ML19282B997

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Feb 1979
ML19282B997
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 03/08/1979
From: Shively C
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19282B994 List:
References
NUDOCS 7903190238
Download: ML19282B997 (5)


Text

AVER AGE D AILY UNIT POWER LEVEL DOCKET NO. 50-313 h UNIT Unit I DATE 03-OR 70 COMPLETED BY C_N. Shively TELEPHONE 501/968-2519 MONTil February DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) t MWe Neti 1 0 i7 812 2 0 18 810 3 0 19 809 4 0 809 20 5 39 21 811 6 347 22 809 7 604 809 23 g 781 808 24 9 810 25 806 10 807 26 808

, 807 808 27 12 810 28 Rn7 13 809 29 NA 14 810 NA 30 15 783 33 y, ,

16 771 INSTRUCTIONS On this format.hst the average daily unit power leselin MWe-Net for each day in the reporting inonth. Compute to the nearest whole rnegawati.

(9/77) 7903?,905:t58

OPERATLNG DATA REPORT DOCKET NO. 50-313 DATE 03-08-79 COMPLETED BY C.N. Shively TELEPHONE. 501 /o 6R-7519 OPERATING STATUS

1. Unit Name: Arkansas Nuclear One - Unit I Notes
2. Reporting Period: February 1-28 1979
3. Licensed Thermal Power (MWt): 2568
4. Nameplate Rating (Gross MWe): 902.74
5. Design Electrical Rating (Net MWe): 850
6. Maximum Dependable Capacity (Gross MWe): 883
7. Maximum Dependable Capacity (Net MWe): 916
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Gise Reasons:

NONE

9. Power Level To Which Restricted.lf Any (Net MWe): _NONE
10. Reasons For Restrictions.lf Any: NA This Month Yr.-to-Date Cumulative i1. Hours In Reporting Period 679 0 1416.0 36787.0
12. Number Of Hours Reactor Was Critical 579.8 579.8 26289.9
13. Reactor Resene Shutdown Hours 92.2 614.4 2604.3
14. Hours Generator On.Line 555.9 559.9 25769.6
15. Unit Reserve Shutdown Hours n0 0.0 205.2
16. Gross Thermal Energy Generated (MWH) 1366623.0 1366623.0 62173332.0 17 Gross Electrical Energy Generated (MWH) 449720_.9___ , 449720.0 20690401.0
18. Net Electrical Energy Generated (MWH) 429230.0 429230.0 19739776.0
19. Unit Senice Factor 82.7 39.3 70.1
20. Unit Availability Factor 82.7 39.3 70.6
21. Unit Capacity Factor (Using MDC Net) 76 4 16 1 64.2
22. Unit Capacity Factor (Using DER Net) 75.1 35.7 63.1
23. Unit Forced Outage Rate 17.3 60.7 13.3
24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each):

o hnai,1cd R o friol i no . 3/30/79. 8 weeks

25. If Shut Down At End Of Report Period. Estimated Date of Startup: NA
26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIA L CRITICA LITY INITIA L ELECTRICITY COMMERCIA L OPER ATION (9/77)

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-313 UNIT NASIE ANO-I DATE 7/7/74 COMPLETED BY .C . . Shively REPORT SIONTil February TELEPIIONE 501-968-2519

=- o 3 -s : 8

,s( gy 7., .2 e E Licensec =^ ., Cause & Cor rectise No. Date 3 ~g 4 ,3 g 5 Event a3 $? Ateinn in d5 N jdj Report : NC 5L Prevent Recurrence 6

78-9 781231 F 116.1 A 1 N/A HA Turbin Main Low Pressure Turbine Failure (Continued from December, 1978)

I 2 3 4 F: Forced Reason : hiethod: Estnbit G - Instructions S. Scheduled A. Equipment Failure (Explain: I Manual for Preparation of Data D-Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C Rel'ucling 3 Automatie Scram. Event Report (LI:R) File int.'RI G-D Regulatory Restriction 4-Ot her ( E xplain ) 0101i E-Operator Trainmg1 License I:xannnation F-Admnustrati e 5 --

G-Operational Error (Expl.n.0 Estatui 1 Sanie Soma (9/77) li Other ( E xplaini

REFUELING INFORMATION

1. Name of facility. Arkansas Nuclear One-Unit I
2. Scheduled date for next refueling shutdown. 03-30-79
3. Scheduled date for restart following refueling. 05-30-79
4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

If answer is yei, 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)?

vne, enn Tneen- en vnsa a,ena 11 o 7R

5. Scheduled date(s) for submitting proposed licensing action and supporting information. 11 o-78 (Aren,1)
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 voin,a 64 frnch fun 1 ,cen-kline ,m1 nnarnen for ,nnrnv4-,*nty 16 months.

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage poel, 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 590 increase size by 0

9. The projected date of the last refueling tha: can be discharged to the apent fuel pool assuming the present licensed capacity.

DATE: v,rch 1988 8

ll-NRC MONTHLY OPERATING REPORT Operating Summary - February,1979 UNIT I The Unit was placed on line following repair of the Low Pressure Turbine.

It was necessary to rebalance the turbine during startup. The Unit opera-tion proceeded to 100% reactor power and operated without any significant occurrences until 2/9 when the temperature rise across the condenser ex-ceeded the Appendix B Technical Specification limit of 15 DEGF. The high temperature rise was due to a restriction of circulating water flow caused by a collection of trash and fish on the inlet tube sheets. The circulat-ing water inlet valves are being cycled, as necessary, to allow debris to wash off; thus improving the flow rate. (Reference Non-Routine Report No.

50-313/79-1.) On 2/15, the power level was reduced for a short period of time to allow maintenance on the P8 A and B heater drain pumps. The Unit operated throughout the remainder of the month without incident.