ML20071Q023
| ML20071Q023 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/15/1982 |
| From: | Gertsch A ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20071Q022 | List: |
| References | |
| NUDOCS 8212290196 | |
| Download: ML20071Q023 (5) | |
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,'I NRC MONTHLY OPERATING' REPORT t'
OPERATING SUN 4ARY - OCTOBER IW2 a
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UNIT I 4
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r Unit I beg'an the month 'of October at 76.69% fuRoower.
The Unit is in a power coastdown'for the 1-R5 Refueling Outage scheduled, November'26.
On October 26, 1992, reactor power was reduced to apprcximately 65% as'the "B" Reactor Coolani: Pu.np was secured for a seal leak., Jhe Unit operated the remainder of the month,with only three reactor coolant pumps. 'By the end of October, reactor powey had been reduced to,approxirnately 68.48%.
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r 8212290196 821115 FDR ADOCK 05000313 R
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OPERATING DATA REPORT DOCKET NO.
50-313 DATE 11/15/R7 f'
CONIPLETED BY A _._1_ Cor3ch TELEPilONE 501-964-3155 OPERAi!NG STAl US Notes Arkansas Nuclear One - Unit 1
- 1. Unit Name:
- 2. Reporting Period:
October 1-31, 1982 2568
- 3. Licensed Thermal Power 151Wt):
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902.74
- 4. Nameplac Rating (Gross 31We):
850
^
S. Design Electrical Rating (Net StWe):
883
- 6. Stasimum Dependable Capacity (Gross 51We):
- 7. 51asimum Dependable Capacity (Net 51We):
A36
- 8. If Changes Occut in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Gise Reasons:
L
- 9. Power Lesel To Which Restricted if Any (Net 31We):
None N/A
- 10. Reasons For Restrictions. If Any:
m b
This Stonth Yr..to.Date Cumulatise b
II. Ilours in Reporting Period 745.0 7296.0 68971.0 745.0 5558.6 47806.1
- 12. Number Of liours Reactor was Critical 0.0 0.0 5044.0 f
r3. Reactor Resene Shutdown llours 7^5.0 5483.7 46867.5
~
- 14. liours Generator On-Line 0.0 0.0 817.5
- 15. Unit Resene Shutdown liours 1589781.0 11916108.0 111446314.0 h
- 16. Gross Thermal Energy Generated (31Wii, 7
- 17. Gross Electrical Energy Generated t\\lWil) 479385.0 3834395.0 36671151.0 f
l IS. Net Electrical Energy Generated t.\\1 hill 453135.0
__3513054.0 34949455.0 100.0 75.2 68.0 t
- 19. Unit Senice Factor 100.0 75.2 69.1' M
- 20. Unit Asailability Factor 72 8 59.6 60.6
- 21. Unit caiucity Factor (Using 51DC Net) 71.6 58.6 59.6
- 22. Unit Capacity Factor (Using DER Neu 0.0 12.0 15 7
- 23. Unit Forced Outage Rate
- 24. Shutd o a icheduled Oser Next 6 N1onths iType. Date and Duration of Each):
Ret aling outage scheduled for November 26, 1982
,25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status t Prior to Commercial Operation):
1:orecast Achiesed INITI A L CRITICAL.lT Y INil l A I. E LECT RICIIY
( O\\l\\1ERCI \\L OPER \\IlON s
to/77:
7 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-313 UNIT 1
DATE 11/15/82 COMPLETED BY A. J. Gertsch TELEPHONE 501-QAd 1149 MONTH October. 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
Mwe.Ne:3 641 1
17 644 2
644 is 642 3
643 642 39 640 644 4
,o 642 627 5
21 6
641 623 22 640 614 7
33 641 600 8
b41 595 9
25 641 524 10
,6 643 Ii 27 477 12 644 493
,3 644 485 33
,9 645 484 14 3o 645 483 is 3
645 16 INSTRUCTIONS On this format. list the average daily unit power leselin MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77)
REFUELING INFORMATION 1..
Name of facility.
Arkansas Nuclear One - Unit 1 2.
Scheduled date for next refueling shutdown. November 9, 1982-Refueling in Progress 3.
Scheduled date for. restart following refueling. Fah 14; lor 1 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 renort and associated oronosed Soecification changes.
5.
Scheduled date(s) lor submitting proposed licensing action and supporting information. In-house review is in prooress with submittal scheduled by November 19.
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.
' Jill reload 72 fresh fuel assemblies, four of which will be high 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.
l present sno increase size by 170 l
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
DATE: 1986 i
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50-313 UNIf SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. ANO-Unit 1 UNIT N AME DATE Nov.
4, 1982 COMPLETED BY A.
J.
Gertsc11 REPORT MONTH OCTORRR TELEPHONE 501-964-3155 Licensee P,
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Cause & Corrective Action to No.
Date i
3g
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2g5 Event p
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j ;ji g Report a mV Prevent Recurrence H
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none a
4 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-Regulatory Restriction 4-Continuation 0161)
E-Operator Training & Ucense Examination 5-Load Reduction 5
F Administrative 9-Other Exhibit I - Same Source G-Operational Error (Explain) 19/77)
Il Other (Explain)
y' *.
UNIT SHUTDOhNS AND POWE3 REDUCTIONS
/
INSTRUCTIONS This : port 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 *. 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 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 fase 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 Repon 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, 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.
n t a reportable occurrence was involved.) If the outage or power reduction will not result in a reportable occurrence.
NUMBER. Tius 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 n ted 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 penod and ends in another, an entry should be made for both report periods to be sure reduction originated should be noted by the two digit code of Exhibit G Instructions for Preparation of Data Entry Sheets all shutdowns or significant power reductions are reported.
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 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 cor. fonent as 770814. When a shutdown or significant power reduction from Exhibit i Instractions for Preparation of Data Entr>
beginsin one eport period and ends in another, an entry should Sheets for Liecusee Event Report (LER) File (NURLG-Olet 1.
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 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 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 desenbed 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 net fit any existmg 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-tor was on line should equal the gross hours in the reportmg RENCE. Uw the column in a narrative fashion to amplifs ei explain the circumstances of the shutdown or power reduedon period.
The column should include the specific cause for each shui REASON. Categorize by letter designation in accordance down or significant power reduction and the ~immediate anJ with the table appearing on the report form. If category 11 contemplated long term corrective action taken. it appropio must be used. supply brief comments.
ate. This column should also be used for a desenplion of the major safety-related corrective maintenance pertomied dunng METHOD OF SHUTTING DOWN THE REACIOR 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 smgle release of radioactivity or single radiation esposure specifically associ-INote that this ditlers from the Edison Electric Institute ated with the outage which accounts for more th.m 10 percent (EEI) definitions of " Forced Partial Outage" and " Sche, of the allowable annual values.
dated 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 hm small a change to warrant explanation.
narrative.
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