ML19341A049

Monthly Operating Rept for Dec 1980

ML19341A049
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/15/1981
From:	Pendergraft R ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19341A048	List: ML19341A047 ML19341A049
References
NUDOCS 8101210514
Download: ML19341A049 (5)

Text

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b AVERAGE DAILY UNI ROWER LEVEL DOCKET NO., 50-368 UNIT 2

DATE 1/15/81 COMPLETED BY Rex Pendergraft (501) 968~2519 TELEPHONE MONITI nocomhor. lqAn DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVS.

~

(MWe-Net) gy we.g iy 512 54 17 2

303 is 59 3

41R 19 685 4

776 179 20 5

513 21 0

6 0

274 3:

7 0

23 753 8

0 24 585 9

0 25 6R4 10 0

26 685 11 0

27 694 12 0

s 704 13 0

39 7pp 14 n

30 713 15 0

3g 764 i

16 0

INSTRUCTIONS On this formstolist the average daily unit power leselin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

810121C$lf

a l

OPERATING DATA REPORT DOCKET NO.

50-368 DATE l-15-61 COMPLETED BY Rex Pendergraft TELEPHONE (601) 966-2519 OPERATINd STATUS Arkansas Nuclear One - Unit ?

Notn l

1. Unit Name:

December 1 - 31. 1980

2. Reporting Period:

2815

3. Licensed Thermal Power (MWt):

959

4.. Nameplate Rating (Gross MWel:

912

5. Design Electrical Rating (Net MWe):

097

6. Maximum Dependable Capacity (Gross MWe):

RRR

7. Maximum Dependab'e Capacity (Net MWe):

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

NONE NONE

9. Power Letel To Which Restri:ted. lf Any (Net MWe):

N/A l

10. Reasons For Restrictions.lf Any:

This Month Yr to.Date Cumulative 744.0 6,744.0 6,744.0

11. Hours In Reporting Period 427.7 5.030.8 5.030.8

12. Number Of Hour > Reactor was Critical 0

804.6 804.6

13. Reactor Resene Shutdown Hours

14. Hours Generator On.Line 397.2 4,916.0 4,916.0 0

75.0 75.0

15. Unit Resene Shutdown Hours 784,203.0 11,844,162.0 11,844,162.0

16. Gross Thermal Energy Generated (MWH) 256,100.0 3,832,901.0 3,832,901.0'

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Gencruted (MWHI 241.800.0 3,647,197.0-3,647,197.0 53.4 72.9 72.9

19. Unit Service Factor 53.4 74.0 74.0 l

20. Unit Availability Factor U.9 63.0 63.0

21. Unit Capacity Factor (Using MDC Net) 35.6 59.3 59.3

22. Unit Capacity Factor (Using DER Net) 46.6 27.1 2,7 1

23. Unit Forced Outage Rate 2

24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each):

March 15, 1981 to May 15, 1981, Refuelino

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

26. Units In Test Status t Prior to Commercial Operation):

Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (4/77 )

'f.

i

-F 50-368

. OCKET NO.

D UNIT SilUIDOWNS AND POWER REDUCTIONS UNIT NAst E DALE _.1/15/81 COMPLETED llY _ ll o r Pondorcr:nft' REPORT MON fil __b.ecember TELEPilONE 501-968-2519 O

c Licensee

[-r, 59, Cause & Correclise i j?

3 yI~r No.

Date E,

~g 4

.2 s &

Event y7 s.?

Ac tion lo Repois =

<E U E'

Psevent Recurrence

$E 5

3 5 :[

H v

O 80-090/03L PC PIPExx Crack on charging pump suction piping 80-27 12-5-80 F

283.8 A

2 Plant was cooled down and repair ac-complished.

v.

80-28 12-17-80 F

18.10 A

1 None PC VALVEX 2CV-4827 packing Icak caused excess RCS leakage (.91 gpm).

valve was repacked and returned to service.

bu-29 12-20-80 F

44.9 A

2 80-091/0lT IE INSTRU RWT level sensing lines froze, ren-dering all level instrumentation in-operable.

I i

t 1

2 3

4 F:' Forced Reason:

Method:

f sinbie G-Instructions S. Schednled A.fituipinens Fadute(Explain) 1 -Manual for Pseparation of Data 11 Maintenance oi les:

2 Mannal Seraan.

Entry Sheets for 1.icensee C RcIncling

.i Autunutic Soani.

Event Repost ILI Rn File INtlREG-D Regulator) Resniction 4 Olhes (f splain) 01611 I.Operaio Tsaisung & 1 ncnse i.sainination F.Adnusminative 5

1.sinbit I Sanic Soiuce G Opes ational i isos (F spl.n.0 i e.87 7 )

Il Ot he r (lixpl.un)

l l

nua n, M REFUELING INFORMATION l

1.

Name of facility.

Arkansas Nuclear One - Unit 2 2.

Scheduled date for next refueling shutdown.

4/1/81 3.

Scheduled date for restart following refueling.

5/31/81 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

baen rev1 ved 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. Description of effects of new core loading.

5.

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

1/21/81 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.

As cart of a research and development effort, two fuel assemblies will be loaded possessing design characteiistics related to extended bu rnup.

7.

The number of fuel assemblies (a) in the core and (b) in the spent I

b) 58,(New) fuel storage pool.

a) 177 8.

The present licensed spent fuel poc. storage capacity and the size I

of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies, present 486 increase size by 0

9.

The projected date of the last refueling that can be discharged j

to the spent fuel pool assuming the present licensed capacity.

DATE:

1989

NRC MONTHLY OPERATING REPORT l

OPERATING

SUMMARY

- DECEMBER 1980 UNIT II The Unit began this month's operation at a reduced power level due to problems associated with circulating water in leakage to the condenser.

Power fluctuated between 40 and 90% full power while trying to determine the exact mechanism causing the circulating water in leakage. The Unit was forced to Mode 5 operation (cold shutdown) on 12-5-80 due to a leak in the Charging Pump Suction Header Piping. While reducing power, a Feedwater Control Valve failed to close causing a feedwater transient and subsequent Steam Generator Level trip from approximately 30% full power.

Following the transient (approximately two hours later) while feeding the Steam Generators during the cooldown (Mode 3 Operation) the electric driven Emergency Feedwater Pump 2P7B experienced a apump shaf t failure at the inboard bearing location. The Steam Driven Pump 2P7A was immediately started to feed the Steam Generators.

The 2P78 Pum; failure and repair actions prolonged the outage until 12-17-80 when a return to Power Operation was accomplished.

The Unit was forced to return to Mode 3 operation (hot shutdown) the same day due to a packing leak on 2CV-4827-2 (charging return to "B" cold leg).

The valve was repacked and a return to Power Operation was accomplished on 12-18-80.

On 12-20-80 the Unit was again forced to shutdown (Mode 3) due to all RWT Level Instrumentation being inoperable.

Investigation revealed the Heat Tape Power was de-energized and all sensing lines were frozen due to the cold weather conditions.

The Heat Tape Power was returned to operable status.

The Unit returned to Power Operation on 12-21-80 and has operated at a reduced power level (65-90% full power) for tne remainder of this reporting period while investigating the circulating water in leakage problem.

O e

4

ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 [501) 371-4000 January 15, 1981 2-011-18 Mr. Nonnan M. Haller, Director Office of Management and Program Analysis U. S. Nuclear Regulatory Comm.

Washington, D.C.

20555

SUBJECT:

Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Monthly Operating Report (File: 2-0520.1)

Gentlemen:

Attached find the Monthly Operating Report for December,1980 for Arkansas Nuclear One - Unit 2.

Very truly yours, Mc. %21 David C. Trimble Manager, Licensing DCT:DVH:1p Attachments cc: Mr. K. V. Seyfrit, Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Comm.

i Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Mr. Victor Stello, Jr., Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Comm.

Washington, D.C.

20555

{ o*4 iGi 1

MEMBEA MICOLE SOUTH UTILITIES SYSTEM