ML20066E547
| ML20066E547 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/15/1981 |
| From: | Gertsch J ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20066E544 | List: |
| References | |
| NUDOCS 8211150286 | |
| Download: ML20066E547 (6) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL,
+
DOCKET NO.
50-313 I
UNIT DATE 7/15/81 C041PLETED BY J. Gertsch (501) 968-2519 TELEPHONE siONm June DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)
(Mwe-Net )
I 823 17 789 2
823 ig 794 3
88 39 788 4
767 20 787 l
s 820 21 783 6
821 22 782 822 23 782 8
820 24 782 782 9
815 25 Io 810 26 782 11 805 27 782 i
I2 803 28 785 13 801 765 29 14 801 784 30 15 792 3:
N/A l
16 79/
l
(
\\
INSTRUCTIONS On this format.hst the arcrage dail) unit power leselin MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77 )
8211150286 810715
~
PDR ADOCK 05000313 R
OPERATING DATA REPORT 50-313 DOCKET NO.
DATE 07/15/81 COMPLETED BY C. N. Shively TELEPilONE (501) 968-2519 OPERATING STA IUS N"
Arkansas Nuclear One - Unit _1
- 1. Unit Name:
June 1 - 30, 1981
- 2. Reporting Period:
2568
- 3. Licensed Thermal Powcr (MWt):
902.74
- 4. Nameplate Rating (Gross MWe):
850
- 5. Design Electrical Rating (Net MWe):
883
- 6. Masimum Dependable Capacity (Gross MWe):
836
- 7. Masimum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report.Gise Reasons:
- 9. Power Lesel To Which Restricted. lf Any (Net MWe):
N/A
- 10. Reasons For Restrictions. If Any:
This Month Yr..to Date Cumularise 720.0_
4343.0_
57258.0 II. Ilours in Reporting Period 705.8 2568.2 38358.5
- 12. Number Of liour, Reacior was Critical
- 13. Reactor Rewne Shutdown flours
~~_/d/f.0 173c. 4 f6 MOM 0999 0.0 703.2 2489.2 37534.2
- 14. Ifours Generator On Line
- 0. 0_
/) 0-1002.3 n/7 5 122'0.'
- 15. Unit Resene Shutdown liours 1750355.0 6084953.0_
90256919.0
- 16. Gross Thermal Energy Generated IMWill 582576.0 2034106.0 29732667.0
- 17. Gross Electrical Energy Generated iMWill 556798.0_
1942958.0 28358597.0
- 18. Net Electrical Energy Generated (MWill 97.7 57.3 65.6
- 19. Unit Senice Factor 97.7 57.3 67.0
- 20. Unit Asailability Factor 92.5 53.5 59.2
- 21. Unit capacity Factor (Using MDC Net) 91.0 52.6 58.3
- 22. Unit Capacity Factor (Using DER Net) 2.3 2.1 16.4
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each):
3
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior io Commercial Operation):
Forecast Achiesed INITI A L CRITICA LITY INITI A L ELECTRICITY COM%f ERCI AL OPER ATION 08/771
DATE:
July. 1981 REFUELING INFORMATION 1.
Name of facility.
Arkansas Nuclear One - Unit I 2.
Scheduled date for next refueling shutdown.
1/1/83 3.
Scheduled date for restart following refueling.
3/15/83 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 Specification
(
changes.
Also, the safety analysis of eight demonstration high burn-up assemblies will be provided.
i 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
10/1/82 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.
Will reload 72 fresh fuel assemblies and operate for approximately
_J6 months.
Eight of which will be high burn-up test assemblies.
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.
present 589 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:
1986
UNIT SHUTDO5NS 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.
LICENSEE EVENT REPORT 2r.
Reference the applicable ficant reduction in power level (greater than 20% reduction 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 reduction. Enter the first four parts (event year, sequential should b'e noted, even though the unit may not have been shut down completely. For such reductions in power level,
'ePort number, occurrence code and report type) of the the 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 Report Action t? Prevent Recurrence colurm 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 since should be used to provide any needed explanation to fully further investigation may he required to ascertain whether or describe the circumstances of the outage or power reduction.
n I 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 noted as not applicable (N/A).
ber assigned to each shutdown or significant reductionin power 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, reduction originated should be noted by the two digit code of an entry should be made for both report periods to be sure Exhibit G - Instructions for Preparation of Data Entry Sheets all shutdowns or significant power reductions are reported.
f r Licensee Event Report (LER) File (NUREG.0161).
Until a unit has achieved its first power generation, no num-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 riot 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 1 - Instructions for Preparation of Data Entry beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG-Olbi1.
be made for both report periods to be sure all shutdowns using the following critieria:
or significant power reductions are reported.
A. If a component failed.use the component directlyinvolved.
TYPE. Use "F" or "S" to indicate either " Forced" or " Sche.
~
duled." respectively, for each shutdown or significant powe' 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 chain 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.
i completed in the absence of the condition for which corrective ing the other components which fail. should he described l
action was taken, under the Cause and Corrective Action to Prevent Recur.
rence column.
l DURATION. Self-explanatory. When a shutdown extends Components that do not fit any existing code should be de-l beyond the end of a report period. count only the time to the signated XXXXXX. The code ZZZZZZ should be used fm end of the report period and pick up the ensuing down time events where a component. designation is not applicable.
m 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.
RENCE. Use the column in a narrative fashion to amplif os 3
for was on line should equal the gross hours in the reportmg explain the circumstances of the shutdown or peer reduction l
pnod.
The column should include the specific cause for each shm-down or significant power reduction und the~immediate and l
REASON. Categorize by letter designation in accordance contemplated long term corrective action taken, if appropo.
with the table appeanng,on the report form. If category 11 ate. This column should also be used for a description of the must be used. supply brief comments.
major safety-related corrective maintenance performed during the outatie or power reduction including an identification of METilOD OF SilUTTING DOWN Tile REACTOR OR the critica! path activity and a report of any single release of REDUCING POWER.
Categorite by number designation radioactivity or single radiation expostae specifically associ-INote that this differs trom the Edison Electric Institute sted with the outage which accounts for more than 10 percent
~
i of the allowable annual values.
(EEI) definitions of " Forced Partial Outage" and " Sche.
daled Partial Outage." For these terms. EEI 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 reducimn for this is too small a change to warrant explanation.
narrative.
50-313 DOCKET NO.
UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME ANO - Unit I DATE
.Tulv 7_
los1 COMPLETED BY Y
Nmh REPORT MONTH June TELEPHONE (5011 96R M19 j?
3
)Y Licensee
,E-t, "t
Cause & Corrective No.
Date i
58 I;
.I @ $
Event gg g3 Action to H
f~
jgg Report a mo O
Preveni Recurrence g
6
{
81-06 810603 F
16.8 A
3 N/A HA Instru Main turbine low oil pressure trip mechanism malfunction - defective diaphragm. Replaced diaphragm and added component to preventive main-tenance schedule.
I 2
3 4
F: Forced Reason:
Method:
Exlubit 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 G-Operational Eirur (Explain)
Exhibit I - Same Source 19/77)
Il Other (Explain) 1
s NRC MONTHLY OPERAT'ING REPORT OPERATING
SUMMARY
- JUNE 1981 UNIT I Unit One began the month at 100% full power and continued there until June 3, 1981. On this date, the reactor tripped on the anticipatory trip circuitry for loss of main turbine bearing oil pressure. A malfunction of the low oil pressure trip mechanism initiated the trip.'
Unit One resumed 100% full power operations June 4, 1981, and continued there until June 10, 1981.
Continued fouling of the "A" OTSG required a unit power reduction to reduce the water 1cvel in the downcomer region of the "A" OTSG.
On June 10, 1981, Unit one began a gradual power reduction, with power limited by the downcomer water level of the "A" OTSG. The "A" OTSG downcomer water level stabilized June 18, 1981, with the reactor at 96.7% full power.
Unit One continued to operate at 96.7% full power through the end of the month.
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