ML20066E412

Monthly Operating Rept for Oct 1981.Narrative Summary Encl

ML20066E412
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/10/1981
From:	Bramlett L ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20066E403	List: 1CAN118103, Forwards Monthly Operating Rept for Oct 1981 ML20066E412
References
NUDOCS 8211150160
Download: ML20066E412 (6)

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OPERATING DATA REPORT 50-313 DOCKET NO.

DATE 11/10/81 COMPLETED BY I

S Bramlett TELEPHONE M01) 9fi4-3155 OPERATING STAT US N"

Arkansas Nuclear One - Unit 1

1. Unit Name:

October 1 - 31, 1981

2. Reporting Period:

68

3. Licensed Thermal Power (MWr):

4. Nameplate Rating (Gross MWe):

850

5. Design Electrical Rating (Net MWe):

883

6. Maximum Dependable Capacity (Gross MWe):

836

7. Maximum Dependable Capacity (Net MWe):

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

None None

9. Power LevelTo Which Restricted. If Anv (Net MWe):

N/A

10. Reasons For Restrictions. If Any:

This Month Yr..to Date Cumulatise 745.0 7296.0 60211.0 II. Ifours in Reporting Period 745.0 4993.2 40783.5

12. Number Of liour, Reactor was Critical 149.0 5044.0 0.0

13. Reactor Resene Shutdown flours 745.0 4874.8 39919.8

14. Ilours Generator On-Line 0.0 0.0 817.5 I

15. Unit Resene Shutdown flours 1784533.

11944093.

96116059.

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16. Gross Thermal Energy Generated (MWill 603305.

3984155.

31682716.

17. Gross Electrical Energy Generated (MWill 574809.

3801980.

30217619.

18. Net Electrical Energy Generated (MWill 100.0 66.8 66.3

19. Unit Senice Factor 100.0 66.8 67.7

20. Unit Availability Factor /

2.3 62.3 60.0

21. Unit Capacity Factor (Using MDC Neti

22. Unit Capacity Factor (Using DER Net)/

90.8 61.3 59.0 0.0 11.3 16.6

23. Unit Forced Outage Rate y

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

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

26. Units in T est Status (Prior io Commercial Operationi:

Forecast Achicied INITI A L CRITICA LITY INITIAL ELECTRICITY CO\\lMERCI AL OPER ATlON 8211150160'811'110

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AVERAGE D AILY UNIT POWER LEVEL.

50-313 DOCKET NO.

UNIT I

11/10/81 DATE CON 1PLETED By L. S. Bramlett 501-964-3155 TELEPHONE MONm October DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

IMwe-Net )

1 792 17 768 2

790 is 769 789 767 3

9 4

7RR 20 764 785 764 5

21 6

783 22 762 7

783 23 759 g

783 760 24 759 9

783 25 760 10 781 26 779 760 l

3j 27 12 7An 28 760 t

l 13 776 755 29 l

775 754 34 30 753 15 772 3

16 769

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INSTRUCTIONS On this format.hst the ascrage daily unit pimer levelin MWe Net for each day in the reporting month. Compute io the nearest whole megawait.

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NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- OCTOBER, 1981 UNIT I Unit I began the month at 96.19% full power. The unit is in a power limited condition due to fouling of the "A" Steam Generator.

Periodic power reductions have been required throughout the month to prevent flooding of the feedwater nozzles. Unit I ended the month at 91.18%

full power with further power reductions anticipated.

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UNIT SHUTDO5NS AND POWER REDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns during 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-LICENSEE EVENT REPORT :r.

Reference the applicable ficant reduction in power level (greater than 207c reduction 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 pertaining to the outage or power reduction. Enter the first four parts (event year, sequential should b'e noted, even though the unit may not have been shut down completely. For such reductions in power level, report number, occurrence code and report type) of the the l

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 Er,try Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG-0161). This information may not be Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns. of course. since further investigation may be required to ascertam whether or should be used to provide any needed explanation to fully describe the circumstances of the outage or power reduction.

n t a reportable occurrence was mvolved.) If the outage or power reduction 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 n ed as not applicable (N/A).

ber assigned to each shutdown or significant reductionin power 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.

reduction originated sh'ould be noted by the two digit code of

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an entry should be made for both report periods to be sure Exhibit G -Instructions for Preparation of Data Entry Sheets all shutdowns er significant power reductions are reported.

for Licensee Event Report (LER) File (NUREG-0161).

Until a umt has achieved its tirst power generation, no num-ber should be assigned to each entry.

Systems that do not fit any existing code should be designa-id XX. Ti e code ZZ should be used for those events where l

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 componem as 770814. When a shutdown or significant power reduction from Exhibit 1 - Instructions for Preparation of Data Entry beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG-OlolI.

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-

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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 vahe operated through error; hst valve as initiated by no later than the weekend following discovery component.

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

l completed in the absence of the condition for which corrective ng 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 Components that do not fit any existirg code should be de.

beyond the end of a report period. count only the time to the signated XXXXXX. The code ZZZZZZ should be used for end of the repori period and pick up the ensuing down time events where a component. designation is not applicable.

in the following report periods. Report duration of outages l

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

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-The sum of the total outage hours plus the hours the genera-RENCE. Use the column in a narrative fashion to amplif or 3

tor was on hne should equal the gross hours m the reporting expla n the circumstances of the shutdown or power reducuon pnd The column should include the specific cause for each shut.

down or significant power reduction and the ~immediate.mJ REASON. Categorize by letter designation in accordance contemplated long term corrective action taken. if appropo-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 the outage or power reduction including an identification of MET 110D OF SilUITING DOWN Tile REACTOR OR the critical path activity and a report of any single release of REDUCING POWER. Categori/e by number designation radioactivity or single radiation exposure specifically. associ-INote that this datters from 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. EEI uses a change of For long textual reports continue narrative on separate paper 30 MW as the break point. For larger power reactors.30 MW and reference the shutdown or power reduction for this is too small a change to warrant explanation.

narrative.

REFUELING INFORMATION

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1..

Name of facility.

Arkansas Nuclear One - Unit 1 2.

Scheduled date for next refueling shutdown. 1/1/83 1

3.

Scheduled date for restart following refueling. 3/15/83 l

4.

Will refueling or resumption of operation thereafter require a

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technical specification change or other license amendment?

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

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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.

Reload report and associated proposed Technical 1

Specification changes. Also, the safety analysis of eight demonstration high burn-up assemblies will be provided.

5.

Scheduled date(s) for submitting proposed licensing action and supporting information. 10/1/82 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.

Will reload 72 fresh fuel assemblies and operate for approximately 16 months.

Eight of which will be high burn-up test assemblies.

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The number of fuel assemblies (a) in the core nnd (b) in the spent fuel storage pool.

a) 177 b) 244 l

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The present licensed spent fuel pool storage capacity and the size l

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

present SRQ 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:

1986

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