ML20066E631

Monthly Operating Rept for Nov 1981

ML20066E631
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/14/1981
From:	Bramlett L ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20066E630	List: 2CAN128101, Forwards Monthly Operating Rept for Nov 1981 ML20066E631
References
NUDOCS 8211150342
Download: ML20066E631 (5)

Text

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OPERATING DATA REPORT 50-368 DOCKr.T NO.

DATE I2/l4/81 COMPLETED BY Bramlett TELEPilONE sf11-954-3145 OPERATING STAT US Notn Arkansas Nuclear One - Unit 2

1. Uni Name:

November 1-30, 1981

2. Reporting Period:

2815

3. Licensed Thermal Power (MWt):

942.57

4. Nameplate Rating (Gross MWe):

9I2 S. Design Electrical Rating (Net MWe):

9

6. Maximum Dependable Capacity (Gross MWe):

7. Masimum Dependable Capacity (Net MWe):

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

None

9. Power Lesel To Which Restricted.lf Anv (Net MWe):

None NA

10. Reasons For Restrictions.If Any:

This Month Yr..to.Date Cumulatise 720.0 8016.0 14760.0 l

11. Ilours In Reporting Period 700.2 5136.2 10167.0

12. Number Of Hours Reactor Was Critical 0.0 209.1 1013.7

13. Reactor Resene Shutdown flours 690.2 4917.4 9833.4 l

14. Ilours Generator On.Line 0.0 0.0 75.0

15. Unit Resene Shutdown liours 1664622.

12090619.

23934781.

16. Gross Thermal Energv Generated (MWill 538426.

3939801.

7772702.

17. Gross Electrical Energv Generated (MWHf 511284.

3752214.

7399411.

l

18. Net Electrical Energv Generated (MWH1 95.9 61.3 66.6 l

19. Unit Senice Factor 95.9 61.3 67.1 f

20. Unit Availability Factor 82.8 54.6 58.4

21. Unit Capacity Factor (Using MDC Neti 77.9 51.3 55.0

22. Unit Capacity Factor (Using DER Net) 4.I 12.6 20.5

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date and Duration of Eachl:

None

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

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

Forecast Achiesed INIII A L CRIIICA LITY INITI A L EL ECTRICITY CO\\l\\lERCI A L OPER ATION 8211150342 811215 DR ADOCK 05000368 (0/77 )

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AVERAGE DAILY UNIT POWER LEVEL 50-368 DOCKET NO.

LwrT 2

DATE 12/14/81 COs1PLETED By Bramlett TELEPif0NE 501-964-3145 MONUf November DAY AVERAGE DAILY POWER LEVEL DAY AVER ACE DAILY POWER LEVEL (MWe Net)

(MWe Net) i 593 876 i;

861 875 2

jg 3

RA3 19 876 4

482 877 20 97 874 5

21 6

291 873 376 468

~

7 23 8

371 24 737 9

4ll 872 25 713 872 10 26 808 II 412 2,

12 874 645 2s 873 871 13 872 14 869 30 15 872 N/A 3:

872 16 l

INSTRUCTIONS On this format.hst the arc:qc daily unit pov.cr leselin Mwe Net fuI cach da) in the repornne month. Compute to I

l e nearest whole megawatt.

t 4

(9/77 )

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NRC MONTHLY OPERATING REPORT OPEPATING

SUMMARY

- NOVEMBER, 1981 UNIT 2 The Unit began the month at 60% power for checkout and operation of "B" Main Feedwater Pump.

On 11-2-81 the Unit reached 100% power operation.

The Unit operated at 100% until the reactor tripped on 11-4-81 due to a Channel 3 and 4 low DNBR trip. The low DNBR was traced to an anomalous T in c n.

e nit was returned to H

Mode 1 on 11-5-81, however, the reactor tripped on ASI limits.

The Unit was again returned to Mode 1 on 11-5-81 and remained at approximately 50% power while searching for condenser tube leaks until 11-9-81.

100% power operation was obtained on 11-11-81 and the Unit operated there for 12 consecutive days. On 11-23-81 the Unit was tripped due to an I&C technician inadvertently causing the supply breaker for "A" Steam Generator level to trip. The Unit reached 100% power operation on 11-24-81.

On 11-27-81 the Unit tripped on a spurious control signal causing a feedwater flow upset.

Later that day Mode 1 was reached and the Unit was manually tripped when both Main Feedwater Pumps tripped.

The Unit was returned to 100% power operation on 11-28-81 and operated there the remainder of the month.

e P

A l

4 DOCKET NO.

50-368 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N AME ANO-II DATE 12-3-81 REPORT MONTil November COMPLETED BY T-

<- Rrnmlort TELEPHONE (5n1) 964-3145 P

~i-

=

m 3m 5

.2 _e

,5X Licensee g-t

=%

Cause & Corrective No.

Date g

3g 3,

,g g g Event sg S.~2 Action to o

j0

$E 5

j di g Report e 80 Prevent Recurrence 6

81-28 811104 F

12.7 H

3 None ZZ ZZZZZZ Unit trip on low DNBR due to Anomalous T inputs to the CPC's.

H 81-29 811105 F

2.1 H

3 None ZZ ZZZZZZ Unit trip on high LPD due to ASI.

81-30 811123 F

5.1 G

3 None ZZ ZZZZZZ Unit trip on low S/G 1evel when the level instrumentation's power sup-ply tripped. (Human Error) 81-31 811127 F

5.3 H

3 None ZZ ZZZZZZ FW Flow upset; spurious 81-32 811127 F

4.6 H

1 None ZZ ZZZZZZ FW pumps tripped; Rx manually tripped. Spurious l

2 3

4 F: Forced Reason:

Method:

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

Entry Sheets for Licensee C Refueling 3-Automatic Scram.

Event Report (LER) File (NUP.EG-D Regulatory Restriction 4-Continuation 0161i E-Operator Training & License Examination 5-Load Reduction 5

F Administrative 9-0ther G-Operational Error (Explain)

Exhibit I - Same Source 19/77) 110ther (Explain)

.N, a

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REFUELING INFORMATION 1..

Name of facility.

Arkansas Nuclear One - Unit 2 -

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 licenss 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 c

core reload (Ref.10 CFR Section 50.59)?

Yes.

Description of effects of new core loading.

sy dh

• s,

-t w.

5.

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

6/1/82

%2" -

1 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.

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

5 l

7.

The number of fuel assemblies- (a) in the core and (b) in the spent fuel storage pool, a) 177 b) 60 t

8.

The present licensed spent fuel pool 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.

l present 485 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.

i DATE:

1989 i

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