2CAN088311, Monthly Operating Rept for Jul 1983

Monthly Operating Rept for Jul 1983

ML20024F040
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/15/1983
From:	Bramlett L, John Marshall ARKANSAS POWER & LIGHT CO.
To:	Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
2CAN088311, 2CAN88311, NUDOCS 8309080143
Download: ML20024F040 (7)

Text

,

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

JULY 1983 UNIT 2 The unit began the month at 90% power.

On July 3, power was reduced to 65%

due to a condensate pump suction strainer that needed cleaning.

On July 4, the unit attained 100% full power and operated there through July 7.

On this date power was reduced for an attempt to start boric acid addition to the steam generators. This was aborted when Unit 1 shut down with a steam generator tube leak.

On July 15, the unit was brought to 90% power for Moderator Temperature Coefficient Testing.

On July 18, the unit returned to 100% full power and continued operation there throughout the end of the month.

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OPERATING DATA REPORT DOCKET NO.

50-368 DATE 8/15/83 COMPLETED BY l.S.Bramlett TELEP110NE 501-(364-3145 OPERATING STAT US Notes Arkansas Nuclear One - Unit 2

1. Unit Name:

July 1-31. 1983

2. Reporting Period:

3. Licensed Thermal Power (MW ):

2815 942.57

4. Nameplate Rating (Gross MWe):

912

5. Design Electrical Rating (Net MWe):

897

6. Maximum Dependable Capacity (Gross MWe):

858

7. Maim am Dependable Capacity (Net MWe):

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

NONE

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

10. Reasons For Restrictions. If Any:

This Month Yr to-Date Cumularise 744.0 5.087.0 29,351.0 iI. Flours In Reporting Period 744.0 4.289.7 20,445.9

12. Number Of flours Reactor Was Critical 0.0 91.6 1,430.1

13. Reactor Reserve Shutdown flours 744.0 4,222.6 19,771 T I4. Ifours Generator On-Line 0.0 0.0 75.0

15. Unit Resene Shutdown Ilours 2,050,196.0 11,456,822.0 49,707,883.0

16. Gross Thermal Energy Generated (MWill 661,235.0 3,732,857.0_ 16,108,161.0 17 Gross Electrical Energy Generated (MWil) 631.074.0 3 565,127.0 15,343,513.0 1

18. Net Electrical Energy Generated (MWill 1

100.0 83.0 67.4 1

19. Unit Senice Factor 100.0 83.0 67.7

20. Unit Availability Factor 98.9 81.7 60.9

21. Unit Capacity Factor (Using MDC Net) 93.0 76.8 57.3

22. Unit Capacity Factor (Using DER Net) 0.0 17.0 20.0

23. Unit Forced Outage Rate 24.' Shutdowns Scheduled Oser Next 6 Months (Type. Date,and Duration of Each):

Refueling outage scheduled for October-January,1983

25. If Shut tiow i At Em! Of Repdrt PerN.fifimated Date of Startup:

26. Units in Test Status (Pnpr ic Commercial Operation):

Forecast Achiesed

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INITIAL ELECTRICITY COMMERCIAL' OPERATION f

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-368 E

UNIT DATE 8/15/83 L.S.Bramlett COMPLETED BY TELEPHONE 501-964-3145 MONm July, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 804 783 I

17 2

865 837 18 754 865 3

750 860 4

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869 859 5

21 871 858 6

22 863 857 7

23 8

871 858 24 9

869 858 25 10 871 26 860 870 II 27 858 869 1,

28 858

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69 857 13 29 869 859 14 39 857 856 15 3,

786 16 INSTRUCTIONS On this format. list the average daily unit power leselin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(4/77 )

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50-368 DOCKET NO.. ANO-2 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME DATE Auaust 4_ igm COMPLETED BY L.5. Bramlett REPORT MONTH Julv. Igg 3 TELEPHONE (501) 964-3145 "i

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Cause & Corrective E4 Licensee g-t

.2 _e E

-o No.

Date g

3g g

,g g 5 Event 7$

S' Action to fL

$, E 5

jgg Report :

n0 Prevent Recurrence d

NONE 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 of 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-Adrainistrative 9-Other Exhibit I - Same Source G-Operational Er ror (Explain)

(9/77) ll Other (Explain)

UNIT SHUTDONNS AND POWER REDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns during the in accordarNe with the table appeanng on the report form.

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

If category 4 must be used supply brief comments.

stion of significant dips in average power levels. Each signi-ficant reduction in power level (greater than 20'7e reduction LICENSEE EVENT REPORT #.

Reference the applicable 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 />) reportable occurrence pertaining to the outage or power should b'e noted, even though the unit may not have been reduction. Enter the first four parts (event year sequential shut down completely. For such reductions in power level, report number occurrence code and report type) of the Ine l

the duration should be listed as zero,the method of reduction part designation as described in item 17 of Instructions tur should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) Hle (NUREG-0161). This information may not be Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdawns, of course. smce should be used to provide any needed explanation to fully further investigation may be required to ascertam whether or describe the circumstances of the outage or power reduction.

not a reportable occurrence was involved.) If the outage or power reduction will not result in a reportable occurrence.

NUMBER. This column should indicate the sequential num-the positive indication of this lack of correlation should be bet assigned to each shutdown orsignificant reductionin power n ted as not applicable (N/A).

for that calendar year. When a shutdown or significant power SYSTEM CODE. The system in 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 Prepara'. ion of Data Entry Sheet >

Until a unit has achieved its first power generation, no num-f r Licensee Event Report (LER) File (NUREG-0161).

ber should be assigned to each entry.

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

of each shutdown or significant power reduction. Report as year, month, and day. August 14,1977 would be reported COMPONENT CODE. Select the most appropriate component as 770814. When a shutdowr: or significant power reduction from Exhibit I Instructioni for Preparation of Data i ntr>

beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG 0lol L be made for both report periods to be sure all shutdowns using the following critieria:

or significant power reductions are reported.

TYPE. Use "F" or "S" to indicate either " Forced" or " Sche-duled." respectively, for each shutdown or significant power B.

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

of an off-normal condition. It is recognized that some judg-ment is required in categorizing shutdowns in this way. In C.

If a chain of failures occurs, the first component to mal-general, a forced shutdown is one that would not have been function should be listed. The sequence of events. includ-completed in the absence of the condition for which corrective ing the other components which fait should be described action was taken, unJer the Cause and Corrective Action to Prevent Recur-rence column.

DURATION. Self. explanatory. When a shutdown extends beyond the end of a report petiod. 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 events where a component. designation is not applicable.

in the following report periods. Report duration of outages rounded Io the nearest tenth of an hour to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

The sum of the total outara hours plus the hours the genera.

RENCE. Use the column in a narrative fashion to amplift m tor was on line should equal the gross hours m the reportmg expla n the circumstances of the shutdown or power reduction period.

The column should include the specille cause for each shut

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REASON. Categorize by letter designation in accordance contemplated long term corrective action taken. it appropo-with the table appearing on the report form. If category 11 must be used, supply brief comments.

ate. This column should also be used for a description of the major safety related corrective maintenance perfomied durmg the outage or power reduction including an identification of METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER. Categorire by number designation the critical path activity and a report of any single release of radioactivity or single radiation exposure specifically associ-INote that this differs from the Edison Electric Institute ated with the outage which accounts for more than 10 percent (EEI) definitions of " Forced Partial Outage" and " Sche.

of the allowable annual values.

daled Partial Outage." For these terms. EEI uses a change of For long textual reports continue narrative on separate paper 30 MW as the break point. For larger power reactors. 30 MW and reference the shutdown or power reduenon for this isIou small a change to warrant explanation.

narrative.

l l

9 REFUELING INFORMATION l..

Name of facility.

Arkansas Nuclear One - Unit 2 2.

Scheduled date for next refueling shutdown.

October. 1983 3.

Scheduled date for restart following refueling.

January. 1984 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)?

To be determined 5.

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

October. 1983 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.

To be determined l

l 7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 112 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 988 increase size by 503 l

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

~~

DATE:

2001

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ET-4' ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK ARKANSAS 72203 (501) 371-4000 August 15, 1983 2CAN088311 Mr. Harold S. Bassett, Director Division of Data Automation and Management Information Office cf Resource Management U. S. Nuclear Regulatory Commission Washington, D. C.

20555

SUBJECT:

Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Monthly Operating Report (File:

2-0520.1)

Gentlemen:

Attached is the NRC Monthly Operating Report for July 1983 for Arkansas Nuclear One - Unit 2.

Very ruly yours, hohnR. Marshall Manager, Licensing JRM:SAB:rd Attachment cc:

Mr. John T. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Mr. Richard C. DeYoung Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, LC 20555 MEMBE A MIDDLE SOUTH UTILITIES SYSTEM i

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