ML20031A323

Monthly Operating Rept for Aug 1981

ML20031A323
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/14/1981
From:	Bramlett L ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20031A322	List: 1CAN098105, Forwards Monthly Operating Rept for Aug 1981 ML20031A323
References
NUDOCS 8109230136
Download: ML20031A323 (5)

Text

.

OPERATING DATA R EPORT DOCKET NO.

DATE 9/14/81 COSIPLETED BY Rramlett TELEP110NE 968-2519 OPERATING STATUS N"

Arkmsas Nuclear One - Unit 1

1. Unit Name.

2. Reporting Period: Angint 1 - 11

3. Licensed Thermal P. ver (SIWI): 2568

4. Nameplate Rt. ting (Gross Slwe): 902.74 7

5. Design Electrical Rating (Net SIWE):

850 883

6. Staximum Dependable Capacity (Gross SIWE):

836

7. Staximum Dependable Capacity (Net SlWe):

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

None None

9. Power Lesel To which Restricted. lf Anv (Net SIWE).

10. Reasons For Restrictions. If Any: _ NA This Slonth Yr.-to.Date Cumulatise 744.0 5831.0 58746.0 II. Ilours in Reporting Period 523.3 3530.9 39321.2

12. Number Of Hour, Reactor was Critical

13. Reactor Reserve Shutdown flours 0.0 149.0 5044.0 501.3 3414.6 38459.6

14. Ilours Generator On.Line 0.0 0.0 817.5

15. Unit Resene Shutdown Hours

16. Gross Thermal En. rgy Generated ($1Will 1_254205.

8370027.

92541993.

409380.

2780255.

30478816.

17. Gross Electrical Energy Generated (SlWil) 390206.

2653949.

29069588.

18. Net Electrical Energy Generated (51Will 67.4 58.6 65.5

19. Unit Senice Factor 67.4 58.6 66.9

20. Unit Asailability Factor 02*7 54.4 59.2

21. Unit Capacity Factor (Using SIDC Net) 6I./

53.5 58.2 l

22. Unit Capacity Factor (Using DER Net) 32.6 15.3 17.1

23. Unit Forced Outage Rate

24. ShutdowniScheduled Oser Next 6 Slonths 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 A L CRITICA LITY INIIIA L ELECT RICITY

(

CO\\l\\lERCI AL OPER ATION k

to/77i R

AVERAGE DAILY UNIT POWER LEVEL 50-313 DOCKET NO.

UNIT 1

DATE 09/14/81 L. S. Bramlett COMPLETED BY 501-968-2519 TELEPHONE MONE August DAY AVERAGE D AILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(MWe-Net) i 801 786 37 801 775 is

~

3 80G 777 19 4

798 784 20 s

797 241 21 794 0

6 22 7

795 0

23 797 0

8 24 9

798 10 795 0

26 1I 798 0

27 12 800 0

2t 13 798 0

29 798 14 30 0

15 792 148 31 16 787 INSTRUCTIONS On this format. list the average daily unit power leselin MWe Net for each day in the repornng month. Compure to the neara=1 whole megawatt.

(9/77 )

j

1 NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- AUGUST 1981 UNIT I Unit I began the month at 100% power and continued there until August 15, 1981. As in the previous months, ' fouling of the tube sheet support plates in the "A" OTSG, with the resulting increase in downcomer level re-quired a reduction in Unit power. A gradual reduction of power was begun on August 15 and by August 20 m steady state condition at 97%

full power was achieved. On August 21, Unit I tripped on the power /

pump circuit when power was temporarily lost to the "A" and "C" RCP's.

A bolt in a diode heat sink on the diode wheel of the Main Generator Exciter had worked loose causing a short to ground of the Generator Exciter field. The resulting turbine trip and load shed caused a temporary loss of power to "A" and "C" RCPs. The Unit was brought to cold shutdown and remained down until August 30, to affect repairs on the Main Generator Exciter and "A" and "d" t..~

seals. Unit I went critical at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on August 30, and the generator was placed on line at 0340 hours0.00394 days <br />0.0944 hours <br />5.621693e-4 weeks <br />1.2937e-4 months <br /> August 31.

At 0411 hours0.00476 days <br />0.114 hours <br />6.795635e-4 weeks <br />1.563855e-4 months <br /> on August 31 with the reactor at approximately 9% full power the Main Turbine tripped when a diaphragm between the lubrication oil and the electrohydraulic control fluid in the turbine auto stop valve ruptured. The diaphragm was re-placed and the generator was back on-line at 1028 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91154e-4 months <br />, August 31.

Unit I ended the month at approximately 26% full power in trancit to 100% full power.

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r DOCKET NO. 50-313 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME ANO-Unit 1 DATE S.cL.Ismbgr 3_

1981 COMPLETED BY.T _ Cort,r h REPORT MONTH Anmmr TELEPHONE (sn i) o AA_3155

.! ?

3 Yk Licensee

,En,

'q, Cause & Corrective No.

Date i

3g j

.3 g 5 Event u?

c'?

Action to

~ 5 =j

, Report *

(A V 5'

Prevent Recurrence

$~

u u

e C

81-10 810821 F

236.4 A

3 N/A HA CENERA Rx tripped on power / pump circnit when power was temporarily loss to "A" and "C" RCP's.

A bolt holding a diode heat sink to the diode wheeI of the Main Generator Excito r had worked loose causing a short to ground of the Exciter Field.

The subsequent turbine trip and load shed tripped the Rx on the power / pump circuit. Repaired exciter diode heat sinks and diode uheel.

81-11 810831 F

6.3 A

N/A N/A HA MECFUN Turbine tripped when auto stop eil valve diaphragm ruptured. Replaco 1 diaphrags l

I 2

3 4

F: Forced Reason:

Method:

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

En -) Sheets for Licensee C Refueling 3 Automatic Scram.

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

E-Operator Training & License Exammation 5-Lcad Reduction 5

F Administrative 9-Other G. Operational Eirur (Explair.)

Exhibit ! - Same Source (9/77)

Il-Other (Explain)

REFUELING INFORMATION 1.

Name of facility.

Arkansas Nuclear One - Unit 1 2.

Scheduled date for next refueling shutdown.

1/1/83 3.

Scheduled date for restart following refueling.

3/15/83 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

If ansvar is yes, what, in general, will these be?

If answer is no, has the reload fuel desiga 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.

Reload report and associated proposed Technical Soecification chanaes. Also, the safety analysis of 4

eiaht demonstration high burn-up asscmblies will be provided.

5.

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

10/1/82 6.

Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unrevicwed design or performance analysis methods, significant changes in fuel design, new operating procedures.

Will reload 72 fresh fuel assemblies and operate for approximately 16 months.

Eight of which will be high burn-un test astemblips.

7.

The number of fuel assemblies (a) in the cora and (b) in the spent fuel storage pool. a) 177 b) 244 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 589 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:

1986

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