ML20082S727

Monthly Operating Rept for Aug 1991 for Waterford 3

ML20082S727
Person / Time
Site:	Waterford
Issue date:	08/31/1991
From:	Burski R, Kllona L ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
W3F1-91-0475, W3F1-91-475, NUDOCS 9109170257
Download: ML20082S727 (7)

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R. F. Durski W3 F1 0-175 A4.05 QA September 13, 1991 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Subject:

Waterford 3 SES Docket No. 50-382 License No. NPF-38 Monthly Operating Report Gentlemen:

Attached is the subject monthly report which covers the operating statistics for the month of August,1991. This report is submitted per Section G.9.1.G of the Waterford 3 Technical Specifications for Facility Operating Licensa No. NPF-38.

Very trulp ours, RFB/TJG/ssf

' f tw Attachment ec: R.D. Martin, NitC Region IV D.L. Wigginton, NRC-NRR R.B. McGehee N.S. Reyncids J.T. Wheelock (INPO Records Center)

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i NRC' MONTHLY OPERATING REPORT I i

SUMMARY

OF OPERATIONS WATERFORD~3 >

f August 1991

- The unit operated at an average reactor power of 94.8% -and experienced one (1) forced-' outage during the period.  :

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PRESSURIZER SAFETY VALVE- l

.-FAILURES AND CllALLENGES WATERFORD 3 i

During the month of' August 1991,--there were no pressurizer safety valve j failures or challenges. j L

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UNIT NAME:-WATERFORD 3 CITY / STATE: KILLONA/LA DATE: SEPTEMBER 1991 )

OPERATING STATUS-

1. Docket: 50-382 Notes

2. Reporting Period: AUGUST 1991-

3. Utility

Contact:

PATRICK CENT 0LANZI l Phone Number: (504) 739-6683

= 4. -- Licensed Thermal- Power (MWt): 3390 15.-Nameplate _ Rating (Gross Mwe): 1200

6. Design Electrical Rating (Net MWe): 1104 7;! Maximum Dependable _ Capacity-(Gross MWe): 1120 8.U.1aximum' Dependable Capacity (Net MWe): 1075

.9. . If Changes Occur _ in _ Capacity Ratings (Items Number 4 Through 8) Since Last Report, Give Reasons:

'10. Power Level To Which-Rest'ricted, if Any (Net MWe): NONE ill. EReasons for Restrictions, If Any: N/A This Mouth Yr.-to-Date Cumulative

.-12. _ Hours InJReporting Period'

- 744 5,831 52,032 113. ' Number-Of Hours Reactor Was Critical 716 4,090.1 42,182.8

14. LReactor Reserve Shutdown Hours l 15 Hours' Generator On-Line- 709.8 3,978.2- __41,486.1_ _ _

116.-IUnit-Reserve Shutdown Hours 4 4

~ W310204B

OPERATING DATA REPORT (Continued)

This flor.th Yr.-to-Date Cumulative

17. Gross Thermal Energy _2,389,958 13,206,005 135,834,798 Generated (tMI)

18. Gross Electrical Energy 794,940 ' 4,365,630 45_,6101 300 '

Generated (tMl)

19. Net Electrical Energy 757,514 4,15h721 43,426,238~ ~~

Generated (tMI)

20. Unit Service Factor 95.4 68.2 79.7

21. Unit Availability Factor 95.4 68.2 79.7

22. Unit Capacity Factor 94.7 (5.2 77.6 (Using MDC Net.)

23. Unit Capacity Factor 92.2 - 64.5 75.6 (Using DER Net)

24. Unit Forced Outage Rate 4.6 2.2 4.5 25, Unit Forced Outage llours 34.2 91.0 1,950.5

26. Shut. downs Scheduled Over Next 6 tionths (Type, Date, and Duration of Each):

27. If Shut Down At End of Report Period, Estimated Date Of Startup: _

28. Unit.s In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 3/4/85 INITIAL ELECTRICITY 3/18/85 C0t1'!ERCIAL OPERATION 9/24/85 W310204B 1

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l AVERAGE DAILY UNIT PObT.R LEVEL DOCKET NO. 50-382 __

UNIT WATERFORD 3 DATE SEPTEMBER 1991 COMPLETED BY PATRICK CENT 0 LANZ 1 TELEPHONE 504-739-6683 MONTli AUGUS L 199_1 DAY AVERAGE DAILY POWER LEVEL DAY AW. RAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1076 17 1082 2 1074 18 1083 3 1078 19 1082 4 1076 20 :081 5 1076 21 1079 6 1076 22 . . .

1080 7 1076 23 1079 8 1076 24 1079 9 1076 __

25 60 10 1078 26 232 11 1078 27 1074 12 1078 28 1078 13 1079 29 1078 14 1079 30 1080 15 1080 31 1081 16 1081 INSTRUCTIONS On this format,_ list the avecage daily unit power level in MWe-Net fo, each day in the reporting month, Compute to the nearest whole megawatt, W310204B .

UNIT SifUTDOWNS AND POWER REDUCTIONS REPORT FOR AUGUST 1991 DOCLTT NO 50-382 UNIT NAME WATERFORD 3 DATE SEPTEMBER 1991 -

COMPLETED BY PATRICK CENT 0LANZI TELEPHONE 504-739-6683 hethod of Licensee Cause & Corrective Event System Component Action to Du ra t i on Shutting Down Reactor 3 Report fi Code 4 Code 5 Prevent Recurrence No. Date Type l (HOURS) REASON 2 l

3 91-019 JS JC The speed at which 91-05 910825 F 34.2 A the test button was pushed affected the l Plant Protection System circuitry, causing ESFAS I actuation.

Installation of a test button which is speed independent will correct the problem.

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Reason Method F: Forced A-Equipment Failure (Explain) 1-Manual S: Scheduled B-Maintenance or Test 2-Manual Scram.

C-R fueling 3-Automatic Scram.

D-Regulatory Restriction 4-Continuation 4 E- Operator Training & 5-Load Reduction IEEE Std. 805-1984 9-Other 5 License Examiitation IEEZ Std. 803A-1983 F-Administrative G-Operational Error (Explain)

H-Other (Explain)

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