2CAN108308, Monthly Operating Rept for Sept 1983
| ML20081M402 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/30/1983 |
| From: | Bramlett L, John Marshall ARKANSAS POWER & LIGHT CO. |
| To: | Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 2CAN108308, NUDOCS 8311170246 | |
| Download: ML20081M402 (8) | |
Text
E OPERATING DATA REPORT DOCKET NO.
50-368 DATE 10/15/83 COMPLETED BY L.S.Bramlett TELEPHONE (501) 964-3145 OPERATING STATUS N '""
- 1. Unit Name:
Arkansas Nuclear One - Unit 2
- 2. Reporting Period:
SeDtember 1-30.-1983 2815
- 3. Licensed Thermal Power IMWt):
942.57
- 4. Nameplate Rating (Gross MWe):
2
- 5. Design Electrical Rating (Net MWel:
897
- 6. Maximum Dependable Capacity (Grow MWe):
-858
- 7. Maximum Dependable Capacity (Net Mhe):
~
- 8. If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Last Report. Gise Reasons:
None 9 Power Lesel To Which Restricted. lf Any (Net MWe):
.10. Reasons For Restrictions.lf Any:
This Month Yr to.Date Cumulatise 720.0 6,551.0 30,815.0 i1. Hours in Reporting Period 614.0 5,470.9 21,627.1
- 12. Number Of Hours Reactor Was Critical
- 13. Reactor Reserve Shutdown Hours 0.0 91.6 1,430.1 605.8 5,381.6 20,950.3
- 14. Hours Generator On.Line 0.0 0.0 75.0
- 15. Unit Resene Shutdown Hours
- 16. Gross Thermal Energy Generated iMWH) 1.664.479.0 14.298.479.0 52.549.540.0
- 17. Gross Electrical Energy Generated iMWH) 538.570.0 4.641,647.0 17,016,951.0
- 18. Net Electrical Energy Generated (MWH) 513,937.0 4,427,954.0 16,206,340.0 84.1 82.1 68.0
- 19. Unit Senice Factor 84.1 82.1 68.2
- 20. Unit Asailability Factor 83.2 78.8 bl.J
- 21. Unit Capacity Factor (Using MDC Neti 78.3 74.1 57.7
- 22. Unit Capacity Factor (Using DER Nett 15.9 17.9 20.1
- 23. Unit Forced Outage Rate
- 24. Shutdowns Schedukd Oser Nest 6 Months (Type. Date,and Duration of Eacht:
Nowin scheduled refuelin9 and maintenance outa9e October,1983-January,1984
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
January, 1984
- 26. Units in Test Status t Prior to Commercial Operationi:
Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCI AL OPER ATION 8311170246 830930 4
PDR ADOCK 05000368
- gof77, R
PDR*
l l
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO, 50-368 2
~
UNIT DATE 10/15/83 COMPLETED BY L.S.Bramlett TELEPHONE (501) 964-3145 September, 1983 MONT11 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe Neti IMWe Net) 1 88 868 i7 2
725 867 18 861 3
19 870 866 4
20 874 864 21 881 3
862 881 6
865 7
23 879 8
866 879 24 866 877 9
25 10 864 26 589 11 864 0
27 12 867 0
28 872 0
13 39 874 0
34 30 15 874 31 16 871 INS 1 RUCTIONS th n are i 1[>l
' Id'Cl in MWe Net for each day in the reportinF inuntli. Compute io
"" ' P" asv 08/77)
L
NRC MONTHLY OPERATING REPORT OPERATING SUP94ARY SEPTEMBER, 1983 UNIT 2 The Unit began the month offline in a continuation of last p:enth's outage.
The outage was performed to replace a reactor coolant pump seal and to conduct other maintenance.
On September 2, the Unit was returned to 100%
full power and operated there until September 26.
On this date, the. Unit was shutdown because of battery cells which failed to meet Technical Specification limits.
The Unit continued in Mode 5 for the remainder of the month.
i 50-368 DOCKET NO.
UNIT SHUTDOWNS AND POWER REDUCTIONS
. UNIT NAME ANU-2 DATE Oct. 2. 1983 COMPLETED BY L.5. Bramlett REPORT MONTH September TELEPHONE (501) 964-3145
~~
=
Licensee
,En, h,
.!?
3 hYk Cause & Corrective No.
Date g
sj j
.g g &
Event g?
c-?
Action to fG Prevent Recurrence
$~
j di, g Report a mO H
6 83-08 830824 F
10.7 G
4 N/A ZZ ZZZZZZ While performing a diesel generator surveillance test, the reactor tripped during an electrical transient caused by an inadvertent breaker closure. Also, maintenance was perfonned on a Reactor Coolant Pump seal.
83-09 830926 F
103.5 A
1 50-368-83-44 EC Battery Battery cells failed to meet surveillance test requirements.
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{ontinuation 0161)
E-Operator Training & Ucense Examination 5-Load Reduction 5
F Administrative 9-Other G-Operational Error (Explain)
Exhibit ! Same Source (9/77)
Il-Other (Explain)
~
I UNIT SHUTDO5NS AND POWE2 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 bnef commenis.
ation of significant dips in average power levels. Each signi-LICENSEE EVENT REPORT *. Reference the appheabic 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 />) reportable occurrence pertaining to the outage or pow should lie noted, even though the unit may not have been reduction. Enter the first four parts (event year, sequential shut down completely c For such reductions in power level, f* Port number, occurrence code and report type) of the (ne 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 Da:a Entry Sheets for Licensee Esent Repori Action to Prevent Recurrence column should explain. The (LER) File (NUREG-0161). This information may not be Cause and Corrective Action to Prevent T.ecurrence 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. This 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 m which the outage or power reduction begins in one report period and ends m another*
reduction originated sh' uld be noted by the tw'o digit code of o
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-red 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 1 - Instractions for Preparation of Data i ntry beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG-OlolI.
be made for both report periods to be sure all shutdowns using the following critieria:
or signifie3nt power reductions are reported.
TYPE. Use "F" or "S" to indicate either " Forced" or " Sche.
duled," respectively, for each shutdown or significant power 3.
If not a component failure, use the related component.
reduction. Forced shutdowns include those reqmred to be e.g.
wrong valve operated through error: list valve as initiated by no later than the weekend following discovery component.
of an eff. 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.melud.
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 Corrective Action to Prevent Recur.
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.
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 amphis or tor was on line should equal the gross hours in the reportmg expla n the circumstances of the shutdown or power reduc 5on period.
The column should include the specific eause for each shui down or significant power reduction and theimmediate and REASON. Categorize by letter designation in 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 description of the must be used, supply brief comments.
major safety-related corrective maintenance performed durmg METHOD OF SHUTTING DOWN THE REAClOR 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 release of radioactivity or single radiation exposure specifically associ-INote that this differs from the Edison Electric Institute ated with the outage which accounts for more than 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 too small a change to warrant explanation.
narrative.
REFUELING INFORMATION 1.
Name of facility.
Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown.
October,1983 i
3.
Scheduled.date for restart following refueling.
January,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 associated with the core reload (Ref.10 CFR Section 50.59)?
No; review in progress 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
October, 1983 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 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, 988 present 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 ----
O ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTL E ROCA. ARKANSAS 72203 (501) 371-4000 October 15, 1983 2CAN198308 Mr. Harold S. Bassett, Director 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 September 1983 for Arkansas Nuclear One - Unit 2.
Very truly yours, John R. Marshall Manager, Licensing JRM:SAB:rd Attachment cc:
Mr. John T. Collins 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 Q
Washington, DC 20555 7
h i k 1
MEMBER MlOOLE SOUTH UTILITIES SYSTEM