ML20198D244

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Monthly Operating Repts for Nov 1998 for Ano,Units 1 & 2. with
ML20198D244
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 11/30/1998
From: Coffman S, Vandergrift J
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
OCAN129807, NUDOCS 9812230046
Download: ML20198D244 (14)
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y Entergy Operations,Inc.

1448 S.R. 333 RusselMile, AR 72801 4

, Tel 501858-5000 J l

l December 15,1998 l

OCAN129807 U.'S Nuclear Regulatory Commission Document Control Desk Mail Station OPI-17 Washington, DC 20555

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

Arkansas Nuclear One (ANO), Units 1 and 2 Technical Specifications 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 November 1998.

l Very truly yours,

/ J. D. V nder 'A Director, Nuclear Safety JDV/eam attachment 9812230046 981130

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PDR ADOCK 05000313 .

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U. S. NRC December 15,1998

'. OCAN129807 Page 2 j- cc: Mr. Ellis W. Merschoff Regional Administrator.

U. S. Nuclear Regulatory Commission Region IV L 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064

NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Mr. Nick Hilton NRR Project Manager Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 0-13-G-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Chris Nolan i NRR Project Manager Region IV/ANO-2 'i U. S. Nuclear Regulatory Commission >

NRR Mail Stop 0-13-G-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 i

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Arkansas Nuclear One Unit 1 Monthly Operating Report l

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OPERATING DATA REPORT DOCKET NO: 50-313 UNIT: ANO Unit 1

, DATE: December 15,1998 i COMPLETED BY: Steve Coffman TELEPHONE: (501) 858-5560 OPERATING STATUS

1. Unit Name: Arkansas Nuclear One - Unit 1
2. Reporting Period: November 130
3. Licensed Thermal Power (MWt): 2,568
4. NWe Rating (Gross MWe): 903 l _ 5. Design ElectricalRating(Net MWe): 850 l 6. Maximum dmo Capacity (Gross MWe): 883
7. Maximum Dependable Capacity (Net MWe): 8_3_6 3

- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: 1 l

9. Power Ievel To Which Restncted. If Any (Net MWe): 1
10. ReasonsForRestricuons if Any:

I MQEW YR-TO-DATE CUMULATIVE l

l 11. Hours in Reporting Pened 720.0 8,016.0 209,947.0 l 12. Number of Hours Reactor Was Critical 720.0 6.830.0 160,085.6 l- 13. Reactor Reserve Shutdown Hours 0.0 0.0 5,044.0 l 14. Hours Generator On-Line _

720.0 6,779.4 157,598.4

15. Unit Reserve Shutdown Hours 0.0 0.0 817.5 l 16. Gross Thermal Energy Generated (MWH) 1,847,856 - 17,266,502 370,651,254
17. Gross Electncal Energy Generated (MWH) 645,056 5,977,130 124,6 % ,002
18. Net Electrical Energy Generated (MWH) 619,206 5,717,401 118,753,737
19. Unit Scavice Factor 100.0 84.6 75.1
20. Unit AvailabilityFactor 100.0 84.6 75.5
21. Unit Capacity Factor (Using MDC Net) 102.9 85.3 67.7
22. Unit Capacity Factor (Using DER Net) 101.2 83.9 66.5
23. Unit Forced Outage Rate 0.0 2.7 9.1
. 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)
25. If Shut Down At End of Report Period. Estimated Date of Startup:

l 26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY 08/06n4 INITIAL ELECTRICITY 08/17n4 j COMMERCIAL OPERATION 12/19n4 4

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l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50 313 UNIT: ANO Unit 1 DA'IE: December 15,1998 COMPLETED BY: Steve Coffman TELEPHONE: (50l) 858 55(4 MONTH November 1998 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 1.................... s5e 2 . . . ... . a58' 3 858 4................. s58 5 . . . . . .. 859 6e . s59 7- . . . . . 859 8- 859 9............ . . . . . . 860 10 , ... 860 1 1 .. . .. ... ... 860 12 . . . . . . . . . . . . 860 13 .. .... .. . . . . . . . . . . . . 852 14 .. ....... 858 15...................... 859 16...................... 861 17 .. .. .... . .. 862 18 ... . .. a62 19.......... 862 20.............. . . . . . . . . 362 21..................... 861 22...................... 862 2 3 . .. .. . . .. . ... . 862 24.................. s61 25 - . . . . . 861

26. . 862
27. . . . . 861 28- . . . . . . . R61 29 . ... .. . . . 861 30................... a61 AVGS: 860 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for each day in reporting month.

Complete to the nearest whole megawatt.

i UNIT SHUTDOWNS AND POWER REDUCTIONS  ;

REPORT FOR NOVEMBER 1998 f DOCKE1NO. 50-313 l UNIT NAME ANO Unit i DATE December 15,1998  !

COMPLETED BY Steve Cof5nen TELEPHONE 501-858-5560 F

L METHOD OF LICENSEE I DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO

!!$h DAH I R E' (HOURS) REASON 2 REACTORS REPORT 8 Eglg8 Egigs PREVENT RECURRENCE I F

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1 2 3 4 F: Forced Reason: Methed: Exhibit G -Isotructises S: Scheduled A- Equipament Failure (Explais) 1 - Meeuel for Properaties of Data j B - Meistemence of Test 2 - Manuel Scromo Entry Sheets for IJceasse C -Refhelleg 3 - Autennetic Screen. Event Report (LER) Fue (NUREG-4161)

Ib Regulatory Restriction 4 - Contieuntion E - Operater Talesing & IJcesse Esseninetion 5-Imed Reducties F- Adveinistration 9 - Other 5 G-Operatseest Error Exhibit I- Samme Source H - Other(Emplain)

1 NRC MONTIILY OPERATING REPORT )

OPERATING

SUMMARY

NOVEMBER 1998 UNIT ONE The unit began the month operating at 100% power. At 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on the thirteenth, a power  ;

reduction to 85% was commenced for the monthly turbine governor valve testing. Following the  !

completion of the monthly turbine governor valve test, the unit was returned to 100% power at 2320 hours0.0269 days <br />0.644 hours <br />0.00384 weeks <br />8.8276e-4 months <br /> that same day. The unit operated the remainder of the month at full power.

There were no challenges to the primary system code safeties nor automatic actuations of the i electromatic relief valve during this reporting period.

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Reporting Period: November 1998 REFUELING INFORMATION

1. Name of facility: Arkansas Nuclear One - Unit 1
2. Scheduled date for next refueling shutdown: September 10.1999
3. Scheduled date for restart following refueling: October 14.1999
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 there be? If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee (PSC) to determine whether any unreviewed safety questions are associated with the core reload (Ref.10CFR Section 50.59)?

There are no reload rg.latsdjgchnical specification channes identified for the refueline ontana. He reload reoort for the next fuel cycle has not vet been rengw_qd by PSC.

5. Scheduled date(s) for submitting proposed licensing action and supporting information:

N1%

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.

None olanned

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

a)lll b) 818 c) 48

8. He 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 268 increase size by 0

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

Full core off-load capability is no lonner available until a sufficient amount of spent fuel can ts placed in on-site dry storanc,

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1 Arkansas Nuclear One  !

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Unit 2 l Monthly Operating Report I

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' OPERATING DATA REPORT DOCKET NO: 50-368 I

UNIT: ANO Unit 2 DATE: December 15,1998 COMPLETED BY: Steve Coffman i TELEPHONE: (501) 858-5560 OPERATING STATUS

- 1. Unit Name: Arkansas Nuclear One - Unit 2

2. Reporting Period: November 1-30  !
3. Licensed ThermalPower(MWt): 2,815 l
4. Nameplate Rating (Gross MWe): 942.57 l
5. _ Design Electncal Rating (Net MWe): ,8% l
6. Maximum Dependabi: Capacity (Gross MWe); 897 7, Maximum Dependable Capacity (Net MWe): 858'
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons  ;

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9. Power Level To Which Restricted. If Any (Net MWe):
10. Reasons For Restnctions If Any:

MONTH YR-TO-DATE CUMULATIVE

.11. Hoursin Reporting Period 720.0 8,016.0 163,776.0

12. Number of Hours Reactor Was Critical 720.0 7,265.7 130,843.6
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 720.0 7,251.8 128,594.1
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 2,025,839 20,194,284 344,577,734
17. Gross Electncal Energy Generated (MWH) 664,748 6,565,944 113,608,691
18. Net Electrical Energy Generated (MWH) 635,358 6,259,934 108,161,527
19. Unit Serrice Factor 100.0 90.5 78.5
20. Unit Ave . lability Factor 100.0 90.5 78.5

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21. Unit Capacity Factor (Using MDC Net) 102.8 91.0 77.0
22. Unit Capacity Factor (Using DER Net) 96.8 85.6 72.4
23. Unit Forced Outage Rate 0.0 2.2 9.I
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling outase 2R13 scheduled to commence January 8,1999 with an expected duration of 45 days

25. If Shut Down At End of Report Penod Estimated Date of Startup:
26. Units in Test Status (Pnor to Commercial Operation): Forecast Achieved INITIAL CRITICALITY 12/0$ns l INITIAL ELECTRICITY 12/2608 COMMERCIAL OPER3 TION 03/26/80 j

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s AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-368 UNIT. ANO Unit 2 DATE: December 15.1998 l COMPLETED BY: Steve Comnan  !

TELEPHONE: (501) 858-5560 'I MONTH Hmsmber 1998 DAY AVERAGE DAILY POWER LEVEL j (MWe-Net) I 1 . .. . . . . 879 2....................... as2 3..................... as2  ;

4 ... 883 1 5 . . .. . . . . . . . . . . , as4

6. . . . .. ass
7. ....... ..... . 885
8. . . . . . . . . 884 9... . . . . . 882 10 . . . ....... . . . . . . . . . as2  !

11.. ... 885 12 .. .... . . . . . . . . . ass 13 = . 384 14 ... . .. . . ... . . . . s83 15......................... as2 16.................... 882 17- as3 18 - . . . . . 882 19 ......... ... as1 20....................... as4 21..................... as4 22.................... as3 23...................... as1 2 4 .. .. .. . . . . 881 25... .. . 881 26 ..... .. . 883 27 ... . . . . . . . as2

?R. . . . . . . . sao 29.. ..... 879 30 . . . .. . . . . ast AVGS: 882 INSTRUCTION On this fonnat, list the average daily unit power level in MWe-Net for each day in reporting month.

Complete to the nearest whole megawatt.

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UNIT SHUTDOWNS AND POWER REDUCTIONS -

REPORT FOR NOVEMBER 1998 DOCKET NO. 50-368 UNIT NAME ANO Unit 2 DATE December 15,1998 COMPLETED BY Steve Coffman TELEPHONE 501-858-5560 METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO Eg- PAIX Iyf1' SOURS) REASON 8 REACTOR' BF.tPEU EDDF CODES PREVENT RECURRENCE meme 1 2 3 4 F: Forced Reesen: Methat Exhibit G -Instructices 5: Scheduled A - Equipment Failure (Explain) 1 - Memeal for Preparation of Data B - Mainiemance of Test 2 - Manu6 i Scram. EntrySheets forIJceasee C- Refueling 3 - Automa* Screma. Event Report (LER) Flie (NUREG-0161)

D- Reguletory Restriction 4 - Contines ties E - Operator Troising & IJcease Enemination 5- Imed Reduction F - Admielstration 9 - Other 5 G - Operatiesel Error Exhibit I-Some Source H - Other (Emplais)

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e NRC MONTIILY OPERATING REPOL OPERATING

SUMMARY

NOVEMBER 1998 UNIT TWO The unit operated the entire month at 100% power.

There were no challenges to the primary system code safeties nor automatic actuations of the low temperature overpressure protection valves during this reporting period.

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Reporting Period: November 1998 REFUELING INFORMATION

1. Name of facility: Arkansas Nuclear One - Unit 2
2. Scheduled date for next refueling shutdown: January 8.1999
3. Scheduled date for restart following refueling: February 22.1999
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 there be? If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee (PSC) to determine whether any unreviewed safety questions are associated with the core reload (Ref.10CFR Section 50.59)?

The MSSV/PSV setooint tolerance technical specification channe has been identified for the refuelina outane. Also. the reload report for the next fuel cycle has not yet been reviewed by PSC.

5. Scheduled date(s) for submitting proposed licensing action and supporting information:

Eb

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. '

i None olanned

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

a)122 b) 613 c).L43

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 288 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: January 1999 doss of full core off-load capability)

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