ML20027E750

Monthly Operating Rept for Nov 1981.Narrative Summary Encl

ML20027E750
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/14/1981
From:	Bramlett L, Gertsch A ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20027E748	List: ML20027E747 ML20027E750
References
NUDOCS 8211150684
Download: ML20027E750 (6)

Text

,

OPER ATING DATA REPORT DOCKET NO.

DATE 12/14/81 CO.\lPLETED BY Bramlett TELEPliONE 501-961.3145 OPERAlING STAT US Notn

1. Unit Name:

Arkansas Nuclear One - Unit 1 .

2. Reporting Period: .llo31mb_er 1-30.1981

3. Licenwd Thermal Power (AlWI): __2568

4. Nameplate Rating (Gross AlWe):

902.74 850 s

5. Design Electrical Rating (Net alWet

6. 31asimum Dependable Capacity (Gross alWe):

7. Alasimu.n Dependable Capacity (Net blWe)-

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

None .

None

9. Power Lesel To Which Restricted. lf Anv (Net htWen

10. Reasons For Restrictions. If Any: WA

't i

This 51onth Yr.-to-Date Cumulatise 720.0_ 8016.0 60931._q

11. liours in Reporting Period 41503.5 ,

720.0 5713.2

12. Number Of flours Reactor Was Critical 149.0 5044.0-T I 13. Reactor Resene Shutdown flour, 0.0 770 0 5594.R 40639 8 -

14. liours Generator On-Line 817.5

15. Unit Resene Shutdown llour, 0. 0 _ 0.0 1700636. 13644729. 97816695. -

16. Gross Thermal Energy Generated 151Wil)

17. Gross Electrical Energs Generated 131Wil, 575490. 4559645. _ .32258206..

547804. . 4349784. 307;5423.

l 18. Net Electrical Energy Generated th!Wlil 69.8 66.7 100.0 l

19. Unit Senice Factor 100.0 69.8 68.0

20. Unit Asailability Factor 60.4 9I.U 64.9

21. Unit Capaciay Factor (Using SIDC Net) 39.4 89.5 63.8_

22. Unit Capacity Factor (Using DER Net) 0.0 10.0 ifLa

23. Unit Forced Outage Rate -

24. Shutdowns Scheduled Oser Next 6 51onths (Type.Date.and Duration of Eacht:

l None -

9

25. If Shot Down At End Of Report Period. Estimated Date of Startap: s

26. Units In Test Status (Prins to Commercial Operationi: Forecast Achiesed INITI A L CRITICA LITY .__

INITIAL ELECTRICITY ,

CO\l%1ERCI AL OPER A TION

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~

l t f'PDR ADOCK8211'150694

} 03000313 Bi1215 c /77:

l R PDR y

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] AVER AGE DAILY UNIT POWER LEVEL i

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g DOCKET NO. _50-313 _

t, ( UNIT I DATE I2/l4/8I

, CO4tPLETED BY L. S. Bramlett 7 ELEP!10NE __.501-964-3145 P

MONfy _ November DAY AVERAGE OAhY POWER LEVEL' DAY AVER AGE DAILY POWER LEVEL eiwe.sco iuWe.sen 1 752 i7 747 2 747 762 is 3 741 i, 756 762 4 741 20 5 750 / -

770 6 '768 .

22 767 .

7 771 33 765 s 768 764 24 9- 772

, 25 765 to 760 26 762

! 11 781 758 27

12 7R7 754

- 28 782 -

752 13 __

( 39 l 14 .. 777 727

+,

30

\

IS 774 3: N/A I

16 747 l

INSTRUCTIONS On this inimat, list the ascNte daily' unit pimer lesclin MWe Net for each day in the seporting snanth. Lumpuie to the nearest whole mefawait;

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(M /77 I p .

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- e NRC HONTHLY OPERATING REPORT OPERATING

SUMMARY

- NOVEMBER, 1981 UNIT 1 Unit 1 began the month at 91.03% full power. The-Unit is in a power limited condition due to the fouling of the "A" Steam Generator. Periodic power adjustments have been required throughout the month to prevent flooding of the feedwater nozzles. Unit 1 ended the month at 87.81% full power with further power reductions anticipated.

1 I, .

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DOCKET NO. 50-313 UNIT SHUTDOWNS AND POWER REDUCTIONS ANO-LNIT 1 UNIT NAME DATE DECEMBER 2.1981 COMPLETED BY _A. J GER'lbCH REPORT MONTH NOVEMBER TELEPHONE 501-964-3155 I .

- ,, =. c

. .i ? g fs x Lkensee ,E-r, E * '1, Cause & Correctne No. Date g 3g 4 ,3 g 5 Event v7 S3 Action to H

$E 5 Report :r rN0 Prevent Recurrence j5 fU C

NONE l

i 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 Repor (LER) File (NUREG-D Regulatory Restriction 4-Continuation 0161)

E-Operator Training & Ucense Examination 5-Load Reduction F Administrative $

G-Operational Error (Explain) 9-Other Exhibit I - Same Source 08/77) Il Other (Explain)

. 6

UNIT SHUTDONNS AND POWER REDUCTIONS ,

INSTRUCTIONS This report should describe all plant shutdowns during the in accerdance 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 ar. Reference the applicable ficant reduction in power level (greater than 20% 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 />) 'ePortable occurrence pertaining to the outage or power should b'e noted, even though the unit may not have been reduction. Lnter the first four parts (event year sequential shut down completely l. For such reductions in power level, 'eport number, occurrence code and report type) of the ine the duration should be listed as zero, the method of reduction part designation as described in item 17 of Instructions for should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Lvent Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG-0161). This information may not he immediately evident for all such shutdowns. of course, smce Cause and Corrective Action to Prevent Recurrence column further investigation may he required to ascertain 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 involved.) 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 noted 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 an entry should be made for both report periods to be sure Exhibit G Instructions for Preparation of Data Entry Sheets all shutdowns or significant power reductions are reported.

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

Until a unit has achieved its first power generation, no num-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 r$ot 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 cignificant power reduction from Exhibit I - Instructions for Preparation of Data Entr.s beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG-Olet 1.

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" cr " 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 errer: hst valve 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-j t

rence column.

DURATION. Self-explanatory. When a shutdown extends Components that do not fit any existing 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 (m end of the report period and pick up the ensuing down time esents where a component. designation is not applicable.

m the following report periods. Report duration of outages rounded to the nearest tenth of an hour to facilitate summation. CAUSE & CORRECTIVE ACTION TO PRFVENT RECUR-The sum of the total outage hours plus the hours the genera- RENCE. Use the column in a narrative fashion to amplifs m '

i tor was on line should equal the gross hours m the reportmg expla n the circumstances of the shutdown or power reduction .

j paiod. The column should include the specific cause for each shui I . . down or significant power reduction and the immediate and l REASON. Categorige by letter designation m accordance contemplated long term corrective action taken. if appropo.

with the table appearmg 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 Juring the outage or power reduction including an identification of METHOD OF SHUTTING DOWN THE REACTOR OR the critical path activity and a report of any single release of REDUCING POWER. Categorite by number designation radioactivity or single radiation exposure specifically associ-I Note that this ditters from the Edison ESetric institu; ated with the outage which accounts for more than 10 percent (EEI) definitions of " Forced Partial Outage" and "S/ .. of the allowable annual values.

doled Partial Outage." For these terms. eel 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 shuidown or power reduction for this is too small a change to warrant explanation. narrative.

L

REFUELING INFORMATION

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

2. Scheduled date for next refueli % shutdown. 1/1/83

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

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

4 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 determin5 whether any unreviewed safety questions are associated with the i

core reload (Ref. 10 CFR Section 50.59)?

Yes. Reload report and associated proposed Technical Specification l chances. 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 i

j 16 months. $lght of which will be high burn-up test assemblies.

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, a) 177 b) 244 l 8. The present licensed spedt fuel pool storage capacity and the size

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

present 589 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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