ML19343B262

Monthly Operating Rept for Nov 1980

ML19343B262
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/12/1980
From:	Pendergraft R ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19343B261	List: ML19343B260 ML19343B262
References
NUDOCS 8012160415
Download: ML19343B262 (5)

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AVER AGE DAILY UNIT POWER LEVEL h DOCKET NO. 50-368 2

UNIT DATE 12/12/80 COMPLETED BY Rex Pendergraft TELEPHONE (501) 968-2519 MONTH November, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (ywe.y, )

i 882 37 515 2 883 is 264 3 699 i, 15 4 0 20 433 s 4 21 263 6 648 22 267 i 7 878 23 259 8 803 3 250 ,

9 546 23 252 to 265 26 270

507 303 2.,

12 47; 830 23 ,

13 514 ,9 882 34 515 878 39 15 525 3, 16 516 INSTRUCTIONS On this formst, hst the aver. ige d;ily unit power lesel in MWe Net for each day in the reporting month. Compure to the nearest whole megawatt.

(9/77) 8012160 %

OPERATING DATA REPORT DOCKET NO. 50-368 DATE 12/12/80 COMPLETED BY Rav Pandergraft TEL EPHONE (501) 0^8-2519 OPERATING STATUS N"'"

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

2. Reporting Period:

November 1-30, 1980 2815

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWel: 959

5. Design Electrical Rating (Net MWel:

912

6. Maximum Dependable Capacity (Gross MWe): 897

7. Masimum Dependable Capacity (Net MWe): 858

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

None Net MWe): None

9. Power Lesel To which Restricted. If Any (N/A

10. Reasons For Restrictions. If Any:

This Month Yr.-to-Date Cumulatise

11. Hours in Reporting Period - 77n n 6,nnn n A,nnn n

12. Number Of Hours Reactor was Critical 661.0 d.6n1_1 a_gna_1

13. Reactor Reserve Shutdown Hours 23.5 ~804.6 ~804.6

14. Hours Generator On-Line 641.0 4,518.8 4,518.8

15. Unit Resene Shutdown Hour, 0.0 75.0 75.0 1,182,257.0 11,059,959.0 11,059,959.0

16. Grnss Thermal Energy Generated IMWH) 3b9,4/U.0 3,b/6,601.0 3,5/6,801.0

17. Gross Electrical Energy Generated IMWHI

18. Net Electrical Energy Generated IMWHi 346.565.0 3.405.397.0 3.4n5.347.0

19. Unit Service Factor 89.0 75.3 75.3

20. Unit Availability Factor 89.0 76.6 76.6

21. Unit Capacity Factor (Using MDC Net) 56.1 66.1 66.1 1 22. Unit Capacity Factor (Using DER Net) 52.8 62.2 62.2

23. Unit Forced Outage Rate 11.0 24.7 24.7

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Each t:

March 15. 14R1 tn Mav 1R. 1QR1. Rafnplinn

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

26. Units In Test Status tPrior to Commercial Operationi: Forecast Achiesed INITIA L CRITICA LITY INITIAL ELECTRICITY COMMERCIAL OPER ATION l

(4/7 7 )

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

2~

50-368 '.,

DOCKET NO.

• UNIT SilUIDOWNS AND POWER REDUCTIONS ANO Unit II a UNIT N AME DATE _12/12/80

• COMPLETED BY Rex Pendergraft REPORT MON fil November TELEPHONE 501-968-2519 li E

-, ,[E 3 j$? Licensee ,E-r, E*o -

Cause & Correctne i No. Dale c- EE 4 2 E5 Event s7 s? Attionto N j$ 5 5 ;j3 = Repori:- E0 E' Prevent Recurrence e  ! L

, d  ;

80-24 11-3-60 F 49.5 A 1 80-080/03L CB MECFUN Unit shutdown due to excessive RCS leakage. Leak was isolatable. Leak '

occurred in the. RCP DP sensing line. ,

Fatigue weld failure was repaired and unit returned to power.

80 11-9-80 F 0.0 A N/A None N/A N/A A forced power reduction occurred due C to a condenser tube leak. Leak was y found and repaired. Duration of power reduction was approximately 219 hours0.00253 days <br />0.0608 hours <br />3.621032e-4 weeks <br />8.33295e-5 months <br />.

}

g 1 80-26 11-18-80 F 29.5 A 1 80-084/03L SD VAVLEX MSIV (2CV-1010) was declared inoper-able due to excessive stroke time. -

EE'.59 Valve was adjusted and returned to operable status.

Y4 .

2EED e i 2 3 4 17 Forsed Reason: Method: Estubit G -Instructions S. Scheduled A fquipment Failure (Expl.iin) 14tanual for Preparation of Data -

B. Maintenance of Test 24f anual Seram. Entry Sheets for Liecusee C Refueling 3 Autonutic Scram. ihent Repois Ill'80 File INUREG-D Regulatory Resitietmo 4-Other I E splain) 0161)

- I -Oper:nor Traimng & Latense l'samination F- Ad minist ra si .e 5 JOp. rational Lero IEsp:.on) 1.stubu I - Same Source l'J/77) ll Other (E splain)

1 1

l REFUELING INFcRMATION '

i 1. Name of facility. Arkansas Nuclear One - Unit 2 I 2.

l Scheduled date for next refueling shutdown. 3/15/81 l 3. Scheduled date for restart following refueling. 5/15/81 1

. 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 these be?

If answer is no, has the reload fuel design and core configuration j been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Raf. 10 CFR Section 50.59)7

! Yes. Description of effects of new core loading.

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

, supporting information. 1/15/81 i 6. Important licensing considerations associated with refueling, e.g. ,

i new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, k new operating procedures.

As oart of a research and development effort, two fuel assemblies l will ho inaded Dossessing design characteristics related to extended burnup.

)

i 7.

The fuel number storage of fuel assemblies pool. a) 177 (a) in the coreb)and (b) in) the spent 58, (New I

j 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 486 0 increase size by l

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

DATE: 1989 P

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NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- NOVEMBER 1980 UNIT II The Unit began this reporting period at full power operation. On 12/3/80 a forced outage occurred due to excessive unknown RCS leakage.

The Reactor was manually shutdown. The RCS leakage was found to be due to a weld failure on the "B" Reactor Coolant Pump Delta Pressure sensing line. The weld failure was found to be isolatable and repair operations were completed while maintaining Mode 3 operation. During the return to power operation (11-5-80) with the reactor critical, a failure occurred in the Instrument Air System which resulted in a loss of instrument air (solder joint separated in Main Line Header). The Reactor was manually tripped and the Instrument Air System was repaired.

A return to power operatica was accomplished on 11-5-80. A forced power reduction from 100% to ~ 60% full power occurred on 11-9-80 due to a water chemistry problem associated with a Main Condenser Tube leak. Power was maintained between 40 and 75% full power until 11-18-80 when the Unit was forced to shutdown due to problems with the Main Steam Isolation Valves. During the routine surveillance testing of the Main Steam Isolation Valves, a problem developed in the test circuit which required the Unit to shutdown to verify Main Steam Isolation Valve operability.

The Unit returned to reduced power operation on 11-19-80 and investiga-tion of the Main Condenser Tube leakage continued with the power level fluctuating between 40 and 75% full power depending on the needs of the Maintenance Staff investigating the tube leakage problem. On 11-28-80 a return to full power operation was accomplished following condenser tube repairs. The Unit remained at full power operation for the remainder of the month. On 11-30-80 the secondary water chemistry indicated a tube leak was developing.