ML19338D534

Monthly Operating Rept for Aug 1980

ML19338D534
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/15/1980
From:	Pendergraft R ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19338D533	List: ML19338D532 ML19338D534
References
NUDOCS 8009230410
Download: ML19338D534 (6)

Text

..

3 AVERAGE' DAILY UNIT POWER LEVEL.-

DOCKET NO.

~50-368

~

UNIT 2

DATE 9/ 15/ 80 COMPLETED BY' Rex Pendergraft -

TELEPHONE _(501) 968-2519 MONm

~ August; 1980 D AY-AVERAGE DAILY POWER LEVEL ~

DAY AVERAGE DAILY POWER LEVEL

.(MWe Net) ggwe.geg) 1 R65 g7 794 2

- 865 599 is 3

868 i9 195 4

- 866 20 838

-5

- 866 21 743 6

864 22 0

7

~ ~864 742 23 8

864

-24 867

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'9 865 25 865 lo 865" 26 865

-11

- 80 8 865 27 12 _

827 33 868 13-

866 29 871 14 866 871 30 3

869

. 15.

531' 16 19 8 l

l INSTRUCTIONS.

On this format list the avenge daily unit power lesel in MWe-Net for cach day in the reporting month. Compute to the nearest whole megawatt.

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- OPERATING DATA REPORT DOCKETNO. 50-368 DATE 9/1b/80

. COMPLETED BY KeX Pendergraft TELEPHONE (bu11965-z519

' OPERATING STATUS '

1.' Unit Name: Arkans as i Ny. clear. One - - Uni t 2' Notes

2. Reporting Period: ' Augus t 1 - 31. lo Art "3. Licensed Thermal Power IMWtli:

2815:

4. Nameplate Rating (Gross MWeji

-959 L 5." Design Electrical Rating tNet MWe):

912

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J6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe):

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

NONE 1

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9. Power 1.evel To which Restricted. lf Anv (Net MWe):

NONE N/A

10. Reasons For Restrictions. lf Any.

2 u

- This Month Yr..to-Date Cumulative.

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11. Hours in Reporting Period.

'744.0 3815.0 3815.0 i

J12. Number Of Hours Reactor Was Critical 700.1

'3148.2 3148.2

13. Reactor Reserve Shutdown Hours 42.4 124.8

-124.8

-14. Hours Generator On-Line

'691.7 3099.9 3099.9

15.. Unit Rewne Shutdown Hours -

0.0 75.0 75.0

16. Gross Thermal Energy Generated IMWH) 1845897.0 7773645.0 '

7773645.0 ~

17. Gross Electrical Erbrgy Generated (MWH) 593560.0 2523800.0 2523800.0

18. Net Electrical Energy Generated (MWHI ;

566350,0 2404879.0 2404879.0-

19. Unit' Service Factory 93.0

-81.3 81.3 4 20. Unit AsailabilitiFactor ;

93.0 83.2-

<83.2

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83.5 69.1~

69.1

21. Unit Capacity Factor (Using MDC Net) 83.5 64.-1 69.1-

22.. Unit Capacity Factor (Using DER Net).

23. Unit Forced Outage Rate' 7.0 18.7'

18.7

24. Shutdowns Scheduled 0 er Next 6 Months (Type. Date and Duration of Each):

3

' March :15 -.1981 to May '15,1981. Refue1ina

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

26. Units in Ted StatA (Prior to Commercial Operation):

Forecast Achieved

~,1NITIA L CRITICALITYJ

- INITIAL ELECTRICITY -

COMMERCIAL OPERATION -

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' UNIT SilU FDOWNS AND POWER REDUCTIONS.

DOCKET NO.

50-368J

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UNIT NAME.. ~ ANO-Ifni e 2 -

-DATE W D M COMPLETED llY ne.- p - a- --.ct:

REPORT MONTil August

.TELEPilONE 501 968-25f9

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er,

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Cause & Corrective.

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Event ag e.

Report = '

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Prevent Recurrence ~

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80-16 8-15-80l

-F 13.1 G

3 None WG ZZZZZZ Lost stator cooling.w'ater due"to human

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- error while switching Control 4 Room-chillers and main chillers.

80-17

'8-16-80 F

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3

'.ione CH.

PIPEXX Low S/G level trip from -17%-power due to faulty control oil line. fitting.

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Fitting was replaced.=

80-18

.8-18-80 F.

8.6 A

3 None Cll INSTRU Low S/G level tripifroml full power due to blown fuse in feedwater' control.

system cabinet..-Fuse was: replaced.

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Method:

Exhibit G. Instructions LM-

. S: Scheduled.

A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test.

2 Manual Scram.

Entry Sheet 5 for I.icensee r1 C Refueling 3 Autonfatie Scram.

Event Report (Ll'R) File (NUREG '

b D. Regulatory Restriction Other (E xplain) 0161) li Operator Tiaining & License Examination F-Administrative 5

(, Op. gtion..I lis ro t Expliia)

Exhibit I-Same Source Py / /)

Il Other (Explain)

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. DOCKET NO. c 50--368 -..

.f. s. p UNIT SilUI'llOWNS AND POWER REDUCTIONS.

UNIT NAME, ANO-Unit'~ 2 -

4 DATEI 9[9/W

..-COMPLETED BY1. Rav Paviovovert:

- REPORT MONTil August TELEPIIONE ' snt or,n_9 d_o_

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80 :8-21-80' F-25.6 G

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.None IA INSTRU~

Human error:,DNBR/LPD_ trips occurred -

~ on' the CPC's 'due to improper'. switching ',. ',

of inverter'~ power.

(Station battery

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to AC),

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Reason:

Method:

Exhibit G. tnstructions 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 Reppet (ITR) File t N1IREG-D. Regulatory Restriction 4 Otheg (Explain)-

0161)

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E-Operator Tsaining & Liu nse lixamination F Admin:strative 5

G-Operational *. mr (l' iplaial Exhibit I Same Source 19/ 4 )

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. September,,1980 "

- DATE:

M REFUELING ~INFORMATION*

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r 71h Name of facility Arkansas Nuciear 0ne:-- Unit:2i i

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Scheduled-date!for nextirefusling shutdown.

3/15/811 i

s 3. - Scheduleid.date for restart'following. refueling..

5/ 15/ 81

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?4. -- =Will' refueling.or resumptionLof~ operation thereafter require-a>

technical specification change:or other license amendment? -

. If Lanswer is~ yes', yhat; in general,iwill 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-CFRtSection-50.59)?-

-Yes. ' Description of effects of new core loadino.

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5.

- Schehuled-date(s) for submitting' proposed licensing action and

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supporting:information.- 1/ 15/8 1-6.-

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

'.newfor'different fue15 design or supplier, Onreviewed design or performance analysis methods, significant. change's in fuel design, 7

new operating procedures.

p As part of a'research and development effort.-two fuel assemblies-will? be loaded possessing design characteristics related to ' extended burnuD.

i-The number of-fuel assemblies (a) in' the core and (b) in the spent.:

7.'

fuel storage poo1~.~

a) 1177' b) S8"(New, normalTy stored in

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n new fuel.p1t) l.

. 8.'

The presentW11 censed' spent fuel l pool storage capacity and the size.

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offany l increase in l' censedistorage capacity that has been requested

?or -is; planned,:;in number of' fuel ~ assemblies.

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present-J486I

-increaseisize by 0

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. 9'. [The~ projected 'date of,the last' refueling that can'be discharged

'S to the._ spent 1 fuel ^poolfassuming the present licensed capacity.

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?NRC MONTHLY OPERATING REPORT s,

OPERATING

SUMMARY

.- AUGUST,,1980

_ UNIT II-p The Unit was operating 'at 100% power at the beginning;of this

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reporting period. A brush fire under the 500 kv transmission

line forced a' power reduction-to approximately 55% power on

' 8-11-80._ ;; A return _.to '100% power.was -accomplished early. in the morning on 8-12-80.

The Unit - tripped. from 100%. full power on the 15th of ' August;due' to loss.of stator cooling water (human error) to the' main generator. ~High generator amperage caused a generator runback. The reactor tripped on high RCS pressure.

While-returning to power on 8-16-80, the ~ reactor tripped from

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approximately 17%'fuir power dueito low steam generator level.

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Investigation revealed an oil leak. on the electrohydraulic

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' control oil' system for.the' main feedwater. pumps causing the steam ~ generator level'. problem. - A faulty oil line fitting'was replaced'and.a return to 100% full. power operation was accom-

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plished on. 8-17-80.

On 8-18-80 a blown fuse in:the main feed-

l water control cabinet caused-a reactor trip'from.100% power duetto_ low steam generator level..The blown fuse was replaced and 100% power operation ~was reached on 8-19-80.

A brush fire under-a 500'kv transmission ~line caused a forced power reduction

to_approximately 60% power on 8-21-80.

While returning to full

~

. power. operation,:a. reactor trip was experienced from 90% power.

DNBR/LPDl trips were received on the "B" & "D" core protection calculators causing the. trip logic to automatically trip the

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reactor.

Cause.of the.DNBR/LPD trips were attributed to human

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error. An. improper method.of transferring inverter power from R

station batteries to primary AC caused a voltage spike _which.

initiated.the DNBR/LPD trips. The Unit returned to 100% full power on 8-23-80;and has operated at full power for the' remain-der of the reportin'g period.

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