ML20071Q161

Monthly Operating Rept for Oct 1982

ML20071Q161
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/15/1982
From:	Bramlett L ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20071Q156	List: 2CAN118207, Forwards Monthly Operating Rept for Oct 1982 ML20071Q161
References
NUDOCS 8212290236
Download: ML20071Q161 (6)

Text

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NRC MONTHLY OPERATING REPORT OPERATING SUMARY - OCTOBER 1982 UNIT II The Unit was shutdown for refueling and maintenance for the entire month.

1 C'212290236 021115 DR ADOCK 05000 6

OPERATING DATA REPORT DOCKET NO.

50-368 DATE 11-15-82 COMPLETED BY l-S. Bramlett TELEPHONE 501-964-3145 OPE RATING STAlUS Notes

1. Unit Name:

Arkansas Nuclear One - Unit 2

2. Reporting Period:

October 1-31, 1982

3. Licenwd Thermal Power (MWt):

2815 _

942.57

4. Nameplate Rating (Gross MWe):

912

5. Design Electrical Rating (Net MWe):

897

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe):

M8

8. If Changes Occur in Capacity RatinFs (items Number 3 Through 7) Since Last Report, Gise Reasons:

l flone

]

9. Power Lesel To Which Restricted. lf Any (Net MWe):

fl/A j

10. Reasons For Restrictions.lf Any:

This Month Yr.-to Date Cumulatise 745.0 7296.0 22800.0

11. Ilours in Reporting Period 0.0 4268.0 15162.6 l

12. Number Of flours Reactor was Critical 0.0 324.8 1338.5

13. Reactor Resene Shutdown llour,

14. Ilours Generator On.Line 0.0 4215.8 14757.6

15. Unit Rewne Shutdown flours 0.0 0.0 75.0

16. Gross Thermal Energy Generated q MWil) 0.0 10936806.0_

36722675.0 0.0 3512866.0 11884784.0

17. Gross Electrical Energy Generated (MWil, 0.0 3_3_45381.0 11316379.0 iM. Net Electrical Energy Generated (MW111 0.0 57.8 64.7

19. Unit Senice Factor

20. Unit Asailability Factor 0.0 57.8 65.1

21. Unit Capacity Factor (Using MDC Net) 0.0 53.4

22. Unit Capacity Factor (Using DER Net) 0.0 50.3 57.8 54.4 0.0 24.2 21.0

23. Unit Forced Outage Rate

24. Shutdowm Scheduled Oser Next 6 Months 1 Type. Date.and Duration of Each t:

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

26. Units in lest Statm (Prior to Commercial Operation):

Forecast Achic red INI TI \\ L CRITICA LIT Y INI TI A L El.ECIRICI TY CO\\l\\lERCIAL OPER A IlON (0/77i

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-368 UNIT 2

DATE 11/15/82 COMPLETED BY L 4. Bramlett TELEP110NE 501-964-3145 MONTil October, 1982 DAY AVER AGE DAILY POWER LEVEL DAY AV R AGE DAILY POWER LEVEL (MWe-Neti I MWe-Neti 1

0 0

i7 0

2 n

18 3

0 19 0

4 0

20 0

s 0

0 21 6

22 0

7 0

23 0

8 0

0 24 0

9 25 0

10 0

26 0

II O

27 0

0 0

12 2s 13 0

29 0

14 0

30 0

0 15 3

o 16 0

INSTRUCTIONS On this format, list the aserage daily umt pimer lesel in MWe Net for each day m the reporting month. Compute to the nearest whole megawatt.

01/77) w

REFUELING INFORMATION l..

Name of facility.

Arkansas Nuclear One - Unit 2 2.

Scheduled date for next refueling shutdown.

October 1, 1983 3.

Scheduled date for restart following refueling.

January 1, 1984 4.

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

i 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)?

Tn Rn notormined 5.

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

N/A 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.

N/A 7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 112 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, 485 503 present increase size by 9.

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

DATE:

1gR4

e

,s DOCKET NO.

50-368 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME ANO_ Unit 2 DATE Nov.

8.

1982 COMPLETED BY T.

s. nrnminer REPORT MONTil OCTORFR TELEPHONE 501-964-114s "i.

f'%

3?

3 h ik Cause & Corrective E

Licensee

, -t, c-Action to f'3 No.

Date g

3g 4

,3 g 5 F.se nt a7

$5 5

jig Report :

EU Prevent Recurrence r

H l

d 1

82-11 820820 S

745 C

4 N/A ZZ ZZZZZZ Refueling Outage 1

2 3

4 Method:

Exhibit G-Instructions F: Forced Reason:

S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintqnance of Test 2-Manual Scram.

Entry Sheets for Licensee 3-Automatic Scram.

Event Report (LER) File (NUREG-C-Refueling 4-Continuation 01611 D Regulatory Restriction E-Operator Training & License Examination 5-Load Reduction 5

F-Administrative 9-Other Exhibit 1 Same Source G-Operational Error (E xplain)

(9/77)

Il Other (Explain)

UNIT SHUTDO5NS 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 brief comments.

ation of significant dips in average power levels. Each signi-LICENSEE EVENT REPORT c.

Reference the appbcab!c ficant reduction in power level (peater 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 outage or power reduction. Enter the first four parts (event year, sequennal should b'e noted, even though the unit may not have been shut down completely. For such reductions in power level, report number. occurrence code and report type) of the tne l

the duration should be listed as zero, the method of reduction part designation as desenbed 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.

not 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 positive indication of this lack of correlation should be ber assigned to each shutdown or significant reduction in 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 begins in one report period and ends m another.

an entry should be made for both report periods to be sure all shutdowns or signifiernt power reductions are reported Exhibit G - Instructions for Preparat.on of Data Entry Sheets 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 nos 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 ieduction. Report a 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 beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG-Olol L 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 cr 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 vahe 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 cham of failures occws. the first component 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 desenbed action was taken.

unJer 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 ht any existing code should be de-signated XXXXXX. The code ZZZZZZ should be used tm end of the report period and pick up the ensuing down time events where a component. designation is not appheable m 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 hours the genera-RENCE. Use the column in a narrative fasluon to amplits ei tor was on line should equal the gross hours in the reporting explain the circumstances of the shutdown or power reduction pe nod.

The column should include the specific cause for each shm

• ""N"

""'P"**"

E REASON. Categorize by letter designation in accordance contemplated long term corrective action taken. if appropo-with the table appearing on the report form. It. category 11 ate. This column should also be used for a descripuon of the must he used. supply brief comments major safety related corrective mamtenance performed duneg MET 110D OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an il 7tification of REDUCING POWER.

Categonie hy nun.ber designation the critical path activity and a report of any smgle release of radioactivity or smgle radiation exposure specifically associ-INote that this differs trom the Edison Electric Institute ated with the outage whith accounts for more than 10 perceni (EEI) definitions of " Forced Partial Outage" and " Sche.

of the allowable annual values.

daled Partial Outage.' For these terms. EEI uses a change of For long textual reports continue narratrve on separate paper 30 MW as the break pomt. For larger power reactors.30 MW and reference the shut dow n or powei reducnon for ilus is too small a change to warrant explanatan.

narranve.

_