0CAN109806, Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with

Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with

ML20154L524
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/30/1998
From:	Coffman S, Vandergrift J ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
0CAN109806, CAN109806, NUDOCS 9810190341
Download: ML20154L524 (14)

Text

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DAVIS BESSE Dopket No. 50-346 l

cc:

Mary E. O'Reilly Attorney General Centerior Energy Corporation Department of Attorney 300 Madison Avenue General Toledo, OH 43652 30 East Broad Street Columbus, Ohio 43216 Mr. James L. Freels Manager- Regulatory Affairs Mr. James W. Harris, Director Toledo Edison Company Division of Power Generation Davis-Besse Nuclear Power Plant Ohio Department of Industrial 5501 North State - Route 2 Regulations Oak Harbor, Ohio 43449 P.O. Box 825 Cc!umbus, Ohio 43216 Gerald Charnoff, Esq.

Shaw, Pittman, Potts Ohio Environmental Protection Agency and Trowbridge DERR--Compliance Unit 2300 N Street N.W. ATTN: Zack A. Clayton Washington, D.C. 20037 P. O. Box 1049 Columbus, OH 43266-0149 Mr. Robert B. Borsum Babcock & Wilcox State of Ohio Nuclear Power Generation Division Public Utilities Commission 1700 Rockville Pike, Suite 525 180 East Broad Street Rockville, Maryland 20852 Columbus, Ohio 43266-0573 Resident inspector. Mr. James R. Williams U.S. Nuclear Regulatory Commission State Liaison to the NRC 5503 N. State Route 2 Adjutant General's Department Oak Harbor, Ohio 43449 Office of Emergency Managemt Agency 2855 West Dublin Granville Road Mr. James H. Lash, Plant Manager Columbus, Ohio 43235-2206 Toledo Edison Company Davis-Besse Nuclear Power Station President, Board of County 5501 North State Route 2 Commissioners of Ottawa County Oak Harbor, Ohio 43449 Port Clinton, Ohio 43452 Robert E. Owen, Chief Roy P. Lessy, Jr., Esq.

Bureau of Radiological Health Andrew G. Berg, Esq.

Service Akin, Gump, Strauss, Hauer & Feld, Ohio Department of Health L.L.P.

P. O. Box 118 1333 New Hampshire Avenue, N.W.

Columbus, Ohio 43266-0118 Suite 400 Washington, D.C. 20036

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.O- Ent rgy oper:tions,Inc.

1448 SA 333

[- RusseMie, AR 72801 Tel 501858 5000

~ October 14,1998  ;

OCAN109806 U. S. Nuclear Regulatory Commission l Document Control Desk '

Mail Station OPI-17 Washington, DC 20555 l

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 Oentlemen:

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 September 1998.

Very truly yours, Ji y D. Vandergnft Director, Nuclear Safety JDV/nbm attachments

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9810190341 900930 ?

PDR ADOCK 05000313 R PDR-

! U. S. NRC l ,- October 14,1998 l

/ OCAN109806 Page 2 i ,

l l cc: M'r. Ellis W. Merschoff l

! Regional Administrator l U. S. Nuclear Regulatory Commission l RegionIV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064

, NRC Senior Resident Inspector

! Arkansas Nuclear One i P.O. Box 310 l London, AR72847 Mr. William Reckley.

NRR Project Manager Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 0-13-G-8 One White Flint North 11555 Rockville Pike Rockville, MD 20852 l

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a-4 Arkansas Nuclear One Unit 1 i Monthly Operating Report l a

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l OPERATING DATA REPORT DOCKET NO: 50-313 DATE: October 1,1998 e

COMPLETED BY: Steve Coffman TELEPHONE: (501) 858-5560 OPERATING STATUS

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

2. Reporting Period. S%A 1-30 l

' 3. Liemnand Thermal Power (MWt): 2,568 )

i 4. N=Wasa Rating (Gross MWe): 903  ;

5. Design Electrical Rating (Net MWe): 850 I i 6. Maximum m-;-r "- Capacity (Gross MWe): 883 l

7. . Maximum n .aaMa Capacity (Net MWe): 836 1

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

i* ' 9. Power Level To Wluch Restncted. If Any (Net MWe): l

10. Reasons For Restrictions. If Any:

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< MON'III YR 'IO-DATE CUMULATIVE

11. Hoursin Reporting Period 720.0 6,551.0 208,482.0

12. Number of Hours Reactor Was Critical 720.0 5,365.0 158,620.6

13. Reactor Reserve Shutdown Hours 0.0 0.0 5,044.0

14. Hour: Generator On-Line 720.0 5,314.4 156,133.4

15. Unit Reserve Shutdown Hours 0.0 0.0 817.5

16. Gross Thermal Energy Generated (MWH) 1,847,903 13,509,977 366,894,729 4

17. Gross Electrical Energy Generated (MWH) 637,286 4,668,574 123,387,446

18. Net Elecaical Energy Generated (MWH) 610,741 4,461,796 117,498,132 i 19. Unit Service Factor 100.0 81.1 74.9

20. Unit Availability Factor 100.0 81.1 75.3 21, Unit Capacity Factor (Using MDC Not) 101.5 81.5 67.4

22. Unit Capacity Factor (Using DERNet) 99.8 80.I 66.3

23. Unit Forced Outage Rate 0.0 3.4 9.2

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:

26. ' Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY 08/06n4

, INITIAL ELECTRICITY 08/17n4 COMMERCIAL OPERATION 12/19n4 5

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-313 UNIT: One DATE: vcunn ' 8998 COMPLF"" o BY: Steve Comnan TELEPHONE: (501) 858-5560 -

MONTH F = - '=.1998 MMan ""

DAY AVERAGE DAILY POWER LEVEL l (MWe-Ne0 1.......................... 842 2 .. 843 3 . .... . . . . . 843 4............................ 843 5.......... 844 6......... ... 845 7 ..... ......... 845 8............................ 844 9 . . . . . . . . ...

848 l l

'10............................ 850 l 11.......................... 841 12............................ 850 13.......................... 851 14..................... 852 15 ..

853 16....................... 853  !

I 17 . . ... . . 854 I8.......................... 853 19....................... 852 20 ... .. .......

850 21... ...........

848 22............................ 849 23 . .... 849 24......................... 849

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25........................ 850 ,

I 26........................... 850 l 27............... 849 28...................... 850 29 .. 849-849 30........................

1 l AVGS: 848 1

INSTRUCTION l 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.

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UNIT SHUTDOWNS AND POWER REDUCTIONS , ,

REPORT FORSEPTEMBER,1998 .

DOCKET NO. 50 313 UNITNAME . ANO Unit I t DATE October 1,1998 ,

COMPLETED BY Steve CofBnen l TEI2 PHONE 501458-5560 i ME11tOD OF LICENSEE DURATION SHUITING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO +

-Ha DAIE I R E8 GIOURS) REASOs(2 REACTOR 8 REPORT # Eggy SQDg PREVENT RECURRENCE mame .

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1 2 3 4 F: Forced F- W Exhibit G-Instructises S: Scheduled A- Equipeneet FeMure (Explain) 1 -Manoel for 7. , " - - of Data B- Malmeemance of Test 2 - Manuel Screen. Entry h forIJcomaee C- Reeseling 3 - Auteenatic Scrams. Event Report (12R) fee (NUREG4161)

D-Reguineery Restricties 4 - CentW E - Operator Training & IJcense Exeunisation 5-Imed Reducties F- Adunimistraties 9 - Other 5 G - Operettomal Error ExhibitI hSeuree H- Other(Explais)

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NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

SEPTEMBER 1998 UNIT ONE l-l The unit began the month operating at 100% power. At 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on the eleventh, a power reduction to 85% was commenced for the monthly turbine governor valve test. Following the completion of the test, the unit was returned to 100% power at 2247 hours0.026 days <br />0.624 hours <br />0.00372 weeks <br />8.549835e-4 months <br /> that same day. The unit operated the remainder of the month at full power.

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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! Reporti'ut Period: September 1998 REFUELING INFORMATION

1. Name of facility: Arkan=== Nuelaar One - Unit 1

2. Scheduled date for next refueling shutdown: Latamhar 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 =W-t? If answer is yes, what, in general, will there be? If answer is no, has the reload l

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.10CFR l Section 50.59)?

Here are no raland ralat~i tachnical snacincatina chanaae idaatihd for the refueline ontana.

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

N/A

6. Important licensing considerations associated with resia11ag. e.g., new or different fuel design or supplier, unreviewed design or p,rformance analysis methods, significant changes in fuel design, new operatmg procedures.

None olanned

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

a) 122 b)118 c)41

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 96_t increase size by Q

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

Full core offdoad canability is no lonner available until a sufficient amount of soent fuei can be placed m on-site dry storane.

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Arkansas Nuclear One

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Unit 2 Monthly Operating Report i

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OPERATING DATA REPORT

i. DOCKET NO: 50-368 l DATE: October 1,1998 l COMPLETED BY: Steve Comnan l TELEPHONE: (501) 858 5560 OPERATING STATUS t;

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

2. Reporting Period: September 1-30 l 3. Licansari Thermal Power (MWt): 2,815

( 4. NaWete Rating (Gross MWe): 942.57

5. Design Electrical Rating (Net MWe): 8%

6. Maximum Dependable 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:

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

10. Reasons For Restnctions. If Any:

MONTH YR-TO-DATE CUMULATIVE

11. Hours in Reporting Period 720.0 6,551.0 162,311.0

12. Number of Hours Reactor Was Critical 720.0 5,800.7 129,378.6

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 720.0 5,786.8 127,129.I

15. Unit Reserve Shutdown Pours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 2,025,991 16,072,179 340,455,629

17. Gross Electrical Energy Generated (MWH) 657,644 5,215,678 112,258,425

18. Net Electrical Energy Generated (MWH) 627,928 4,% 9,629 106,871,222

19. Unit Service Factor 100.0 88.3 78.3

20. Unit Availability Factor 100.0 88.3 78.3

21. Unit Capacity Factor (Using MDC Net) 101.6 88.4 76.7

22. Unit Capacity Factor (Using DER Net) 95.6 83.2 72.2

23. Unit Forced Outage Rate 0.0 2.8 9.2

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

2R13 Refueling Outage a:x! condt.nser replacement, January 9,1999, scheduled for 45 da31s.

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

26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved i

l INITIAL CRITICALITY 12/05n8 l INITIAL ELECTRICITY 12n6n8 COMMERCIAL OPERATION 03/26/80 t

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l AVERAGE DAILY UNIT POWER LEVEL l

l DOCKET NO: 50-368 l UNIT: Two l DATE: October 1,1998 l

COMPLETED BY: Steve Coffman TELEPHONE: (501) 858-5560 1

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l. MONTH September.1998 DAY AVERAGE DAILY POWERLEVEL (MWe-Net) 1 . . .. . . . . . . . . . . . . . 871 2......................... 872 3............................ 872 4, ............ 868 5........................ 869

6. ............ 870

7. .. 870 8....... . . . . . . . . . . . . . . 87I .

9......................... 878 4 10..................... 878 l 11.................... 875 1 12......................... 874 I

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874 1 l

14 : 872 j 15.......................... 874 l 16 .. . ...

875 l 17........................ 872 18 .. . . . . . . . . .

872 19........................ 872 20.......................... 87I 21......................... 87I 22 ....... ... 872 23........................ 876 24..................... .

873 1

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870 i 26 .. .....................

871 27........................... 87I 870 28.....................

870 29...................

870 30...................s.....

! AVGS: 872 l

l 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.

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UNIT SHUTDOWNS AND POWER REDUCTIONS .

REPORT FOR SEPTEMBER,1998 ,

DOCKET No. 50-368 UNIT NAME ANO Unit 2-DATE October 1,1998 COMPLETED BY Steve CofBasa L

TELEPHONE 501-858-5560 ME1110D OF IJCENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO lig DA]I TYPE' GROURS) REASON 2 REACTOR 8 REPORT # EgRE' ggpls PREVENT RECURRENCE

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1 2 3 4 F: Forced na -

W- Exhibit G -Instructions  !

I S: Scheduled A- EcW FaBure (Explaia) 1 - Manuel for T. _, - "- of Data R- Maintenance of Test 2 - Manuel ScremL Entry Sheets fleri h  !

C- Reheeling 3- Autonestic ScramL Event Report (IER) Flie (NUREG4161)

D-Regulesery Restrictise 4 - Contimenties E - Opermeer Training & IJcease Eu==l== tion 5 -Imed Reducties F- Adunimistration 9 - Other 5 i G - Operm*Ea==I Error ExhibitI SenseSesrce l H- Other (Explain) ,

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0 l l NRC MONTIILY OPERATING REPORT I OPERATING

SUMMARY

l l SEPTEMBER 1998 1 UNIT TWO l

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 (LTOP's) that occurred during the month.

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Reporting Period: September 1998 REFUELING INFORMATION 1.- Name of facility: Ark- Nnetaar One - Unit 2

2. Scheduled date for next refueling shutdown: J=a v 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 to deternune whether any unreviewed nfety questions are associated with the core reload (Ref.10CFR Section 50.59)?

There are no raland re stad tach _nical enaciEcatiaa chanaae idantified for the refineline antnaa.

5. Scheduled date(s) for submitting proposed licensing action and supportmgm' formation:

N/A

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed deeign or performance analysis methods, significant changes in fuel design, new operating procedures.

N90g olanned

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

a)J12 b)291 c) 26

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:

present 28_8 increase size by 9

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

DATE: Janua:y 1999 doss of full core off-load cacudity) l i

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