ML20070Q881

Monthly Operating Rept for Nov 1982

ML20070Q881
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/15/1982
From:	Gertsch A ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20070Q865	List: 1CAN128205, Forwards Monthly Operating Rept for Nov 1982 ML20070Q881
References
NUDOCS 8301270190
Download: ML20070Q881 (6)

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OPERATING DATA REPORT I

DOCKET NO. 50-313 DATE 12-15-82 COMPLETED BY A.J. Certsh TELEPHONE 501-964-3155 i OPERATING STAl th.

Notes

1. Unit Name: ___ Arkansas Nuclear One - Ifnf t 1

2. Reporting Period: November 1 - 30. 1982

3. Licenwd Thermal Power (MWI): 2568

4. Nameplate Rating (Gross MWe): 902.74

5. Design Eicctrical Rating (Net MWe): 850

6. Maximum Dependable Capacity (Gross MWe):

883 836 l 7. Maximum Dependable Capacity (Net MWe):

l 8. If Chan6es Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

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9. Power Level To Which Restricted.lf Anv (Net MWe): None

10. Reasons For Restrictions.If Any: N/A This Month Yr. to Date Cumulative f

11. Hours in Reportug Period 720.0 8016.0 69691.0

12. Number Of Hours Reactor was Critical 201,2 5759.8 48007.3

! 13. Reactor Reserve ENtdown Hours 0.0 0.0 5044.0

14. Hours Generstm On-Line 19') . 0 5673.7 47057.5

15. Unit Reserve Shutdown Hours 0.0 0.0 817.5

16. Gross Thermal Energy Generated IMWHI 323500.0 12239608.0 111769814.0

17. Gross Electrical Energy Generated (MWH) 93893.0 3928288.0 36765044.0

. 18. Net Electrical Energy Generated (MWH) 88355.0 .3221409.0 35037810.0

19. Unit Senice Factor 26 6_

70.8 67.5

20. Unit Availability Factor 26.4 70.8 68.7

21. Unit Capacity Facior (Using MDC Net) _

14.7 55.5 60.1

-22. Unit Capacity Factor (Using DER Net) 14 4._ 54.6 59.1

23. Unit Forced Outags Rate 0.0 11.7 15.6

24. Shutdowns Sci eduled Oser Next 6 Months tType. Date,and Dur

rion of Each1:

Unit now in scheduled 1-R5 refuelinn outane which benan November 8.

25. If Shut Down At End Of Report Period. Estimated Date of Startup: Feb run ry _ 1981

, 26.' Units In Test Status IPrior to Commercial Operationi: Forecast Achiesed l

! INIThL CRITICALITY I INITIAL ELECTRICl1 Y

' COMMERCIAL OPER ATION .

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-313 UNIT I DATE .12-15-82 COMPLETED BY A.J. Gertsh TELEPHONE 501-964-3155 MONTH November DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net ) (MWe-Net) 474 37 0

2 466 gg 0 3 469 39 0 4 4I'4 20 0 5 469 21 0 6 472 22 0 7 467 23 0

.8 400 24 0 9 0 25 0 10 0 26 0 II O 77 o 12 0 28 ._

0 13 0 29 0 14 0 30 0 15- 0 3g 16 0 INSTRUCTIONS On this format. list the average daily unit power leselin MWe-Net for each day in the repo. ting month. Compute to the nearest whole megawatt.

(9/77 )

NRC MONTHLY OPERATING REPORT OPERATING SUpttARY - NOVEMBER 1982 4

UNIT I Unit 1 began the month of November at 67.66% full power. The unit was in a '

power coastdown for the 1-R5 refueling outage. On November 8 a seal leak in the "B", Reactor Coolant Pump exceeded technical specifications and Unit I was required to shutdown. The reactor was tripped at 0912 hours0.0106 days <br />0.253 hours <br />0.00151 weeks <br />3.47016e-4 months <br /> November 9 and the 1-R5 refueling outage was begun.- ,

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DOCKET NO. 50-313-UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME AND - Unit 1 DATE Dec. 4.1932

' COMPLETED BY A L Gertsch REPORT MONTH flovember TELEPHONE _ GA1 GAA 11RR m

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, .$ ? 3g jYl Licensee ' g-r, j%'

Cause & Corrective No. Date g 3g jg5 Event p c8 Action to

$~~ $ j di g Report x mu jU Prevent Recurrence t 6 B2-07 821108 S 530.0 C 1 N/A N/A N/A 1-R5 Refueling Outage 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 or Test 2-Manual Scram. Entry Sheets for Licenses C-Refueling 3 Automatic Scram. Event Report (LER) File (NUREG-D Regulatory Restriction 4-Continuation 0161)

E-Operator Training & License Examination 5-Load Reduction F-Administrative 5 9-Other Exhibit I Same Source G-Operational Error (Explain)

(9/77) Il Other (Explain)

UNIT SHUTDO5NS AND FOWER 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 <agnificant dips in average pc.wer 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 />) fePortaole occurrence pertaining to the outage or power should b'e noted. cven though the unit may not have been reduction. Enter the first four parts (event year. sequential shut down completelyl . For such reductions in power level, report nu.aber, occurrence code and report type) of the fiw the duration should be listed as rero, 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) File (NUREG-0161). This information may not be Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns. of course, smee 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.

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

for that calendar reduction year.

begins in one When report a shutdown period significantSYSTEM and ends ir,oranother powe', CODE. The system in which the outage or power reduction originated sh'ould be noted by the tw'o digit code of an entry should be made for both report periods to be sur all shutdowns or sigaificant power reductions are reported. Exhibit G Instructions for Preparation of Dva Entry Sheets Until a unit has achieved its first power generation, no num- for Licensee Event Report (LER) File (NUREG.0161).

- ber should be assigned to each entry. Jystems 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 I - 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-01611.

be made for both report periods to be sure all shutdowns using the following critieria:

or significant power redections 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 required to be e.g.. wrong valve operated through error: list valve a>

initiated by no later than the weekend follwing 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.

rence column.

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

' rounded to the nearest tenth of an hour to facilitate summation. ~ y, .h 'RRECTIVE 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 reporting M i

• ib column in a narrative fashion to amphfs .9' gaai w omstances of the shutdown or power reductinn Period. he column should include the specific cause for each shut-

• " ' E" #" "' F*#' " * "" # "## ' " ' "

REASON. Categorize by letter designation in accordance contemplated long term corrective action taken. if appropa-with the table appearing on the report form. If category 11 ate. This column should also be used for a description of the must be used. supply brief comments.

major safety-related corrective maintenance perfonned during the outage or power reduction inef acing an identification of METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER. Categorite by number designation the critical path activity and a repe : e :my single release of radioactivity or single radiation exposure specifically associ.

INote that this differs from the ikdison Electric Institute sted with the outage which accounts for more than 10 percent

. (EEI) definitions of " Forced Partial Outage" and " Sche. of the allowable annual values.

daled 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 shrdown or power reduction for this is too small r change to warrant explanation. narrative.

DATE: November, 1982 REFUELING INFORMATION

~ 1.. Name of facility. ARKAtlSAS tlVCLEAR ONE - Unit 1

2.

• Scheduled date for next refueling shutdown. November 8,1982 - Refueling in

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progress.

13.' - Scheduled date for restart following refueling. February 15, 1983

- 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 specification change

-(82A-14).

- 5. Scheduled date(s) for submitting proposed licensing action and supporting information. Submitted flovember 19, 1982.

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.

Will reload 72 fresh fuel assemblies, four of which will be high 4 burn-up test assemblies, and operate for.approximately 16 months.

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7. The number of fuel assemblies (a) .in the core and (b) in the spent fuel storage pool, a) 177 b) 244

8. The present licensed spent fuv1 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 589 increase size by 379

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

DATE: 1986

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