ML20066D150
| ML20066D150 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/15/1982 |
| From: | Bramlett L ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20066D146 | List: |
| References | |
| NUDOCS 8211110185 | |
| Download: ML20066D150 (6) | |
Text
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OPERATING DATA REPORT DOCKET NO. 50-368 DATE.10/15/R2 COSIPLETED BY L.S. Bramlett TELEP110NE E01 4M 1145 OPERATING STAT US Notes Arkansas Nuclear One - Unit 2
- 1. Unit Name:
- 2. Reporting Period:
September 1-30, 1982
- 3. Licensed Thermal Power (S!Wt):
2815.
942.57
- 4. Nameplate Rating (Gross SIWE):
912
- 5. Design Electrical Rating iNet MWe).
897
- 6. Stasimum Dependable Capacity (Gross alWe):
858
- 7. Masimum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons:
- 9. Power Lesel To Which Restricted. lf Any (Net MWe):
NONE NA
- 10. Reasons For Restrictions. lf Any:
This Month Yr..to-Date Cumulatise 720_0 6551.0 22055.0
- 11. Ilours in Reporting Period
- 12. Number Of liours Reactor Was Critical 0.0 4268.0 15162.6 0.0 324.8 1338.5
- 13. Reactor Resene Shutdown flours 0.0 4215.8 14757.6
- 14. Ilours Generator On-Line
- 15. Unit Resene Shuidown liours 0.0 0.0 75.0 0.0 10936806.0 36722675.0
- 16. Gross Thermal Energy Generated iMWil) 0.0 3512866.0 11884784.0
- 17. Grow Electrical Energy Generated (MWil) 0.0
_3_345381.0 11316379.0
- 18. Net Electrical Energy Generated IMWill 0.0 64.4 66.9
- 19. Unit Senice Factor l
- 20. Unit Asailability Factor 0.0 64.4 67.3 0.0 59.5 59.8
- 21. Unit Capacity Factor (Using MDC Net) 0.0 56.0 56.3
- 22. Unit Capauty Factor (Using DER Net) 0.0 24.2 21.0
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date.und Duration of Each):
i a
l t
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achiesed l
INITI A L CRI flCA LIT Y f.
INI flAL ELECTRICI FY CO\\lMERCI A L OPER ATION F211110185 821015 PDR ADOCK 05000368 R
- pij77, l
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-368 2
UNIT 10/15/82 DATF_
COMPLETED BY L. S. Bramlett 501-964-3145 TELEPHONE MONTil September 1982 DAY AVERAGEt.ILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
'IWe-Net I (MWe-Neti I
17 0
b 2
l8 0
3 0
19 0
0 0
20 4
0 5
21 0
0 0
22 6
0 7
23 0
0 8
24 9
0 25 0
0 0
10 26 0
lI 27 0
0 0
12 28 0
0-13 29 14 30 0
15 3,
0 16 INSTRUCTIONS On this format. list the average daily unit power lesel in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77i
i O
2 i
i NRC MONTHLY OPERATING REPORT OPERATING SU N RY - SEPTEMBER 1982 UNIT TWO l
The unit was shut down for refueling and maintenance during the entire month.
4 l
d i
i k
4 1
1 l
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1
..,..., ~..,. _
_,____.,-,.,_____,___,.m
s 50-363 DOCKET NO.
UNii SHUTDOWNS AND POWER REDUCTIONS UNIT NAME ANO-Unit 2 DATE (Yr. 4. 10R7 COMPLETED BY L.S. Brnmlert REPORT MONTH SEPTEMRFR TELEPHONE (5011 46d-Tla5
.- ~:.
c
.5 ?
3 4 $3 Licensee h
j?t, Cause & Corrective EE Event u7 c-Action to 3;j $
- s d
No.
Date c.
$ ~@
Report x
$0 50 Prevent Recurrence S
=
g u
e C
82-11 820820 S
720 C
4 N/A ZZ ZZZZZZ Refueling Outage l
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 of Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3 Automatic Scram.
Event Report (LER) File (NUREG-D-Regulator) Restriction 4 Continuation 01611 E-Operator Training & Ucense Examination 5-Load Reduction 5
F-Administrative 9-Other j
G-Operational Error (Explain)
' Exhibit I - Same Source (9/77)
Il-Other (Explaini
4 UNIT SHUTDONNS AND POWER 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 significant dips in average power levels. Each signi-ficant reduction in power level (greater than 20% reduction LICENSEE EVENT REPORT
-r.
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 />)
'eportable occurrence pertaining to the outage or power reduction. Enter the first four parts (event year. sequential should b'e noted, even though the unit may not have been shut d.wn completely. For such reductions in power level, report number, occurrence code and report type) of the fne l
the duration should be listed as zero, 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 fu.ther 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 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 begins 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 all shutdowns or significant power reductions are reported.
Exhibit G - Instructions for Preparation 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 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 app:icable.
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 Entrs beginsin onc report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG.01(315.
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 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 as initiated t'y 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 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 XXXXXX. The code ZZZZZZ should be used for end of the report period and pick up the ensuing down time events where a component. designation is not applicable.
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 hours the genera.
RENCE. Use the column in a narratise fashion to amplifs or tor was on hne should equal the gross hours m the reportmg expla n the circumstances of the shutdown or power reduetion period.
The column should include the specific cause for each shui
- ""'*E""
"' I"*" '# "
- "2# ' ' # ""
REASON. Categorize by letter designation in accordance contemplated long term correctise action taken. if appropo-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 dunng METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identification of REDUCING POWER.
Categori/e by number designation the critical path activity and a report of any single release of radioactivity or single radiation exposure specifically associ-INote that this differs from the Edison Electric Institute ated 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. EEI 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 shuidown or power reduction for t hi>
is tno small a change io warrant explanation.
narrative.
DATE: September 1982 REFUELING INFORMATION 1.
Name of facility.
Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown.
September 20, 1982 3.
Scheduled date for restart following refueling.
November 1, 1982 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)?
No.
The reload fuel design and confirmation along with the safety analysis has been reviewed by the Plant Safety Committee in accordance with 10CFR Section 50.59 with a determination that prior NRC review and approval is not required.
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) 60 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 485 increase size by 503 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
DATE:
19R9 l
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