ML19225A473

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Monthly Operating Rept for June 1979
ML19225A473
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 07/11/1979
From: Shively C
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19225A470 List:
References
MOR-790630, NUDOCS 7907190388
Download: ML19225A473 (4)


Text

{{#Wiki_filter:AVER AGE DAILY UNIT POhER LEVEL . DOCKET NO. 50-313 UNIT I DATE July 11.-1979 COMPLETED BY C. N. Shively TELEPHONE {501) 968-2519 MONTH __ dune DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (M We-Net I ( MWe-Net ) 1 0 i, 0 2 n is 0 3 0 39 0 4 0 20 0 5 0 0 2i 6 0 0 22 7 0 0 23 8 0 47 24 9 n 25 252 10 n 261 26 11 n 267 27 12 n 426

s 13 n 594 29 14 0 703 30 15 0 NA 3

16 INSTRUCTIONS On thn f ormat. list the ase: age da:! 3 urut pow er loel in MWe-Net for each day m the reporting inoath. Lompuie to the nearest whole me;awatt. (0 /77 ) 7 907190sgg 420 131

OPERATLNG DATA REPORT DOCKET NO. 50-313 DATE ihil y 11, 1979 COMPLETED BY r N- Shively TELEPHONE (501 968-257 9 OPERATING STATUS Arkansas Nuclear One - Unit 1 N tes

1. Unit Name:
2. Reporting Period: June l-30,1979
3. Licensed Thermal Power (Mh t i: 2568
4. Nameplate Rating (Gross MWer 902.74
5. Design Electrical Rating (Net MWe): 850
6. Maximum Dependable Capacity (Gross MWe): 881
7. Maximum Dependable Capacity (Net Mbe): 836 6 If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Gise Reasons:

NONE

9. Power Lese! To Which Restricted. If,A,ny (Net MV s,. NONE
10. Reasons For Restrictions. If Any:
  • This Month Yr.-to Date Cumulatise
11. Hours in Reporting Period 720.0 4343.0 39714.0
12. Number Of Hours Reactor was Critical 259.8 1556.2 27266.3 13 Reactor Resene Shutdown Hour, 190.9 1158.6 3148.5
14. Hours Generator On-Line 164.6 1436.7 2t,bbu.4
15. Unit Resene Shutdown Hours 238.2 591.5 796.7
16. Gross Thermal Energy Generated (MWH) 222220.0 3404765.0 64211474.0 17 Gross Electrical Energy Generated (MWH) 67137.0 1116215.0 21356896.0 lb Net Electrical Energy Generated (MWH) 61201.0 1063563.0 20374109.0 Unit Senice Factor 22.9 33.1 67.1 21 Unit Asailability Factor 55.9 46.7 69.I 2 .- Unit Capacity Factor (Using MDC Net) 10.2 29.3 61.4 22 Unit Capacity Factor (Using DER Net) 10.0 28.8 60.4
23. Unit Forced Outage Rate 64.6 51.3 14.7
24. Shutdowns Scheduled Over Next 6 Months (Type Date,and LNration of Each):
25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units in Test Status (Prior to Commercial Operatio.1): Forecast Achiesed INITI A L CRITICALIT)

INITI A L ELECTRICITY _ COMMERCI AL OPER ATION 420 02 (9/77 )

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79-1 790331 S 41.4 C 1 NA NA NA NA 790602 F 291.7 D NA NA NA NA NRC lloid due to procedural questien 790614 S 111.4 C NA NA NA NA 790619 F 8.1 D NA NA NA NA NRC lloid due to EFW question l 790619 S 102.8 E NA NA NA NA Zero Power Physics Testing F d 9 l 2 3 4 F Forced Reason: Meibod: Esinbu G . Instrucuons bic hed uled A.Egi"pment Failnre ( Exolain) 1. Manual for Preparanon ot' Data N u. Maintenance or Test 2 \tanna! Scrain. Entry Sheen ser Licensec O C-Reluchng 3. Auloinatic Scr.nn. Esent Reron (LI R) Fife (NI'RI.G-D Ret;ularory Rcsinstion 1 Ot her (!: splani) O l t. ! ) 1: Operator Tiainine 1 Lhen'.c ! sannn.n on

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. DATE: June,1979 REFUELING INFORMATION .

1. Name of facility. Arkansas Nuclear One - Unit 1
2. Scheduled date for next refueling shutdown. 10-01-1980
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3. Scheduled date for restart following refueling. 12-01-1980
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 snswer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine uhether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)? Yes, Reload Report and associated proposed 'echnical Specification Changes.

5. Scheduled date(s) for submitting proposed licensing action and supporting information. 08-01-1980
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 16 months.

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 176
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 that can be discharged to the spent fuel pool assuming the present licensed capacity.

DATE: Larch . 1988

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4 NRC MONTHLY OPERATING REPORT

'

OPERATING

SUMMARY

- JUNE, 1979 UNIT I The unit was in a heatup condition until 6/2, when the NRC ordered the unit shutdown due to Emergency Feedwater System operating procedure questions. Operations was conducting a surveillance test to prove the operability of the Main Feedwater Check Valves. The Emergency Feedwater pump actuation was defeated to preclude an undesirable auto start. This conditien was not authorized by the controlling procedure, nor was it allowed by the Technical Specifications. Operating procedures were modified accordingly.

Heatup of the unit resumed, following NRC approval, cn 6/14. The plant heatup process continued until 6/19, when the NRC requested a delay until they could inquire about several items that the resident NRC inspector had observed and reported during the heatop evolution. The unit was returned to Hot Shutdown conditions. After a delay of approximately eight hours, the NRC concerns were successfully resolved and the unit startup was resumed. The reactor was declared critical on 6/20 and the Zero Power Physics Testing was begun. Testing was completed and the unit placed on line on 6/24. Physics Testing at the 40% rated reactor power level was completed on 6/28. Testing at the 75% power level continued through-out the month.

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