1CAN038404, Monthly Operating Rept for Feb 1984
| ML20087M577 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/29/1984 |
| From: | John Marshall, Morton K ARKANSAS POWER & LIGHT CO. |
| To: | Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 1CAN038404, 1CAN38404, NUDOCS 8403300068 | |
| Download: ML20087M577 (7) | |
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OPERATING DATA REPORT DOCKET NO. 50-313 DATE 3/15/84 COMPLETED fly K.L. Mortnn TELEP110NE 501-964-3115 OPERATING STA10S
- 1. Unit Name:
Arkansas Nuclear One - Unit 1 N"
- 2. Reporting Period:
February 1-29, 1984 2568
- 3. Licenwd Thermal Power (MWri:
902.74
- 4. Nameplate Rating (Grou MWe):
- 5. Design Electrical Rating (Net MWel; 850 883
- 6. Maximum Dependable Capacity (Grou MWe):
86
- 7. Masimum Dep(ndable Capacity (Net Mhel:
- 8. If Changes Occur in Capadiy Ratings titems Number 3 Through 7)Since Last Report.Gise Reasom:
None
- 9. Power Lesel T4, which Restricted. lf Any (Net MWe):
- 10. Reasons For Restrictions.lf Any:
T his Month Yr..to Date Cumulatise ll flours In Reporting Period 696.0 1,440.0 80,635.0
- 12. Number Of flours Reactor was Critical 696.0 1.440.0 53,875.5
- 13. Reactor Resene Shutdown llour, 0.0 0.0 5,044.0
- 14. Hours Generator On-Line 696.0.
1,440.0 52,690.2
- 15. Unit Rewne Shutdown liour, 0.0 0.0 817.5
- 16. Gross Thermal Energy Generated iMWill 1.648.365.
3,549,633, 125,469,930.
- 17. Grow Electrical Energy Generated (MWil) 554.700.
1,194,755.
41,333,120.
- 18. Net Electrical Energy Generated (MWHI 530,977.
1,145,442.
39,403,830.
- 19. Unit Senice Factor 100.
100.
65.3 100.
100.
66.4
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (Using MDC Neti 91.3 95.1 58.5-89.8 93.6 57.5
- 22. Unit Capacity Factor (Using DER NetI 0.0 U.U 13.0
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Ov- %st 6 Months (Type. Date,and Duration of Eachi:
NONE
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in rest StatusiPrior io Commercial Operations:
Forecast Achiesed INITIA L CRITICA LITY -
INITIA L ELECTRICI fY COMMERCIAL OPER ATION 9403300068 840229 PDR ADOCK 05000313
'"III'-
R PDR J
O AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.
50-313 UNIT One DATE 3/15/84 K.L. Morton COMPLETED BY 501-964-3115 TELEPHONE MONTH February, 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 781 759 17 781 758 2
18 782 757 3
4 20 757 5
782 757-2 759 6
77n 22 7
762 23 758 8
760 24 759 760 760 9
25 759 757 10 23 11 27 757 758 756 28 759 755 13
,9 I4 30 l
760 IS 31 i
760
~
16 l'
INSTRUCTIONS On this format.hst the average daily unit power lesel in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77)
i i
NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
FEBRUARY-1984 UNIT 1 The Unit started the month at 94% power due to a suspected tube degradation in the "A" OTSG.
On February 6, the Unit's power level was further reduced to 92% due to a slight increase in the "A" OTSG tube leak rate. The Unit remained at this power level throughout the end of the month.
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DOCKET NO. 50-313 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME ANO-Unit 1 DATE March 15. 1991 COMPLETED BY bn Mnr+nn F
REPORT MONTH ebruary. 1984 TELEPHONE (5nt} ggA_3375 "b
e r.
1:
5*
.2 _e ysX Licensee g%
=o Cause & Corrective No.
Date g
gg 3
,g g 5 Event a?
S.3 Action to H
$5 5
}odig Repors =
(N0 Prevent Recurrence d
N/A-N/A N/A N/A N/A N/A N/A N/A N/A N/A L
l i
i 2
3 4
F: Forced Reason:
Method:
Exhibit G Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintqnance or Test 2-Manual Scram.
Entry Sheets for Licensee C Refueling 3 Automatic Scram.
Event Report (LER) File (NUREC-D-Regulatory Restriction 4-Continuation 0161)
E-Operato'r Training & License Examination 5-Load Reduction 5
F Administrative 9-Other G-Operational Error (Explain)
Exhibit I - Same Source
-(9/77)
Il-Other (Explain)
~
UNIT SHUTOONNS 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-f: cant reduction in power level (greater than 20% reduction L!CENSEE 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 pertaining 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. sequential l
shut down completely. For such reductions in power level, report number, occurrence code and report type) of the Ine 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 he Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns, of course smce 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.
n t a reportable occurrence was involved.) If the outage or power reductmn will not result in a reportable occurrence.
NUMBER. This column should indicate the sequential num, the positive indication of this lack of correlatmn 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 reduction begins in one report period and ends in another.
SYSTEM CODE. The system in which the outage or power 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.
I f UCen5ee 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 applicable.
of each shutdown or significant power reduction. Report as year, month, and day. August 14,1977 would be reported as 770814. When a shutdown or significant power reduction COMPONENT CODE. Select the most appropriate component 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.01til1 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 reqmred to be initiated by no later than the weekend following discovery e.g., wrong valve operated through error; list valve as component.
of an off-normal condition. It is recognized that some judg.
ment is required in categorizing shutdowns in this way. In C.
general, a forced shutdown is one that would not have been If a chain of failures occurs, the first comp (ment to mal-completed in the absence of the condition for which corrective function should be listed. The sequence of events,includ.
action was taken.
ing the other components which fail should be described under the Cause and Corrective Action to Prevent Recur.
rence column.
DURATION. Self-explanatory. Ghen 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.
end of the report period and pick up the ensuing down time signated XXXXXX. The code ZZZZZZ should be used for m the following report periods. Report duration of outages events where a component. designation is not applicable.
I rounded to the nearest tenth of an hour to facilitate summation.
The sum of the total outage hours plus the hours the genera' CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.
tor was on line should equal the gross hours m the reportmg RENCE. Use the column in a narrative fashion to amplifs or period
- explain the circumstances of the shutdown or power reduction The column should include the specifie cause for each shm REASON. Categorize by letter designation in accordance "I F*#'
with the table appearing on the report form. If category 11 contemplated long term emrective action taken. if appropo.
must he used. supply brief comments.
ate. This column should also be used for a description of the major safety-related corrective nuintenance perfomied dunng METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identification of REDUCING-POWER. Categorize by number designation the critical path activity and a report of any single release of radioactivity or single radiatwn exposure specifically associ.
INote that this differs 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.
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 reduction for this is tno small a change to warrant explanation.
narrative.
4 8
REFUELING INFORMATION 1.
Name of facility.
Arkansas Nuclear One-Unit I l
1 2.
Scheduled date for next refueling shutdown.
November 1, 1984 3.
Scheduled date for restart following refueling.
January 10, 1985 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 Technical Soecification chanae.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
September 1. 1984 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.
Yes, the reload analysis will be done usino newly developed thennal hydraulic codes.
Babcock & Wilcox will be submitting Topical Reports on the new codes for NRC review prior to September 1,1984.
7.
The nuuber of fuel assemblics (a) in the core and (b) in the spent fuel ~ storage pool, a) 177 b) 11(;
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-988 licensed but increase size by under construction 9.
The projected date of the last refueling that-can be discharged to the spent fuel pool assuming the present licensed capacity.
DATE:
-1998~
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O ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 (501) 371-4000 March 15, 1984 1CAN038404 Mr. Harold S. Bassett, Director Division of Data Automation and Management Information Office of Resource Management U. S. Nuclear Regulatory Commission Washington, D. C.
20555 SUSJECT: Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Monthly Operating Report (File:
0520.1)
Gentlemen:
Attached is the NRC Nonthly Operating Report for February 1984 for Arkansas Nuclear One - Unit 1.
Very truly yours, ohn R. Marshall Manager, Licensing JRM:SAB:si Attachment cc:
Mr. John T. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV
((l y 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 iff Mr. Richard C. DeYoung
{
Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 MEMBER MICOLE SOUTH UTILITIES SYSTEM