ML20066D370

Monthly Operating Rept for Sept 1982

ML20066D370
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/15/1982
From:	Gertsch A ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20066D366	List: ML20066D364 ML20066D370
References
NUDOCS 8211110302
Download: ML20066D370 (5)

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OPERATING DATA REPORT DOCKET NO. 50-313 DATE 10-15-82 COMPLETED BY A.J. Gertsch TELEPl!ONE 501-964-3155 OPERATING STAIUS N"

1. Unit Name: Arkansas Nuclear One - Uni _t._1

2. Reporting Period: SeDtember 1-30. 1982

3. Licensed Thermal Power (MWD: 2568

4. Nameplate Rating (Gross MWei: 902.74

5. Design Electrical Rating (Net MWe): 850

6. Masimum Dependable Capacity (Gross MWe): 883

7. Masimum Dependable Capacity (Net MWe): 836 .

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7)Since Last Report. Give Reasons:

9. Power Lesel To which Restricted. lf Any (Net MWe): NONE NA

10. Reasons For Restrictions. If Any:

This Month Yr to-Date Cumulatise i1. Ilours in Reporting Period 720.0' 6551.0 68226.0

12. Number Of flours Reactor Was Critical 712.9 4813.6 47061.1

13. Reactor Resene Shutdown flou,, 0.0 0.0 5044.0

14. Ilours Generator On-Line 698.4 4738.7 46122.5

15. Unit Resene Shutdown liours 0.0 0.0 817.5 1557688.0 10326327.0

16. Gross Thermal Energy Generated IMWill 109856533.0

17. Gross Electrical Energy Generated IMWil) 460360.0 3355010.0 36191766.0 l

l 18. Net Electrical Energy Generated IMWill 434437.0. 3119919.0 34496320.0

19. Unit Senice Factor 97.0 72.3 67.6 i

l 20. Unit Asailability Factor 97.0 72.3 68.8

21. Unit Capacity Factor (Using MDC Neti 72.2 58.1 60.5

22. Unit Capacity Factor (Using DER Net) 71.0 57.1 59.5

23. Unit Forced Outage Rate 3.0 13.7 15.9

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Each):

l 25. If Shut Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIA L CRi flCAllIY INITIAL ELECIRlCi fY

( COM\lERCI AL OPER AllON l 3211110302 821015 F.DR ADOCK 05000313 i

6 PDR P/77:

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-313 _

UNIT I DATE 10-15-82 COMPLETED BY A.J. Gertsch TELEPHOAE 501-964-3155 MONTH September, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe-Net i 658 i7 643 2

642 645 18 3 642 i9 644 4 641 20 643 5 640 21 643 6 640 22 643 7

40 646 23 8 641 24 644 9 25 643 10 641 26 458

639 27 70 l 12 641 271 28 l

l 13 642 29 588 14 641 30 644 l5 641 l 3, g 642 l

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INSTRUCTIONS On this format, list the average daily unit power lesel in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

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NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- SEPTEMBER 1982 UNIT ONE Unit One began the month of September at 92.21% full power. Reduced power operations have been required since August 29, following failure of an expansion joint in the extraction line to the E-4A feedwater heater.

Subsequently, failure of an expansion joint in the extraction line to the E-3A feedwater heater has caused reactor power to be reduced to 1 approximately 87% full power. At 1705 hours0.0197 days <br />0.474 hours <br />0.00282 weeks <br />6.487525e-4 months <br /> September 26, the unit was manually tripped. Failure of the Group 6 Control Rod Drive programmer had caused Group 6 control rods to insert uncontrollably. The reactor was manually tripped to prevent exceeding rod index and imbalance limits.

Following repair of the programmer, the unit was brought on line at 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br /> September 27. Unit One ended the month at 87.44% full power.

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DOCKET NO. 50-313 UNII SHUTDOWNS AND POWER REDUCTIONS UNIT N AME ANO-Unit 1 DATE Nt a lor 7 COMPLETED BY T ('Ev+m-b REPORT MONTH (;FPTEMRFR TELEPHONE A(501T 96F3155

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- e,  : u. :

-o .5 ? s yEX Licensee ,E-to [q, Cause & Corrective No. Date 5@  ;; 25$ Event s? c.? Action to i (E 0 H

$E 5 j di g Repori #

fU Prevent Recurrence 6

82-06 820926 1 21.6 A 1 N/A IF INSTRU Group 6 Control Rod Drive programer.

failed causing group 6 to insert con-tinuously. Rx was manually tripped.

I 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data 2-Manual Scram. Entry Sheets for Licensee B-Maint<: nance of Test C Refueling 3-Automatic Scram. Event Report (LER) File (NUREG.

D Regulatory Restriction 440ntinuation 0161)

E-Operator Training & License Examination 5-Load Reduction F-Administrative 5 9-Other Exhibit I - Same Source Goperational Error (Expla!n) 03/77) Il Other (ExplainI

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UNIT SHUTDO',NS AND POWE2 REDUGIONS INSTRUGIONS This report should describe all plant shutdowns daring the in accordance with the table appearing on the report form.

report period in addition,it should be the source of explan. If category 4 must be used, supply brief comments.

ation of significant dips in average power levels. Each signi-ficant reduction in power level (greater than 20% reduction LICENSEE EVENT REPORT *. Reference the appheable in average daily power level for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) reportable occurrence pertaming to the outage or power should tie noted, even though the unit may not have been reduction. Enter the first four parts (event year, sequential shut down completelyl . For such reductions in power leva report nu.nber, occurrence code and report type) of the fne the duration should be listed as zero, the method of reduction part designation as desenbed in item 17 of Instructions for should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG4161) This inform: tion may not be Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns. of course. smer should be used to provide any needed explanation to fully further investigation may be required to ascertam whether or describe the circumstances of the outage or power reduction. not a reportable occurrence was involved.) If the outage or power reduction wdl not result in a reportable occurrence.

NUMBER. Tius column should indicate the sequential num- the positive indication of this lack of correlation should be ber assigned to each shutdown or significant reductionin power noted as not apphcable (N/A).

for that calendar year. When a shutdown or significant power SYSTEM CODE. The system in which the outage or power reduction begins in one report period and ends in another.

an entry should be made for both report periods to be sure reduction originated should be noted by the two digit code of all shutdowns or significant power reductions are reported. Exhibit G Instructions for Preparation of Data Entry Shecis Until a unit has achieved its first power generation, no num- f r Licensee Event Report (LER) File (NUREGol61).

ber should be assigned to each entry. Systems that do not fn any existing code should be designa.

ted XX. The code ZZ should be used for those events where DATE. This column should indicate the date of the start a system is not applicable.

of each shutdown or significant power reduction. Report as year, month, and day. August 14,1977 would be reported COMPONENT CODE. Select the most appropriate component as 770814. When a shutdown or significant power reduction from Exhibit I - Instractions for Preparation of Data 1.ntr>

beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG-Olot L be made for both report periods to be sure all shutdowns using the following critieria:

or significant power reductions are reported.

TYPE. Use "F" or "S" to indicate either " Forced" or " Sche-duled," respectively, for each shutdown or significant power B. If not a component failure, use the related component.

reduction. Forced shutdowns include those required to be e.g.. wrong valve operated through error; list valse as initiated by no later than the weekend following discovery component.

of an off-normal condition. It is recognized that some judg.

ment is required in categorizing shutdowns in this way. In C. If a chain of failures occurs. the first component to mal.

general a forced shutdown is one that would not have been function should be listed. The sequence of events. includ.

completed in the absence of the condition for which corrective ing the other components which fail should be described action was taken. under the Cause and Corrective Action to Prevent Recur.

rence column.

DURATION. Self-explanatory. When a shutdown extends beyond the end of a report period. count only the time to the Components that do not fit any existing code should be de-s gnated XXXXXX. The code ZZZZZZ should be used for end of the report period and pick up the ensuing down time in the following report periods. Report duration of outages events where a component. designation is not applicable.

rounded to the nearest tenth of an hour to facilitate summation.

The sum of the total outage hours plus the hours the genera. CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

tor was on line should equal the gross hours in the reporting RENCE. Use the column in a narrative fashion to amphis on penod' explain the circumstances of the shutdown or power reduction The column should include the specilie cause for each shut REASON. Categorize by letter designation in accordance down or significant power reduction and the'immediale .md with the table appearing on the report form. 11 category 11 contemplated long term correctise action taken. if ap'propo-must be used, supply brief comments. ate. This column should also be used for a description of the major safety.related corrective maintenance performed during METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction induding an identification of REDUCING POWER. Categorite by number designation the critical path aetmty and a report of any smgle release of radioactivity or single radiation esposure specifically associ-INote that this ditters from the Edison Electric institute sted with the outage whah accounts for more than 10 percent (EEI) definitions of " Forced Partial Outage" and " Sche. of the allowable annual values.

daled Partial Outage " For these terms. EEI uses a change of For long textual reports continue narrative on separate paper 30 MW as the break pomt. For larger power reactors. 30 MW and reference the shuidown or power reduction for thi>

is too small a change to warrant explanation. narrative.

t REFUELING INFORMATION 1.- Name of facility. Arkansas Nuclear one - Unit 1

2. Scheduled date for next refueling shutdown. November 26. 1982

3. Scheduled date for restart following refueling. February 15. 1993

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 these be?

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine s

whether any unreviewed safety questions are associated with the

core reload (Ref.10 CFR Section 50.59)?

i Yes. Reload report and associated proposed Soecification chanaes.

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

", supporting information. Novanhpr 15.1QR9 r

6. Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or 4 performance analysis methods, significant changes in fuel design, '

l new operating procedures.

i Will reload 72 fresh fuel assemblies. four of which will be j hiah burn-up test assemblies. and operate 'ca aooroximately 16 months.

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7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 244

8. The present licensed spent fuel pool storage capacity and the size 4

of any increase in licensed storage capacity that has been requested i or is planned, in number of fuel assemblies.

present 589 increase size by 379

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

DATE: 1936

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