1CAN018405, Monthly Operating Rept for Dec 1983

Monthly Operating Rept for Dec 1983

ML20079M715
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/31/1983
From:	John Marshall, Morton K ARKANSAS POWER & LIGHT CO.
To:	Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
1CAN018405, 1CAN18405, NUDOCS 8401270399
Download: ML20079M715 (7)

Text

,

OPERATING DATA REPORT DOCKET NO. 50-313 DATE An. 1984 COMPLETED BY KT.Mnvem.

TELEPHONE 301- % 4-3115 OPERATING STA l US

1. Unit Name: Arkansas Nuclear Che - lhit 1 N"

December 1-31, 1983

2. Reporting Period:

3. Licensed Thermal Power (MWt):

2%R

4. Nameplate Rating (Gross MWe):

902.74

5. Design Electrical Rating tNet MWe6:

850 883

6. Maximum Dependable Capacity (Gross MWe):

636

7. Maximum Dependable Capacity (Net MWe):

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

E

9. Power Level To Which Restricted if Any (Net MWe):

10. Reasons For Restrictions. lf Any:

This Month Yr..to.Date Cumulatise 744.0 8,760.0 79.195.0

~

I1. Hours in Reporting Period

12. Number Of Hours Reactor was Critical 744.0 4.428.2 52,435.5 0.0 0.0 5,044.0

13. Reactor Reserve Shutdown Hours 744.0 4,192.7 51.250.2

14. Hours Generafor On.Line 0.0 0.0 817.5

15. Unit Resene Shutdown fiours 1,907,984.

10,150.483.

121,920,297.

16. Gross Thermal Energy Generated (MWil)

17. Gross Elecujcal Energy Generated iMWil) 643.325.

3,373,321.

40.138.365.

18. Net Electrical Energy Generated (MWHI 616,383.

__3 m22_0.578.

38,258,388.

100.0 47.9 64.7

19. Unit Service Factor 100.0 47.9 65.7

20. Unit Availability Factor 99.1 44.0 57.8

21. Unit Capacity I actor (Using MDC Net) 97.5 43.3 56.8

22. Unit Capacity Factor (Using DER Net) 0.0 19.6 15.9

23. Unit Forced Outage Rate

24. ShutdownsScheduled Oser Next 6 MonthsiType. Date,and Duration of Each):

N0tE

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

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

Forecast Achiesed INITIA L CRITICA LITY INITIA L ELECTRICITY COMMERCIAL OPER ATION 8401270399 831231 PDR ADOCK 05000313 PDR R

p,j77,

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-313 UNIT One Jan. 1984 DATE COMPLETED BY K. L. Morton TELEPHONE 501-964-3115 MONTH December, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) 1MWe.NetI i

827 17 828 822 2

I8 829 830 828 3

39 4

830 829 20 5

1 21 826 831 6

22 827 829 827 7

23 8

830 24 828 27 9

25 827 88 828 jo

'6

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828 27 830 12 829 828 28 829 828 33 29 14 830 829 3o 15 829 828 3,

829 16 INSTRUCTIONS On this format. list the average daily unit power Jeselin MWe Net for each da in tile reporting month. Compute to the nearest whole megawatt.

p;177 3

/

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

DECEMBER 1983 Unit 1 The unit started the month at 100% full power.

At 1137 hours0.0132 days <br />0.316 hours <br />0.00188 weeks <br />4.326285e-4 months <br /> on December 9th, the "B" drip pump was inadvertently tripped.

This resulted in an auto start of the "C" condensate pump and a runback of the unit to 96%

power. The unit was returned to 100% full power at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> and remained there until the end of the month.

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50-313 DOCKET NO.

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME AIO-lhit 1 DATE. Jan. 5, 1984 K

Decenber,1983 COMPLETED BY l. Mortan REPORT MONTH TELEPHONE (5011 964-111'i

.5 ?

3 Licensee j-t,

),

Cause & Corrective Action to No.

Date g

3g s

yg5 Event g-p' '

3 g =g Report a mV Prevent Recurrence yE e

e u

C N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 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 8 Continuation 0161)

E Operator Training & License Examination 5-Load Reduction 5

F-Administrative 9-0ther Exhibit 1 - Same Source G-Operational Error (Explain)

W/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 4 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 fne l

the duration should be listed as zero, the method of reduction Part designation as described in item 17 of, Instructions tot should be hsted as 4 (Other), and the Cause and Corrective. Preparation of Data Entry Sheets for Licenwe Event Repon Action to Prevent Recurrence column should explain. The (LER) File (NURFG-0161). This information may not be Cause an) Corrective Action to 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, not a reportable occurrence was involved.) If the outage or power reductic, will not rest /,t in a reportable occurrence.

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 reductionin power noted as not apphcable (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 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 Entry 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 k - Instractions for Preparation of Data Entr>

beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG-0161 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 component.

reduction. Forced shutdowra include those required to be e.g.. wrong valve operated through error: list 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. melud-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.

rence column.

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

rounded to the nearest tenth of an hour to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

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

tor was on line should equal the gross hours m the reportmg RENCE. Use the column in a narrative fashion to amphri ei period.

explain the circumstances of the shutdown or power reduetmn Ths column should include the specilie cause for each shut

"' I"* # '

REASON. Categorize by letter designation in accordance contemplated Icag term corrective action taken. il appropn.

with the tame 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 performed dunng METHOD OF SHUTTING DOWN THE REACIOR OR the outage or power reductmn including an identification of REDUCING POWER. Categort/e by number designation the critical path activity and a report of any single release of radio etivity or single radiation exposure specifically associ.

INote that this differs fram the Edison Electric Institute sted with the outage which accounts for more than 10 rercent (EEI) definitions of " Forced Partial Outage" and " Sche.

of the allowable annual values.

duled 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 shut dow n or power reduct mn for ihn i

is too small a change m warrant explanation.

narrative.

9

DATE: December, 1983

_ REFUELING INFORMATION

- 1.

Name of facility.

Ar:aans:m: Ntmlam Me - Ihit 1 2.

Scheduled date for next refueling shutdown.

November 1. 1984

.3.

Scheduled date for restart following refueling. January 10. 1985 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)?

I Yes. RelnM repud ed associated proposed Techtical specification Change 5.

Scheduled date(s) for submitting proposed licensing action and

-supporting information.

Sept 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.

Yes, the reload analysis will be done using newly developed thermal hydraulic codes. Eabcock & Wilcox will be submitting Topical Reports on the new codes for NRC review prior to September 1,1984 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, io number of fuel assemblies.

prasent

%8 licensed but increase size by under construction 9.

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

.DATE:

1998 - ' - ~~

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4 I

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_.. ~. _ _ _ _. _.. _,,. _.. _.. _. _,. _ _,. _ _.. _.. _ _.. _ _..

y_1 ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 (5011371-4000 January 13, 1984 1CAN0184E5 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 hRC Mont.hiy Operating Report for December 1983 for Arkansas Nuclear One - Unit 1.

Very truly yours, 2/LA@

ohn R. Marshall Manager, Licensing JRM:SAB:s1 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 7

sk MEMBER MiOOLE SO'JTH UTILITIES SYSTEM