0CAN069802, Monthly Operating Repts for May 1998 for ANO Units 1 & 2

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Monthly Operating Repts for May 1998 for ANO Units 1 & 2
ML20249A907
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 05/31/1998
From: James D, Whitt M
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
0CAN069802, CAN69802, NUDOCS 9806190094
Download: ML20249A907 (13)
v • d • e


Text

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a~ ~ asa RusseMo. AR 72801 Tal501858 5000 ,

June 15,1998 1

OCAN069802 U. S. Nuclear Regulatory Cc.. .Mi Document ControlDesk

Mail Station OPI-17

- Washington, DC 20555

Subject:

Arkansas Nuclear One- Units I and 2 Docket Nos. 50-313 and 50-368 Tk-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 May 1998.

Very truly yours, f C ale RT Acti ector, Nuclear Safety DEJ/eam .

. Attachment g

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9806190094 990531 PDR ADOCK 05000313 R PDR.

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- -___--_-_2______.______-_-_-.

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, U. S. NRC June 15,1998 OCAN069802 Page 2 1

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, cc:

~

.Mr. Ellis W. Merschoff .J Regional Administrator U. S. Nuclear Regulatory Commission RegionIV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior ResidentInspector 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 Flint North 11555 Rockville Pike Rockville, MD 20852

_ _ - - ___A

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Arkansas Nuclear One Unit 1 Monthly Operating Report

-s -

OPERATING DATA REPORT

. DOCKET NO: 50-313 DATE: June 15,1998 COMPLETED BY: M. S. Whitt TELEPHONE- (50I) 858-5560 GPERATING STATUS

1. . Unit Name: Arkanees Nuclear One-Unit 1
2. Reporting Period ,h4g,1-31
3. Licensed Thenmal Power (MWt): 2,56s 4.' Nmneplate Rating (Gross MWe): 903
5. Design Electrical Rating (Not MWe): 350 l 6. Maximan W Capacity (Gross MWe): as3 7, Maulanuma normadmHe Car u ;y (Net MWe): 836 l

l s. If Changes Occur in Capa..ry Catings (items Number 3 Through 7) Since l Last Report, Give Reasons

9. Power IAvel To Which Restnoted If Any (Not MWe):
10. Ransons For Rastricuens. If Any:

l MONTH XR-TO-DATE CUMULATIVE

11. Hours la Reporting Period 744.0 3,623.0 205,554.0
12. Nwaber of Hours Reactor Was Critical 541.3 2,437.0 155,692.6
13. Reactor Reserve Shutdowr, Hours 0.0 0.0 5,044.0
14. Hours Generator On-Line 507.s 2,386.4 153,205.4
15. Unit Reserve Shukiown Hours 0.0 0.0 s17.5
16. Gross Thennel Energy Generated (MWH) 1,201,084 5,996,03s 359,380,790
17. Gross Electrical Emergy Generated (MWH) 413.036 2,0s8,720 120,807,592
18. Net Electrical Energy Generated (MWH) 390,677 1,990,02s 115,026,364
19. Unit Service Facsor 6s.3 65.9 74.5
20. Unit Availshility Factor 68.3 65.9 74.9
21. Unit Capacity Factor (Using MDC Net) 62.s 65.7 66.9
22. Unit Capacdy Factor (Using DER Net) 6 I .s 64.6 65.s
23. Unit Forced Outage Rate 0.0 7.2 9.4
24. Shutdowns Scheduled Over Next 6 Months (Type, Dale, and Duimion of Each):

L

25. If Shut Down At End o" Report Period Estimated Date of Startup:
26. Units in Test Status (Prior to Comunercial Opersuon): Forecast Actueved INITIAL CRITICALITY Os/06n4 INITIAL ELECTRICITY 08/l7n4 COMMERCIAL OPERATION 1U19n4 L

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_. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ l

1 l AVERAGE DAILY UNIT POWER LEVEL i

i

. . DOCKET NO: 50-313

!. UNIT: One 1

i DATE: June 15u l998 l COMPLETED BY: M. S. Whitt TELEPHONE: (501) 858-5560 MONTH May).226 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1............. -4 2....................... -4 3 . . .. ... . . . . . . -3 4............................ -6 5............................ -6 6............................. 10 7............................. -33 8............................. -33 9............................ -33 10....................... 2 11...................... I82 12 .... . . . . .

399 13.......................... 670 14.......................... 804 I5........................... 801 16............................ 846 17 ....... .

834 18........................... 842 19............................ 831 20 : ...............

850 21........................... 850 2 2 . .. .. . . ..... . .

849 23 ..... . . . . . . .

851 24 . ..........

852 25............................. 850 i 850 26...........................

27........................... 85I 851 28 . . .

851 29......................

851 30............................

850 3I...........................

AVGS: 525 INSTRUCTIVE ,.

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NRC MONTHLY OPERATING REPORT

. OPERATING

SUMMARY

MAY 1998 UNIT ONE I

The unit began the month off-line for refueling outage IR14. The reactor was rrale critical on May 9 at 1042 hours0.0121 days <br />0.289 hours <br />0.00172 weeks <br />3.96481e-4 months <br />. The turbine was tied to the grid at 1604 hours0.0186 days <br />0.446 hours <br />0.00265 weeks <br />6.10322e-4 months <br /> on the tenth offichily marking the end ofIR14.

The turbine was tripped at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on the eleventh in order to perform the overspeed trip test.

Following completion of the test, the turbine was placed back on-line at 0508 hours0.00588 days <br />0.141 hours <br />8.399471e-4 weeks <br />1.93294e-4 months <br /> that same day. At 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> on the fourteenth, normal power escalation was halted at approximately 95%

due to excessive iron fouling of the condensate polishers as a result of the condenser replacement during IR14. At 2012 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.65566e-4 months <br /> that same day, power was escalated and then halted at 99% due to loop "B" T-hot reaching its limit of 602.63* F. At 0007 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> on the seventeenth, a power reduction to 94.5% was commenced for a condensate polisher swap. Following the polisher ,

change out, power was returned to 99% at 0505 hours0.00584 days <br />0.14 hours <br />8.349868e-4 weeks <br />1.921525e-4 months <br /> that same day. After lowering RCS T-ave to 579* F without exceeding the T-hot limitation, full power was attained at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on the

- eighteenth. The unit operated the remainder of the month at 100% power.

There were no challenges to the primary system code safeties or automatic actuations of the electromatic relief valve during this reporting period I

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. Reporting Period: May 1998 REFUELING INFORMATION

1. Name of facihty: Adapans Nucinar One-Unit 1
2. 4Milad date for next refueling almadown' Septeniher_11L1222 I
3. Schadulad date for restart following refueling: October 10.1999
l. - 4. Will refuehag or resumption 6f operation thernaRer require a technical specification change or other l- license amendment? if answer is yes, what, in general, will there be? If answer is no, has the reload fuel design and corewi.,, miicii been reviewed by your Plant Safcty Review Committee.to determine whether any s-dd safety questions arc ===ari=*ad with the core reload (Ref.10CFR Sectaan 50.59)?

I No.No

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

Blh

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

None planned

7. He number of fuel assemblics (a) in the core, (b) in the spent fuel storage pool and (c) dry cask storage a) 112 b)111 c) 11
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 2 fit increase size by 9 ,

9. De projected date of the last refueling that can be discharged to the W f.sc! pool assuming the presentliccused capacity:  ;

Full core off land a==m v is no W avan-ha+a a suf66 ===aa=* of =aa=* fuel can be  !

glaeaf in an-site drv =ea mae 1

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= _ _ _ _ _ _ _ _ _

Arkansas Nuclear One Unit 2 l

Monthly Operating Report l

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OPERATING DATA REPORT

". - DOCKET NO: 50-368 DATE: June 15,1998 COMPLETED BY: M. S. Whitt TELEPHONE- (501) 858-5560 OPERATING STA'IUS

1. Unit Name: Arkansas Nuclear One-Unit 2

' 2. Reporting Period May 1-31

3. Licensed Thorinal Power (MWt): 2,815
4. I'n'"- Rating (Gross MWe): 942.57 ,

! 5.

6.

Design Electrical Rating (Not MWe): 912 Maxianun Dependable Capacity (Gross MWe): 897

7. Maxinuun C , . ' ": Capacity (Not MWe): 858
8. If Changes Occur in Capacity Ratings (leems Nurnber 3 Through 7) Since Last Report, Give Reasons
9. Power level To Wluch Restncted if Any (Net MWe):
10. Reasons For Restrictions. If Any:

MONTH YR-TO-DATE CUMULATIVE I1. Hours in Reporting Penod 744.0 3,623.0 159,383.0

12. Numberof Hours Ranctor Was Critical 666.3 2,872.7 126,450.6 1.1 Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 661.4 2,858.8 124,201.1
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) . 1,838,301 7,848,322 332,231,772
17. Gross Electrical Energy Generated (MWH) 581,906 2,555,002 109,597,749
18. Net Electrical Energy Generated (MWH) 552 667 2,430,462 104,332,055
19. Unit Service Factor 88.9 78.9 77.9
20. Unit Availability Factor 88.9 78.9 77.9
21. Unit Capacity Factor (Using MDC Net) 86.6 78.2 76.3
22. Unit Capacity Factor (Using DER Net) 81.5 73.6 71.8
23. Unit Forced Outage Rate i 1. I 5.4 9.4
24. S hutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25. If Stut Down At End of Report Period Estimated Date of Startup:
26. Unitt in Test Status (Prior to Comunercial Opershon): Forecast Achieved INITIAL CRITICALITY 12/05n8 INITIAL ELECTRICITY 12/26n8 COMMERCIAL OPERATION 03/26/80 1

m

AVERAGE DAILY UNIT POWER LEVEL

. . DOCKET NO: 50-368 UNIT: Two DA'IE: June 15,1998 COMPLETED BY: M. S. Whitt TELEPHONE: (501) 858-5560 MONTH May 1998 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1........................... 880 2............................ 880 3.......................... 880 4.......................... 879 5 ....... ............. 877 6......................... 874 7........................ 876 8........................... ,,,, 870 9 .. .. ............... 579 10........................ 831 11.......................... 877 12...................... 875 13........................... 875 14.......................... 874 15........................ 872 I6........................... 872 17...................... 876 18.......................... 874 19............................ 874 20......................... 231 21............................. -27 22........................... -25 23 .. ... ...............

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24............................ 479 863 25.......................

874 26....................

872 27......................

874 28............................

872 29.......................

868 30.........................

3I......................

AVGS: 743 INSTRUCTION On this format, list the average daily unit power level in MWe-Net fa cach day in repomng month.

Complete to the nearest whole megawatt.

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NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

MAY 1998 UNIT TWO The unit began the month operating at 100% power.

At 2155 hours0.0249 days <br />0.599 hours <br />0.00356 weeks <br />8.199775e-4 months <br /> on the eighth, a power reduction to 70% was commenced due to a condenser h tube leak. . Following repairs, the unit was returned to full power at 0943 hours0.0109 days <br />0.262 hours <br />0.00156 weeks <br />3.588115e-4 months <br /> on the tenth.

A power reduction to 95.5% was commenced at 0855 hours0.0099 days <br />0.238 hours <br />0.00141 weeks <br />3.253275e-4 months <br /> on the sixteenth for main turbine

! control valve stroke testing and at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> that same day the unit was returned to 100%

power. At 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> on the twentieth, a power reduction was commenced due to a condenser tube leak. At 0807 hours0.00934 days <br />0.224 hours <br />0.00133 weeks <br />3.070635e-4 months <br /> that same day the reactor was manually tripped to take the unit to hot standby due to impurity levels reached in the steam generators caused by the l

condenser tube leak. Following condenser tube plugging and steam generator chemistry cleanup activities, the reactor attained criticality at 1350 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.13675e-4 months <br /> on the twenty-third. The turbine was placed back on line at 1841 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.005005e-4 months <br /> on the twenty-third, and on the twenty-fourth at 1110 hours0.0128 days <br />0.308 hours <br />0.00184 weeks <br />4.22355e-4 months <br /> the unit returned to 100% power. The unit operated the remainder of the month at 100% power.

There were no challenges to the primary system code safeties or automatic actuations of the low temperature overpressure protection valves during the reporting period.

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Reportug Period: May 1998

, . 1 REFUELING INFORMATION i

1. Name of facility: Arkansas Nuclear One - Unit. 2
2. Scheduled dose for next refueling shutdown: _f-- y8.1999
3. Scheduled date for restart following refueling: February 22.1999
4. Will refueling orin f = of operation therenAer require a technical specificaten change or other .

hcense arnandment? If answer is yes, what, in general, will there be? If answer is no, has the reload fuel design and core configuration been rewewed by your Plant Safety Renew Comenittee to -

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

No.No

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

N/A

6. Impostant licensing considerations ===acia*M with refueling, e.g., new or different fuel design or supplier, unreviewed design or perfonnance analysis methods, significant changes in fuel design, new operating procedures.

None planned

7. The number of fuel assemblies (a) in the core (b) in the spent fuel storage pool and (c) dry cask storage, a)112 b)212 c) di
8. %e 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:

present211 incrase size by Q

9. De projected date of the last refueling that can be discharged to the spent fuel pool assummg the present heensed capacity:

- Full w arm --- "nav is no t-- = av "^'" -*a a =ne '=2 ===1e of =--e fuel can be niman,1 ja e dgy annrame or aaa"8 haal naal ana^a" cc 2=E *-' man-fuel ri-----r Tl; are rec 0Vered.

.

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