2CAN028405, Monthly Operating Rept for Jan 1984

Monthly Operating Rept for Jan 1984

ML20080T882
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/31/1984
From:	Bramlett L, John Marshall ARKANSAS POWER & LIGHT CO.
To:	Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
2CAN028405, 2CAN28405, NUDOCS 8403020081
Download: ML20080T882 (6)

Text

i 1

OPERATING DATA REPORT DOCKET NO.

50-368 DATE Jan.

1984 COMPLETED BY - L. S. Bramlett TELEPllONE 501-964-3145 OPERATING STAT US

1. Unit Name:

Arkansas Nuclear One - Unit 2 N

2. Reporting Period: A m_tary 1-31. 1984

3. Licenwd Thermal Power (MWil:

2815

4. Nameplate Rating (Gross MWel:

942.57

5. Design Electrical Rating (Net MWe):

912

6. Maximum Dependable Capacity (Gross MWe):

897

7. Masimum Dependable Capacity (Net MWel:

858

8. If ChangeiOccur in Capacity Patings (Items Number 3 Through 7) Since Last Report. Gise Reasons:

}

9. Power Lesel To Which Restricted,if Any (Net MWel:

None

10. Reasons For Restrictions. If Any:

T his Month Yr. to-Date Cumulatise I1. Ilours in Reporting Period 744.0 744.0 33,768.0

12. Number Of Hours Reactor has Critical 127.6 127.6 21,754.7

13. Reactor Reserve Shutdown flours 0.0 0.0 1,430.1

14. Ilours Generator On-Line 0.0 0.0 20,950.3

15. (n.it Resene Shutdown liours 0.0

0. 0__

75.0~

16. Gross Thermal Energy Generated (MWill 202.7 202.7

_52,549,742.7

17. Gross Electrical Energy Generated iMWill

0. 0_

0.0

_17,016,951.0

18. Net Electrical Encryy Generated IMWill 0.0 0.0 16,206,34u.U

19. Unit Senice Factor 0.0 0.0 62.0

20. Unit Availability Factor 0.0 0.0 62.3

21. Unit Capacity Factor (Using MDC Net!

0.0 0.0 55.9

22. Unit Capacity FactorIUsing DER Net) 0.0 0.0

52. E

23. Unit Forced Outage Rate 0.0 0.0 20-(

24. Shutdowns Scheduled Oser Nest 6 Months tType. Date.and Duration of Each t:

Unit now in scheduled refueling and maintenance outage which started early, September 26, 1983, and is expected to last until February 1984.

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

Fahrin ry _ 1984

26. Units in rest Status tPrior to Commercial Operations:

Forecast Achiesed i

INITIA L CRITICALITY INITIAL. ELECTRICI TY CO\\lMERCI A L OPER A TION 9403020081j4 pog ADOCK 0

8 PDR R

C'/77 )

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-368 UNIT _TWO Jan., 1984 DATE COMPLETED BY

-l. S. Bramlett TELEPHONE 501-964-3145 MONTH Januarv.1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net)

I O

i7 0

2' 0

0 18 0

3 39 4

0 0

20 s

0 0

21 0

0 6

22 l

0-7 23 0

0 i-0 24 0

0 25 8

0 26 ll 0

0 27 0

0 12 0

13 29 0

14 0'

30 0

15

'33 0

16 INSTRUCTIONS On this format. list the average daily unit pow. lesel in MWe Net for each day in the reporting month. Compute to

the nearest whole nwgawatt.

')f77 )

f

Sheets for Licensee Event Report (LER) File (NUREG.01611.

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 compiment reduction. Forced shutdowns include those reqmred to be e.g.. wrong valve operated through error; list valve as initsated 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 fail, should be described action was taken.

under the Cause and Corrective Action to Prevent Recur.

ience 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 end of the report period and pick up the ensuing down time in the fellowing report periods. Report duration of outages events where a component. designation is not arplicable 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-RENCE. Use the column in a narrative fashion to amplifs ei tor was on line should equal the gross hours in the reportmg explam the circumstances of the shutdown or power reduction penod.

The column should include the specific cause for each shui

'"'I"**'

1. * "2#

- REASON. Categorite by letter designation in accordance with iLe table appearing on the report form. If category 11 contemplated h'ng term corrective action taken. it appropn.

must be used, supply bnef comments.

ate. This column should also be used for a description or the major safety-related corrective maintenance perfonned during

- METHOD OF SHUTTING DOWN THE REACIOR OR the outage or power reduction including an identification of RTDUCING POWER. Categorire by number designation the critical path activity and a report of any single release of radioactivity or single nadiatwn exposure specifically associ.

INote that this differs from the Edison Electric institute sted with the outage wluch accounts for more th.m 10 percent (EEI) definitions of " Forced Partial Outage" and " Sche.

of the allowable annual values.

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

narrative.

DATE: January, 1984 l

REFUELING INFORMATION l

1.

Name of facility.

Arkansas Nuclear One - Unit 2

2.

• Scheduled date for next refueling shutdown.

June, 1985 I-3..

Scheduled date for restart following refueling. August, 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 aru associated with the core reload (Ref.10 CFR Section 50.59)?

Yes, some proposed software changes to the Core Protection Calculators are being considered.

5.

Scheduled datela) for submitting proposed licensing action and

-supporting information.

March. 1985 6.

Impcreant licen;ing 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.

___ Burnable noison rods may be used in reload fuel.

7.

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

-177 b) 168 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 0

9.

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

DATE:

2003-

'~

~

ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 (501) 371-4000 February 15, 1984 2CAN028405 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 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 January 1984 for Arkansas Nuclear One - Unit 2.

Very i.ruly yours, 1John R. Marshall Manager, Licensing JRM:SAB:sc Attachment - See hard copy for complete 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 pM*)f Office of Inspection and Enforcement U. S. Nuclear Regislatory Commissic,n i;f Washington, DC 20555 MEMBEA MlOOLE SOUTH UTILITIES SYSTEM

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