ML20062F899

Monthly Operating Rept for June 1982

ML20062F899
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/09/1982
From:	Bramlett L ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20062F894	List: ML20062F890 ML20062F899
References
NUDOCS 8208120197
Download: ML20062F899 (6)

Text

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OPERATING DATA REPORT 4

i DOCKET NO.

50-368 DATE // 9/W COMPLETED BY l.S. Bramlett i

TELEPHONE (501) 964-3145 OPERAllNG SI A IUS N"

Arkansas Nuclear One - Unit 2

1. Unit Name:

June 1-30, 1982

2. Reporting Period:

2815

3. Licenwd 'Ihermal Power 15thi):

942.57

4. Nameplate Rating (Grow Mhe):

912

5. Design Electrical RatingiNet MWet 097

6. Masimum Dependable Capacity (Grow MWe)-

858

7. Masimum Dependable Capacity INet Mhe):

M. If Changes Occur in Capacity RatinFs (items Number 3 through 7) Since Last Report. Gise Reasons:

i NONE

9. Power Lesello hhich Restricted,if Any (Net MWe):

N/A

10. Reasons l'or Restrictions,if Any:

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T his Month Yr. to Date Cumulatise i

720.0 4.343.0 19847.0

11. Ilours in Reporting Period 511.2 3,187.2 14081.8

12. Number Of flours Reactor was critical

13. Reactor I.esene Shutdown llour,,

0.0 324.8 1338.5 501.5 3,137.0 13,678.8

14. Ilours Genetor On Line 0.0 0.0 75.0 l

15. Unit Rewne Shutdown llours

16. Grow Thermal Energv Generated aMWID 1_,329716.

_8J19604.

34.005473.

17. Grow I lectrical l{nerg) Generated t \\lWil) 424,526.

2,642692.

11,0_14610.

404,466.

2519_184.

10,490182.

l lS. Net Electrical Energ) Generated IMhill 69.7 72.2 68.9

19. Unit Senice Factor 69.7 72.2 69.3

20. Uni Asailabilits Factor

21. Unit Capacity Factor (Using Ml)C NetI 65.5 67.6 61.6 61.6 63.6 58.0

22. Unit capat-ity Factor iCsing i)ER Net, i

23. Unit Forced Outage Rate 30.3 27.8 21.6

24. Shutdowns Scheduled Oser Nest 6 Months tType. Date,and Duration of Each).

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

26. Units in lest Status iPrior to Commercial Operation):

1orecast Achiesed INil l \\ l. CRillCTI.ll Y INill \\ l. Ell C I Rifi f Y i

( OMMI RCI \\L Orl.R \\IlON i

I 8208120197 820714 P'/77 8 PDR ADOCK 05000368 R

PDR

AVER AGE DAILY UNIT POWER LEVEL 50-368 DOCKET No.

2 Unix DATE 7/9/82 COMPLETED BY L.S. Bramlett TELEPHONE (501) 964-3145 M O N ril June, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) iMWe-Net )

I 867 17 46 2

870 705 18 389 860 3

19 0

863 4

20 0

863 s

21 0

844 6

22 0

861 7

23 0

861 8

24 0

858 9

25 0

861 to 26

??

861 ii

. ' ' - ~

27 un.:

862

s 792 859 13 9

857 858 14 30 857 15 38 553 l

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INSTRUCTIONS Ori this torrnst.hst the.ncoge dash umt pov.er leselin MWe Net for cach da) m the re;<ortmp month. Lumpuie to the nearest whole meyawait.

19177)

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WP-0400 i

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NRC MONTIILY OPERATING REPORT JUNE, 1982 - UNIT 2 The Unit began the month at 100% full power until 6/3/82 when it was shutdown due to repairing a motor operated isolation valve of f the pressurizer. The Unit remained shutdown until 6/11/82 when the reactor was taken critical. Operation at 100% power was reached on 6/13/82.

On 6/16/82 the Unit tripped on DNBR (exact cause unknown).

The Unit was returned to 100% power on 6/18/82 and continued there through the remainder of the month.

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DOCKET NO. }0-W UNII SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Ah i

DATE W82 COMPLETED BY L.

S.

Bramlett i

REPORT MONTH June TELEPHONE 501 964-3145 Licensee 5-t, Cause & Corrective

.! ?

3 h $h Date c-ti E 4

2 :E $

Event 7?

F- ?

Action to i

2 Report =

EC Prevent Recurrence 3d=!

C

.c v

6 82-08 820603 F

197.2 A

1 N/A CA VALVEX Packing leak on a 'rnotor operated isolation ~ valve. The valve was i

repacked i

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82-09 820616 F

21.3 II 3

N/A ZZ ZZZZZZ The unit tripped on DNBR.

The exact cause is unknown.

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F: Foiced Reason:

Method:

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

Entry Sheets for Licensee i

C-Refueling 3 Automatic Scram.

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

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

F-Administrative 9-0ther I

G-Operational Er ror (E xplain t Exhibit I - Same Source 19/77)

Il-Other (Explain) f

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j UNIT SHUTDO'.NS AND POWER REDUCTIONS INSTRUCflONS i

This report should describe all plant shutdowns during the in accordance with the table appearmg on the report toim.

)

3 report period, in addition,it should be the source of explan.

if category 4 must be used. supply hnef comments.

l ation of significant dips in average power levels. Each signi.

ficant reduction in power level (greater than 20% reduction LICENSEE EVENT REPORT u.

Reference the apphcable in average daily power level for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

'eportable occurrence pertaining to the outage or power should tie noted, evcn though the unit may not have been reduction. 1:nter the first four parts (event year, sequennal shut down completely. For such reductions in power level, report number, occurrence code and report type) of the Ine l

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the duration shouhl be listed as zero, the method of reduction part designatmn as desenbed in item 17 of Instructions im

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should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Event Repon I

Action to Prevent Recenence column should explain. The (LER) f ile (NUREG.0161) This mlormation may not be Cause and Corrective Action to Prevent Recurrence column i mediately endent for all such shutdowns of course, smce should be used to provide any needed explanation to fully further msestigation nuy be requaed to ascertam whether or desenbe the en umstances of the outage or power reduction.

not a reportable occurrence was mvolvedd if the outage or power reductmn will not result m a reportable occurrence.

NUM13ER.

• his column should indicate the sequential num, the posmve mdication of this bok of conebnon should be ber asugned to each shutdown orsignificant reduetionin power noted as not appheable (NIA).

for that calendar year. When a slutdown or significant power SYSTEM CODE. The system m which the outage or power reduction begins in one report period and ends m another.

an entry should be made for both report periods to be sure reduction originated should be noted by the two digit code of all shutdowns or significant power reductions are reported.

Exhibit G. Instructions for Preparation of Data Entry Sheets Until a unit has achieved its first power generation, no num, for Licensee Lvent Report (LER) File (NURIL0161).

ber should be assigned to each entry.

Systems that do not fit any existmg code should be designa-ted XX. The code ZZ should be used for those events where DATE. This column should mdicate the date of the start a system is not appheable.

of each shutdown or significant power reduction. Report as year, month, and day. August 14,1977 would be reported COMPONENT CODE. Select the most appropnate component as 770814. When a shutdown or significant power reduction from Exhibit ! Instractions for Preparation of Data Lntr>

begms m one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NURI G-Olot L be made for both report periods to be sure all shutdowns using the followmg entieria.

or significant power reductions are reported.

IYPE. Use "F" or "S" to mdicate either " Forced" or " Sche.

duled," respectively, for each shutdown or significant power B.

If not a component failure, use the related component reduction. Forced shutdowns include those requned to be e.g.. wrong valve operated through error: hst valse as iniuated by no later than the weekend following discovery component.

of an off normal condition. It is recognized that some judg.

ment is required m categoriang shutdowns in this way, in C.

If a cham of failures occurs. the first component to mal.

general, a forced shutdown is one that would not have been funcuon should be listed. The sequence ut events. melud-completed in the absence of the condition for w hich corrective ing the other components which fail. should be described action was taken unJer the Cause and Corrective Acuon to Prevent Recur.

rence column.

DURATION. Self. explanatory. When a shutdown extends beyond the end of a report penod. count only the time to the Components that do not fit any existing code should be de.

signated XXXXXX. The code ZZZZZZ should be used for end of the report period and pick up the ensuing down time e

ha omponent. deugnation a not apphcable.

m the following report penods. Report duration of outages rounded to the nearest tenth of an hour to f acilitate summation.

CAUSE & CORREC11VE AC110N 10 PREVEN 1 RECUR-The sum of the total outage hours plus the hours the genera.

tor was on hne should equal the gross hours in the reportmg RENCE. Use the column m a narrative fashion to amphts m expla n the circumstances of the shutdown or power reducnon P#""d' The column should mdude the specilie cause for each sino down or significant power reduction and the immediate and REASON. Categorite by letter deugnanon in accordance contemplated long term tonectne actmn taken. it appropu with the table appearmg on the report form. Il category 11 must he used, supply brief comments.

ate. This column should also be used for a dessuption of the or safet).related conective mamtenance performed dunng METHOD OF SilU111NG DOWN Tile REACIOR OR the outage m powei redustion meludmg an idennficanon ot

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1. N '" ' ' # P* ' "I '"I ""

REDUCING POWLR.

Categon/e by number deugnation radioactivity or ungle radiation esposure spesifically associ-INote that ihn ditten f rom the Edison Electne Institute ated with the outage whhh auounts im mme than 10 persent (Lil) definitions of " Forced Partial Outage" and " Sche.

of the allowable annual values.

daled Pattial Outage.' for these terms. EE! uses a change of For long textual reports continue narrative on separate paper 30 MW as the break pomt. For larger power reactors. 30 MW and reference the shutdown m power iedusnon for tini is tou small a thange to wanant esplananon.

narrative.

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 answnr 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)?

No.

The reload fuel design and configuration along with the safety analysis will be reviewed by the Plant Safety Connittee in accordance with 10CFR Section 50.59 5.

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

NA 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.

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The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool.

a) 177 b) 60 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 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.

l DATE:

1989 I

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