-043).

A Mnger cycle and a change in in-core fuel management from out-in-in to in-in-out are also planned. When pending Technical 5)ecification chenges are approved, we expect te install a revised C)C program during Cycle 5.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel j

storage pool.

a) 177 b) 289 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:

2003

ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK ARKANSAS 72203 (501) 371-4000 May 15, 1986 2CAN058605 Mr. Harold S. Bassett, Director Division of Data Automation and Management Information Office of Resource Management U. S. Nuclear Regulatory Commission Washington, D. C.

20555

SUBJECT:

Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Monthly Operating Report

Dear Mr. Bassett:

The Arkansas Nuclear One - Unit 2 Monthly Operating Report for April 1986 is attached.

Very truly yours, i

J. Ted Enos, Manager Nuclear Engineering and Licensing JTE:MCS:sg Attachment cc:

Mr. Robert D. Martin Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Mr. James M. Taylor, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 jk MEMBEA MIDOLE SOUTH UTauTIES SYSTEM l

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