ML20073F710

Monthly Operating Rept for Feb 1983

ML20073F710
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/15/1983
From:	Gertsch A ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20073F698	List: 1CAN038302, Forwards Monthly Operating Rept for Feb 1983 ML20073F710
References
NUDOCS 8304150530
Download: ML20073F710 (5)

Text

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OPERAIING DATA REPORT DOCKET NO. 50-313 DATE 3/3/83 COMPLETED BY A.J. Gertsch TELEPilONE 501-964-3155 OPERATING STATUS N"

1. Unit Name: Arkansas Nuclear One - Unit 1

2. Reporting Period: February l-28, 1983

3. Licensed Thermal Power (MWtp: 2568

4. Nameplate Rating (Gro s MWe):

902.74 850

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

883 836

7. Masimum Dependable Capacity (Net MWe):

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

9. Power Lesel To Which Restricted. lf Any (Net MWe): None

10. Reastms For Restrictions. If Any:

This Month Yr..to.Date Cumulatise i1. Ilours In Reporting Period 672.0 1416.0 71851.0

12. Number Of flours Reactor has Critical 0.0 0.0 4g007.3

13. Reactor Rewne Shutdown flours 0.0 0.0 5044.0

14. Itours Generator On Line nn 0.0 47057.5

15. Unit Resene Shutdown liours 0.0 0.0 817.5

16. Gross Thermal Energy Generated (MWlh 0.0 _., 0.0 111769814.

17. Gross Electrical Energy Generated tMWill 0.0 0.0 36765044.

18. Net Electrical Energy Generated (Mbill 0.0 0.0 35037810.

19. Unit Senice Factor 0.0 0.0 65.5

20. Unit Asailability Factor 0.0 0.0 66.6

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 58.3

22. Unit Capacity Factor (Using DER Net) 0.0 0.0 57.4

23. Unit Forced Outage Rate 0.0 0.0 15.6

24. Shutdowns Scheduled Oser Nest 6 Months tType, Date.and Duration of Each t:

Unit now in scheduled refueling outage which began November 8,1982.

25. If Shut Down At End Of Report Period. Estimated Date of Startup: March 15, 1983

26. Units in Test Status IPrior to Commercial Operationi: Forecast Achiesed INiil \ L CRITICA LITY INITI AL ELECTRICITY CO\l%IERCIAL OPER ATION NO4150530 830315 PDR ADOCK 05000313 to/77)

R PDR

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

UNIT I DATE 3/15/83 COMPLETED BY A.J. Gertsch TELEPHONE 501-964-3155 MONTH Fa brita rv . 19R3 1

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

I O 17 0 2 0 18 0 3 0 i9 0 __

i 4 0 20 0 5 0 21 0 l 6 0 22 0 7

0 0 23 0 0 8 24 9 0 25 0 10 0 0 l 26 0 0 II 27 i 12 0 28 13 0 y, o l

0 0 14 3g 0

15 3l 16 0 I

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

l (9/77) d e

,- - , . , - . , - - . .- -.--m.n , a _ - ,. .. ,, , , . _ . - , - , - . , - ,, ,-

r NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- FEBRUARY 1983 UNIT 1 The unit remained shutdown the entire month for the 1-R5 refueling outage.

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s DOCKET NO. 50-313 UNII SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Ai,0-Unit 1 DATE 3/3/83 COMPLETED BY A .1 Gartech REPORT MONTil February TELEPHONE E01 0AA-3155 "t

- =

j? 3 j ~$ 5 Licensee j-t, t j?

Cause & Corrective No . Date ~g 4 2 $ Event 77 a Action to t rE R L

• y, - 5 jf Report a Prevent Recurrence c

82-07 821108 5 672.0 C 4 N/A N/A N/A 1-RS Refueling Outage 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. Entr> Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D Regulatory Restriction 4 Continuation 0161)

E-Operator Training & License Examination 5-Load Reduction 5

F Administrative 9-0ther Exlubit I - Same Source G-Operational Error (Explain) c)/77) Il-Other (Explain)

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UNIT SHUTDONNS AND POWER REDUCTIONS t .

INSTRUCTIONS This report should describe all plant shutdowns during the m accordance with the tai,le appearing on the report toim.

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 20'7e reduction LICENSEE EVENT REPORT :r. Reference the rppheable 4 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 pertaimng to the outage or power should b'e 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 level, report number, 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 2

should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Event Report i Action to Prevent Recurrence column shoull explain. The (LER) File (NUREG-0161) This information may not be Cause and Corrective Action to Prevent Recurrence column immediately evident foi all such shutdowns. of course, smce should be used to provide any needed explanation to fully further investigation may be required to ascertam whether or describe the circumstances of the outag'e or power reduction. not a reportable occurrence was involved.) If the outage or i power reductmn will not result in a reportable occurrence.

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

for that calendar year. When a shutdown or significant power SYSTEM CODE. The system m which the outage or power reduction begms 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 i all shutdowns or significant power reductions are reported. Exhibit G Instructions for Preparation of Data Entry Sheets Until a unit has achieved its first power generation, no num- f r Licensee Event Report (LER) File (NUREG.0161).

ber should be assigned to each entry.

Systems that do not fit 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 1 as 770814. When a shutdown or significant power reduction from Exhibit I instractions for Preparation of Data Ento l begmsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NURLG-01of L

be made for both report periods to be sure all shutdowns using the following critieria; I

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 I reduction. Forced shutdowns include those required to be e.g.. wrong valve operated through error; list sahe 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 sequente of events. includ-

! completed in the absence of the condition for w hich corrective ing the other components which fait should be described action was taken. under the Cause and Corrective Action ta 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-j signated XXXXXX. The code ZZZZZZ should be used for q end of the report period and pick up the ensuing down time m the followmg report penods. Report duration of outages events where a component. designation is not appheable.

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! roemded to the nearest tenth of an hour to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-l The sum of the total outage hours plus the hours the genera-RENCE. Use the column in a narrative fashion to amphti or 1

tor was on hne should equal the gross hours in the reportmg '

explain the circumstances of the shutdown or power reduction penod.

, The column should include the specilie cause for each shui j down or significant power reduction and the nnmediate and REASON. Categorite by letter designation in accordance contemplated long term corrective action taken. il appropo-j with the table appearing on the report form. If category 11 ate. This column should also be used for a description of the

must be used, supply brief comments.

major safety.related corrective maintenance performed dunng METHOD OF SHUTTING DOWN Tile REACTOR OR the outage or power reduction including an identification of l REDUCING POWER. Categonic 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 ditfers f rom the Edison Electric Institute ated with the outage which accounts for more than 10 percent (EEI) definitions of " Forced Partial Outage" and " Sche. of the allowable annual values.

dated Partial Outage.' For these terms. eel uses a change of For long textual reports continue narratrve on separate paper 30 MW as the break point. For larger power reactors. 30 MW and reference the shutdown or power reduction for ihn is too small a change to warrant explanation. narrative.

DATE: February,1983 t

REFUELING INFORMATION

1. Name of facility. Arkansas Nuclear One-Unit 1 I 2. Scheduled date for next refueling shutdown. September 15, 1984

3. Scheduled date for restart following refueling. December 15, 1984 i

4. Will refueling or resumption of operation thereafter require a i technical specification change or other license amendment?

. If answer is yes, what, in general, will these be?

i If answer is no, has the reload fuel design and core configuration l 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)?

i Yes. Reload report and associated proposed specification change.

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5. Scheduled date(s) for submitting proposed licensing action and supporting information. September 1, 1984

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.

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To be detennined 1

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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) 316

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

of any increase in licensed storage capacity that has been requested

or is planned, in number of fuel assemblies.

j present Sag increase size by 379 I

9. The projected date of the last refueling that can be discharged ,

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to the spent fuel pool assuming the present licensed capacity. '

DATE: Igno 1

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