ML20052G103
| ML20052G103 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/12/1982 |
| From: | Bramlett L ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20052G100 | List: |
| References | |
| NUDOCS 8205140309 | |
| Download: ML20052G103 (6) | |
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OPERATING DATA REPORT
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50.368 DOC KET NO.
DATE 04/12/82-
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'J CO.\\lPLETED llY L. S,_Bramlett TELEPil0NE L5H1) 964-3145 OPERATING SI AI,Up *
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- i. Unit Name:. Mkansas Nuclear One - Unit j Notes c
- 2. Reporting Perited:,P. arch 1 - 31_,1 W u. L 20'I b b
- 3. Licenud lhengall'ows:(N!'VI).
. o 942*57
- 4. Nameplate Rating (Gro*qNther e -..
9l2
- 5. Design Electri.) Rating (Net 51WeL m,
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- 6. Slasimum Dependable rapacity (Gross N1We): Mw_4_
- 7. Stasimum Dependable bpacity (Net SlWe):
ON
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- 8. If Chc.iges Occur in Capacity Ratings (stems Number 3 Ilirough J) Since Last Report. Gise Reasons:
N-None
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None
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- 9. Power LoM to Which Restikted. lf Anv (Net 5then
- 10. Reasems f ir Restrictions. If Any:
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lhn 51onth Yr..to.Date Cumulati e
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744.0 2160.0 17164.0
- 11. lioun in Reporting Period
- 12. Number Of liours Reactdr Was Critical 718, 8 ' "
1753.5 12648.1.
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0.0 1013.7
- 13. Reactor Resene Shutdown floun
- 14. Iloun Generator On Line LO7. 8,_,,
1737 A __
12279.0 0. 0 '.._. '
' 0. 0 75.0 r,
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- 15. Unit kewne Shutdown flous,.
1906738.
4608874.,
30394743.
- 16. Gross t her.nal Energy Geu-rated OlWill
- 17. Gross Electrical Energ> Generwed oiWII) 615849.J 1489896?.
9861814.
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1420245._'.
9391243.
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- 18. Net Electrkot Enyra Generat 'J 01WiD 90 1 80.4 59.5 s
- 19. Unit Senice Factor
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9'5 l 80.4'
.59 9
- 20. Unit Auitability Factor 2
3 h.b_
72,1 58.3 76.6 6?.0
- 21. Unit Capacity Factor (Using 51PC Neti Co
- 22. Unit Capatity Factor (Using Dell Net) 44 Jje# '
19.6
- 23. Unit Forted Outage Pate m
- 24. Shutdowns Scheduled Oser Nest 6 Wnths t Type. D.ne.and Duration of Eacht
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3 9
- 25. If Shut Down \\t I.nd Of Report Puind. Estimated Date of Startup:
- 26. Unin la Iest Status IPnor tu Commercial Operationt Forecast -
Achiesed INill \\ L CRillCAI.IIY INill \\l. Et i CIPirli Y
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AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. -- 50-368 UNIT DA1E 04/12/82 L. S. Bramlett COMPLETED BY 501-964-3145 TELEPHONE MONTH March,1982 DAY AVERAGE D AILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe Net) i 873 862 37 2
860 862
,g 3
R61 i9 854 4
873 869
,o 5
876 873 21 6
875 872
,2 7
815 871 33 8
0 869 24 9
96 869 33 10 E9 26 871 11 863 873 2,
i, 845 874
,g 13 785 39 871 14 785 865 30 15 822 867 3
Ob1 16 INSTRUCTIONS On this format,hst the ave age d:ily unit power leselin MWe Net for cach day in the reporting month. Compute o the nearest whole megawatt.
(9/77 )
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NRC MONTHLY OPERATING REPORT OPERATING SUtiMARY - MARCH, 1982 UNIT II The unit began the month at 100% full pcwer and essentially operated there until March 7, with the exception of minor power reductions due to FW Chemistry. On March 7, the unit tripped when a turbine runback was initiated by Main Generator stator cooling pressure /
temperature / flow limits. The unit was returned to 100% power on March 11, and operated there until March 12. On this date power was reduced to 90% for a moderator temperature coefficient test.
Power was returned to 100% power on March 15, and continued there through the remainder of the month.
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4 DOCKET NO 50-368 UNIT SHUTDOWNS AND POWER REDLCTIONS UNIT NAME ANO-2 DATE 4-S-82 COMPLETED BY T.
S-Ernmlett REPORT MONTH March TELEPHONE 501-964-3145 "i
Licensee
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Cause & Corrective o
No.
Date i
58 a
2sE Event
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El Action to
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Report 2
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Prevent Recurrence H
e 6
82'04 820307 F
36.2 A
3 N/A HA INSTRU Turbine runback to approx.
20MW initiated by stator e
cooling pressure / temperature /
flow limits.
Reactor tripped on high steam generator level.
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i 2
3 4
F: Forced Reason:
Method:
Exhibit G -Instructhms S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maint<: nance of Test 2-Manual Scram-Entry Sheets for Licensee C Refueling,
3-Automatic Scram.
Event Report (LER) File (NUREG-D Regulatory Restriction 440ntinuation 01611 E-Operator Training & License Examination 5-Load Reduction 5
F Administrative 9-Other G-Operational Error (Explain)
Exhibit 1 - Same Source N/77)
Il Other (Explain)
7 UNIT SliUTD0' NS AND POWER REDUCTIONS INSTRUGIONS This report should descobe all plant shutdowns during the in accordance with the table appe,inny on the report fonin 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 iri power level (greater than 20% reduction LICENSEE EVENT REPORT :r.
Reference the apphcable 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 pertammg to the outage or power reduction. Enter the first four parts (event year, sequential should be noted, even though the unit may not have been shut down completely. For such reductions in power level, report number. occurrence code and report type) of the tne l
the duration should be bsted as iero, the method of reduction part designation as desenbed in item 17 of Instructions for should be hsted as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee I. vent Report Action to Prevent Recurrence column should explain. The (LER) File (NURI G.0161 L This mtormation may not be i mediately evident for all suth shutdowns. of course. smce Cause and Corrective Action to Prevent Recunence column dmuld be used to provide any needed explanation to fully further investigation ma> be requaed to ascertam whether or describe the circumstances of the outage or power reduction.
n t a reportable occurrente was involved.) If the outage or power reduction wd! not result in a reportable occurrence.
NUMiiER. This column should indicate the sequential num, the positive indication of this lask of conelation should be ber assigned to each shutdown or significant reduction in power
""ted as not apphcable (N/A).
for that calendar year. When a shutdown or significant power SYSTEM CODE. The system m which the outage or power reduction begins m one report period and ends in another.
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an entry should be made for both report periods to be sure reduction originated should be noted b the two digit code of Y
all shutdowns or significant power reductions are reported.
Exhibit G, Instructions for Preparat on of Data Lntry Sheen Until a unit has achieved its first power generation, no num-f r Licensee Lvent Report (LER) File (NURLG-0161).
bet should be assigned to each entry.
Systems that do not fit any existmg 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 appropn.ete component as 770814. When a shutdown or significant power reduction from Exhibit I instractions for Preparation of Data i ntr>
begmsin one report period and ends m another, an entry should Sheets for Licensee Event Report (LER) File (NURI.G-Olol L be made for both report periods to be sure all shutdowns using the followmg critieria:
or sigmficant power reductions are reported.
lYPE. Use "F" or "S" to mdicate either " Forced" or " Sche-duled," respectively, for each shutdown or significant power it if not a component fadure. use the related component reduction. Forced shutdowns include those required to be e g, wrong valve opera.ed through error; hst vahe as miturted by no later than the weekend following discovery component.
of an of f. normal condition. It is recognized that some judg-ment is requned m categorizmg 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 hsted. The sequence of events. melud-completed in the absence of the condition for w hich corrective ing the other components which fail, should be desenbed action was taken.
under the Cause and Corrective Action to Present Recur.
rence column.
DUR ATION. 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 eiosting 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 apphcable in the followmg report periods. Report duration of outages rounded to *he nearest tenth of an hour to facilitate summation.
CAUSE & CORRECllVE ACTION TO PREVENT RECUR The sum of ths total outage hours plus the hours the genera-RENCE. Use the column m a nanatne fashion to amphis m tor was on hne should equal the gross hours in the reporting expla n the circumstances of the shutdown or power reduchon P#""d' The column should include the specific c.iuse foi cach simi down or significant power reduction and the immediate and REASON. Categon/e by leuer designation in accordance contemplated long term corrective acuon taken. if appropn with the table appeanng on the report fonn. It category 11 ate. This column should also be used for a desenpuon of the must be used. supply briel comments maior safety.related conectise mamtenance performed dunng MElllOD OF SilUTTING DOWN Tile REACTOR OR tb outag or power reducuon induing an WenMicaWn ot t
cnnea path acuq and a repon of any sinpe rdeaw M REDUCING POWER.
C ategon/c by number designation radioastivity or smgle radianon esposure spa thcall) assocF INote that this ditters from the Edison Ilectnc Institute ated with the outage whath accounts for more than 10 percent (EFI) delimtions of " Forced Partial Outage" and " Sche.
of the allowable annual values.
daled Pattial Outage.' I or these terms. eel uses a change of For long textual reports continue narrative on separate paper 30 MW as the break pomt. I or larger power rnetors.30 MW and reference the shutdown os pow er reducnon for this n too small a thange in wanant esplananon.
narrat ve.
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REFUELING INFORMATION 1
1.
Name of facility.
Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown. 9/l/82 3.
Scheduled date for restart following refueling.
11/1/82 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 configuration along with the safety analysis will be reviewed by the Plant Safety Committee in accordance with 10CFR Section 50.59.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information. NA 6.
Important licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, ur. reviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
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 0
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
DATE:
1989
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