ML20062F583

Monthly Operating Rept for June 1982

ML20062F583
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/09/1982
From:	Gertsch A ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20062F582	List: 1CAN078204, Forwards Monthly Operating Rept for June 1982 ML20062F583
References
NUDOCS 8208120086
Download: ML20062F583 (6)

Text

OPERATING DAT A REPORT DOCKET NO. 50-313 DATE 7/9/82 COMPLETED TELEPil0NE 501)By ( 964-3155 A.J.Gertsch OPER ATING S1 A I US Arkansas Nuclear One - Unit 1 N"'"

1. Unit Name:

June 1-30, 1982

2. Reporting Period:

2568

3. Licensed Ihermal Power (MWt):

4. Nameplate Rating (Gross 31We):

902.74 850 S. Design Electrical Rating (Net SlWel:

6. Maximum Dependable Capacity (Gross MWe):

883

7. Masimum Dependable Capacity (Net Mhe):

836

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

9. Power Lesel lo Which Restricted,if Any (Net MWe): NONE

10. Reassms For Restrictions. If Any: N/A l his Month Yr. to-Date Cumulatise 720.0 4,343.0 66,018.0 i1. Ifours in Reporting Period 494.6 2,930.4 45,177.9

12. Number Of liours Reactor was Critical

13. Reactor Resene Shutdown llours 0.0 0.0 5.044.0

14. Ilours Generator On-Line 490.5 2,889.5 44,273.3

15. Unit Rewne Shutdown flours 0.0 0.0 817.5 16 Gross t hermal Energy Generated iMWil, 1156217. 5972916. 105503122.

17. Gross Electrical Energy Generated iMwil, 379190. 1984410. 34821166.

18. Net Electrical Energy Generated (Mhill 360807. 1879193. 33195594.

19. Unit Senice Factor 68.1 66.5 67.1

20. Unit Asailability Factor 68.1 66.5 68.3

21. Unit Capacity Factor (Using MDC Neil 59.9 51.8 60.1

22. Unit Capacity Factor tusing DER Neo 59.0 50.9 59.2

23. Unit Forced Outage Rate 31.9 11.9 15.9

24. Shutdowns Scheduled Oser Nest 6 Months t I)pe. Date,and Duration of Each):

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

26. Units in test Status (Prior to Commercial Operation): Forecast Achiesed INI TI A L CRillCT Lil Y INillAL El.LCIRlCllY 00\l\l1 RCl \L 0P1 R A IION 8208120086 820714 PDR ADOCK 05000313 'Y7 8 R PDR

/

, AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-313 UNIT 1 DATE /9!O C0stPLETED By A.J. Gertsch TELEPHONE (501) 964-3155 MONT11 June 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net ) (ywe.Neg) 1 0 17 809 2 0 ig 808 3 0 in 807 4

0 807 20 5 0 21 807 6 0 -

807 22 7 0 803 23 h 0 804 24 9 0 803 23 to 55 806 26 11 304 805 2,

12 330 804 23 13 664 805

,9 la 791 803 39 is 803 3, 16 807 INSTRUCTIONS On this tormat, hst tbc ase?qe daily urut pimer lesel in MWe Nei for cas-h da) ni the reporting inonth. Coir.pute to the nearest whole rnegawait.

(9/771

NRC MONTHLY OPERATING REPORT OPERATIONS

SUMMARY

- JUNE, 1982 UNIT I Unit One began June in the cold shutdown mode for repair of a tube leak in the "A" Steam Generator. Following repairs to the "A" 0TSG heat up of Unit One began June 8. The reactor was brought critical at 0904 hours0.0105 days <br />0.251 hours <br />0.00149 weeks <br />3.43972e-4 months <br /> June 10 and the generator was placed on line at 1333 hours0.0154 days <br />0.37 hours <br />0.0022 weeks <br />5.072065e-4 months <br /> June 10. Unit One achieved 100 percent full power June 15, where it remained through the end of the month.

i l

l l

50-313 DOCKET NO. O-Unit 1 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME

.Tiily 1. 14 R ?_

DATE COMPLETED BY A. J. Gertsch REPORT MONTig .Itine TELEPHONE 501-964-3155 5 E

[-r, I'% Cause & Corrective

, 3? 3 _ $3 Licensee E? Action to No. Date  :- iE I; EE$ Ihent 77 NC S js 5 d Report : ,! 0 Present Recurrence 6

82-03 820525 F 229.5 A 4 012 CC IrrEX0I Continuation of the outage for repair of a tube leak in the "A" OTSG.

l 3 4 t 2 Method: Exhibit G -Instructions F: Forced Reason: for Preparation of Data A Equipment Failure (Explain) 1-Manual r S' Scheduled Entry Sheets for Licensee B-Maintenance of Test 2-Manual Scram.

3-Automatic Scram. Event Report (LER) File (NUREG-C Refueling 0161)

D Regulatory Restrietion 4-Continuation E-Operator Training & License Examination 5-Load Reduction 5 F Administralise 9-Other Exhibit I Same Source Goperational Error (E xplain)

W/77) Il Other (Explain)

UNIT SHUTDONNS AND POWER REDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns during the in accordmce with the table appeanng on the report fmm.

report period. In addition,it should be the source of explan. If category 4 must be used, supply bnef 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 pertammg to the outage or power should lie noted, even though the unit may not have been reduction. Enter the first four parts (event year, sequentui shut down completelyl . For such reductions in power level, report number. occurrence code and report type) of the fne the duration should be listed as /ero, the method of reduction part designation as desenbed in item I7 of Instructions for should be hsted as 4 (Other), and the Cause and Conective Preparation of Data Entry Sheets for Lhensee i vent Repon Action to Prevent Recurrence column should explain. The (LER) File (NUREG-0161). T his mformation may not be Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns. of course. smce simuld be used to provide any needed explanation to fully further investigation may be required to ascertam whether or desenbe the circumstances of the outage or power reduction. not a reportable occurrente was involved.) If the outage or power reduction will not result in a reportable occurrence.

NUMilER. Tlus wlumn should indicate the sequential num. the positive mdication 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 sigmticant power SYSTEM CODE. The system m which the outage or power reduction begms in one report period and ends m another.

an entry should be made for both report periods to be sure reduction originated should be noted by the two digit code of Exhibit G, Instructions c Preparation of Data Lntry Sheeb all shutdowns or sigmficant power reductions are reported.

Until a unit has achieved its first power generation, no num- f r Licensee laent 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 1 Instractions for Preparation of Data i ntry begmsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG Olot t.

be made for both report penods to be sure all shutdowns using the followmg critieria:

or significant power redu,tions are reported.

IYPE. Use "F" or "S" to mdicate either " Forced" or " Sche-duled," respectively, for each shutdown or significant power IE If not a component failure. use the related component red uction. Forced shutdowns include those required to be e g.. wrong valve operated through error; hst uhe as mitiated by no later than the weekend following discovery component, of an off-normal condition. It is recognized that some judg.

ment is required in categorinng shutdowns in this way. In C. If a chain of failures occurs, the first componen' 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 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 existmg code should be de-signated XXXXXX. The code ZZZZZZ should be used fm end of the report period 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.

The sum of the total outage hours plus the hours the genera. CAUSE & CORRECTIVE ACTION 10 PREVEN 1 RECUR-tor was on hne should equal the gross hours in the reporting RENCE. Use the column m a narratise fasluon to amphis m pe nod.

explain the circumstances of the shutdown or power reduction The column should include the specilie cause for each shui down or significant power reduction and the nnmediate and REASON, Categonze by letter designation in accordante with the table appearir g on the report form. It category 11 contemplated long term correctne action taken, il appropo-must be used. supply bnef comments. ate. This column should also be used for a desenplion of the m de lad mmw mmmm pedormed dunny METilOD OF SilUTTING DOWN Tile REACTOR OR the outage or power reduction includmg an identificaison ot REDUCING POWER. Categonie by number designation the entical path activity and a report of any smgle release or radioactivity or smgle radution exposure specifically assoca-INote that this ditters f rom the Edison Electric Institute ated with the outage winsh accounts for more ilun 10 perceni (EEI) definitions of "I orced Partial Outage" and " Sche. of the allowable annual values.

daled Paitial 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 reastors.30 MW and reference the shutdown m pow er redus non for ihn n too small a change to wanant explanation. narrative.

. Une 1982 REFUELING INFORMATION

1. Name of facility. Arkansas Nuclear One - Unit 1

2. Scheduled date for next refueling shutdown. 12/1/82

3. Scheduled date for restart following refueling. 2/15/83

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 changes.

5. Scheduled date(s) for submitting proposed licensing action and supporting information. 9/1/82

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 and operate for appro-ximately 16 months. Four of which will be high burn-up test assemblies.

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 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 589 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: 1986