ML19344A786

Monthly Operating Rept for Jul 1980

ML19344A786
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/15/1980
From:	Pendergraft R ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19344A785	List: ML19344A784 ML19344A786
References
NUDOCS 8008220207
Download: ML19344A786 (5)

Text

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AVERAGE D AILY UNIT POWER LEVEL.

DOCKET NO. 50-368 UNIT 2

DATE 8/15/80 COMPLETED BY Rex Pendergraft TELEPHONE (501) 968-2519 uly, 1980 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe Net) g gw,,3,,,

1 0

17 865 2

18 866 3

461 19 865 4

787 20 864 5

811 867 21 6

'811 868 22 7

380 872 23 8

452 24 185 i

9 848 25 730 10 862 26 866 11 863 27 855 I2 861 8

g77

.13 862 29 869 864 14 30 865 863 15 31 864 16 861 l

INSTRUCTIONS On this forrnato list the average d:ily unit power lesel in MWe. Net for each day in the reponing inonth. Cornpute to the nearest whole rnegawatt..

i (9071 8008220 2,0 7

OPERATING DATA REPORT DOCKET NO. 50-368 DATE 2

COMPLETED BY. Rex Pendergraft TELEPHONE (501) 968-2519 OPERATING STATUS rkansas Nuclear One - Unit 2 Notes

1. Unit Name:

2. Reporting Period:

July 1 - 31, 1980

3. Licensed Thermal Power (MWt):

2815 959

4. Nameplate Rating (Gross MWe):

912

5. Design Electrical Rating (Net MWe):

Not Yet Determined

6. Maximum Dependable Capacity (Gross MWe):

Not Yet Determined

7. Maximum Dependable Capacity (Net MWe):

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

None i

9. Power Level To which Restricted,if Any (Net MWe):

None

10. R'easons For Restrictions,if Any: N/A This Month Yr. to.Date Cumulatise 744.0 3071.0 3071.0

11. Hours in Reporting Period

12. Number Of Hours Reactor Was Critical 685.8 2448.I 2448.I

13. Reactor Resene Shutdown Hours 0.0 80.9 80.9

14. Hours Generator On.Line 679.1 2408.2 2408.2 15.' Unit Reserve Shutdown Hours 0.0 75.0 75.0

16. Gross Thermal Energy Generated (MWH) 1784930.0 5927748.0 5927748.0 573260.0 1930240.0 1930240.0

17. Gross Electrical Energy Generated (MWH) 546883.0 1838529.0 1838529.0

18. Ne't Electrical Energy Generated (MWH)

19. Unit Service Factor 91.3 78.4 78.4

~ 20. Unit Availability Factor 91.3 80.9 go,9

21. Unit Capacity Factor (Using MDC Net) 80.6 65.6 65.6

- 22. Unit Capacity Factor (Using DER Net) 80.6 65.6 65.6

23. Unit Forced Outage Rate 8.7 21.6 21.6

24. Shutdowns Scheduled Over Next 6 Months (Type.Date,and Duration of Each1:

~

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 INITIA L CRITICA LITY INITIA L ELECTRICITY COMMERCIAL OPER ATION (4/771

\\

50-368 I

UNir Silu rDuWNS AND POWER REDUCIlONS ANO - Unit 2 E

DATE _8/15/80 COMPLETED BY Rex Pendercraft REPORI MONTil

'I"lY W PilONE 501-968-75i9-

= u, 3

=

e, 4 E 's 1.icensee

,E -t l~t, Cause & Correttive 5E

=

o No,

Date r;-

3@

_5 5 5 Event 3?

9E Adion to

$3 5

55:

Rcport :

54 0 5'

Present Recurrentc

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c

~

80-13 6-24-80 F

39.2 A

3 80-042/0lT EA ELECON Outage Continued from previous month 80-14 7-7-80 F

13.9 C

3 None IA INSTRU Outage occurred when CEAC #1 was placed in the test mode with CEAC #2 in the inop mode. Unit tripped due to large penalty factor associated with both CEAC's inoperable.

80-15 7-24-80 F

11.8' A

3 None RB INSTRU CEA #48 dropped into the core due to a circuit board failure. The board was replaced and CEA #48 was functionally tested.

I 2

,1 4

1:: 1 orced Reason:

Method:

Eshini G -Instsuctions S. Scheduled A-lk uipment Failure (Explain) 1 Manual for Preparation of Data l

ll-Maintenance of Test 2 Manual Scram.

1:nir> Sheets for I.icemee C-Itcfueling

,1 Automatic St r.am.

livent Repini (1.l!R) Fde (NilRI.G.

D Itegulator) Resiriction 1 Other (Esplain) 0161) i li-Opesalor Training & license lisanunation F-Administ ralive 5

G Operalinnal I s ens (IN laia)

Estubii 1 - S.nne Source i

08/77)

Il-Ot he r i t:xplani) l

REFUELING INFORMATION 1.-

Name of facility.

Arkansas Nuclear One - Unit 2 2.

Scheduled date for next refueling shutdown.

3/19/81 3.

Scheduled date for restart following refueling. 5 / 19/ 8 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 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.

Descriution of effects of new core loadine.

1 5.

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

1/19/81

' tant licensing considerations associated with refueling, e.g.,

6.

. Im; r

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 he landed ness essing design charteteristics related to extended burnup.

7.

The nunber of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 58. (New. norma 11v 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 486 increase size by 0

9.

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

DATE:

1989

NRC MONTHLY OPERATING REPORT OPERATING SLTfARY - JULY 1980 UNIT 2 The Unit was off-line at the beginning of this reporting period due to problems associated with the 6-24-80 Unit trip of last month.

J A return to power was accomplished on 7-2-80.

The Unit tripped on 7-7-80 when Control Element Assembly Calculator (CIAC) No.1 was placed in the test mode with CEAC No. 2 in the mode. The penalty factor associated with both CEAC's being inoperable caused the Core Protection Calculators (CPC's) to trip the Unit on DNBR/LPD. The Unit was returned to power operation on the same day and operated at 100% full power until a Unit trip occurred on 7-24-80. Investiga-tion revealed a circuit board failure caused CEA No. 48 to drop into the Core. The CEA misalignment caused the Unit to trip on DNBR/LPD.

A return to power operation was accomplished on 7-24-80.

The Unit has operated at 100% full power for the remainder of July.

I 1

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