ML19344B535

Monthly Operating Rept for Sept 1980

ML19344B535
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/15/1980
From:	Bramlett L ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19344B533	List: ML19344B532 ML19344B535
References
NUDOCS 8010210423
Download: ML19344B535 (6)

Text

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l AVER AGE D AILY UNIT POWER LEVEL DOCKET NO. 50-313 +

UNIT' AN0-1 l

DATE 10/15/80 COMPLETED BY L. S. Bramlett TELEPHONE - (501) 968-2519 l.

September, 1980 MONm DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

- (MWe Net) 1MWe-Net) l 1 748 37 o f-l 2 746 ig 0 l 3 746 0 19 4 744 20 0 205 5  :: 0 6 0  : 0 7 0 23 0 8 0 24 o 9 0 25 0 to 0 26 0 11 0  :: 0

, 12 0' ,s 284 13 0 600 29 14 0 715 30 15 0 31 N/A 16 0 i

INSTRUCTIONS On this t'ormat.hsr the asenge diily unit pimer leselin MWe Net for each day in the reportin: month. Compute to the nearest wholeyrgawatt.

(9/77 )

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OPERATING DATA REPORT 4

DOCKET NO. 50-313

. DATE 10/15/80 COMPLETED BY L. 5. Bramlett TELEPHONE tDUIJ 900-2519 4

OPERATING STATUS q.

Arkansas Nuclear One - Unit 1 Not"  :

l. Uni Name: '

j September 1 - 30,1980

2. Reporting Period:

!. .1. Licensed Thermal Power (MWti:

2568

4. Nameplate Rating (Gross MWel: 902.74

! 5. Design Electrical Rating iNet MWe): 850'

6. Maximum Dependable Capacity 4 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. Gise Reasons:

!- None l

l None b

9. Power Leiel To which Restricted.lf g(Net MWe):-

- 10. Reasons For Restrictions. If Any:

I This Month Yr..to.Date Cumulatise 1

II. Hours in Reporting Period 720.0 6,575.0 50.706.0 1 12. Number Of Hour, Reactor was Critical 179*9 3,457.2 33,595.6

13. Reactor Reserve'Shutdc.wn Hours . 73.7 647.6 4,895.0 170.4 3,391.8~ 32,862.3 '

!. 14. Houn Generator On Line-J

15. Unit Resene Shutdown Hours -

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0.0- 20.8 817.5 i

16. Gross Thermal Energy Generated iMWHi 394,986.0- 8,090,744.0 79,352.788.0 'l I - 17. Gross Electrical Enkrgy Generated IMWH,

-121,130.0 2,493,620.0 26,214,776.0 l'8. Net Electrical Energy Generated (PtwHi 114,907.0. 2 u3]_1,967.0 25,006,004.0

19. Unit Service Factor . 23.7 51.6 64.8

20. Unit Availability Factor 23.7 51.9z 66.4-

21. Unit Capacity Factor tUsing MDC Net) :19.1 43.2 59.0

-22. Unit Capacity Factor (Using DER Net) 18.8 42.4 58.0

23. Unit Forced Outage Rate .. 76.3 35.4 18.2 j' 24. Shutdowns Scheduled Oser Ne.st 6 Months (Type. Date.and Duration of Eacht:

January 1 1981 to March :1,1980 Refueling

25.. If Shut Down At End Of Report Period. Estimated Date of Startup: i 26.' Units in Tot Status t Prior to Commercial Operationi: Forecast Achieved

. INITIA L CRITICALITY-INITIAL ELECTRICITY COMMERCIAL OPER ATION ___ ,

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UNil SillIIDOWNS AND l'OWER lti:DliC110NS DOC ~ K ET NO:

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Pievent Rcsinren,e u

Q 80-09 800905. -F 549.6- A 1 80 034 /03L CC llTEXCH . The outage was caused when a tube leak developed in the'"A" OTSC. .One. tube g

was leaking and was plug'ged. Eddy current testing was used to check other P '

tubes for integrity.

,%., w. - me I': I ort.ed Re. nun . Klettvid: 1 slobit G - Instens ti.un S. $s t.oluleil ' . A.I..piipinent I ailure (l xpl un) 141.in n.i! tos Pity.u.itsun .d D.it~

Is41.iintenance or lest 1 \tanual Sera.o I otr> Shee > ias 1 emec C.Rductuig . 4 Autoenstic Ss. ' ant. laen I:crint ii l'lO I ile (NItRI G-D Regul.itor) Itc>t riction 4 tlehes (I splaint u l til I '

. I Opci.atens 'leaining.t Iisenw I sanunation l' d*lIl431el'.II .It l'.C .

b C OpesJttoil.nl I lito (l' Aplanil , 1.\llabel 1 - S.tute $**talie P8/s/l 11 Ot her ilispl.un)

REFUELING INFORMATION -

, 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 o

4. Will refueling or resumption of operation thereafter require a -

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

i 5'. Scheduled date(s) for sub'mitting proposed licensing action and

supporting information. 11/1/80 -

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 68 fresh fuel assemblies and.operat'e for approximately 2~

16 months. Four 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) 176

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

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Nhc MONTHLY OPERATING REPORT OPERATING

SUMMARY

- SEPTEMBER 1980 UNIT I The Unit began the month at .100% power with. normal operation. However, on September 5, a primary to secondary leak was detected in "A" OTSG and the Unit was taken offline. ,The Unit remained-in cold shutdown through September 26, in order to correct the OTSG tube-leak, to perform main-tenance on two RCP seals'and Reactor Building Coolers. One OTSG tube was found leaking and was plugged. Approximately 500 other tubes were tested for possible defects.

The Unit.was placed in operation on September 28, and returned to normal operations.

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- , e-ARKANSAS' NUCLEAR OhI - UNIT I Periodic Core Power' Distribution Comparison

• Radial Power' Distribution comparisons were performed at 188.6 and

215.0 EFPD. .The RMS.(root-mean

square). values of the' differences

--between measured and predicted power at the -52 instrumented fuel assembly locations were calculated. The RMS values.were 0.027 at 188.6 EFPD and 0.028' at .215.'0 EFPD. Both values'are within the 1 . acceptance criteria:of 0.073.

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