ML19296B502

Monthly Operating Rept for Jan 1980

ML19296B502
Person / Time
Site:	Arkansas Nuclear
Issue date:	02/15/1980
From:	Pendergraft R ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19296B498	List: ML19296B497 ML19296B502
References
NUDOCS 8002200714
Download: ML19296B502 (5)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-368 UNIT A f,'O-2 DATE 2/15/80 COMPLETED BY R. A. Pendergraft 1ELEPHONE (5011968-2519 MONTH Januarv 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY PCWER LEVEL (Mwe. Net)

(Mwe. Net) 1 522 40 i7 607 is 30 3

708 19 637 4

71 8

o 216 5

7?2 21 375 6

7?n 825 7

654 23 880 S

424 24 894 9

d?7 25 898 to 4??

26 881 11 109 27 901 12 413 898 23 13 419 710 29 14 Cd4 30 0

15 594 3i 0

16 5c8 INSTRUCTIONS On this format. hst the m age d:aly amt power leseiin MWe. Net for each day m the reporting inonth. Compute to the nearest whole megawat?

(9/77) 8 0 02 200 rjfy

OPERATING DATA REPORT DOCKET NO.

50-368 DATE 7/IC/00 CONIPLETED BY P. A. Pendercraft TELEPHONE

1. 50 i968-2519 CPERATING STATUS

1. Unit Name:

Ark n<ac Norlaar Ana fir 4 + 7

2. Reporting Period: January 1-31. 14P0 2815

3. Licensed Thermal Power iNihti:

959

4. Nameplate Rating (Gross 31We):

5. Design Electrical Rating (Net SIWE): 9l2 NA

6. Sf aximum Dependable Capacity (Gross 51We):

NA 7 Stasimum Dependable Capacity (Net 5the):

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

Nona

9. Power Lesel To Which Restricted. if Any (Net 31We):

Nnne

.10. Reasons For Restrictions. If Any:

NA This 31onth Yr..to Date Cumulatise

11. Hour,in Reporting Period 744.0 744.0 102a8.0

12. Number Of Hours Reactor has Critical 6 91.0 Sol.0 4c1o.4

13. Reactor Resene Shutdown Hours 0.0 0.0 3A45.1

14. Hours Generator On-Line 628.1 628.1 3665.0

15. Unit Resene Shutdown Houn 0.0 00 21_7

16. Gross Thermal Energy Generated (51WH) 13??Q66.0*

1322966.0 4819777.0

17. Gross Electrical Energy Generated t.\\tWH) 434827.0 434827.0 1418112.0

18. Net Electrical Energy Generated (5th H) 410234.0 410234.0 1296043.0

19. Unit Senice Factor

20. Unit Availability Factor

21. Unit Capacity Factor (U>ing 51DC Net)

Na tfMTTL r09 EoCIAL goES TIO"

' 22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate j

24. Shutdowns Scheduled Oser Next 6 5tonths (Type. Date.and Duration of Each'l:

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

26. Units In Test Status t Prior to Commercial OperationI:

Forecast Achieved INITI A L CRITICA LITY 12/6/7R INITIAL ELECTRICITY 12/26/78 CO\\t%1ERCIAL OPER ATION Early 1980 to!77 I

DATE:

January 1980 REFUELING INFORMATION 1.

Name of facility.

arkancas Nuclear One - Unit 2 2.

Scheduled date for next refueling shutdown.

3/19/81 3.

Scheduled date for restart following refueling.

5/19/81 4.

Will refueling or resu=ption of operation thereafter require a technical specification change or other license a=end=ent?

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

Yes. Descriotion of effects of new core loading.

3.

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

1/19/81 6.

Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or perfor=ance analysis methods, significant changes in fuel design, new operating procedures.

None 7.

The nu=ber of fuel asse=blies (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 nu=ber of fuel assemblies.

present acg increase size by 0

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assu=ing the present licensed capacity.

DATE:

1989 O

,3 180Gl:1 NO.

.50-M@

UNH SilillDOWNS AN18 POWI R HilallCllONS I! Nil N Akti ANO lin i t 2 -

Drii:._2/J S/no NH'1111.D W D

ntlema h Hi PORT MONill.lanuary I l l.1 l' lion E _31)l-9(if-251L 5 u, N f

=

I :-

,EX l. a c mc.-

g -r,,

c.n.se A co,,ctnse y;q, No.

Daic i

3g i

ji g y l:seni p7 g

4, g,,n g,

$E 5

55:

Report =

E0 5L rec u ni i:cennence F

u 6

80-01 1-17-80 F

42.1 A

3 NONE lill Feedwater cont rol valve failed due to loss of airline. Airline was replaced.

80-02 1-19-80 F

14.5 A

3 NONE IIA TUlullN

/ Turbine Generator Tripped due to ghighvibration. After second trip 80-03 1-21-80 F

6.3 A

3 NONE IIA TilRit!N J vlbration problem no lonper existed.

80-04 1-29-80 S

53.0 B

2' NONE N/A N/A Scheduled Reactor / Turbine Trip Per Startup Testing Sequence.

G53 Em=D E42) i

-i 1

.i (c-J-F:

i.,ad Reason:

nedn,a;

, s n,n,, c.,m,,,,c,,,,,, s S: Sclieduled A-liipiipmens failure (1:xpiain) 14tannal

., p, c i..,,, n.,n,,

9., i,,

c:iS) 11 Maintenance of Test 2 41.enna! Scr.ini.

I ni,3 shecis ini i accmec O.iteincling

.l. Anininanc scr.nn, gwnepep,n,gglg)g,ieggingg.c.[cg@.

D itegulator) Itosukinni

.I Ilihe: 11: splain )

ole,i) 1 Operator Tsaining A la ense I.s.wn.eison

%d F. Adnunkt eative s

"~

G-Operanin. I l'uos (1:splaial I sinhu 1 5.ine S.nn...

08/77) 11 Other (1:xplam) h--

NRC MONTHI.Y OPERATING REPORT OPERATING SU$.'ARY - JANUARY,1980 CNIT II The startup testing program continued as the unit returned to 30%

percent full power at the beginning of this reporting period. On 1-17-80, feedwater control problems resulted in a reactor trip from approximately 65% power. The unit was returned to power on 1-18-80 and then had to reduce power due to problems with a pres-surizer spray ~ valve.

Power escalation continued after the spray valve was repaired until the unit tripped on 1-19-80 due to high vibration on the main turbine generator. The unit was returned to approxinately 90% full power and again tripped due to high vi-bration on the main turbine generator. After returning to power on 1-21-80, the vibration problem no longer existed.

Power esca-lation continued until 1-29-80 when a scheduled trip occurred from 100% full power per the startup testing sequence. The unit ha ;

remained shutdown for the remainder of the month for the scheduled February outage.

.