ML19263E014

Monthly Operating Rept for Mar 1979

ML19263E014
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/13/1979
From:	Shively C ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19263E011	List: ML19263E010 ML19263E014
References
NUDOCS 7904240337
Download: ML19263E014 (5)

Text

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AVER AGE D AILY UNIT POWER LEVEL 50-368 IiOCKET NO.

1:Nii MO-2 DATE April 13, 1979 C.N. Shively E0\\f PLETED BY 501/968-2519 TELEPfl0NE

\\l0Nng March DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL

{ \\lhe-Net )

IMwe. Net) 1 0

0 17 2

__q 1h 0

3 0

0 19 4

0 0

20 0

0 s

21 0

0 6

22 n

23 0

8 0

0 24 0

0 9

25 0

0 10 26 Ii 0

0 27 0

12 2S 13 0

0 29 14 0

0 30 is 0

0 31 0

16 INSTR UCTIONS On thrs Intmat.hst the.ne, e da t

" P"" Ic"'! "I \\f We Net for each dd) n: the remitting m.inik L'o, m the nearest whole mepwa,;

(9/77) 4240337

OPERATING DATA REPORT DOCKET NO.60-368 DATE ApriT lL 1979 COMPLETED BY C.N.Shively TELEPHONE Sm /uAR_96]9 OPERATING STATUS

1. Unit Name:

Arkansas Nuclear One -Unit 1 Nues

2. Reporting Period: March 1-31, 1979

3. Licensed Thermal Power (Mht):

2815

4. Nameplate Rating (Gros MWe):

464

5. Design Electrical Rating (Net MWeI:

012

6. Maximum Dependable Capacity (Gross MWe):

NA

7. Sf aximum Dependable Capacity (Net MWe):

NA

h. If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Last Report.Gise Reasons:

Nnne

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

None 10 Reasons for Restrictions. If Any:

NA This Month Yr.to.Date Cumulative

11. Hours a. Reporting Period 744.0 2160.0 2904.0

12. Number Of Hours Reactor was Critical 0.0 680.9 1115.8 1.1 Reactor Resene Shutdown Hours 147.6 598.0 740.2

14. Hours Generator On.Line 0.0 603.1 655.9

15. Unit Resene Shutdown flours 0.0 1.1 1i

16. Gross Thermal Energv Generated (MWil)

O.U 321836.U 366414.0 17 Gross Electrical Energv Generated (MWH) 0.U 70137.0 75704.0 lb. Net Electrical Energy Generated (MhH) 0.0 52357.0 56341.0

19. Unit Service Factor

20. Unit Asailability Factor

21. Umt Capacity Factor (Using MDC Net)

NA UNTIL COMMERCIAL OPERATION

22. Unit Capacity Factor (Using DER Neti

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date,and Duration of Eachl:

NA

~

25. If Shut Down At End Of Re' port Period. Estimated Date of Startup:

NA

26. Umts in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIA L CRITICA LITY 12-5-78 INITI A L ELECTRICITY I2 Eb 78 COMM ERCI A L OPER iTION 3-28-J9 (4/77 )

UNIT SliUIDOh NS AND POWER REDUCTIONS DorKETNo 50-368 UNIT N A\\lE ANO-Unit !I D r TE.4/13/70 REPOR T sf 0N Dg March CO%1PLETED BY C. PL Shively TELErilONE 501-968-2519

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4an,n to d' C ,5 '= Present Res urrente d5 5 h5j R c P"' t 2_ 79-8 790213 F 744 A N/A ft/A CB PUMPXX Reactor Coolant Pump Motor Failure

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I } 4 f F.u. e d Reaun At e t h od E stnNs G Inst ru.ticos S Sched n'e d A-Equ:pment Fadure f E=p!an) 1 -M a n u al for Prep van. n ot' Data

0. Maintenance or Test

2. Man ual Ssram Entn Shem f or Lucince C Ref ueling 3 Autocuire Suani.

Esent Herosi (LI R1 F ic t Nt:RI G. O Rego!v.ns Rev utmo 4 Other(Lupi.nni O t c.i t ! 0; crator Trarmne i tiscus. I sam nai: in F Admnustrate.e 5 G 0;scrational litor (E spi n il E sh:Nri S m S. w e (4/77) 11 Ot her I E splau:1

DATE: March 1979 REFUELING INFORMATION 1. Name of facility. Arkansas Nuclear One - Unit 2 2. Scheduled date for next refueling shutdown. 10-01-80 3. Scheduled date for restart following refueling. 12-01-80 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 been reviewed by your Plant Safety Review Commi* tee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)? Yes Description of effects of new core loading. 5. Scheduled date(s) for submitting proposed licensing action and supporting information. 08-01-80 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 -D-7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 0 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 increase size by U 9. The projected date of the last refueling that can be discharged to the opent fuci pool casuming the present licensed capacity. DATE: Ma rch, 1988

NRC MONTHLY OPERATING REPORT Operating Summary - March,1979 Unit II Maintenance on all four reactor coolant pump motors continued fran the previous month's report. Motor repair was completed on 3/25/79. On 3/5, the "B" Low Pressure Safety Injection Pump developed a noise resembling a small loose part. Investigation revealed a pin designed to index the flow distributor plate inside the pump casing had worked loose. The "A" LPSI pump and both Reactor Building spray pumps were disassembled and inspected for similar problems. No abnonnalities were noted. Unit heatup began on 3/25/79 and the Hot Standby Mode was achieved on 3/26/79. During a main steam safety valve blowdown test, a low steam generator level was received, actuating the Emergency Feedwater System. The EFW pump received a low suction pressure signal and was automatic-ally lined up to the service water header releasing chlorides and par-ticulate into the Feedwater System. Approximately twelve hours were required to return the feedwater back to spec conditions. Main steam safety valve testing continued throughout the remainder of the month.}}