ML19323J290

Monthly Operating Rept for May 1980

ML19323J290
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/13/1980
From:	Bramlett L ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19323J287	List: ML19323J286 ML19323J290
References
NUDOCS 8006190689
Download: ML19323J290 (7)

Text

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AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-313 UNIT _ ANO-1 DATE 6/13/80 COMPLETED BY L.S.Bramlett TELEPHONE 501/968-25_19 MONT11 May, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL Dlhe Net) ty We.Seg; I 0 0-37 2 0 is 0 3 0 39 0 4 0 0 20 36 5

0 6 294

0 645 0 23 s 665 0 24 9 668 0 25 10 71 0 26

0 77 o

0 ;3 o 13 0 0 29 14 0 0 30 15 0 o 3,

16 0 INSTRUCTIONS On this format.hst the ase age dal) unit power leselin MWe Net for caeh day in the reporting month. Compute the nearest whole mepwan.

(9/77 )

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OPERATING DATA REPORT DOCKET NO. 50-313 DATE 6/13/80 COMPLETED BY L . S . B raml e t, *,

TELEPHONE 501/968-2519 OPERATING STATUS N '"

1. Uni Name: Arkansas Nuclear One - Unit 1

2. Reporting Period: May 1-31, 1980

3. Licen ed Thermal Power (MWt): 2568

4. ' Nameplate Rating (Gross MWel: 902.74

5. Design Electrical Rating (Net MWe) 850

6. Maximum Dependable Capacity (Gross MWe):

883

7. Masimum Dependable Capacity (Net MWel: 836

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

None

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

10. Reasons For Restrictions.lf Any: NA This Month Yr.-to-Date Cumulatise

11. Hours In Reporting Period 744.0 3647.0 47778.0

12. Number Of Hours Reactor Was Critical 128.7 1710.4 31848.6

13. Reactor Reserve Shutdown Hours 90.2 464.8 4712.2

14. Hours Generator On Line 109.3 1671.6 31142.1

15. Unit Rewne Shutdown Hours 0.0 20.8 817.5

16. Gross Thermal Energv Generated IMWH) 201913.0 3844695.0 75106739.0

17. Gross Electrical Energy Generated MWH) 60927.0 1198925.0 24920081.0

18. Net Electrical Energy Generated IMWH1 57078.0 1140353.0 23774389.0

19. Unit Senice Factor 14.7 45.8 65.2

20. Unit Availability Factor 14.7 46.4 66.9

21. Unit Capacity Factor (Using MDC Net, 9.2 37.4 59.5

. 22. Unit Capacity Factor IUsing DER Neti 9.0 36.8 58.5

23. Unit Forced Outage Rate . 82.8 28.0 16.4

24. Shutdowns Scheduled Over Next 6 Months IType. Date,and Duration of Eacht:

25. If Shut Down At End Of Report Period. Estimated Date of Startup: June 6. 1980

' 26. Units In Test Status Prior to Commercial Operation): Forecast Achiesed INIIIA L CRITICALITY INITIAL ELECTRICITY

.COMMERCIA L OPER ATION to/77 6 1

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, I UNIT SilUIDOWNS AND POWER REDUCTIONS IXK KE I NO. sn t11 - i.

UNIT NAME ANO lin{t'T DATE 6-13-80 l'04PLETED BY 1.- e_ nro.i .e c .

HEPOR T h!ONTil _.Eay TELEPilONE 501-968-2519 e.

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-, .i ?  ;- Lwensee ,E -r, No. Date- i 5? 5 .5 s 5 . Event UT s.] . Action so H

fE E = Repunt: EU i Present Recurrence 3 gg !

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80103 800419 s 105.35 F 1 NONE ZZ ZZZZZ The outage was administrative 1y. ,

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authorized for economic reasons.

80-04 800505 S 4.11 B . NONE ZZ ZZ Turbine overspeed trip. test. ,

80-05' 800510 F 525.22 A 1 NONE CA Pumpxx "C" RCP seal failure.

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• l': I onced Reason: hie hod: Eslabit G - Insrenetions S: Sched uleil A-l'iguipment I ailure(Expland 1 -Man ual for Picparanon of Dat.:

[1-Maintenance of Test 2 Manual Sci.un. Ents) Shecis for 1.iernsee C-Refueling 4-Autornath Scram. 1: vent Reposi (Lt R) l'ile (NURLG-D-Regul.is o 3 Restriction Oa her i thplain) 0161)

I? Operator Tsaining11 henw Euininaison F Adnunistraine 5 G Op. e.stion.d L ia (lapi.eSi) I sinbit I - S.nns Suztee i*" ' 4 II Ot her il% plain)

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REFUELING INFORNATION 1

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

2.. Scheduled date for next refueling shutdown. 1/1/81

3. Scheduled date for restart following refueling. 3/1/81 __

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

Yes. reload recort and associated proposed Technical Soecification changes. Also, the safety analysis of four demonstration high burn-uo assemblies will be provided.

5. Scheduled date(s) for submitting preposed licensing action and supporting information. 10/1/80

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

new or different fuel design or supplier, unreviewed design or performance analysis mechods, significanc changes in fuel design, new operating procedures.

Will reload 68 fresh fuel assemblies and operate for approximately 16 months. Four of which will be hiah burn-uo test assemblies.

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, a) 177 b) 176

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 590 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

c,. .

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- MAY 1980 UNIT I The. unit began ths month in the cold shutdown mode to complete 80-03 outage work. The unit' was . tied on line May 5~ and af ter 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> of operation the unit was taken off line for the turbine over speed trip test. The test was Leompleted satisfactorily on May 5 and the unit was placed back on line the same day. The unit operated until

'May 10, when it'was taken off line due to the failure of "C" reactor coolant pump seal. The unit was down the remainder of the month for repair and preventive maintenance work on reactor coolant pumps.

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ARKANSAS NUCLEAR ONE - UNIT I Periodic Core _ Power Distribution Comparison

. A Radial Power Distribution comparison was performed at 156.2 EFPD.

The RMS (root .mean square) of. the differences between measured and

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predicted at the 52 instrumented fuel assembly locations was 0.028 which is well within the acceptance criterion of 0.073.

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