ML19323A499

Monthly Operating Rept for Mar 1980

ML19323A499
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/11/1980
From:	Pendergraft R ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19323A492	List: ML19323A491 ML19323A499
References
NUDOCS 8004210280
Download: ML19323A499 (6)

Text

_ _ _ _ _ _ _ _ _ _ -.

AVER AGE D AILY UNIT POWER LEVEL DOCKET NO.

50-368 LWIT 2 DATE 4/11/80 COMPLETED BY Ray Pandar9 raft TELEPHONE 501/968-2'519 MONTH March, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe. Net) g yw,,3,g 1

0 17 0

2 0

0 18 0

3 19 0

0 4

20 66 0

309 5

21 0

112 6

0 7

23 193 0

24 577 8

0 9

836 25 0

891

{

10 me cial Operados 0

27 891 0

80

'2 28

'3 29 261

'd 30 863

'S 3

886 16 0

INSTRUCTIONS

!h) nit,)ou r lesel m MWe Net for each da) m the repomne month. Compute to he nearest whol a-l l

(9/77 )

800.421oggg

NON-COMMERICAL OPERATION DATA END OPERATING DATA REPORT DOCKET NO.

50-368 DATE 4 /11/ An COSIPLETED BY R A-Pandergraft TELEPHONE Enl/ ORA-2519 OPERATING STATUS Notn

1. Unit Name:

Arkanene Phyc193r nng - Unit p

2. Reporting Period: March 1-25. 1980

3. Licensed Thermal Power (StWt): 2Rl R

4. Nameplate Rating (Gross.\\iWe): 959

5. Design Electrical Rating (Net StWe):

419 NA

6. Stasimum Dependable Capacity (Gross 51We):

NA

7. Stasimum Dependable Capacity (Net StWe,:

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

None

9. Power Lesel To which Restricted. lf Any (Net StWe):

None NA

10. Reasons For Restrictions. If Any:

This Stonth Yr. to Date Cumulatise

11. Hours In Reporting Period 600.0 2040.0 11544.0 127.2 818.2 4646.6

12. Number Of Hours Reactor was Critical 0.0 30.5 2323.6

13. Reactor Reserve Shutdown Hours 112.0 740.1 3777.0

14. Hours Generator On-Line

15. Umt Resene Shutdown Hours nn nq 71 7

16. Gross Thermal Energy Generated 1.\\1WH) 176304.0 1acc?70 n agognR1 n

17. Gross Electrical Energ,s Generated (NIWH) 54318.0 a8c145.0 1472430.0

18. Net Electrical Energy Generated 15tWHi 50234.0 46Ca68.0 1346277.0

19. Unit Senice Factor

20. Unit Asailability Factor

21. Unit Capacity Factor (Using.\\tDC Neti NA Until Cn"arcial 0,noratinn

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nest 6.\\lonths(Type. Date.and Duration of Eacht:

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

26. Units in Test Status (Prior to Commercial Operationi:

Forecast Achiesed INITI A L CRITICA LITY 17,/c /78 INITIAL ELECTRICITY 12/?6/78 CO\\l%1ERCI A L OPER ATION 3/26/80 I"i77i

BEG 1NNING OF COMMERCIAL OPERATION OPERATING DATA REPORT DOCKET NO.

50-368 DATE 4/11/80 COSIPLETED BY R.

A. Pendergraft TELEPHONE 501/968-2519 OPERATING STATUS N

I

1. Unit Name:

Arleaneae Nnclear Ann Ifnft ?

2. Reporting Period: March 26-31. 1980

3. Licensed Thermal Power t31Wt): 2815 959

4. Nameplate Rating 1 Gross.\\lhel:

912

5. Design Electrical Rariar Net SIWel:

NA

6. 31aximum Dependabr capacity (Gross SlWe):

NA

7. Stasimum Dependable Capacity (Net 31We):

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

Nnna

9. Power Level To Which Restricted. lf Any INet Slwel:

Mo=

10. Reasons For Restrictions. lf Any:

NA This 51onth Yr..to Date Cumulatise

11. Hours in Reporting Period 144.0 1ad.0 1da n

12. Number Of Hours Reactor b as Critical 124.0 124.0 124.0

13. Reactor Resene Shutdown Hours 11.5 11.5 11.5 112.4 112.4 112.4

14. Hours Generator On.Line

15. Unit Rewne Shutdown Hours 0.0 0.0 00

16. Gron Thermal Energy Generated tilhH) 296229.0 296229.0 296229.0

17. Gro, Electrical Energy Generated 151WH) 97510.0 97510.0 97510.0 92967.0 92967.0 92967.0 iS. Net Electrical Energy Generated 151WHi 78.0 78.0 78.0

19. Unit Senice Factnr

20. Unit Asailability Factor 7A n 79 n 78.0

21. Unit Capacity Factor ICsing SIDC Neti 70.8 70.8 70.8

22. Unit Capacity Factor IUning DER Net) 70.8 70.8 70.8

13. Uni Forced Outage Rate 22.0 22.0 22.0

24. Shutdowns Scheduled Oser Nest 6 \\lonths tType. Date.and Duration of Eacht:

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

26. Units in Test Status Prior to Commercial Operation):

Forecast Achiesed INITI AL CRITICALITY INITIAL ELECTRICITY CO\\l\\tERCIAL OPER ATION 1o/77i

REFL 9'NG INFORMATION 1..

Name of facility.

Arkansas Nuclear One - Unit 2 2.

Scheduled date for next refueling shutdown. 3/19/80 l

3.

Scheduled date for restart following refueling. 5/19/81 4.

Will refueling or resumption of operation thereaf ter 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 c6nfiguration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the l

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. 1/19/81 r

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 7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 58 (new. normallv stored in new fuel pit) 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 4A6 increase size by n

9.

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

DATE:

1089

. ~.

.. -..... -.... ~.................;

UNil SilUIDOWNS AND POWEll RLI)UCilONS DOCK ET NO.

50-368 UNIT NA%f E ANO-Unit II DATE.@/_11/b0 COMPLETED BY Rex Pendergraft March RI:POR I MON DI lELEPilONE sni oAn-9sio

.*e

E E.,9,

=,

ae s

., s '.;

i.itensee gt Cause A Corrects.e E_

No.

Daic y,

.V 4

.h ;g 5 I.veni tv f M'

Asian to

$5 5

5 6; !

Reposi:

(E U E'

Pseveni llecurrente o

C 80-04-2 1-29-80 S

456.6 B

2 NONE N/A N/A Scheduled reactor trip per power

~

escalation testing sequence.

80-05 3-20-80 F

i1.6 A

3 NONE IA INSTRU "CPC" Cenerated trip. CEA #26 dropped. Rod was recovered.

80-06 3-22-80 S

19.82 B

2 NONE N/A N/A Scheduled trip per T.P. 2.800.01 Appendix BB I

80-07 3-28-80 F

11.5 A

3 NOIIE llc INSTRU Main feedwater pump trip due to loss of level indicator on condenser hotwell.

Indicator was repaired.

80-08 3-28-80 F

8.5 11 3

NONE TA INSTRU "CPC" Cencrated range limit trip.

CPC' tripped reactor at-0.6 ASI (Axial Shape Index)

I 2

4 4

F ' Forced Reason:

Method:

Estubii G - Inst ructions S. Scheduled A l'quipment failure (Explam) i 41 annal for Preparation of Data 1 Maintenance of lest 241anual Ser.sm.

linisy Sheets for Licensee C. Refueling 1 Automatic Scram.

then: Repos e (LLill File iNtlRLG-D Regulatory Restsicsson

-1 Other (Esplaml 01bl) liOpesato: 1:ainmg & L nense liuminaison F.Admisminati.c 5

G Opesaiion.d I s e.. ( f s pl.n.O lahibii I. Same Sontee l')/77) 11 Othes (l;splaud

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- MARCH, 1980 UNIT TWO The unit was shutdown at the beginning of this reporting period for TMI related modifications. During a surveillance test on the #1 Emergency Diesel Generator, the generator shaft failed which extended the scheduled outage.

On 3/18/80 at 19:30, the reactor was critical and then tripped at 22:30 the same.

day due to a control rod dropping to the bottom of the core. The reactor was critical again at 03:42 on 3/19/80 and later tripped at 15:53 the same day due to low steam generator level, caused by feedwater control oscillations. Both the above trips were at low power levels and with the generator off line. At 18:18 on 3/19/80, the reactor was brought back to critical operation and power escalation was started. At 13:39 on 3/20/80, the unit tripped from approxi-mately 44% full power due to a Control Element Assembly Calculator failure.

The unit returned to power at 17:55 on 3/20/80 and operated until a scheduled trip was performed per the power escalation testing sequence (20% Full Power Station Blackout Test, TP 2.800.01, Appendix BB). At 18:15 on 3/22/80, the unit returned to power operation and escalated to 100% full power.

The unit was declared commercial at 24:00 on 3/25/80. A reactor trip from 100% full power was experienced on 3/28/80 due to a main feedwater pump tripping. Cause of the main feedwater pump trip was found to be due to a loose wire connection on the condenser hotwell level indicator.

While returning to power (approxi-

=ately 20% power), the unit tripped on a Core Protection Calculator range limit trip (minus.6ASI).

The unit returned to power on 3/29/80 and has remained at 100% full power for the remainder of the conth.

-l l

.