1CAN088307, Monthly Operating Rept for Jul 1983

Monthly Operating Rept for Jul 1983

ML20024F015
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/15/1983
From:	John Marshall, Morton K ARKANSAS POWER & LIGHT CO.
To:	Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
1CAN088307, 1CAN88307, NUDOCS 8309080119
Download: ML20024F015 (7)

Text

fn ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK ARKANSAS 72203 (501)371-4000 August 15, 1983 1CAN088307 Mr. Harold S. Bassett, Director Division of Data Automation and Management Information Office of Resource Management U. S. Nuclear Regulatory Commission Washington, D. C.

20555

SUBJECT:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Monthly Operating Report (File:

0520.1)

Gentlemen:

Attached is the NRC Monthly Operating Report for July 1983 for Arkansas Nuclear One - Unit 1.

Very truly yours, John R. 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, DC 20555

[1 9309080119 030815 PDR ADOCK 05000313 R

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MEMBER M100LE SOUTH UTILtTIES SYSTEM

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i NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

JULY 1983 UNIT 1 The unit started the month in a power escalation from an outage caused by a failure of the Main Turbine Generator Exciter.

The unit attained 100% full power on July 3.

On July 8, the unit began a controlled shutdown due to a steam generator tube leak.in the "A" steam generator.

The main turbine generator was tripped off line at 0211 hours0.00244 days <br />0.0586 hours <br />3.488757e-4 weeks <br />8.02855e-5 months <br />.

On July 26 at 0923 hours0.0107 days <br />0.256 hours <br />0.00153 weeks <br />3.512015e-4 months <br />, the unit was placed back on line and attained a power level of 90% on July 27.

The unit remained there through the end of the month due to a condenser tube leak.

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OPERATING DATA REPORT 50-313 DOCKET NO.

DATE 8/15/83 I

COMPLETED BY K.L. Morton TELEPilONE 501-964-3115 OPERATING STATUS N

Arkansas Nuclear One - Unit 1

1. Unit Name:

2. Reporting Period:

July 1-31, 1983 2568

3. Licensed Thermal Power (MWt):

902.74_

4. Nameplate Rating (Gross MWe):

850

5. Design Electrical Rating (Net MWe):

883

6. Maximum Dependable Capacity (Gross MWe):

836

7. Maximum Dependable Capacity (Net Mhe):

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 Any (Net MWe):

10. Reasons For Restrictions. If Any:

This Month Yr..to-Date Cumulatise 744.0 5.087.0 75.522.0

11. Hours in Reporting Period 314.9 877.5 48,884.8

12. Number Of Ilours Reactor Was Critical 0.0 0.0 5,044.0

13. Reactor Resene Shutdown Hours 297.6 691.0 47,748.5

14. Hours Generator On-Line

15. Unit Resene Shutdown Houn 0.0 0.0 817.5

16. Gross Thermal Energy Generated (MWH) 656,154.0 1,472,021.0 113,241,835.0 214,105.0 480,511.0 37,245,555.0

17. Gross Electrical Energy Generated (MWil)

18. Net Electrical Energy Generated (MWHI 203,286.0 4_55,590.0 35,493,400.0 40.0 13.6 63.2

19. Unit Senice Factor 40.0 13.6 64.3

20. Unit Availability Factor 32.7 10.7 56.2

21. Unit Capacity Factor (Using MDC Net) 32.1 10.5 55.3

22. Unit Capacity Factor (Using DER Net) 60.0 55.1 16.7

23. Unit Forced Outage Rate

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

NONE

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

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achiesed IN!!IA L CRITICA LITY INITIAL EL ECTRICITY COMMERCIAL OPER ATION (0/771

o AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-313 I

UNIT DATE 8/15/83 N*L. Morton COMPLETED BY TELEPl!ONE 501-964-3115 duly, 1983 MONE DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

IMwe Net) 88 17 0

657 2

18 0

790 0

3 19 824 0

4 20 821 5

21 0

817 0

6 22 789 0

7 23 12 0

8 24 0

0 9

25 0

149 lo 26 0

691 ja 27 0

708 l'

28

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0 705 13 29 14 0

708 30 711 0

15 3,

0 16 INSRUCTIONS On this format list the averap daily unit power leselin MWe Net for each day in the reporting month. Compute o the nearest whole megawatt.

(9/77 )

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9 50-313 DOCKET NO.

UNIT SHUTDOWNS AND POWER REDUCTIONS AND Unit 1 UNIT NAME DATE Auaust 4. 1983 COMPLETED BY Man Mnrtnn REPORT MONTH July, 1983 TELEPHONE (501) 964-3115

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Cause & Correctise No.

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Event 37 g"?

Action to Prevent Recurrence H

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d 83-03 830616 F

7.2 A

3 N/A HA GENERA Completion of repairs to Main Turbine Generator Exciter.

83-04 830708 F

439.2 A

1 313-83-017 CC HTEXCH "A" Steam Generator tube leak; tube inspected and defective tubes plugged.

I 2

3 4

F: Forced Reason:

Method:

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

Entr> Sheets for Licensee C-Refueling 3 Automatic Scram.

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

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

F-Administ rative 9-0ther G-Operational Error (Explain)

Eshibit 1 Same Source N/77)

Il Other (Explain)

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

report period. In addition,it should be the source of explan-If category 4 must be used. supply brief comments.

ation of significant dips in average power levels. Each signi-ficant reduction in power level (greater than 20% reduction LICENSEE EVENT REPORT a.

Reference the appheable 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 lie noted, even though the unit may not have been reduction. Enter the first four parts (event year. sequential l

shut down completely For such reductions in power level, rep rt number. occurrence code and report typel of the the the duration should be listed as zero, the method of reduction part designation as desenbed in item 17 of instructions for should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Lvent Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG-0161). This infomiation may not be Cause and Corrective Action tc Prevent Recurrence column immediately evident for all such shutdowns. of course. since 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.

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

y NUMBER. This column should indicate the sequential num, the positive indication of this lack of correlation should be ber assigned to each shutdown or significant reduction in power noted as not applicable (N/A).

for that calendar year. When a shutdown or significant power SYSTEM CODE. The system m which the outage or power reduction begins in one report period and ends in 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 Lntry Sheets 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 shutdown or significant power reduction from Exhibit 1 Instractions for Preparation of Data Entr>

beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NURLG-Olol1.

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 component.

reduction. Forced shutdowns include those reqmred to be e.g.. wrong valve operated through error: list valve as initiated by no later than the weekend following discovery component.

of an oil 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 thutdown 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 fail. should be described action was taken.

under the Cause and Corrective Action to Prevent Recur.

I rence column.

DURATION. Self-explanatory. When a shutdown extends beyond the end of a report period, count only the time to the Components that do not fit any existing code should be de-s gnated XXXXXX. The code ZZZZZZ should be used for end of the report period and pick up the ensuing down time in the following report periods. Report duration of outages events where a component. designation is not applicable.

rounded to the nearest tenth ofan hour to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-l The sum of the total outage hours plus the hours the genera-

[

tor was on line should equal the gross hours m the reporting RENCE. Use the column in a narrative fashion to amplifs e period.

expla n the circumstances of the shutdown or power reduetion The column should include the specific cause for each shut-down or significant power reduction and theimmediate.mJ REASON. Categorize by letter designation in accordance l

with the table appearing on the report form. If category 11 contemplated long term corrective action taken. if appropn-must be used, supply brief comments.

ate. This column should also be used for a description of the major safety-related corrective maintenance performed during METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identification ot REDUCING POWER. Categorite by number designation the critical path aetmty and a report of any single release of l

radioactivity or single radiation exposure specifically associ-I INote that this differs from the Edison Electric Institute sted with the outage whic i accounts for more than 10 percent 8

i (EEI) definitions of " Forced Partial Outage" and " Sche.

of the allowable annual values.

duled Partial Outage." For these terms. EEI us" 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 reduction for this is too small a change to warrant explanation.

narrative.

REFUELING INFORMATION l.

Name of facility.

Arkansas Nuclear One - Unit 1 2.

Scheduled date for next refueling shutdown.

September 15, 1984 3.

Scheduled date for restart following refueling.

December 15, 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)?

Yes.

Reload report and associated proposed Technical Specification change 5.

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

September 1,1984 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 7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 316 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.

968 present increase size by 9.

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

DATE: 1998