ML20053B908

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Apr 1982
ML20053B908
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 05/12/1982
From: Gertsch A
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20053B905 List:
References
NUDOCS 8206010333
Download: ML20053B908 (6)


Text

,, l l,'jj

= - - -

p p ',,f>

. l i s

3,.

OPERATING DATA REPORT DOCKET NO.

313 DATE 5/12/82 COMPLETED BY A.J.Gertsch TELEP110NE

'iOl-9fi4-3155 OPERAllNG STA I US N"'"

1. Unit Name: Arkansas Nuclear One - Unit 1
2. Reporting Period: _ Aoril 1-30.1982

~~

3. Licensed 1hermal Power (MWt):

2568 902.74

4. Nameplate Rating (Gross MWe):

850

5. Design Electrical Rating (Net MWe):

883

6. Maximum Dependahle Capacity (Grow MWe):

886

7. Masimum Dependahle Capacity INet MWe).
8. If Changes Occur in Capacity ttings(items Numtar 3 Through 7)Since Last Report.Gise Reasons:

None None

9. Power f.esel To Which Restricted,if Anv (Net MWe):

M

10. Reaums For Restrictions. lf Any:

This Month Yr..to.Date Cumulatise s

719.0 2.879.0 64.554.0 i1. Ilours in Reporting Period 0.0 2,046.9 44,294.4

12. Number Of Ilours Reactor was Critical 0.0 0.0

-5,044.0

13. Reactor Resene Shutdown llour, 0.0 2,039.3 43,423.1
14. Ilours Generator On-Line 0.0 0.0 817.5
15. Unit Resene ShutAwn llours 0.

4,330,053.

103,860,259.

16. Gross Thermal Energy Generated tMWil)

O.

1,459,576.

34,296,332.

17. Grow Electrical Energy Generated tMwil, 0.

.__ 1,385,330.

32,701.731.

I8. Net Electrical Energy Generated (MWill 0.0 70.8 67.3

19. Unit Senice Factor 0.0 70.8 68.5
20. Unit Asailability Factor 0.0 57.6 60.6
21. Unit Capacity Factor (Using MDC Net) 0.0 56.6 59.6
22. Unit Capacity Factor (Using DER Net, O.0 0.0 15.5
23. Unit Forced Outage Rate
24. Shutdowns Scheduled Our Nest 6 Months tType. Date.and Duration of Eacht:
25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units in lest Status tPrior to Commercis! Operation):

Forecast Achiesed INI Tl \\l. C RI TICA LITY INiil \\ L ELECT RICI TY (pO\\lMERCI AL OPER AllON P2060 10 3n to/77p

~

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

313 I

UNIT DATE 5/12/82 A.J.Gertsch COMPLETED BY TELEPHONE 501-964-3155 i

l MOND1 April 1982 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

yw,,3,,)

1 0

37 2

0 0

,3 0

3 0

4 0

0 20 5

0 0

21 i

6 n

22 0

7 0

0 73 8

0 0

24 9

0 25 0

10 n

26 0

1I O

27 0

12 n

28 0

13 0

0 29 14 0

30 0

I5 0

N/A 3,

16 0

INSTRUCTIONS On this format, hst the ascoge daily unit pimer seselin MWe Net for caeh day in the reporting inonth. Compute to the nearest whole megawatt.

4 (9/77) h 4

+

m.

Attachment to ANO-82-3378 NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- APRIL, 1982 UNIT I Unit One remained in the cold shutdown mode during the month of April for replacement of the "A" OTSG feedwater nozzles.

l l

50-313 DOCKET NO.

UNil SHUTDOWNS AND POWER REDUCTIONS UNIT N AME ANO-Unit 1 DATE Shv 3 1982 COMPLETED BY A.T _ rorte r-b REPORT MONTil April TELEPHONE (Rn1) O M tles E

E Licensee j-t,

['?

3?

'h jYi t

Cause & Corrective c

Action to No.

Date c-EE 4

ss Event 27 Report :

A' 0

!0 Present Recurrence S

js 5

35:g u

6 82-02 820326 S

719.0 B

4 N/A CC IITEX01 Unit was brought to cold shutdown to replace the feedwater nozzles in the "A" OTSG.

I 2

3 4

F: Forced Reason:

Method:

Exhit)it G - Insttuctions 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 Reimrt (LER) File (NUREG-D-Regulatory Restriction 4{ontinuation 0161)

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

F-Administrative 9-0ther G-Operational Error (Explain)

Exhibit I - Same Source (9/77)

Il-Other (Explain)

UNIT SHUTDONNS AND POWER REDUCTIONS 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 should be the source of explan.

If category 4 must be used, supply bner somments.

ation of significant dips in average power kvels. 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 pertaming to the outage or power should b'e noted, even though the unit may not have been reduction. Enter the first four parts (event year, sequennal I

shut down completely. For such reductions in power level, report number, occurrence code and report type) of the the the duration should be hsted as zero, the method of reduction part designation as desenbed in item 17 of instructions im should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensea Event Repon Action to Prevent Recurrence column should explain. The (LER) File (NUREG.0161). This information may not he Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns. of course. since dmuld 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 wdl 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 shutdown or significant power SYSTEM CODE. The system in which the outage or power reduction begms m one report penod and ends in another.

an entry should be made for both report periods to be sure reduction originated should be noted by the two digit code of all shutdowns or significant power reductions are reported.

Exhibit G Instructions for Preparation of Data Entry Sheet >

Until a unit has achieved its first power generation, no num-f r Licensee Evpnt 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 i Instractions for Preparation of Data Entry begins m one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG-Olot L be made for both report periods to be sure all shutdowns usmg 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 it 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 sabe 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 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 he listed. The sequence of events.includ-completed in the absence of the condition for w hich corrective ing the other components which fail. should be describc; 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 penod. count only the time to tne Components that do not fit any existing code should be de.

5 gnated XXXXXX. The code ZZZZZZ should be used for end of the report period and pick up the ensuing down time in the followmg report penods. Report duration of outages events where a component. designation is not applicable.

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 ime should equal the gross hours in the reporting RENCE. Use the column in a narrative fashion to amphf3 or P"""d' explain the circumstances of the shutdown or power reduenon The column should include the specific cause for each shut REASON. Categorite by letter deugnation in accordance down or significant power reduction and the immediate and i

with the table appeanng on th: report form li category 11 contemplated long term corrective action taken. it appropo.

must be used.suppiy ooet comments.

ate. This column should also be used for a descuption of the major safety-related corrective mamtenance performed during METHOD OF SHUTTING DOWN THE REACTOR OR the outage oi power reduction including an identification of REDUCING POWER.

Categon/e by number designation the critical path actmty and a report of any single release of radioactivity or smgle radiation exposure specitically associ-INote that this ditfers f rom the Edison Electric Institute ated with the outage which accounts for more than 10 percent (Ell) 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 shutdown or power reducoon for this is too small a change to warrant esplana: ion.

narrative.

I

DATE: April 1982 REFUELING INFORMATION 1.

Name of facility.

Arkansas Nuclear One - Unit 1 2.

Scheduled date for next refueling shutdown.11/26/82 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, r

new operating procedures.

Will reload 72 fresh fuel assemblies and operate for approximately 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

. - _ _