0CAN119808, Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with

Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with

ML20195D457
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/31/1998
From:	Coffman S, Vandergrift J ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
0CAN119808, CAN119808, NUDOCS 9811180053
Download: ML20195D457 (14)

Text

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.O Enttrgy Oper tions,Inc.

[O U

1448 S.R. 333 RussdMae, AR 72801

, . Td 501858-5000 i

November 12,1998 0CANI19808 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station OPI-17 Washington, DC 20555

Subject:

Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Monthly Operating Report Gentlemen:  !

1 Arkansas Nuclear One (ANO), Units 1 and 2 Technical Speci6 cations 6.12.2.3 and 6.9.1.6,  ;

respectively, require the submittal of a Monthly Operating Report. The purpose of this letter is to complete the reporting requirement for October 1998.

Very truly yours, Mc

. D. ergrift Directo , Nuclear Safety JDV/nbm attachment s l

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, < 3 'y,$

9811100053 M1031 ""

PDR R ADOCK 05000313 PDRo

, U. S. NRC November 12,1998

. OCANI19808 Page 2

'ec: Mr. Ellis W. Merschoff Regional Administrator U. S. Nuclear Regulatory Commission RegionIV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident inspector Arkansas Nuclear One P.O. Box 310 London, AR72847 Mr. Nick Hilton NRR Project Manager Region IV/ANO-1 l U. S. Nuclear Regulatory Commission l l

NRR Mail Stop 0-13-G-3 One White Flint North 11555 Rockville Pike l Rockville, MD 20852 i Mr. Chris Nolan NRR Project Manager Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 0-13-G-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 l

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Arkansas Nuclear One Unit 1 Monthly Operating Report 1

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OPERATING DATA REPORT DOCKET NO: 50-313 UNIT: ANO Unit 1 DA'IE: November 1,1998 COMPLETED BY: Steve Coffman ,

TELEPHONE: (50l) 858-5560

1. Unit Name: Arkansas Nuclear One - Unit 1

2. Reporting Period October 1-31

3. Licensed Thermal Power (MWt): 22 568

4. Nameplate Rating (Gross MWe): 903

5. Design ElectncalEating(Net MWe): 850

6. Maximum Dependable Capacity (Gross MWe): 883

7. Maximum Dependable Capacity (Net MWe): 836

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

9. Power Level To Which Restncted If Any (Net MWe):

10. Reasons For Restrictions. If Any:

MON'IR YR-TO-DATE CUMULATIVE I1. Hours in Reporting Period 745.0 7,296.0 209,227.0

12. Number of Hours Reactor Was Critical 745.0 6,110.0 159,365.6

13. Reactor Reserve Shutdown Hours 0.0 ,

0.0 5.044.0

14. Hours Generator On-Line 745.0 6,059.4 156,878.4

15. Unit Pm Shutdown Hours 0.0 0.0 817.5

16. Gross Thermal Energy Generated (MWH) 1,908,669 15,4I8,646 368,803,398

17. Gross Electncal Energy Generated (MWH) 663,500 5,332,074 124,050,946 l 18. Net Electncal Energy Generated (MWH) 636,399 5,098,195 118,134,531 l 19. Unit Service Factor 100.0 83.1 75.0

20. Unit Availability Factor 100.0 83.1 75.4

21. Unit Capacity Factor (Using MDC Net) ,_

102.2 83.6 67.5

22. Unit Capacity Factor (Using DER Net) 100.5 82.2 66.4

23. Unit Forced Outage Rate 0.0 3.0 9.2

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

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

26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY 08/06n4 INITIAL ELECTRICITY 08/17n4 COMMERCIAL OPERATION 12/19n4 l

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i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-313 UNIT: ANO Unit 1 i DATE: November 1,1998 l OMIPLETED BY: Steve Cofman I T EPHONE: (501) 858 5560 MONIH October.1998 l -  ;

DAY ' AVERAGE DAILY POWER LEVEL i (MWe-Net) l l

1........................... 846 l

2.......................-... 852 i 3............................ s53 j 4............................. 853- 1 i

5........................ 853 j 6............................ 855 1 I

7.............................. 856 d l

l, 8........... . ass i l

9............................ '

802 l 10....................... s56  !

11'........................... 855 ,

.12......................... 855 1 13........................ 857 14........................... 858 15........................~ 857 16.......................... 856 17............................. 856 18....................... 856 19........................ 155 20....................... a56 '

21............................. asa 22..........................

857 ,

23............................. 858 24........................ ,3, 25......................... -

858 i

.26..........................

858 27.............................

85s 28............................ ,3, 29.............................

858 30.................... ass 31............................

AVGS: 854 I

INSTRUCTION On this fc rmat, list the average daily unit power level in MWe-Net for each day in reportir.g month. Complete to the nearest whole megawatt.

UNIT SHUTDOWNS AN3 POWER RCUCTIONS ,

REPORT FOR OCTOBER,1998 DOCKET NO. $0 313 UNIT NAME ANO L%it I DATE Novanber 1,1998 COMPLETED BY Stew CofBnen _

TEt2FRONE 501-858-5560 METHOD OF IJCENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAU$E & CORRECTIVE ACTION TO N.Q DATE IRX' GIOURS) REASON 2 REACTOR

• REPORTf CODE' EQRE' PREVENT RECURRENCE meme 1 2 3 4 F: Forced Reesen: Mothed. Exhibit G-Instructions S: Scheduled A-!,_,  : Fallere (Explain) 1 - Messel for P wyeraties of Data B - Maintemence of Test 2 - Messel Screes. Entry Sheets for IJr===

C- Refleeling 3 - Autensatic Screes. Event Report (IER) File (NUREG-0161)

D- Regulatory Restricties 4 - Contimmaties E - Operator Training & IJcense Exeselmaties 5 - Lead Reduction F- Adunielstration 9 - Other 5 G - Operatiesel Ener EskiMt I-Seene Source H - Other (Exp7ain)

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• l NRC MONTHLY OPERATING REPORT ,

! OPERATING

SUMMARY

OCTOBER 1998 UNIT ONE f

q The unit began the month operating at 100% power. At 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on the eighth, a powe, i reduction to 98.5% was commenced to troubleshoot the EI A feedwater heater level control valve

)' oscillations. The unit was returned to 100% power at 1355 hours0.0157 days <br />0.376 hours <br />0.00224 weeks <br />5.155775e-4 months <br /> that same day. At 1341 hours0.0155 days <br />0.373 hours <br />0.00222 weeks <br />5.102505e-4 months <br /> on the ninth, a power reduction to 85% was commenced for the monthly turbine governor valve

test, and to allow for repairs of the EI A feedwater heater level controller. The EI A level control valve repairs were completed at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> on the ninth, and following the completion of the monthly turbine governor valve test, the unit was returned to 100% power at 2352 hours0.0272 days <br />0.653 hours <br />0.00389 weeks <br />8.94936e-4 months <br /> that a same day. At 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> on the twelfth, a power reduction to 97% was commenced to perform a 3 planned condensate pump swap. The unit was returned to 100% power at 1511 hours0.0175 days <br />0.42 hours <br />0.0025 weeks <br />5.749355e-4 months <br /> that same l

]- day. The unit operated the remainder of the month at full power. l i

j Note: There were no challenges to the primary system code safeties nor automatic actuations of

the electromatic relief valve (ERV) that occurred during the month.

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Reportmg Period: October 1998 1

REFUELING INFORMATION l

1. Name of facdoty. Arkansas Nuclear One - Unit 1 ,

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2. Mw=hilad date for next refuehag shutdown September 10.1999 l

3. Scheduled date for restart following refuehag October 14.1999

4. Will refuehng or r~a=atian of operation thercaAer require a tachnical specification change or other heense amendment? If answer is yes, what, he general, will there be? If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee (PSC) to determme whether any unreviewed santy questions are ==aamatad with the core reload (Ref.10CFR

, Section 50.59)?

e hc are no F and l F l='ad e=F...ient z.uiftentinn c'- - --- i.L..::M for the refnd-.= a='=aa. The

raland renort for the aart fuel evele has not beni reviewed by PSC.

5. Schadulad date(s) for submitting proposed I";- action and supportmg information:

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! 6. Iir.poitnot licensmg 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

! operatmg procedures.

j None planned

7. 'Ihe number of fuel assemblies (a) in the core, (b) in the spent fuel storage pool and (c) dry cask k

i l a) jl2 b) 118 c)41 1

8. 'Ilie 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:

2

present 268 increase size by 0 j 9. 'Ihe projW date of the last refueling that can be discharged to the spent fuel pool assunung the

present licensed capacity

i Full core offland c=hility is no laaaar av=il=hla na'il a aufhina* ma=nt of scent fuel can be niaced in on-site dry storane-

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Arkansas Nuclear One Unit 2 L

Monthly Operating Report I

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OPERATING DATA REPORT DOCKET NO

50-368 l UNFl: ANO Unit 2 F DA'IE: Novemher 1,1998 COMPLEIED BY: Steve r'amnan

'IELEPHONE- (501) 858-5560 OPERATING STATUS

1. Unit Namac- Arkansas Nuclear One-Unit 2

2. Reporting Period, October 1-31

3. Licensed'IhennelPower(MWt): 2,815

4. N==arinaa Rating (Greas MWe): 942.57

- 5. Design ElodncalRating(Not MWe): 896

6. Mari=== Daraad=hla Capacity (Gross MWe): 897

7. Maxianunnarandahla Capacity (Net MWe): 858

8. If Changes Occur in Capuaty Ratings (Items Nusuber 3 Tluough 7) Since Last Report, Give Reasons-

9. PowerIAvel To Which Restncted. If Any (Net MWe):

10. Reasons For Resenctions If Any:

MON'III YR-10-DATE CUMULATIVE

11. Hoursin Reporting Period 745.0, 7,296.0 163,056.0

12. Nanber ofHours Reactor Was Critical 745.0 6,545.7 130,123.6

13. ReactorReserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 745.0 6,531.8 127,874.1  ;

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 2,096,266 18,168,445 342,551,895 I

16. Gross '!)ennel Energy Generated (MWH)

17. Gross Electncal Energy Generated (MWH) 685,518 5,901,196 112,943,943

18. Net Electncal Energy Gescrated (MWH) 654,947 5,624,576 107,526,169

19. Unit Service Faca 100.0 89.5 78.4

20. Unit Avaitahihey Factor 100.0 89.5 78.4

21. Unit CapacityFactor(Using MDC Net) 102.5 89.8 76.9

22. Unit Capacity Factor (Using DERNet) 96.4 84.5 72.3 ,

23. Unit Forced Outage Rate 0.0 2.5 9.2

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Durabon of Fach): '

2R13 ReAsoling Outase and condenser r= '-* January 8,1999, ar harhilad for 55 days.

25, If Shut Down At End of Report Period. Esti== tad Date of Startup.

- 26. Units in Test Status (Prior to Conumercial Operation): Forecast Achieved INITIAL CRJTICALITY 12M5n8 INITIAL EIh".,TRICITY 12/26ns ,

COMMERCIAL OPERATION ,,, 03/26/80 I

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J AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-368 UNIT: ANO Unit 2 DA'IE: Novembr/1,1998 COMPLETED BY: Steve Comnan TELEPHONE: (501) 858-5560 MONTH October.1998 '

DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1........ . . . . . . . . 875 2......................... 879 3....................... 875 4........................ 873 5....................... 873 6....................... 880 7................. . 881 8........................ 882 9.......................... 882 10........................ g81 11.......................... gao 12 . .. ... ...... ...... g79 l 13............................ gao 14........................... 880 l 15.......................... gyg 16....................... 875 17............................ 875 18........................... ggo 19........................- 882 20............................ 882 21....................... 881 22........................... 883 23........................... g 2 4 .. ........ ... . . . . .

gg3 25..........................'

882 26..........................

880 27.........................

879

.-28........................... g79 29...........................

876 30..........................

875 31.................. .

AVGS: 879 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for each day in reportmg month. Complete to the nearest whole megawatt.

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UNITSHUTDOWNS AND POWER RIOUCTIONS ,

REPORT POR OCTOBER,1998

< DOCKETNO. 50-368 -

i UNIT NAME ANO Unit 2 DATE Nemabar 1,1998 COMPLETED BY Steve Ch -

TEI2 PHONE 501-858 5560 t METHOD OF IJCENSEE  ;

DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE A CORRECTIVE ACTION TO f Eg DAH M' GIOURS) REASON 8 REACTOR 8 REPORT #. EgDE* EQRE' PREVENT RECURRENCE meme i i

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1 2 3 4 F: Forced B- Mothed. ExWMt G-lastructions ,

S: Scheduled A- Equipament Failure (Explain) 1. Manuel for Properstlem of Deas [

B - Meineemence of Test 2- Manuel Screet Entry Sheets forIJcensee l C-Refhelleg 3 - Aueesentic ScrasL Event Itapert (LER) FHe (NUREG-4161)  !

D-F, * - j Restricties 4 - Comehneetion E - Operecer Training A IJessne Exaenimation 5-Imed Iteducties F- Adeninistratism 9 - Other 5 l G- Operatiesel Erter Exhibit I-Seene Source  ;

H - Other (Explain)

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

OCTOBER 1998 UNIT TWO

.s The unit operated the entire month at 100% power.

Note: There were no challenges to the primary system code safeties nor automatic actuations of the low temperature overpressure protection valves (LTOPs) that occurred during the month.

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li Reporting Period: October 1998 l

REFUELING INFORMATION 2

1. Name of facility: Arkan=== Nuctaar One - Unit 2 i

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2. Scheduled date for next refueling shutdown Ja=" v 8.1999 )

3. Scheduled date for restart followmg refueling: February 22.1999 j 4. Will refueling or resumption of operation thereaAer require a technical specificaten change or other license amendment? If answer is yes, what, in general, will there be? If answer is no, has the reload i fuel design and core configuration been reviewed by your Plant Safety Review Committee (PSC) to

, determine whether any unreviewed safety questsons are associated with the core reload (Ref.10CFR

Section 50.59)?

h MSSV/PSV netnoint tolerance techab=1 snecifia=*ina ah===a has been identified for the refuelina j m*= =a. Also. the rela =A renort for the navt f.iel cycle has not haan reviewed by PSC.

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5. Scheduled date(s) for submitting proposed licensing action and supportmg information l 5

N/A l

6. Important licensing considerations associated with ref=alia . e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant chariges in fuel design, new operatmg procedures.

None plaaagd r

7. W number of fuel assemblics (a) in the core (b) in the spent fuel storage pool and (c) dry cask storage

a) .122 b)63 c) 144

8. 'Ihe 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:

present2H increase size by Q

9. "Ihe projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

DATE: January 1999 Goss of full core off-load canability)