0CAN049802, Monthly Operating Repts for Mar 1998 for Arkansas Nuclear One,Units 1 & 2

Monthly Operating Repts for Mar 1998 for Arkansas Nuclear One,Units 1 & 2

ML20216J650
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/31/1998
From:	James D, Whitt M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
0CAN049802, CAN49802, NUDOCS 9804210447
Download: ML20216J650 (14)

Text

.

.. g g- Entergy operations,Ir.c.

y 1448 S.R. 323 RmseMo, AR 72801

. Tel 501858 5000 April 15,1998 OCAN049802 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:

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 March 1998.

Very truly yours,

-//b A

k$l y Dale E. James Acting Director, Nuclear Safety DEJ/eam attachment I

t e *' L 9804210447 980331 I i PDR ADOCK 05000313 R PDR J

U. S. NRC

. . April 15,1998 OCAN049802 Page 2

' cc: Mr. Ellis W. Merschoff Regional Admin:4trator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 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 FFnt North 11555 Rockvule Pike Rockville, MD 20852 1

W.

1 1

Arkansas Nuclear One Unit 1 1

Monthly Operating Report l

l I

OPERATING DATA REPORT DOCKET NO: 50-313 DA'IE: April 15,1998 COMPLETED BY: M. S. Whitt TELEPHONE: (50l) 858-5560 OPERATING STATUS

1. Unit Name: Arkansan Nuclear One -Unit 1

2. Reporting Period: March 1-31

3. Licensed Thermal Power (MWt): 2,568

4. Nameplate Rating (Gross MWe): 903

5. Design ElectricalRating(Net MWe): 850

6. Maximum Dependable Capacity (Gross MWe): 883

7. Maximum Dependable Capacity (Net MWe): 836 1

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

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

10. Reasons For Restrictions. If Any:

MONTH YR-TO-DATE CUMULATIVE

11. Hours in Reporting Period 744.0 2,160.0 204,091.0

12. Number of Hours Reactor Wa'. Critical 650.8 1,895.7 155,151.3

13. ReactorReserve Shutdownihrs 0.0 0.0 5,044.0

14. Hours Generator On-Line 648.3 1,878.6 152.697.6

15. Unit Reserve Shutdown Hours 0.0 0.0 817.5

16. Gross Thermal Energy Generated (MWH) 1,654,695 4,794,955 358,179,706

17. Gross Electrical Energy Generated (MWH) 578,464 1,675,684 120,394,556

18. Net ElectncalEnergy Gme.ated (MWH) 553,979 1,601,143 114,637,479

19. Unit Service Factor 87.1 87.0 74.8

20. Unit Availability Factor 87.1 87.0 75.2

21. Unit Capacity Factor (Using MDC Net) 89.I 88.7 67.2

22. Unit Capacity Factor (Using DER Net) 87.6 87.2 66.I

13. Unit Forced Outage Rate 0.0 9.0 9.4

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: May 10,1998

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

AVERAGE DAILY UNIT POWERLEVEL DOCKET NO: 50-313 UNIT: One DATE: April 15.1998 COMPLETED BY: M. S. Whitt TELEPHONE: (501) 858-5560 MONTH March 1998 DAY AVERAGE DAILY POWER LEVEL l (MWe-Net)

1. . . . . . . 863 2= 862 3........................ 862 4............................. 862 5 . . . . .. 863 6 .... ...... 857 7: .............. 855

8. . . . . 859 9 ..... ...... 859 10..................... 863 1 1 ....... . . . . . 861 12 . ............. 860 13 . . . . ... . . . . .. 860 14 . .. ... . .. . .. 861 15 . .. . . . ..... 861 16.......................... 86I l 17 .. . . .. .. . .. 861 l I 18 . . .. .... ... 861 )

l 19 .... 860 1 20 . . ..... . ... 859 21... 863 22............................. 863 23............................. 863 24 . ........

863 25 . . . . . . . .

860 26 ........ 847 27.......................... 768 28 .= -25 29, . . . . . .

-20 30 .. ... . . . .. -7 31....................... *3 AVGS: 745 INSTRUCTION 4

On this fonnat, list the average daily unit power level in MWc-Net for each day in reporting month. l Complete to the nearest whole megawatt.

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NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

{

l MARCII 1998 UNIT ONE {

f The unitbegan the month of March operating at 100% power.

At 2238 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.51559e-4 months <br /> on the sixth, a power reduction to 85% was commenced for main turbine governor valve testing. Following the completion of the turbine test, the unit was returned to 100% power at 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br /> on the seventh. A power reduction to 98% was commenced at 2015 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.667075e-4 months <br /> on the twenty fifth for main steam safety valve (MSSV) testing. Following the completion of the MSSV testing, the unit was returned to 100% power at 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br /> on the twenty-sixth. A power reduction to take the unit off-line was commenced at 1905 hours0.022 days <br />0.529 hours <br />0.00315 weeks <br />7.248525e-4 months <br /> on the twenty-seventh. The turbine was taken off-line at 0018 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> on the twenty-eighth marking the start of 1R14. The unit .

remained off-line for the rest of the month.

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

l l

i I

Reporting Period: March 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 followmg refueling: October 10.1999

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 determine whether any unreviewed safety questions arc associated with the core reload (Ref.10CFR Section 50.59)?

No.No

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

N/A

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.

l None olanned

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

a) jlZ b)25_8 c) 48

8. The present licensed spent fuel pool storage capwity and the size of any increcse in hensed storage capacity that has been requested or is planned, in number of fuel assemblies:

present 268 increase size by 0

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

Full core off-load capability was remained on 3/10/98 by relocatma miscellaneous materials sto:ed. in the noent fuel rwJ. This can=bility will be lost ===ia followina the refMine wa a with the dieh=rne of the decided assemblies.

l l

i 1 .

B Arkansas Nuclear One Unit 2 Monthly Operating Report 1

l l

l l

l I

. OPERATING DATA REPORT DOCKET NO: 50 368 DATE: April 15,1998 COMPLETED BY: M. S. Whitt TELEPHONE: (501) 858-5560 OPERATING STAT _QS

1. Unit Name: Arkansas Nuclear One - Unit 2

2. Reporting Period: March 131

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

4. Nameplate 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-l

9. Power Ixvel To Which Restricted. If Any (Net MWe):

10. Reasons For Restrictions. If Any: 1 MQN_B{ YR-TO-DATE CUMULATIVE )

l

11. Hours in Reportia Period 744.0 2,160.0 157,920.0

12. Number of Hours Reactor Wu Critical 263.4 1,487.4 125,065.3

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 254.4 ~

1.478.4 122,820.7

15. Unit Reserve fhutdown Hours 0.0 0.0 0.0

16. Gross Th:rmal Energy Generated (MWH) 546,422 3,987,412 328,370,862 )

17. Gross Electrical Energy Generated (MWH) 173,922 1,309,810 108,352,557 l

18. Net Electrical Energy Generated (MWH) 159,729 _l,243,958 103,145,551 l

19. Unit Service Factor 34.2 68.4 77.8

20. Unit AvailabilityFactor 34.2 68.4 77.8 l

21. Unit Capacity Factor (Using MDC Net) 25.0 67.I 76.1 l

22. Unit Capacity Factor (Using DER Net) 23.5 63.I 71.6

23. Unit Forced Outage Jase 24.3 5.2 9.4

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 Cc : cial Operation): Forecast Achieved INITIAL CRITICALITY 12/05n8 INITIAL ELECTRICITY 12/26n8 COMMERCIAL OPERATION 03/26/80

1

\

l l

AVERAGE DAILY UNIT POWER LEVEL 1 DOCKET NO: 50-368 UNIT: Two DATE: April 15,1998 -

I COMPLETED BY: M. S. Whitt TELEPHONE: (501) 858-5560

]

MON'IE March 1998 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) i 1........................... -4

)

2.......................... -4 3......... -4 4........ . -4 5................... .. -4 6........ .. -4 7.............................. -4 8................... -4 9..................... 5 l 10,.................... -4 11.. . .. . . . . . -8

! 12 . .. . . .. . . . 11 13..................... -11 14 .. .. . . . . . . . . . . . . . . . . . . -11 15........................... .

-12

! 16.................... 12 17..................... -11 l 18. . . . . . . . . . .

-11 l 19- 19 20..................... 28

21. ....................... 30

22. 182 23..................... I81 24.... . ,

508 25..................... 876 I 26...................... 814 27....................... 876 28..................... 875 29 . .. .................. 875 30 ... ... 862 31- . . . . . . . . . . . .

753 AVGS: 215 INSTRUQ))D1!

On this format, list the average daily unit power level in MWe-Net for cu:h day in reporting month Complete to the nearest whole megawatt.

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. 1 l

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

MARCH 1998 UNIT TWO The unit began the month of March off-line for planned steam generator inspection outage j 2P98. .

l At 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on the eighteenth, the outage had to be extended past its planned end date due to reactor coolant pump (RCP) seal problems. ARet the RCP seal was replaced, the unit continued its startup and at 0039 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> on the twenty-first the reactor was declared critical.

The unit was placed on-line at 0938 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.56909e-4 months <br /> the same day. The unit continued its normal power escalation until 0635 hours0.00735 days <br />0.176 hours <br />0.00105 weeks <br />2.416175e-4 months <br /> on the twenty-third, when the power escalation was halted due to a condenser tube leak. Following plugging of the leaking condenser tube, the unit resumed power escalation at 0112 hours0.0013 days <br />0.0311 hours <br />1.851852e-4 weeks <br />4.2616e-5 months <br /> on the twenty-fourth. Full power operation was attained at 0305 hours0.00353 days <br />0.0847 hours <br />5.042989e-4 weeks <br />1.160525e-4 months <br /> on the twenty-fiRh. A power reduction to 70% was commenced at 0038 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br /> on the twenty-sixth, due to a leaking condenser waterbox manway. Following repairs to the manway, power was returned to 100% at 1710 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.50655e-4 months <br /> that same day. A second power reduction to 70% was commenced at 2140 hours0.0248 days <br />0.594 hours <br />0.00354 weeks <br />8.1427e-4 months <br /> on the thirtieth due to a leaking condenser waterbox manway. Following repairs to the manway, power was returned to 100% at 0705 l hours the next day. The unit operated the remainder of the month at 100% power. 1 There were no challenges to the primary system code safeties nor automatic actuations of the  !

low temperature overpressure protection valves during the reporting period.

3 l

l Reporting Period: March 1998 1 REFUELING INFORMATION

1. Name of facility: Arkansas Nuclear One - Unit 2 )

l

2. Scheduled date for next refueling shutdown: January 8.1999 l

3. Scheduled date for restart followmg refueling: February 22.1999

4. Will refueling or resumption of operation thereafter require a technical specificaten change or other i 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 to determine whether any unreviewed safety questions are associated with the core reload (Ref.10CFR 'l Section 50.59)?

No.No 4

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

N!M

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

Nonc planned

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

a) J,22 b)249 c) 48

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has boca requested or is planned, in number of fuel assemblies:

present RIL8 increase size by 0

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

i Full core off-lod canability no lonaer available until a sufficient amount of scent fuel can be placed in on site j dty moraae s I