ML20027E823

Monthly Operating Rept for Oct 1981

ML20027E823
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/10/1981
From:	Bramlett L ARKANSAS POWER & LIGHT CO.
To:
References
NUDOCS 8211160215
Download: ML20027E823 (6)

Text

.

OPERATING DATA REPORT DOCKET NO. 50-368 DATE 11/10/61 COMPLETED BY

-l. S. Bramlett 501-964-3155 TELEP110NE OPERATING STATUS N "'

Arkansas Nuclear One - Unit 2

l. Unit Name:

October 1 - 31, 1981

2. Reporting Period:

3. Licensed Thermal Power (MW ):

2815 942.57

4. Nameplate Rating (Gross MWe).

912

5. Design Electrical Rating (Net MWe):

097

6. Maximum Dependable Capacity (Gross MWe):. 858

7. Masimum Dependable Capacity (Net MWe):

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

None None

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

10. Reasons For Restrictions. If Any: _N/A This Month Yr.-to Date Cumulative 745.0 7296.0 14040.0

11. Ilours In Reporting Period 466.3 4436.0 9466.8

12. Number Of Ilour, Reactor Was Critical 154.2 209.1 1013.7

13. Reactor Resene Shutdown flours

_ 4227.2 9143.2 439.9

14. Ifours Generator On-Line 0.0 0.0 75.0

15. Unit Resene Shutdown 11our, 1095955.

10425997.

22270159.

16. Gross Thermal Energy Generated (MWii) 358990.

3401375.

7234276.

17. Gross Electrical Energy Generated (MWill 341631.

3240930._

6888127.

18. Net Electrical Energy Generated (MWH) 59.0 57.9 65.1

19. Unit Senice Factor 59.0 57.9 65.7

20. Unit Availability Factor bd.4 51.8 57.2

21. Unit Capacity Factor (Using MDC Net) 50.3 48.7 53.8

22. Unit Capacity Factor (Using DER Net) 41.0 13.8 21.5

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Next 6 MonthsIType.Date.and Duration of Each1:

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

26. Units in Test Status IPrior to Commercial Operationi:

Forecast Achieved INITI A L CRITICALIIY INITI A L ELECTRICITY CO\\l\\lERCI AL OPER ATION 8211160215 811110 PDR ADOCK 05000368 R

PDR p,p7,

e AVER AGE DAILY UNIT POWER LEVEL 50-368 DOCKET NO.

2 UNIT 11/10/81 DATE

~

COMPLETED BY L. S. Bramlett.

(501) 964-3155 TELEPHONE October MONns DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)

(MWe-Net) 0 37 880' 889 2

0 ig 890 3

0 39 889 4

0 20 5

0 883 21 22 835 6

0 7

0 890 23 i

8 0

24 885 9

0 258 25 10 0

26 476 in 55 854 27 687 884 33

,g 877 13 21 29 i4 94 880 39 15 665~

591 3:

16 843 l

INSTRUCTIONS On this format, hst the aserage daily unit powc lesel in MWe-Net fur caeh day in the reporting month. Compute tu the nearest whole megawait.

9 (9/77) l I

e NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- OCTOBER, 1981 UNIT II The unit began the month at cold shutdown in a continuation of Outage 81-20 for the repair of feedwater heater extraction line expansion joints and other maintenance. The unit was placed on line 10-11-81 and reached 100% FP on 10-12-81.

Later that day the unit tripped due to a high MSR level.. The unit was returned to power on 10-13-81 but was shut down later that day due to high oxygen in the feedwater.

The unit was returned to Mode 1 on 10-14-81, but tripped on low S/G 1evels later that day. On 10-15-81 the unit reached 100% FP and operated until 10-25-81 when it tripped on low DNBR/high LPD due to a RCP spurious trip. Later that day during power escalation, the unit tripped on a deviation in misalignment of a PLCEA. The unit was returned to 100% FP on 10-27-81 and operated the remainder of the month. On 10-31-81 power was reduced to 60% in order to place a "B" MFW pump in service.

• e l

e e

b

.-,-m

i DOCKET NO.

50-368 UNIT SilVTDOWNS AND POWER REDUCTIONS UNIT NAME ANO-II DATE 11 R R1 COMPLETED BY t e n,,i-REPORT MONTil October TELEPHONE (501) 964-3145 a

3?

3

.EE Licensee

[-r, l7, Cause & Corrective

-?

gl Action to No.

Date i

3g il 2s5 Event g

U Report a mV 5

Prever.1 Recurrence H

y-5 3 ;f3 =

O e

6 81-20 810927 F

241.2 A

4 None llJ PIPEXX Shutdown to make repairs on FW ex-traction line f ailure and other equip-tqent maintenance items.

81-21 811011 F

11.5 H

3 None ZZ ZZZZZZ MFW pump trip; Rx trip on low S/G level.

81-22 811012 F

12.0 H

3 None ZZ ZZZZZZ Turbine trip on high ?iSR level; Rx trip on DNBR/LPD.

81-23 811013 F

13.6 A

1 None HH PIPEXX Shutdown to repair condensate pump suction expansion joint. Excess oxygen in FW.

81-24 811014 F

7.3 H

3 None ZZ ZZZZZZ Rx trip on low S/G level.

I I

2 3

4 F: Forced Reason:

Method:

Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintqnance of Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3 Automatic Scram.

Event Report (LER) File (NUREG-D-Regu!atory Restriction 4-Continuation 0161)

E-Operator Training & License Examination 5-Load Reduction 5

F Administrative 9-Other G-Opcutional Error (Explain)

Exhibit I - Same Source (9/77) ll Other (Explain)

.t 1

ET O UNIT SilUTDOWNS AND POWER REDUCTIONS O

DATE 11-3-81 COMPLETED BY 1-R_

n r.,m 1,, r e REPORT MONTil October TELEPHONE /;nli or, A_ ti z5

~:.

c

.! ?

3 4YE Licensee

--r, ft Cause & Corrective 3

Action to No.

Date g

3g i;

.s s 5 Event g'g gg H

fE jg Report r en o Prevent Recurrence g

d 81-25 811025 F

9.0 11 3

None ZZ ZZZZZZ "D" RCP Trip; Rx Trip on DNBR/LPD.

81-26 811025 F

'10.5 II 3

None ZZ ZZZZZZ Rx Trip on DNBR; dropped PLCEA.

81-27 811031 S

0.0 B

1 None ZZ ZZZZZZ Reduced power to 60% in order to placc "B" MFW pump in operation.

I 2

3 4

F: Forced Reason:

Method:

Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B. Maintenance ci Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3 Automatic Scram.

Event Report (LER) File (NUREG-D Regulatory Restriction 4-Continuation 0161)

E-Operator Training & License Examination 5-Load Reduction 5

F Administrative 9-Other G-Operational Eirur (Explain)

Exhibit 1 - Same Source 19/77)

Il-Other (Explain)

REFUELING INFORMATION 1.

Name of facility.

Arkansas Nuclear One - Unit 2 2.

Scheduled date for next refueling shutdown. 9/1/82 3.

Scheduled date for restart following refueling. 11/1/82 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.

Description of effects of new core loading.

5.

Scheduled date(s) for submitting proposed licensing action and supporting information. 6/1/82 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.

Possible utilization of Core Protection Calculator (CPC) semi-addressable constants.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 60 l

8.

The present licensed spent fuel pool storage capacity and the size l

of any increase in licensed storage capacity that has been requested l

or is planned, in number of fuel assemblies.

I increase size by 0

l present 485 9.

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

to the spent fuel pool assuming the present licensed capacity.

DATE:

1989 I