ML20073F665

Monthly Operating Rept for Feb 1983

ML20073F665
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/15/1983
From:	Bramlett L ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20073F627	List: 2CAN038306, Forwards Monthly Operating Rept for Feb 1983 ML20073F665
References
NUDOCS 8304150521
Download: ML20073F665 (6)

Text

OPERATING DATA REPORT DOCKET NO.50-16R DATE 3/15/83 COMPLETED BY I S_ Rran11ett TELEPilONE 501-964-3145 OPERAllNG STA I US N"

1. Unit Name:

Arkansas Nuclear One - Unit ?

2. Reporting Period:

February 1-28. 1983 2815

3. Licenwd Thermal Power (MWt):

942.57

4. Nameplate Rating (Gross MWe):

912

5. Design Electrical Rating (Net MWe):

R47

6. Maximum Dependable Capacity (Gross MWe):

RER

7. Masimum Dependable Capacity (Net MWe):

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

9. Power Level To which Restricted. lf Any (Net MWe):

Nnna

10. Reasons For Restrictions.lf Any:

This Month Yr..to.Date Cumulatise i1. Ilours in Reporting Period 672.0 1416 A 25680.0

12. Number Of 11ours Reactor was Critical 520.4 673.3 16829.5 46.0 91.6 1430.1

13. Reactor Rewne Shutdown flours

14. Ilours Generator On-Line 501.0 642.6 16211.3

15. Unit Revne Shutdown Hours 0.0 0.0 75.0

16. Gross Thermal Energy Generated (MWil) 1246447 1633565 39884626 411961 536107 12911411

17. Gross Electrical Energy Generated (MWil,

18. Net Electrical Energy Generated IMb til 393392.

511715 12229459 74.6 45.4 63.1

19. Unit Senice Factor 74.6 45.4 63.4

20. Unit Asailability Factor 68.2 42.1 55.5

21. Unit Cagucity Factor (Using MDC Nein 64.2 39.6 52.2

22. Unit Capacity Factor (Using DER Net)

D*4 54.6 23.1

23. Unit Forced Outage Rate

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

NONE l

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

26. Units in Test Status tPrior io Commercial Operation):

. ' Forecast Achiesed INITI A L CRITICA LITY INITI A L ELEC1RICITY l

COMMERCI AL OPER ATION c

F304150521 830315 DR ADOCK 05000

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l AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.

50-368 2

UNIT DATE 3/15/83 L.S. Bramlett COMPLETED BY TELEPHONE 501-064 1145 MONTH February. 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 0 1

17 0

2 316 18 12 3

826 710

,9 887 822 4

20 887 820 5

21 887 824 6

7 826 l

7 23 886 826 8

24 9

25 831 10 22 832 26 388 833 l

ll 27 858 830 12 73 885 13 2

390 14 3g 0

I5 0

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

((1/771 i

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NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- FEBRUARY 1983 UNIT 2 The unit began the month shutdown in a continuation of the January 83-01 outage.

On February 2, the unit was placed on-line and on the next day reached 100% full power. On February 9, the unit was taken off-line due to an excessive RCS leakage.

The leakage was due to leakage through the pressurizer spray valve.

A leak repair was performed and the unit was returned to power on February 10.

Power operation continued through February 14, when the unit tripped on a false CPC trip.

The unit remained shutdown for maintenance on equipment until February 18.

Unit power level was brought to ~93% and remained there throughout the month.

Power was limited to this level because one circulating water pump was out of service.

A correction to the January reactor " forced shutdown hours" and "not critical hours" was made.

The correction was 591.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in place of 545.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

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50-368 DOCKET NO.

UNII SilUTDOWNS AND POWER REDUCTIONS UNIT N AME ANO-Unit ?

DATE 1/1/R1 COMPLETED BY L.S.~B~ramlett REPORT MONTil February TELEPHONE 501-964-3145 Licensee

[n, bq, 3?

3 h $k Cause & Corrective S?

Action to No.

Date g

3g j

,5 g $

Event 77 E

j5j Report,

gc E'

Prevent Recurrence H

5 83-01 830109 F

25.2 B

4 83-003 SF HTEXCH "A" loop shutdown cooler tuDe leaks 83-02 830209 F

40.4 B

1 NONE PC VALVEX The unit was shutdown due to exces-sive RCS leak rate. The leakage was from the pressurizer spray valve packing.

83-03 830214 F

105.4 A

3 NONE IA INSTRU The unit tripped because of a false CPC generated trip signal.

During the trip recovery it was necessary to perform maintenance on EFW con-trol valves and the unit startup transformer #3.

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.

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

Event Report (LER) File (NUREG-D Regulator) Restriction 4-Continuation 01611 E-Operator Training & License Examination 5-Load Reduction 5

F-Administrative 9-Other Exhibit I - Same Source G-Operational Error (Explain)

(9/77)

Il Other (Explain)

UNIT SHUTDONNS AND POWER REDUCTidNS * +

INSTRUCTIONS This report should describe all plant shutdowns during the in accordance with the table appeanng on the report form.

report period. In addition,it shou!d 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 *. 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 reduction. Enter the first four parts (event year sequential should b'e noted, even though the unit may not have been 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 for 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) Fde (NUREG-0161). This information may not he Cause and Corrective Action to Prevent Recurrence column immediately evident for all sush shutdowns. of course since should be used to provide any needed explanation to fully further investigation may be required to ascertain 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 ber assigned to each shutdown orsignificant reductionin power noted as not applicable (N/A).

for that calendar year. When a shutdo.<n or significant power SYSTEM CODE. The system in which the outage or power reduction begins in one report period and ends in another, g

g g

g an entry should be made for both report periods to be sure 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 (NUREG4)l61).

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 componeni as 770814. When a shutdown or significant power reduction from Exhibit I - Instractions for Prepcration of Data Entr>

begmsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NURLG-Olt>l L be made for both report periods to be sure all shutdowns using the followmg critieria:

or significant power reductions are reported.

TYPE. 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 reqmred to be e.g.. wrong valve operated through error; list vahe 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 m categorizing 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 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.

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.

signated XXXXXX. The code ZZZZZZ should be used for erid of the report period and pick up the ensuing down time events where a component designation is not appheable.

in the following report periods. Report duration of outages 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 in the reporting RENCE. Use the column in a narrative fasluon to amplifs m exp sin the circumstances of the shutdown or power reduction pe nod.

The column should include the specific cause th each shut REASON. Categori/e by letter designation in accordance down or significant power reduction and the immediaic and contemplated long term corrective action taken, if appropn.

with the table appearing on tSe report form. 11, 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 durmg METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identification ot REDUCING POWER.

Catepon/e by number designation the critical path activity and a report of any single release of radioactivity or single radiation exposure specifically associ-i l

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

of the allowable annual values.

dated Paitial Outage." For these terms. eel uses a change of For long textual reports continue narrative on sepa ate 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.

a

...o REFUELING INFORMATION 1.

Name of facility.

Arkansas Nuclear One - Unit 2 2.

Scheduled date for next refueling shutdown.

Jan. 6, 1984 3.

Scheduled date for restart following refueling.

April 1, 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.

December 1. 1983 6.

Important licensing considerations associated with refueling, c.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) 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 485 increase size by sna 9.

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

1991

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DATE:

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