1CAN948401, Monthly Operating Rept for Mar 1984

Monthly Operating Rept for Mar 1984

ML20084E234
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/31/1984
From:	John Marshall, Morton K ARKANSAS POWER & LIGHT CO.
To:	Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
1CAN948401, NUDOCS 8405020196
Download: ML20084E234 (7)

Text

OPER ATING DATA REPORT DOCKET NO. 50-313 DATE 1/15/Ra COMPLETED ilY y L. Morton TELErl10NE Rnt _a AA 1115 OPERAIING STA I US N"I

1. Unit Name:

A r1< n n u n a Mucione nno - tin h 1

2. Reporting Period:

March 1-31. 1984

3. Licenwd Thermal Power IMWil:

2568 902.74

4. Nameplate RatingIGrow MWe):

850

5. Design Electrical Rating tNet MWei.

883

6. Masimum Dependable Capacity (Grow MWe):

7. Masimum Dependable Capacity INet Mhe):

H'16 N. If Changes occur in Capaciry Ratings titems Number 3 Through 7)Since Last Report.Gise Reasons:

9. Power Leiel To Which Restricted. lf Any INet Mwe):

10. Reaums For Restrictions. If Any:

Nnsm

't his Month Yr..to.Date Cumulatise

11. Hours in Reporting Period 744.0 2,184.0.

81.379.0

12. Number Of Ilours Reactor has Critical 382.7

_1;n99_7 sr 9sg.9

13. Reactor Hewne Shutdown llours 0.0 0.0 5.044.0

14. Ilours Generator on Line 382.7 1.822.7_.

53.072.9

15. Unit Rewne Shutdown llour, 0.0 0.0 817.5

16. Grow thermal Energy Generated IMWil, 900,019.0 4.449.653.0

__126.396.954.0

17. Grow I.lectrical Energy Generated IMhili 298,290.0 1.493.045.0 41,631,410.0 IM. Net Electrical Energy Generated IMhili 285,269.0 1 /d0. 711. 0 39,689,099.0 51.4 83.5 65.2

19. Unit Senice Factor

20. Unit Asailability Factor 41 A 83.5 66.2

21. Unit Capacity Factor IUsmg MDC Net) 45.9 78.4_

58._3

22. Unit Capacity Factor tusing DER Nett 45.1 7,7,d, 57.4

23. Unit Forced Outage Rate 0.0 0.0 15.5

24. Shutdowns Scheduled User Nest 6 MonthsIT)pc. Date,and Duration of Eacht:

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

26. Units in f est Status iPrior to Commercial Operationi:

Forecast Achiesed INiilA L CRlilCALIT Y INIil \\l. ELECT RICil Y COMMI RCI A L Orl.R A IlON 8405020196 840331 PDR ADOCK 05000313 (ol77' R

PDR

AVERAGE DAILY UNIT POWER LEVEL 9

DOCKET NO.

sn ti1 UNIT One DATE 3/15/84 COMPLETED BY F L. Morton TELEPHONE 501-964-3115 MONTH March. 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Nel)

( y we.3,g3 I

754 17 0

2 755 18 n

3 754 19 0

4 755 20 0

756 21 0

6 751 22 0

7 7_43 23 0

8 74'l 24 0

9 745 25 0

10 745 26 0

11 744 27 0

12 746 28 0

13 744 3

n 14 746 -

30 0

15 745 o

3, 16 660 INSTRUCTIONS On this forinat. list the aserage daily unit power leulin MWe Net for each day in the reporting inimth. Compute to the nearest whole nwgawatt.

(9/77) 1 m

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

MARC 11 1984 UNIT 1 The unit started the month at 92% power due to a small tube leak ( <.055 gpm).

The unit remained at this power level until 1916 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.29038e-4 months <br /> on March 16.

At this time, the unit was brought down in power in order to prepare for the mid-cycle steam generator inspection. At 2243 hours0.026 days <br />0.623 hours <br />0.00371 weeks <br />8.534615e-4 months <br /> on the same day, the unit tripped from 17.5%

power due to a loss of both main feedwater pumps.

(Reference Transient Report 1-84-01.)

The unit was then placed in cold shutdown for the mid-cycle steam generator inspection outage and remained there through the end of the month.

DOCKET NO.

sn_111 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME AYn-f'n ie i DATE April 15. 1984 COMPLETED BY r.m %,enn REPORT MONTH March. 1984 TELEPHONE sni _o u. _3 t i 5 c

33 3

j :Y5 Licensee pt,

{%

Cause & Correcttve 3y lsent

%?

c7 Action to No.

Date r_

s T;

S 5

jdg fC Report :

EC Prevent Recurrence d

84-01 840316 S

361.3 B

5,3 N/A CC HTEXCH Planned shutdown for mid-cycle steam generator inspection. A normal power reduction was in progress when a trip from 17%

power occurred due to a loss of both main feedwater pumps.

I 2

3 4

F: Forced Reason:

Method:

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

Entry Sheets for Lxensee C-Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 4{0ntinuation 01611 E-Operator Training & Ucense Examination 5-Load Reduction 5

F-Administrative 9-Other G-Operational Error (Explain)

Exhibit I - Same Source (9/77)

H-Other (Explain)

UNIT SHUTDONNS AND POhER REDUCTIONS INSTRUCTIONS l

This report should describe all plant shutdowns during the in accordante with the table appearmg on the report tonn.

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

If category 4 must be used, supply brief comments.

ction of significant dips in average power levels. Each signi.

l ficant reduction in power level (greater than 207c reduction LICENSEE EVENT REPORT at.

Reference the apphcable in average dady 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 />) reportabic occurrence pertaming to the outage or power should tie noted, even though the unit may not have been

' eduction. Enter the first four parts (event year sequennat l

shut down completely. For such reductions in power level, report number. occurrence code and report type) of the Ine the duration should be hsted as rero,the method of reduction part designaimn as described in item 17 of Instructions sur should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Event Repori Action to Prevent Recurrence column should explain. The (LER) File (NUREG-0161). This information may not he Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns of course, smse should be used to provide any needed explanation to fully funhn inusugation may be requued to aner:4m whether or describe the circumstances of the outage or power reduction.

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

NUMBER. This column should indicate the sequential num.

the positive indication of this latk of concianon should be ber assigned to each shutdown or significant reductionin power noted as not appheable (N/A).

for that calendar year. When a shutdown or sigmficant powe' reduction begins in one report period and ends in another, SYSTEM CODE. The system m which the outage or power en entry should be made for both report periods to be sure reduction originated should be noted by the tw'o dig'it code of all shutdowns or significant power reductions are reported.

F.xhibit G. Instructions for Preparation of Data Lntry Sheets Until a unit has achieved its first power generation, no num.

for Licensa bent Report (LER) File (NURI G4)l61).

ber should he 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 shoulJ 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 as 770814. When a shutdown or significant power reduction COMPONENT CODE. Select the most appropriate component from Lxhibit I instractions for Preparation of Data Lntr>

begmsin one report period and ends in another, an entry should ' Sheets for Licensee Event Report (LER) File (NURI G.0le t h be made for both report periods to be sure all shutdowns usmg the following entieria:

or significant power reductions are reported.

l 1 YPE. Use "F" or "S" to mdicate either " Forced" or " Sche.

duled." respectively, for each shutdown or significant power it if not a component failure. use the related component.

reduction. Forced shutdowns include those required to be mittated by no later than the weekend following discovery e g., wrong valve operated through error; hst valse as compt nent.

J of an off. normal condition. It is recognited that some judg.

ment is required in categorizmg shutdowns in this way. In C.

general, a forced shutdown is one that would not have been If a chain of failures occurs, the first component to mal.

completed in the absence of the condition for which corrective function should be hsted. The sequense of events.includ.

action was taken ing the other components which fail, should be desenbed unJer the Cause and Corrective Action to Present Recur.

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.

end of the, report period and pl6k up the ensuing down time signated XXXXXX. The tode ZZZZZZ should be used fm I

in.he following report periods. Report duration of outages evms due a component. designation is not apphcable rounded to the ncarest tenth of an hour to facihtate summation The sum of the total outage hours plus the hours the genera.'

CAUSE & CORRECTIVE AC110N TO PREVENT RECUR.

j tor was on hne should equal the gross hours in the reportmg RENCE. Use the column in a narrative fashion to amphis W penod.

explain the circumstances of the shutdown or power reductmn The column should in61ude the specific cause for each shut t

REASON. Categorite by letter deugnation in accordance down or significant power reduction and the nnmediate and with the table appearmy on the report form, il category 11 contemplated long term (orrective actmn taken, it appropa.

rnust be uwd. supply boet comments.

ate. This column should also be used for a desertpuon of the m$r ufety.related corrective maintenance perkmned dunng METHOD OF SHUTTING DOWN THE REACIOR OR the outage or power reduction intludmg an identification of REDUCING POWER. Categon/e by number designation the critical path activity and a report of any smgle release of radioactivity or smgle rJdiation esposure spesifically associ.

INote that ihn datteri from the lidsson Ilectric Institute ated with the outage whhh acsounts for more than 10 persent (El:1) definitions of " Forced Partial Outage" and " Sche.

of the allowabic annual values.

daled Partial Outape." l'or these terrns. I'l.1 uses a t'hange of For long textual reports continue narrative on separate paper 30 MW as the becak pmnt. l'or larger power reactors.30 MW and reference the shutdown m power redusnon for ihn n too small a thange to warrant explanation.

nasrative.

I

e REFUELING INFORMATION 1.

Name of facility.

Arkansas Nuclear One - Unit 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)?

Yes, Reload Report and associated proposed Technical Snecification 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 fuci 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.

Babcock & Wilcox will be submitting Topical Reports on the new codes for NRC review prior to September 1, 1984.

7.

The number of fuel assemblip (a) in the core and (

in the spent fuci storage pool.

a) b)

a 8.

The present licensed spent fuci 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 licensed but increase size by unoer construction 9.

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

DATE:'1998

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~

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o ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK, ARKANSAS 72203 (501) 371-4000 April 15,1984 1CAN948401 Mr. Harold S. Bassett, Director Division of Data Automation and Management Information Office of Resource Management U. S. Nuclear Regulatory Commission liashington, 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 March 1984 for Arkansas Nuclear One - Unit 1.

Very truly yours, (2 M J J f ohn R. Marshall Manager, Licensing l

JRM:SAB:na l

l Attachment cc: Mr. John T. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, S ite 1000 Arlington, TX 76011 Mr. Richard C. DeYoung Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 M

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