ML19253C245

Forwards Monthly Operating Rept for Oct 1979

ML19253C245
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/14/1979
From:	Trimble D ARKANSAS POWER & LIGHT CO.
To:	Haller N NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA)
Shared Package
ML19210C945	List: ML19210C944 ML19253C245
References
NUDOCS 7911300329
Download: ML19253C245 (1)

Text

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ARKANSAS FOWER & LIGHT COMPANY POST OFFICE BCX 551 LIT 1E ROCK. ARKANSAS 72203 (501) 371-4000 November 14, 1979 l-119-7 Mr. No rman M. Haller, Director Of fice of Management and Program Analysis U. S. Nuclear Regulatory Con::nission Washington, D. C. 20555

Subject:

Arkansas Nuclear One-Unit 1 Docket No. 50-313 License No. DPR-51 Monthly Operating Report (File: 0520.1)

. Gentlemen:

Attached find the Monthly Operating Report for October, 1979, for Arkansas Nuclear One - Unit 1. Also attached is the 30 EFPD interval report of Core Power distribution RMS values as required per our submittal of April 26, 1979, ( Re f . 1-049-16).

Very truly yours,

.%a e. sa David C. Trimble Manager, Licensing DCT /DVH /ew Attachments cc: Mr. K. V. Seyfrit, Director Office of Inst.ection and Enforcement U.S. Nuclear Regula tory Commi ssion ,

Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Mr. Victor Stello, Jr., Director '

Office of Inspection & En f orc ement 1440 523 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 7 9113 00 3M \

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MEMeEA MooLE south UTIUTIES SYSTEM _['

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AVER AGE DAILY UNIT POWER LEVEL

0 DOCKET NO. 50-313 UNIT ANO Unit-1 DATE 11/l4/79 L. S. Bramlett COMPLETED BY TELEPHONE 501/968-2519 MONTH October 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe NetI iMWe Neti 1 823 ,7 827 2 821 18 826 3 R25 i9 765 4 824 20 2 5 824 21 0 6 824 ,2 0 7 826 0 73 8 825 2.s 0 9 825 25 0 10 826 26 0 ii 825 2; O 12 823 ,8 0 13 824 29 0 14 R2R 0 30 is 828 3, 0 16 827 INSTRUCTIONS On this format,hst the arc age daily umt amer inelin Mwe. Net for each day in the reporting month. Compute to the nearest whole megawatt.

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OPERATING DATA REPORT o"= S3&

COMPLETED BY L.S. Bramlett TELEPHONE Rn1/oAA.?q19 OPERATING STATUS N '"

1. Unit Name: arbne=e ""cles n e m o ., n

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2. Reporting Period: OctobeF1'31.1674~

3. Licensed Thermal Power (SIWr): 2 CAR

4. Nameplate Rating (Gross alWeI: 902.74

5. Design Electrical Rating (Net alwel: _.850

6. Slaximum Dependable Capacity (Gross 31We): 883

7. Maximum Dependable Capacity (Net Mhe): 836 l

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

None

9. Power Level To Which Restricted. if Any (Net Mwel: Nnna

10. Reasons For Restrictions. If Any: Ma This Slonth Yr.-to.Date Cumulstise

11. Hours in Reporting Period 745.0 7296.0 42667.0

12. Number Of Hours Reactor was Critical 457.2 3410 'I 741?n 4

13. Reactor Resene Shutdown Hours 287.8 2257.5 4247.4

14. Hours Generator On.Line 456.8 3252.5 2R466.2'

15. Unit Resene Shutdown Hours 00 441 4 74A 7

16. Gross Thermal Energy Generated (MwHi 1160690.0 7970015.0 68776724.0

17. Gross Electrical Energy Generated (MWH) 391873.0 2646835.0 22887516.0

18. Net Electr. cal Energy Generated (MWHI 374828.0. 2526664.0 21837210.0

19. Unit Senice Factor 61.3 44.6 _ _ . .

66.7

20. Unit Availability Factor 61.3 52.7 68.6

21. Unit Capacity Factor (Using MDC Nett 60.2 41.4 61.2

22. Unit Capacity Factor (Using DER Net) 59.2 40.7 60 2

23. Unit Forced Outage Rate nn AL1 3c,1

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

nnno

25. If Shut Down At End Of Report Period. Estimated Date of Startup: Novombar 19- 1Q70

26. Units in Test Status (Prior to Commercial Operationi: Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION 1440 $25 (0/77)

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REFUELING INFORMATION

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

2. Scheduled date for next refueling shutdown. 11/01/1980

3. Scheduled date for restart following refueling. 01/01/1981

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

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 Report and associated proposed Technical Specification Changos.

5. Scheduled date(s) for submitting proposed licensing action and supporting information. 09/01/1980

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

new or different fuel design or supplier, unreviewed design or perfor=ance analysis methods, significant changes in fuel design, new operating procedures.

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

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: March, 1988

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IHWl'ET No. 5n 111 .',.

UNII SilUiDOWNS AND POWLR Hl:DUCIIONS

""'#"^34 $ NL.1 S.MBtamlett 0'

COMPl.E1 E D itY REPORT MONTil October 1ELLPil0NE 501-968-2519

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-,, .5'E 'b -3 E I I itensee 5-to F;. C.mse A Coricuive N. . . Dale C-3? 4 5h5 INent  ?' 5 ~J Adion to H

$5 $ 55g Report = EU 5' Pievens Recturente

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79-05 791020 S 288.2 11 1 NA- lill PUMPXX Commitment to NRC to provide vital RC INSTRU power to P7B, Emergency Feedwater Pump and modify In-Core Temperature Detection Devices.

1 2 3 4 F: Forced Reason: Method: INir. bis G . Insisuctions S: Scheduleil ___. A.Eiguipment Failure (Explain) 1 -Manual f.n Preparanon of Isaia p 11-Maintenance or Test 2 Manual Scia.n. Entiy Sheca, ein I seensee p C Refncling .l Automalic Saani. Event Repose i1.l'ItI lY.e iNilitt G-1)-Itegulatos) Resuittion 4-Olhes llNplain t Ul til I C li Opciator l'saining & t hense lhainination F Administrative 5

• G-Opesaisonal i n or llapl.on) latnbis 1 - Same Sonice

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NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- OCTOBER, 1979 UNIT I The unit operated at 100% reactor power for the first 19 days of the month. On October 20, the unit was taken off line for outage No.

79-05. This outage was scheduled for the provision of vital power to P7B Emergency Feedwater Pump and modification of In-Core Temperature -

Detection Devices. The unit remained in the shutdown mode for the remainder of the month.

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ARKANSAS NUCLEAR ONE - UNIT I Periodic Core Power Distribution Comparison A Radial Power Distribution comparison was performed at 66.4 EFPD. The RMS (root mean square) of the differences between measured and predicted at the 52 instrumented fuel assembly locations was 0.029 which is well within the acceptance criterion of 0.073.

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