ML19225A551

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Monthly Operating Rept for June 1979
ML19225A551
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 07/11/1979
From: Shively C
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19225A546 List:
References
MOR-790630-1, NUDOCS 7907190544
Download: ML19225A551 (5)


Text

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AVER AGE D-slLY UNIT POWER LEVEL

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DOCKETSO. 50-368 UNIT 2 D ATE July 117 1979 COMPLETED BY C. N. Shively TELEPHONE 501/968-2519_

MONT11 June DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (M b e-Net I (Mwe Neti 1 0 i; O 2 0 is 0 3 0 19 0 4 0 20 6 5

l 1 6 0  ;; 126 7 0 80 23 s 1 166 34 9 0 347 25 10 7 26 175 11 73 27 357 12 44 366
s 13 10 29 371 I4 0 379 30 15 0 NA 3i 16 0 INSTRUCT!ONS On this f ormat, hst the neuge da:h una p.... er lesel in MWe Nel for cah day ni the rep.etin in., nth. Compoie to the nearest whole megawvi pil771 790719OW4 413 EE1 030

OPERATLNG DATA REPORT DOCKET NO 50-368 DATE Julv 11, 1979 CO\fPLETED BY C. N. Shively TELEPHONE Eil7M8 2519 OPERATING STATUS

1. Unit Name: A nan w Nuclear One - Unit 2 N tes
2. Reportmg Period. Teo 1-an 107o
3. Licenwd Thermal Power (Mht t '815
4. Nameplate Rating (Gross 5the) 959
5. Design Electrical Rating (Net MWe): 912
6. Maximum Dependable Capacity (Gross MWe): NA
7. Masimum Dependable Capacity (Net Mbe). NA
5. If Changes Occur in Capacity Ratmgs (items Number 3 Through 7 ) Smce Last Report. Gise Reasons.

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9. Power Lese! To Which Restricted. If Any (Net MWe) None
10. Reasons For Restrictions. lf Any: NA This Month Yr -to Date Cumulatise
11. Hours in Reportmg Penod 720.0 4343.0 5087.0
12. Number Of flours Reactor has Critical 336.7 1017.6 1452.5 13 Reactor Resene Shutdown Hours 205.3 1910.6 2052.6
14. Hours Generator On Line 235.4 838.5 691.3
15. Unit Resene Shutdown Hours 20.6 21.7 21.7 16 (,rnu Thernut Energy Generated (MWH) 260277.0 582113.0 626691.0 17 Gross Electrical Energy Generated (MWH) 67816 0 . 137973.0 143540.0 lb. Net Electrical Energy Generated (MWH) 601 % 0 119515.0 116490.0
19. Unit Senice Factor
20. Unit Availabilitv Factor
21. Unit Capacity Factor (Using MDC Net)  ; NA Until Cermercial Operation
22. Unit Capacity Factor (Using DER Net)
23. Unit Forced Outage Rat- ,
24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date, and Duration of Each):
25. If Shut Down At End Of Repor! Period. Estimated Date of Startup-
26. Umts in Test Status (Prmr to Commercial Operation): Forecast A chies ed INITI A L CRITICA LITy _ 12-5-78 INITI AL ELECTRICITY -

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DATE: June 1979 REFUELING INFORMATION -

1. Name of facility. Arkansas Nuclear One - Unit 2
2. Scheduled date for next refueling shutdown. 09-01-80
3. Scheduled date for restart following refueling. 12-01-80
4. Will refueling or resumption of operation thereafter require a technical specification change oc othcr 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. Descriptien of effects of new core loading

5. Scheduled data (s) for submitting proposed licensing action and supptrting information. 08/01/80
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.

NONE

7. The number of fuel asse=blies (a) in the core and (b; in the spent fuel storage pool. a) 177 b) 0
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 to the spent fuel pool assuming the present licensed capacity.

DATE: 1988 413 csgs; 033

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- JUNE, 1979 UNIT II The repair of the "A" Reactor Coolant Pump seal contir ued from the -

previous month. After repairs were completed, the Ma n Steam Relief Valve setpoint and blowdown testing continued. All valves performed satisfactorily.

The reactor was declared critical on 6/6 and the unit was placed on line on 6/8; however, was shutdown five hours later due to a steam leak on one of the main steam lines. The unit was placed back on line on 6/10. During the transfer of auxiliary power supply to the auxiliary transformer, the condenser pumps tripped due to the feeder breaker for electrical bus A-2 being locked out. The main feedwater pump tripped on low suction pressure and the reactor was tripped manually. The unit was returned to tervice on 6/13, but tripped five hours later when a phase to phase and a phase to ground fault was received on the secondary sides of the unit auxiliary, startup #2 and startup #3 transformers. Faults were caused by water entering the electrical buses through the feeder breakers from a cleaning job in the adjacent work area. Repairs were made and the un_t was placed back on line on 6/20- Power Escalation Testing was resumed.

As the unit wa; being escalated from 40% reactor power, the turbine tripped on unit differential voltage. Investigation revealed the A & C phase relay wires were crossed. The unit was returned to power operation, Mode 1, on 6/24 Two days later, a trip was received when test pcrsonnel inadvertantly switched the ground and positive leads of a test recorder, causing the Feedwater Control System to malfunction. The unit was returned to Mode 1 operation the same day.

The 50% power plateau power escalation testing continued throughout the remainder of the month.

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