ML20031G093

Monthly Operating Rept for Sept 1981

ML20031G093
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/12/1981
From:	Bramlett L ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20031G092	List: 1CAN108106, Forwards Monthly Operating Rept for Sept 1981 ML20031G093
References
NUDOCS 8110210099
Download: ML20031G093 (5)

Text

y NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- SEPTEMBER 1981 UNIT 1 Having gone critical on August 30,1981, Unit 1 began September in a hold at 75% full power to allow the core to reach Xenon equilibrium.

At 0329 hours0.00381 days <br />0.0914 hours <br />5.439815e-4 weeks <br />1.251845e-4 months <br /> on September 1,1981, while at the 75% power hold Loop "B" Th failed high causing the ICS to runback reactor power and increase feedwater flow.

Loop "A" TAVE was selected for ICS control and the ICS sensed an irmiediate reduction in TAVE from 5780F to 5600F.

This caused the unit to exceed BTU limits and rods to be continuously wi ti.ci awn. The reactor tripped on high reactor coolant pressure.

The Loop "B" Th instrumentation was repaired and the reactor went critical at 0612 hours0.00708 days <br />0.17 hours <br />0.00101 weeks <br />2.32866e-4 months <br /> September 1.

The unit generator was on line at 0812 hours0.0094 days <br />0.226 hours <br />0.00134 weeks <br />3.08966e-4 months <br /> September 1 and 100% full power was attained by 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> September 2.

As in the previous months, fouling of the "A" 0TSG and the resulting increase in downcomer water level has required a reduction in unit power. On September 13, 1981, a gradual power reduction was begun to reduce downcomer water level and prevent flooding of the feedwater nozzles.

Unit 1 ended the month at 96.19%

full power with further power reductions anticipated due to "A" OTSG fouling.

8110210099 811013 PDR ADOCK 05000313 R

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OPERATING DATA REPORT DOCKET NO.

50-313 DATE 10/12/R1 COilPLETED BY L. S. Bramlett TELEPil0NE 501-968-2519 OPERAIING STATUS N"te' Arkansas Nuclear One-Unit 1

1. Unit Name:

2. Reporting Period:

Sc 7tember 1-30. 1981

3. Licenwd Thermal Power (51Wt):

2568 902.74

4. Namcplate Rating (Gross MWe):

850

5. Dmign Electrical Rating (Net 51We);

883

6. 31asimum Dependable Capacity (Gross.\\lWe):

836

7. Masimum Dependable Capacity (Net \\1he):

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

None None

9. Power Lesel To Which itestricted. If Any (Net.\\lhe):

10. Reasons For Restrictions. If Any:

N/A This 51onth Yr.-to-Date Cumulatise 720.0 6551.0 594660.0 i1. Ilours In Reporting Period 717.3 4248.2

12. Number Of liours Reactor has Critical 40038.5

13. Reactor Rtsene Shutdown llours 0.0 149.0 5044.0__

715.2 4129.8 39174.8

14. Ilours Generator On-Line

15. Unit Resene Shutdown liours 0. 0_

0.0 817.5

16. Gross Therma 1 Energy Generated (. lWil) 1789533.0 10159560 0 Qa nis?6.0

\\

17. Gross Electrical Energy Generated (\\lWil)

Annsos_n 33gng5n n 31079411.0 lb. Net Electrical Energy Generated (MWill 573222.0 3227171.0 29642810.0 99.3 63.0 65.9

19. Unit Senice Factor

20. Unit Asailability Factor 99.3 63.0 67.3 95.2 58.9 59.6

21. Unit Capacity Factor (Using MDC Net) 93.7 58.0 58.6

22. Unit Capacity Factor (Using DER Neti 0.7 13.1 16.9

23. Unit Forced Outage Rate

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

None

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

26. Units in Test Status (Prior io Commercial Operation):

Forecast Achiesed INITIA L CRITICA LITY INITIAL ELEClRICirY CO\\lMERCI AL OPER AllON (0/77)

1 p

AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-313 i

UNIT ANO 1 i

DATE 10/17/R1 COMPLETED By L. S. Bramlett 501-968-25'19 TELEPHONE MONT'd Seotember DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) i 416 17 813 2

761 is 822 i9 821 3

RlR 4

AlR 20 817 5

817 21 812 6

817 22 pil 7

R17 23 R09 3

817 24 808 9

817 25 805 10 817 26 801 11 816 27 799 12 816 2g 799 13 814 29 796 14 807 30 794 15 806 3

16 R06 INSTRUCTIONS On this format. hst the aserage dai 3 unit power leselin MWe-Net for caeh day in the reporting month. Compute to the nearest whole megawatt.

(9/77 )

REFUELING INFORMATION 1.

Name of facility.

Arkansas Nuclear One - Unit 1 2.

Scheduled date for next refueling shutdown.

1/1/83 3.

Scheduled date for restart following refueling.

3/15/83 4.

Will refueling or resumption of operation thereafter require a technical specification change or other liconee amendment?

If answer is yes, what, in general, will these be?

If cnswer 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 Soecification chanaes.

Also. the safety analysis of eiaht demonstration hiah burn-up assemblies will be provided.

5.

Scheduled date(s) for submitting proposed licensing action and supporting information.

10/1/82 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 aooroximately 16 months.

Eiaht of which will be hiah 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

p DOCKET NO.

50-313 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N AME ANO 1 DATE o/A/R1 COMPLETED BY h'

'l rortach REPORT MONTH Seotember TELEPHONE (5n1) 05A_3155 3

f'q, j?

3 Yh Licensee

,g Cause & Corrective E

o Action to

~"

No.

Date g

3g 3

,j g 5 Event 3?

.$E 5

jig Report nU C

Prevent Recurrence d

81-12 810901 F

4.8 A

3 N/A IF INSTRU Failure of Loop "B" TH instrumen-tation initiated ICS runback of Rx power and increased feedwater flow.

In switching ICS control to Loop "A" TAVE Rx tripped on High RCS Pressure.

Repaired Loop "B" Tg instrumentation.

l 1

2 3

4 F: Forced Reason:

Method:

Exhibit G - Instructions 1-for Preparation of Data S: Scheduled A-Equipment Failure (Explain) 2,Mr J B-Maintenance of Test Janual Scram.

Entr> Sheets for Licensee 3-Automatic Scram.

Event Report (LER) File (NUREG-C Refueling D Regulatory Restriction 4-Continuation 0161)

E-Operator Training & License Examination 5-Load Reduction 5

F-Administrative 9-0ther Exhibit I - Same Source G-Operational Error (Explain)

(9/77)

Il-0;her (Explain)

s UNIT SHUTDONNS AND POWER REDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns during the in accordance with the table appearmg on the report tomt.

report period. In addition,it should be the source of explan-If category 4 must be used, supply br.ef comments.

ation of significant dips in average power levels. Each signi-LICENSEE EVENT REPOKf :r.

Reference the appheable ficant reduction in power level (greater than 20% reduction 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 outzge or power should b'e noted, even though the unit may not have been reduction. Enter the first four parts (event year. sequential 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 destnl.ed 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 Repon 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 desenbe 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.

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

for that calendar year. When a shutdown or significant power SYSTEM CODE. The, system m which the outage or power reduction begins in one report period and ends m another, reducti<m originated sho"Id be noted by the two digit code of 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 Sheen Until a unit has achieved its first power generation, no num.

f r Licensee Event 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 sh Id be used for those events where DATE. This column should indicate the date of the start a system is not applicable.

of each shutdow* 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 1 ntr>

begmsin one report period and ends in another, an entry should Sheets for Licensee Event Report (I.ER) File (NUREG-01611.

be made for both report periods to be sure all shutdowns using ti.e following entieria:

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 component.

reduction. Forced shutdowns include those regmred to be e.g.. wrong valve operated through error; list valve 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 categorizing shutdowns in this way. In C.

If a chain of failures occers, the first component to mal-general, a forced shutdown is one that would net have been function should be listed. The sequence of events. ine.ad.

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 Correttive Action to Prevent Recur.

rence column.

9URATION. 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 fm end of the report period and piel, 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 hcurs the genera.

RENCE. Use the column in a narrative fashion to amplifs m tor was on line should equal the gross hcurs in the reportmg expla n the circumstances of the shutdown or power reduction period.

The column should include the specifie cause for each shut down or significant power reduction and the immediate and REASON. Categorize by letter designation in accordance contemplated long team corrective action taken. if appropo with the table appearing on the report form. If category 11 must be used, supply brief comments.

ate. This column should also be used for a description of the majcr safety related corrective maintenance perfomied dunng METHOD OF SHUTTING DOWN Tile REACTOR OR the outage or power reduction includmg an identification ot REDUCING POWER.

Categorite by number designation the critical path activity and a report of any single release of radioactivity or smgk radiation esposure specifically assoce INote that this dif fers from the Edison Electric Institute ated with the outage which accounts for more than 10 peicent (EEI) definitions of " Forced Partial Outage" and " Sche.

of the allowable annual values.

doled 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 red uction for this is too small a thange to warrant explanation.

narrative.

_ =