ML20070R059
| ML20070R059 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/15/1982 |
| From: | Bramlett L ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20070R053 | List: |
| References | |
| NUDOCS 8301270267 | |
| Download: ML20070R059 (7) | |
Text
._
t t
y OPERATING DATA REPORT DOCKET NO.
50-368 DATE 12-15-82 COMPLETED BY L. S. Bramlett TELEPHONE 501-964-3145 OPERATING STATUS ~
Notes
- 1. Unit Name:
Arkansas Nuclear One - Unit 2 November 1 - 30. 1982
- 2. Reporting Period:
- 3. Licensed Thennas Power (MWt):
2815 _
- 4. Nameplate Rating (Gross MWe):
942.57 912
- 5. Design Electrical Rating (Net MWe):
897
- 6. Maximum Dependable Capacity (Gross MWe):
4 858
- 7. Maximum Deper.dable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Irems Number 3 Through 7) Since Last Report.Give Rearrs:
J None
- 9. Power Lesel To Which Restricted,if Any (Net MWe):
- 10. Reasons For Restrictions.If Any:
N/A i
This Month Yr.-to-Date Cumulative 720.0 8016.0 23520.0 i1. Hours in Reporting Period
- 12. Number Of Hours Reactor Was Critical 372.2 4640.2 15534.8-0.0 324.8 1338.5
- 13. Reactor Resene Shutdown Hours
'4441.3' 14983.1
- 14. Hours Generator On-Line 225.5 0.0 0.0 75.0 15.' Unit Resene Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH) 228166.0' 11164972.0 36950841.0 7
- 17. Gross Electrical Energy Generated (MWH) 71916.0 3584782.0 11956700.0 65178.0 3410559.0-11381557.0
- 18. Net Electrical Energy Gencruted (MWHi 31.3
-55.4 63.7-
- 19. Unit Service Factor -
4 31.3 55.4 64.,0
- 20. Unit Asailability Factor.
10.6 49.6 56.4
- 21. Unit Capacity Factor (Using MDC Net).
9.9 46.7 53.1-
- 22. Unit Capacity Factor (Using DER Net) 7.2 23.5 20.8
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Eacht None 4
N/A
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status IPrior to Commercial Operation):
Forecast Achieved '
INITIA L CRITICALITY INITIA L ELECTRICITY COMMERCIAL OPER ATION -
8301270267 821215 W
PDR ADOCK 05000368 goj773 R
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- - - - -, - - ~
AVERAGE DAILY UNIT POWER LEVEL D6 ' VET NO.
50-368 UNIT 2
DATE 12-15-82 COMPLETED BY L. S. Bramlett y
TELEPHONE 501-964-3145 November MONTH DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe NetI (MWe. Net) 1 0
g7 101 2
0 18 7
3 0
0 39 4
0 20 0
0 5
y, o
6 n
22 26 7
0 166 23 8
0 24 236 9
0 25 253 10 0
26 413 11 0
27 242 12 0
28 389 13 0
29 430 14 0
30 417 3
15 0
31 16 36 INSTRUCTIONS On this format. list the average daily unit power lesel m MWe. Net for ea:h day in the reporting month. Compute to the nearest whole megawait.
(9/77 )
NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
- NOVEMBER 1982 UNIT II Unit 2 begar the month in Mode 5 continuing outage #82-11 for refueling.
On November 10 the reactor was brought critical for low power physics testing and was. tripped on November 12 for hare testing.
The reactor was returr ad to criticality on November 12 for continued physics testing.
On November 15, the reactor tripped from 79% power when power supply (PS-12) in "B" Channel PPS failed.
On November 16 the unit was placed on line; however, later that day the reactor tripped on high steam generator level.
The unit was placed back on line.
On November 18 the unit wa-tripped during cooldown for work on incore detectors and a MSR safety valve.
On November 22 the unit was tied on line and reached 50% power on November 23.
Power was maintained at 50% for physics testing until November 27 when the unit tripped on low DNBR.
The unit was returned to power later that day and operated at 50% power through the end of the month.
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DOCKEfNO.
50-368 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME ANO-lhie ?
DATE Dec. 6 1982 COMPLETED BY L.S. Brnmlert I EPORT MONTH November TELEPHONE 501-964-3145 O
C
$ 1, Cause & Correi.tive jg 3
J&E Licensee
[=-t g."]
o Action to No.
Date h
~g 4
.5 s 5 Event gg H
y=
5 35g Report :
mU
,3 Prevent Recurrence v
C 82-11 820820 S
224.0 C
4 NONE ZZ ZZZZZZ Refueling 821112 S
8.6 B
1 NONE ZZ ZZZZZZ Low Power Physics Testing 821115 F
8.6 A
3 NONE CB 1NSTRU Power supply (PS-12) to "B" channel PPS failed. Power supply was re-placed.
82-12 821116 F
8.0 H
3 NONE ZZ ZZZZZZ Unit tripped on high S/G 1evel during low power operations.
82-13 821118 S
111.8 B
1 h0NE ZZ ZZZZZZ Unit. shutdown to repair incore detectors and MSR safety valve.
82-14 821127 F
9.4 A
3 NONE CB RELAYX Unit trip on low DNBR after an RCP trip due to sensitive relay.
The relay was replaced.
3 4
J I
F: Forced Reason:
Method:
Exhibit G Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenacce of Test 2 Manual Scram.
Entry Sheets for Licensee C Refueling 3 Automatic Scram.
Event Report (LER) File (NOREG-D-Regul tory Restriction 4-Continuation 0161)
E-Operator Training & License Examination 5-Load Reduction 5
F-Administrative 9-0ther Exhibit 1 - Same Source GOoerational Error (Explain)
N/77) 110ther (Explain) l
)
o UNIT SHUTDOhNS AND POWER REDUCTIONS l
INSTRUCTIONS 1
This report should describe all plant shutdowns during the in ac->rdance with the tule 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 significar,t 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 />)
Portable occurrence pertaining to the outage or power should b'e ncted, 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 the l
the duration shoua 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 (NUREG0161). 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 occurrerme was involved.) If the outage or power rehetion will not result in a : portable occurrence.
NUMBER. This column should indicate the sequential num-the positive indication of this lack of correlation should be ber assigned to each shutdown orsignificant reductionin 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 period and ends m another.
gg g
g 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-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 shdu!d 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 signific;nt power reduction from Exhibit 1 InstractMns for Preparation of Data Entry beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG.01611.
te made for Lith report periods to be sure all shutdowns using the following critieria:
or significant power reductions are reported.
TYPE. Use "F" or "S" to mdicate 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-8.. wrong valve operated through error: list valve as initiated by no later than the weekend following discovery component.
of a.. off normal condition. It is secognized that some judg.
ment is required in categorizing shutdowns in this way. In C.
If a chain of felures occurs, the first component to mal-general, a forced shutdown is one that would not have been function should be listed. T;te 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.
under the Cause and Currective Action to Prevent Re,. r-rence column.
DURATION. Self-explanatory. When a shutdown extends Components that do not fit any existing code should be de-beyond the end of a report period, count only the time to the s gnated 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 Io the nearest tenth of an hour to facilitate summation.
CAUSE & ")RRECTIVE ACTION TO PREVENT RECUR-The sum of the total outage hours plas the hours the genera-RENCE. Use the column in a narrative fashion to amplifs on tor was on ?ine should equal the gross hours m the reportmg explain the circumstances of the shutdown tr power reduction pniod.
The column should include the specific cause for each shut-down or significant port reduction and the~immediate and REASON. Categorite by letter designation in accordance contemplated long term corrective action taken. if appropH-with the tile appearmg on the report form. If category 11 ate. This c9umn should also be used for a description of the must be used, supply brief comments.
major safety-related corrective maintenance perforrm d during METHOD OF SHUTTING D0WN THE REACTOR OR the outage or power reduction including an identification of REDUCING POWER. Categorite by number designation the critical path activity and a report of any single reiease of radioac'avity or single radution exposure specifically associ.
INot( that this ditfers 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.
doled 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 too sm.ill a change to warrant explanation.
narrative.
REFUELING INFORMATION l.
Name of facility.
ARKANSAS NUCLEAR ONE - Unit 2 2.
Scheduled date for next refueling shutdown.
October 1,1983 3.
Scheduled date for restart following refueling.
January 1,1984 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 ascociated with the core reload (Ref. 10 CFR Section 50.59)?
To be determined.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
N/A 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.
N/A 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b)_,
112 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 503 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
DATE:
1989
Form 301 F 1 Revised 2-15-79 I
Regulatory Report Review k}kA NsA S A]UClent Om Unit:
2 Plant:
hoA)fA L)/
O ACMafrks a
$C902l Report Title; Report Number:
/d i/p.u bsn.,, /f/h Report Type:
Routine:
@ Non-Routine: ()
Special:
() Reportable Occurrence:
14 day ( ) 30 day ( )
3 Prepared By:
hr* [4/0. R. / 0 0 2. o Date:
/2/6 /82.
Reviewed By:
/fEF
- AAsc. FZ.
- oo 2.o Date:
/ 2./t. / I2.
General Manager or Cognizant Manager / Supervisor (Signature, reference or NA)
~
M Date:
/M//[/A Reviewed By:
Cognizan W icensing Reviewer Reviewed and Approved By:
/
/
Date:
/
if @2 Mpager, Licensing'
/
/
Review Required:
PSC YES () NO (V)
SRC YES () NO (7)
. Reviewed By:
- 4 Date:
Plant Safety Committee (Signature or reference)
Reviewed By:
A/4 Date:
Safety Review Committee 1
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