ML20071E908
| ML20071E908 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/15/1983 |
| From: | Gertsch A ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20071E903 | List: |
| References | |
| NUDOCS 8303150384 | |
| Download: ML20071E908 (7) | |
Text
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OPERATING DATA REPORT DOCKET NO.
50-313 DATE 2/15/R3 COMPLETED BY A.1 Car twh TELEPHONE 501-964-3155 OPERATING STATUS N
Arkansas Nuclear One - Unit 1
- 1. Unit Name:
- 2. Reporting Period: January 1-31. 1983
- 3. Licensed Thermal Power (MWt):
2568 902.74
- 4. Nameplate Rating (Gross MWe):
850
- 5. Design Electrical Rating (Net MWe):
883
- 6. Maximum Dependable Capacity (Gross MWe):
836
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:
- 9. Power Level To Which Restricted,if Any (Net MWe):
None
- 10. Reasons For Restrictions. If Any:
This Month Yr.-to-Date Cumulative 744.0 744.0 71.170_n i1. flours In Reporting Period 0.0 0.0 48.007.3
- 12. Number Of tiours Reactor Was Critical 0.0 0.0 5,044.0
- 13. Reactor Resene Shutdown llours 0.0 0.0 47.057.5
- 14. Ilours Generator On-Line
- 15. Unit Resene Shutdown flours 0.0 0.0 817.5 0.0 0.0 111.769.814.0
- 16. Gross Thermal Energy Generated iMWil)
- 17. Gross Electrical Energy Generated (MWii) 0.0 0.0 36.765.044.0 0.0 0.0 as.n37_R10 n
- 18. Net Electrical Energy Generated (MW111 0.0 0.0 66.1
- 19. Unit Senice Factor 0.0 0.0 67.3
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 58.9 0.0 0.0
- 22. Unit Capacity Factor (Using DER Net) 57.9 0.0 0.0 15.6
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each t:
Unit now in scheduled refueling outage which began November 8,1982 March 15, 1983
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achiesed INITI A L CRIIICA LITY INITI AL ELECTRICITY CO\\lMERCIAL OPER ATlON 8303150384 830215 PDR ADOCK 05000313
'"l778 R
AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.
50-313 UNIT I
DATE 2/15/83 COMPLETED BY A. J. Gertsch TELEPHONE 501-964-3155 MONTH January, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe. Net) 1 0
37 0
2 0
18 0
0 3
i9 0
0 0
4 20 5
0 21 0
0 6
22 0
0 7
23 0
8 0
24 n
9 0
25 0
0 10 26 0
0 11 0
27 12 0
28 0
0 13 29 0
0 14 n
3o 0
15 0
3, 16 0
INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(4/77)
t NRC h0NTHLY OPERATING REPORT OPERATING SUP9tARY - JANUARY 1983 UNIT 1
-The unit remained shut down the entire month for the 1-R5 refueling outage.
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DOCKET NO.
50-313 UNII' SHUTDOWNS AND POWER P. EDUCTIONS UNIT NAME.ANO - IInit 1 DATE Fah 7
lont COMPLETED BY A_J_ Odrtid REPORT MONTH Januarv TELEPHONE (401) 06A-M 55 n.
.5 ?
"h hE Licensee gg 9,
Cause & Corre. tive
,5 '8 n.'
Action to No.
Date g
3g 4
2g&
Event u'
H
$E 35g Report r SU Prevent Recurrence a
C 82-07 821108 5
744.0 C
4 N/A N/A N/A 1-R5 Refueling Outage C
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 or Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Reporn (LER) Fiie (NUREG-D-Regulatory Restriction 4-Continuation 0161)
E-Operator Training & License Examination 5-Load Reduction 5
F-Administrative 9-0ther G-Operational Error (Explain)
Exhibit 1 - Same Source P8/77)
Il-Other (Explain)
h UNIT SHUTDO5NS AND POWER REDUCTIONS INSTRUCTIONS This reprrt shpuld describe all plant shutdowns during the in accordance with the table appearing on the report form.
repoit period. In addition,it should be the source of explan.
If category 4 must be used, supply brief cumments.
ation of significant dips in average power levels. Fd ogni-ficant reduction in pcwer level (greater t!.an 20% reduction LICENSEE EVENT REPORT 4 Reference the appliemble 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 p%er 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 fne l
the duration should be listed as zero, the method of reduction part designation as described in item I7 of histructions tot should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Lisensee Event Repon Action to Prevent Recurrence column should explain. The rLER) file (NUREG-0161). This infom;ation may not be Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns. of course. since should be used to provide any needed explanation to fully further investigation may be required to ascertain 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 posit;ve indication of this lack cf 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.
reduction originated sh'ould be noted by the tw'o 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 Sheets Until a urit has achieved its first power generatica, no num-f r Licensee Event Report (LER) File (NUREG-0161).
ber should be astigned to each entry.
Systems that do not fit any existng 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. Se;ect the most appropriate component as 770814. When a shutdown or significant power reduction from Exhibit 1 - 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-0161 L be made for both report periods to be sure all shutdowns using the following critieria:
or significant power reduct.ons 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 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 be listed. The sequence of events.includ.
l 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 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 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 narrative fashion tti amphti m j
tor was on line should equal the gross hours m the reportmg explain the circumstances of the shutdown or power reduction penod.
The column should include the specifie cause for each shut down or significant power reduction and the'immediate anJ REASON. Categorize by letter designation in accordance contemplated long term corrective action taken. if appropo-with the table appearing on the report form. If category 11 ate. This column should also be used for a deseiiption of the must he used, supply brief comments' major safety-related corrective maintenance performed during the outage or power reduction including an identification of l
METHOD OF SHUTTING DOWN THE REACTOR OR l
REDUCING POWER. Categorite by number designation the critical path activity and a report of any smgle release of radioactivity or single radiation exposure specifically associ-INote that this ditters from the Edison Electric Institute sted with the outage which accounts for more than 10 percent (EEI) definitions of " Forced Partial Outage" and " Sche.
of the allowable annual values.
duled 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 shutdown or power reduction for this is too small a change to warrant explanation.
narrative.
L.
REFUELING INFORMATION l..
Name of facility.
Arkansas Nuclear One - Unit 1 2.
Scheduled date for next refueling shutdown. November 8,1982 - Refueling now in progress 3.
Scheduled date for restart following refueling.
March 15.,1983 4.
Will refueling or resumption of operation thereaf ter 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)?
Ypq_
Reload report and associated proposed specification change-(82A-14).
5.
Scheduled date(s) for submitting proposed licensing action and supporting information. Submitted November 19, 1982 6.
Impartant 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, two of which will be hiah burn-up test assemblies, and operate for approximately 16 months.
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 379 l
l 9.
The projected date of the last refueling that can be discharged j
to the spent fuel pool assuming the present licensed capacity.
DATE:
1989
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a CHALLENGES TO THE SAFETY VALVE FAILURE AND RELIEF VALVE FAILURES FOR ANO-1 This annual-report is being submitted in accordance with the requirement of NUREG-0737, Item II.K.3.3.
ANO-1 has experienced no challenges due to system conditions to the Primary System Code Safeties (PSCS) nor Electromatic Relief Valves (ERV) during the year 1982.
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