ML20043G136

Monthly Operating Rept for May 1990 for Jm Farley Nuclear Plant,Unit 1.W/900612 Ltr

ML20043G136
Person / Time
Site:	Farley
Issue date:	05/31/1990
From:	Hairston W, Dennis Morey ALABAMA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9006190107
Download: ML20043G136 (7)

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"s.-t** t Alabama Power Company s

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- 40 inverness C:nt:r P;/kw:y .. ,

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- Birmingham, Alabama 35201;.

- Telephone 205 868 5581

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' ' ,' W. G. Hairston,111' '

Senior Vee President 1 Nuclear Operations AlabamaPower  ;

1 L.},; the southam electic system - '

June 12, 1990

, i Docket No. 50-348 1 ,

-.l n i U. S. Nuclear Regulatory Commission .'j m, ATIN: Document Control Desk i-p. Washington,.D. C. 20555 ,

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' Joseph M. Farley Nuclear Plant Unit'l Monthly Operating Data Report j Attached-is the May 1990 Monthly Operating Report for Joseph M. Farley Nuclear Plant Unit l', required by Section 6.9.1.10 of the Technical * .l Specifications. Also attached is Revision -9 to the 'Offsite Dose-

. Calculation Manual (ODCM) for the Joseph M. Farley Nuclear Plant as j required by Section 6.9.1.10 of the Technical Specifications. . 1

-If you have any questions,'please advise.  ;

Respectfully submitted,  ;

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[ .fG al ton, II JGS: map /1.6 i

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cc: Mr. S. D. Ebneter ~-i Mr. S. T. Hoffman Mr. G.' F. Maxwell l

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9006190107 900531 PDR ADOCK 05000348 /

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. e JOSEIH M. FARLEY NUCLEAR PIARf-5 UNIT.1 NARRATIVE SUbHARY OF OPFRATIONS i:: Phy, 1990 4 s There was ~one significant power reduction during the month of thy.

on May 18, reactor power was reduced to allow contaminan'ts to return from e

- hideout on the secondary side of: the steam generators. This' hideout, return;is- I intexxled to reduce degradation of the steam: generator tubes. The unit was--

returned to full power operation on May 21. -

The.following major safety-related maintenance was performed in the month of.-

May: ,  !

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'1. Miscellaneous correcidse and preventive maintenance was perfonned on--

~the diesel generators.

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OPERATING IWIA REPORT - ,

DOCKET No. 50-348 IWIE June 6, 1990 COMPLE'IED BY D. N. Morey TELEPHONE (205)899-5156 OPERATING S1R'IUS Notes j

-1..' Unit Name: Joseph M. Farley - Unit 1 1) Cumulative data since

2. Reporting Period: May 1990 12-1-77, date of

3. Licensed Thermal Power (MWt): 2,652 comercial operation.

4. Nameplate Rating (Gross Wo): 860

5. Design Electrical Rating (Net MWe): 829

6. Maximum Dependable capacity (Gross Mwe): 866.1

7. Maximum Dependable Capacity (Net MWe): 823.7

8. If Changes Occur in Capacity Ratings (Itema Number 3 Through 7) Since Last Report, Give Reasons: N/A ,

9. Power Level To Which Restricted, If Any (Net MWe):~ N/A

10. Reasons For Restrictions, If Any: N/A 1

'Ihis Month Yr-to-Date Cumlative ,

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11. Hours In Reporting Period 744 3,623 109,559

12. Number Of Hours Reactor was Critical 144.0 3,623.0 83,881.4

13. Reactor Reserve Shutdown Hours 0.0 0.0 3,650.0

14. Hours Generator On-Line 744.0 3,623.F ~

82,333.2

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (NWH) l~5W,T96 9,,338,288 710,492,2 W --

17. Gross Electrical Energy Generated (MWH) 595,314 3,043,432 67,808,582

18. Net Electrical Energy Generated (MWH) 563,324 2,887,382 63,982,348

19. Unit Service Factor 100.0 100.0 75.2

.20. Unit Availability Factor 100.0 100.0 75.2

21. Unit Capacity Factor (Using MDC Net) 91.9 96.8 72.3 91.3 96.1 70.4

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate 0.0 0.0 7.8-

24. Shutdowns Scheduled Over Next 6 Mcaths (Type, Date, and Duration of Each):

N/A

-.25. If Shut Down At End Of Report Period, Estimated Date of Startup: N/A

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved-

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INITIAL CRITICALITY 08/06/77 08/09/77 )

INITIAL ELECTRICITY 08/20/77 08/18/77 _

COMMERCIAL OPERATION 12/01/77 12/01/77 -

l' l l Form 2/34 i

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50-348 DOCKET NO. .

UNIT 1

'DATE June 6, 1990 COMPLETED BY D. N. Morey f TELEPHONE (205)899-5156 t MONTH May- ,

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Me-Net) (MWe-Net) 1 816 17. 808 '

2, 816 18- 574  ;

3 814 19 35 4 814 20 93 1

5 790 21 762 6 819 22 815  :

7 823 23 822 8 819 24 819 9 814 25 817 ,

10 815 26 816 11 822 27 814 12 816 28 812 i

13 815 29 818 14 813' 30 821 15 812 31 817 16' 811 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month, compute to the nearest whole megawatt.

Form 13/21

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• UNIT SHUTDOWES.AND POWER REDUCTIONS DOCKET Wo.

-UNIT RAME ' J .' M . FARLET - UNIT 1 DATE. June 6, 1990 -a COMPLETED ST D. N. MORET REPORT MONTH MAY TELEPHONE (2059899-5156-l CAUSE & CORRECTIVE ;l l l l l l METHOD OF l LICENSEE l. l l

l ACTION TO .l' l l l l DURATION l- l SHUTTING l EVENT l SYSTEM l COMPONENT PREVENT RECURRENCE l' l CODE -l lNO. l DATE l TYPE l (BOURS) l REASON l DOWN REACTOR ' \ REPORT $ 'l CODE 1

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-1 I I i l- 1 I l i 1 I I i -1 1 I I I I l  ! I Reason: Method: *Ex hibit G Instructions P Forced 1-Manual for Preparation of Data 5: Scheduled A-Equipment Failure (Explain) 2-Manual Scram. Entry Sheets for Licensee -

B-Maintenance or Test 3-Automatic Scram. Event Report (LER) File (NUREG- '

C-Refueling 4-other (Explain) 0161)

D-Regulatory Restriction E-Operator Training & License Examinatien

• Exhibit 1 -Same Source F-Administrative G-Operational Error (Explain)

H4ther (Explain)

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ADDENDUM 00NCERNING REVISION 'ID:THE -. ,[ '

n s, ,. OFFSITE DOSE CAlfU1ATION MANUAL o m ._

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g i i ~ Revision 9 to the Offsite' Dose Calculation Manual- (OCDM) was incorporated 'on .?

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r May 18,11990.. This revision. isildentical to Temporary Change 8A ('IDJ 8A): which - 1

" Mf , was approved by the FORC on March 16,1990.and became; effective on that date. o Bs o - The . methodology in Revision 9 'is' consistent with: the previous revision withi the_. t o .following exception: 1 5 --

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A new factor, Dr (required dilution factor for gainma emitters), was~. ,

. , . Introduced into the calculations which determine -the alam/ trip setpoint hic , for the' effluent radiation monitors so that 10CFR20 compliance is met. -

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, .It was determined by:- the ICRC that this change does not reduce the accuracy or,-

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. reliability of dose, calculations or setpoint deteminations. ~

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, 'Ihe ODCM spplies to Farley Nuclear- Plant Unf ts -1 and 2.

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J 2.2 SETPOINI' CALCULATIONS -l Calculations ate made for the radiation monitors to determineThese the '

alara/ trip setpoint so that 10CFR20 compliance is met.

calculations use the= maximum permissible concentrations from 10CFR20 App. B, Table II, colunn 2, and the more conservative of the soluble and insoluble values.

The setpoint M is given by M = (D,/D,)* I C 1 (2.la) for D 1 (Implementing procedure will require a hand calculation of the, >setpoint)

(2.lb) )

oj by: M =_D, IC 1 1 for D f 1 (Implementing procedure / software derived setpoint may be use,d).

M = setpoint in uCi/ml 1

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D, = anticipated dilution factor D, = - required dilution factor for gama-emitting nuclides, which will be calculated as described by -the- ODCM implementing procedure using the expression 2E (C /MPCg )

g for all ganma-emitting nuclides for each release i

E C, = sum over all gama-emitting nuclides.

For the setpoint in cpm j SPC = E, (D,/D,) I C3 +B for D, > 1 ,

.or SPC = E, (D,) E Cg +B for D, f 1 I

EC1 = concentration at the monitor, before dilution E, = monitor efficiency or monitor meter response (cpnVuci/ml), which is a function of the concentration, or of the monitor setpoint in uCi/ml B = monitor background in cpm

-SPC = monitor setpoint in cpm The flow ratio corresponds to the minimum dilution required to get 10CTR20 compliance, with an additional safety factor of 2, as 4

described below.

2-3 Rev. 9

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