2CAN018409, Monthly Operating Rept for Dec 1983
| ML20079M725 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/31/1983 |
| From: | Bramlett L, John Marshall ARKANSAS POWER & LIGHT CO. |
| To: | Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 2CAN018409, 2CAN18409, NUDOCS 8401270402 | |
| Download: ML20079M725 (7) | |
Text
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OPERATING DATA REPORT DOCKET NO. 50-368 DATE An. 1984 COhlPLETED BY T. R Ernmlett TELEPilONE.')U1-964-3145 OPERATING STATUS h sas h iear h - M t 2 Note $
- 1. Unit Name:
- 2. Reporting Period: December 1-31. 1983
- 3. Licensed Thermal Power 15 twt):
2815 942.57
- 4. Nameplate Rating (Gross AlWe):
912
- 5. Design Electrical Rating (Net NIWel:
7
- 6. Maximum Dependable Capacity (Gross atWe):
858
- 7. Stasimum Dependable Capacity (Net stWe):
- 8. If Changes Occur in Capacity RatinFs (items Number 3 Through 7) Since Last Report. Gise Reasons:
E
- 9. Power Lesel To Which Restricted. If Any (Net alwe):
- 10. Reasons For Restrictions. If Any:
This Stonth Yr..to Date Cumularise 744.0 8.760.0 33.024.0 i1. Hours in Reporting Period 0.0 5,470.9 21,627.1
- 12. Number Of Hours Reactor Was Critical 0.0 91.6 1,430.1
- 13. Reactor Resene Shutdown Hour, 0.0 5.381.6 20,950.3
- 14. Hours Generator On Line
- 15. Unit Rewne Shutdown Hours 0.0 0.0 75.0 0.
14.298.479.
52.549,540.
- 16. Gross Thermal Energy Generated 151WH)
O.
4.641.647.
17,016,951--
- 17. Gross Electrical Energy Generated ($1WH, 0.
4J27,954.
16,206,340.
- 18. Net Electrical Energy Generated 15tWHI
- 19. Urdt Senice Factor 0.0 61.4 63.4 0.0 61.4 63.7
- 20. Unit Availability Factor 0.0-58.9 57.2
- 21. Unit Capacity Factor (Using SIDC Net)
- 22. Unit Ca,nacity Factor (Using DER Net) 0.0 55.4 53.8
- 23. Unit Forced Outage Rate 0.0 19.2 20.4 24, Shutdowns Scheduled Oser Next 6 Stunths iType, Date,and Duration of Each1:
Now in scheduled refueling and maintenance outage which started early, Septenber 26, 1983,and is expected to last until February, 1984
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
Fabrimrv. 1984
- 26. Units in Test Status tPrior o Commercial Operation):
Forecast Achiesed INITIA L CRITICA LITY INITIA L ELECTRICITY CO\\l%1ERCIAL OPER ATION O00hfD PDR
("IllI
AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.
50-368 UNIT
~
DATE Jan. 1984 COMPLETED BY L.S. Bramlett 501-964-3145 TELEPHONE MONTH December. 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 0 1
37 o
0 2
,3 0
0 o
3 19 4
0 0
20 0
0 5-21 0
6 22 0
0 23 0
8 0
0 25 0
9 10 0
0 26 11 0
.0 27 0
12 28 0
13 0
0 29 14 0
0 30 0
0 15 31 0
16 INSTRUCTIONS On this format. list the average daily umt power lesel ni MWe-Net ihr each day in the reporting month. Coinpute to the nearest whole megawatt.
Yll77i
NRC MONTHLY OPERATING REPORT OPERATING SUMARY DECEMBER 1983 UNIT 2 The unit remained in the Refueling / Maintenance Outage, 2R3, throughout the month.
O
DOCKETNO. 50-368 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Ah?
DATE Jan. 9. 1984 COMPLETED BY L.S. Breamlore REPORT MONTH abcetiber 1983 TELEPHONE (501196441ta n.
3?
"h Y
Licensee
,E-r, Cause & Corrective No.
Date g
3g i;
jy5 Event g?
gl Action to O
3 5 =g Report :
mO 5
Prevent Recurrence
$E 5
H u
c 83-10 831005 S
744.0 C
4 N/A ZZ
- aun.
Refueling and Maintenance Outage i
i 2
3 4
F: Forced Reason:
Method:
Exhibit G-Instructions S: Scheduled A Equipment Failure (E. niain) 1-Manual for Preparation of Data B-Maintensnce of Test 2-Manual Scram.
Entr> Sheets for Licensee C Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Continuation 0161)
E-Operator Training & License Examination 5-Load Reduction 5
F-Administrative 9-Other G-Operational Error (Explain)
Exhibit I - Same Source P8/77) li-Other (Explaini
UNIT SHUTDO'aNS AND POWER REDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns during the in accordance with the table appearmg 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 !rt power level (greater than 20% reduction LICENSEE EVENT REPORT c.
Reference the appheable 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, sequentu!
l shut down completely. For such reductions in power level,
'ePort number, occurrence code and report type) of the fne 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 Repor Action to Prevent Recurrence column should explain. The (LER) File (NURFG.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 fuPy 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 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 n ted as not applicable (N/A).
for that calendar year. When a shutdown or significant powe' SYSTEM CODE. The system in which the outage or power reduction begins in one report period and ends in another, reduction originated sh'ould be noted by the two 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 unit has achieved its first power generation, no num-for 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 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 i ntr>
beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG.0lbi).
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 signi'icant 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 conditicc. It is recognized that some judg.
ment is required in categorizing shutdowns in this way. In C.
11 a chain of failures occurs, the first component to mal.
l 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.
unJer the Cause and Corrective Action to Prevent Recur.
rence column.
DURATION. Self. explanatory. When a shutdown extends beyond the end of a report penoJ, 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 foi l
end of the report period and pick up the ensuing down time events where a component. designation is not applicahte.
in the following report periods. Report duration of outages I
rounded to the nearest tenth of an hour to facilitate summation.
CAUSE & CORRECTIVE ACTION TO TREVENT RECUR-l The sum of the total outage hours plus the hours the genera.
RENCE. Use the column in a narrative fashion to amphis ei i
tor was on line should equal the gross hours m the reportmg explain the circumstances of the shutdow or power reduction period.
The column should include the specilie cause for each shm down or significant power reduction and the immediate and l
REASON. Categorize by letter designation m 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 desciiption of the l
must be used, supply brief comments.
major safety.related corrective mamtenance performed duriny METHOD OF SHUTTING DOWN THE REACTOR OR
"' 8 8# "' P"*" ' "* " 5" " "E '"
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.
3 Note 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.
duled Partial Outage " For these terms. eel uses a change of For long textual reports continue narrative on separate paper 30 MW as the bicak point. For larger power reactors. 30 MW and reference the shutdown or pow. reductmn for this is too small a change to warrant explanation.
narrative.
S r
C REFUELING INFORMATION 1.
Name of facility.
Arkanene Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown.
June, 1985 3.
Scheduled date for restart following refueling.
February,1984 (current refueling) 4.
W'.11 refueling or resumption of operation thereaf ter require a technf.<!al specification change or other license amendment?
If acswer 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.
Review has been empleted 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
April, 1985 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.
To Be Determined 7.
The number of fuel assembig (a) in the core and g)g in the spent fuel storage pool, a) b)
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.
0 present 988 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:-2003 - -- -
e-w-+-
7+
y--
N ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK, ARKANSAS 72203 (501) 371-4000 January 13, 1984 2CAN018409 Mr. Harold S. Bassett, Dircctor Division of Data Automation and Management Information Office of Resource Management U. S. Nuclear Regulatory Commission Washington, D. C.
20555
SUBJECT:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Monthly Operating Report (File:
2-0520.1)
Gentlemen:
Attached is the NRC Monthly Operating Report for December 1983 for Arkansas Nuclear One - Unit 2.
Very truly yours, 4I2 M. > @
John R. Marshall Manager, Licensing JRM:SAB:s1 I
Attachment - See hard copy for complete attachment l
cc:
Mr. John T. Collins l
Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Mr. Richard C. DeYoung Office of Inspection and Enforcement U. S. Nuclear Regulatory commission Washington, DC 20555 7
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MEMreH MsuuLE SOUTH UTiuTIES SYSTEM
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