ML20027E645

Monthly Operating Rept for Mar 1981

ML20027E645
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/13/1981
From:	Pendergraft R ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20027E639	List: ML20027E638 ML20027E645
References
NUDOCS 8211150566
Download: ML20027E645 (5)

Text

{{#Wiki_filter:. AVERAGE DAILY UNIT POWER LEVEL 50-368 DOCKET NO. 2 UNIT DATE 4/13/81 ~ C041PLETED By Rex Pendergraf t TELEPHONE (501) 968-2519 MONUf March, 1981 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (M We. Net) (Mwe. Net) 1 887 17 0 2 677 18 232 $9 788 3 669 881 4 795 20 5 884 21 882 22 883 6 886 7 886 23 882 8 886 24 881 9 886 25 881 10 99 26 880 11 494 27 830 12 876 2g 24 13 881 29 0 14 882 30 0 O 15 882 3; is 820 INSTRUCTIONS On this format.hst the aserage daily unit power leselin MWe Net for each dayin the reporting month. Compute to the nearest whole megawait. (9/771 I'8211150566'810413 ! PDR ADOCK 05000368 ! R PDR

OPER ATING DATA REPORT DOCKET NO. 50-368 __ DATE 4/13/81 CO\\lPLETED BY Rex Pendergraft TELEPHONE (bul) 960-2519 OPERAllNG STAl US Nate$ Arkansas Nuclear One - Unit _2

1. Unit Name:

March 1-31, 1981

2. Reporting Period:

2815

3. Licensed Thermal Power (MWt):

942.57

4. Nameplate Rating (Gross MWel:

912

5. Design Electrical Rating (Net MWel 897

6. Masimum Dependable Capacity (Gross MWe):

858

7. Masimum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report.Gise Reasons:

NONE NONE

9. Power Letel To Which Restricted.If Anv (Net MWe):

NONE

10. Reasons For Restrictions,if Any:

This Month Yr.-to Date Cumulatise 744.0 2.160.0 8.904.0 i1. Ilours in Reporting Period 595.6-- 1.968.0-6.998.8

12. Number Of liour, Reactor Was Critical 54.9 54.9 859.5

13. Reactor Resene Shutdown flours 587.3 1,952.2 6,868.2

14. Ilours Generator On Line 0.0 0.0 -

75.0

15. Unit Rewne Shutdown flours 1,562,249.0 5,094,885.0 16,939,047.0

16. Gness Thermal Energy Generated (MWiin 511,350.0 1,673,589.0 5,506,490.0

17. Gross Electrical Energy Generated (MWif) 488,514.0_

1,599,905.0 5,247,102.0

18. Net Electrical Energy Generated (MWHI 78.9 90.4 77.1

19. Unit Service Factor 78.9_

90.4 78.0

20. Unit Asailability Factor 76.5 86.3 68.7

21. Unit Capacity Factor (Using MDC Net) 72.0 81 J._.

64J

22. Unit Capacity Factor (Using DER Net) 9.7 5.5 22.0 j

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date.and Duration of Each1:

j l l-

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status iPrior to Commercial Operation):

Fmecast Achiesed INITI A L CRITICALITY INITI A L ELECTRICITY COMMERCI A L OPER ATION l l P8/771 l l

r REFUELING INFORMATION 1 1. Name of facility. Arkansas Nuclear One - Unit 2 2. Scheduled date for next refueling shutdown. 3/28/81 (Shutdown) { 3. Scheduled date for restart following refueling. 6/07/81 l 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 4 core reload (Ref. 10 CFR Section 50.59)? Yes. Description of effects of-new core loading. 1 a 5. Scheduled date(s) for submitting proposed licensing action and supporting information. Has been submitted for Cycle 2. 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. i i As a part of a research and development effort, two fuel assemblies i will be loaded possessino desian characteristics related to extended burnup. 7. The number of fuel assemblies (a) in the core and (b) in the spent l fuel storage pool. a) 177 b) 60 l l 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 486 increase size by 0 9. The projected date of the last refueling that can be discharged l to the spent fuel pool assuming the present licensed capacity. DATE: 1989 i

. j. DOCKET NO. 50-368 UNITSilUTDOWNS AND POWER REDUCTIONS UNIT N A%1E ANO-Unie TT DATE. 4/13/81 C04tPLETED BY Rav A-N'daroraft REPORT A!ONTil March TELEPilONE snt /oAn_7519 Ext. 3115 {? 3 Licensee j-r., t, cause & Correctne N... Daie WE -{ EE5 Event s? e? Action to 2 Report : rN G Present Recurrence 5 3d:! I' u 6 l I 81-03 3-10-81 F 25.8 A 3 None HA GENERA Pilot exciter brushes failed causing a generator low voltage trip. Brushes were replaced. 81-04 3-16-81 F 26.5 lA 3 None CH INSTRU F. W. control system hi level select module failed causing a low S/G level trip. Module was replaced. I 81-05 3-18-81 F 10.7 $G 3 None IA INSTRU Rx tripped while performing testing on the Core Protection Calculators due to human error. Personnel vera ~~ instructed in the proper tt' sting methods. 81-06 3-28-81 S 93.7 C 1 N/A NA NA Refueling shutdown. 1 I I 2 3 4 IL forced Reason: Method: Estubit G-Instructiims S. Scheduled A l;piipment Failure (Explain) 141anual for Prep uarion of Data Isolaintenance of Test 241anual Scram-Entr> Sheets for i :eensee C Refueling 3-Autonutie Scram. lisent Report (Li'R1 Fde iNUREG-D.Regularory Restriction 4-Ot her ( E splain) 01611 li Opesaror Training & License I.xainination F-Adnunist ratr.c 5 G-Operational tiror iEspla:.0 Eshibit I 5.nne Source l'I '7 7 ) ll 0:hcr i E splaint 1 5

+ MONTHLY OPERATION REPORT OPERATING

SUMMARY

- MARCH 1981 UNIT Il The Unit was operating at full power during the start of this reporting period.

Condenser tube leaks forced a power reduction on 3-2-81. Full power operation was achieved on 3-4-81 following temporary repairs to the Main Condenser. The Unit tripped on 3-10-81 due to problems with the pilot Exciter on the Main Generator. The Unit tripped due to low generator voltage. Full power operation was again achieved on 3-11-81. A reactor trip was experienced on 3-16-81 due to failed feedwater control instrumentation (Steam Generator High Level Select Module in the feedwater control system). The instrument problems were corrected and power escala-tion was initiated on 3-18-81. Prior to reaching full power operation a reactor trip occurred from approximately 91% full power. The cause of the trip was found to be due to human error. Instrumentation technicians were performing surveillance testing on the core protection calculstors at the time the trip occurred. The Unit was returned to full power operation on 3-19-81 and remained at power,until 3-28-81 when a scheduled refueling outage occurred. The Unit was brought to a cold shutdown condition for the remainder of this reporting period. e i l ,}}