ML19332D059

Monthly Operating Rept for Oct 1989 for Jm Farley Nuclear Plant,Unit 2.W/891114 Ltr

ML19332D059
Person / Time
Site:	Farley
Issue date:	10/31/1989
From:	Hairston W, Dennis Morey ALABAMA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8911290353
Download: ML19332D059 (5)

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• TNabNma Pc$ver' Company 4

l- u s  ;'E ' 6 40 inverness Center Parkway

- Post Office Box 1295 .

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~ Birmingham, Alabama 35201 i , Telephone 205 068-5561;_

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, W.' G. Hairston,' IU I , 4

' Senior Vice President :

Nuclear Operations . Alabama Power--

' the southem electrc system .

November 14,'1989:

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. Docket No 364

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+ U. S.-- Nuclear Regulatory Comission ATIN: Document Control Desk.

. Washington,.D.' C..- 20555' Joseph M. Farley. Nuclear Plant s

Unit 2' l

, Monthly Operating Data Report ll-Attached'is the October 1989 Monthly Operating Report for Joseph M. Farley-l'  ! Nuclear. Plant Unit 2, required by Section 6.9.1.10 of the Technical.

LSpecifice.tions.

l-If-you have any questions,.please-advise.

R Respectfully submitted, l'

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> G.. ir t I cJGS:sme/1.6-Attachment

• E 'cc: 'Mr.lS. D. Ebneter Mr. E. A. Reeves {

Mr. G. F. Maxwell

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8911290353 891031 1 'PDR ADOCK 05000364:

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JOSEPli M.' FARLEY NUCLEAR P1/Nf UNIT 2 NARRATIVE MtNARY OF OPERATIONS October, 1989 There were two unit shutelowns during the month of October.

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- At 1407 on October 18, the reactor tripped due to lo-lo steam generator level. -The lo-lo steam generator level occurred when the turbine governor.

valves closed. h is closure resulted from a digital electro-hydraulio control.(DHIC) system design error. This error allowed a momentary data loss to be created and resulted in the system performing as if both overspeed protection channels had failed. The unit returned to criticality-at 0600 on October 19.

At'1823 on October 19, while the unit was beint, started up following the reactor-trip, the reactor tripped again due to lo-lo level in the 20 steam generator. - The Unit Operator improperly transferred from auxiliary

- feedwater to main feedwater during the plant startup. The unit returned to

. power operation at 0659 on October 20. "

%e following major safety-related maintenance was perfonmx1 in the month of October:

1. . %e valve position limiter feature which lowers to zero as a backup to closing the governor valves when both overspeed protection channel power supplies- fail was removed from the Unit 1 and Unit 2 DDIC systems.

2. Miscellaneous corrective and preventive maintenance was perfonmxl on tJie diesel generators.

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< - - m ;,; 1 r j,'. OPERATING MM REPORT -

1 DOCKET No. 50-364 1 DME 11/1/89 )

CMPLETED BY D. N. Morey l TELEPH WE (205)899-5156 l l' l Notes

11. Unit.Name: Joseph M. Farley - Unit 2 l

-2.1 Reporting Period:

October, 1989 1) Cumulative data since 4

3. Licensed Thermal Povar,(fMt): 2,652 7-30-81, date_of 1

4. Nameplate Rating (Gross PMe):_ 860 conunercial operation l 1

5. Design Electrical Rating (Net 1Me):- 829

- 6. Maximum Dependable Capacity-(Gross MNe): 870.3 -l

7. Maximum Dependable Capacity (Net MWe): 829.7

-8. If Changes occur in Capacity Ratings-(Items Number 3 Through 7) Since Last Report, Give Reasons: N/A 1

'9. Power Level To Which Restricted, If Any (Net MNe): N/A L10. Reasons For Restrictions, If Any: N/A This Month Yr-to-Date Cumalative 11~. Hours In Reporting Period 745 7,296 72,385 c _12. Number Of Hours Reactor Was Critical 723.1 5,758.9 62,436.8

13. Reactor Reserve Shutdown Hours 0.0 0.0 138.0

14. Hours Generator On-Line 704.1 Y 599.8 61,632.4

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 16.. Gross Thermal Energy Generated (MWH) 1,848,890 14,271,678 156,469,314

17. Gross Electrical Energy Generated (MWH) 609,548 4,672,702 51,408,188

18. Net Electrical' Energy Generated (MWH) 579,496 4,418,636 48,743,922

19. Unit Service Factor 94.5- 76.8 85.1

20. Unit Availability Factor 94.5 76.8 85.1

.21. Unit Capacity Factor (Using MDC Net) 93.8 73.0 82.4

22. Unit Capacity Factor (Using DER Net) 93.8 73.1 81.2

23. Unit Forced Outage Rate 5.5 5.4 4.7

. 24. Shutdowns Scheduled Over Next 6 Months (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 INITIAL CRITICALITY 05/06/81 05/08/81 INITIAL ELECTRICITY 05/24/81 35 /15/81 CCNMERCIAL OPERATICN 08/01/81 07/30/81

- Form 2/30

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DOCKET No. 50-364 UNIT 2 I

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' DATE NOVEMBER 1, 1989 b COMPLETED BY D. N. Morey l

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TELEPHONE (205)899-5156

, ?$ MCNIH October 9

p, PAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

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(Me-Net):- (We-Net)

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'1' 826 17 827 2- 829 18 475 i 3- '

828- 19 0 F :4- 833 20 283 5 :833 21 844

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6- '829 22 845 i 7- 825 23 843 n

1 8 '- 835 24 845 9- 840 25 843 i

.10 837 26 843 11 838 27 841 12 832 28 841 _

i 13 834- 29 839 1

14 833 30 837 836 1 15 831 31

- 16 ~ 827 i

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.

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l Form 13/21

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UNIT SHUTDOWNS AND POWER REDUCTIONS 5 DOCRET No. 50-!64 . . . ._

UNIT MART - 'J. M. FARIAT - IfNIT 2 s4-[_;

ahTE NovsMBER 8, 1989 ,

1D. N. MORET^

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COMPLETED BY REPCRT MONTH OCTOBER TELEPNONE (2051899-5156 R

l l l l l l METHOD OF' l LICENSEE 'l- l l CAUSE.E CORRECTIVE l l l l l DURATION l l SHUTTING l EVENT l STSTEM l COMPONENT l ACTION TO -

lNO. l DATE l TYPE l (HOURS) l REASON -l DOWN REACTOR .l REPORT $ l CODE l CODE l PREVENT RECURRE5CE .' ll :

I I I I I I I I I I LI:

l 009 l 891018 l r l 28.3 l A' l 3 l 89-012-00 l 'JJ l JC- l The reactor trip was caused by a design error'in lL l l l l l ] l l .l l . the digital electro-hydraulic. control..(DENC)' l l l l l l l l l l ~j ' system. This design error allowed a daeontary.- [l '

l l l. l l l' .l l l l data loss to be created and resulted J the- Ll l l l l l l l -l l l system performing as if both overspeed l' l l l l l l l l .l l protection channels had f ailed. '. The feature ..'. l J l l l l l l l l l l which allowed this to occur has been removed l l l l l l l l l l- l from the Unit l'and Unit 2 DENC systems. l '.

I I I I I I I I I i 1 l 010 l 891019 l F l 12.6 l G l 3 l89-013-00 l SJ l LCV l The reactor trip was caused by personnel. error' 'l,-

l l l l l l l l l l in that the Operator improperly transferred from. j' l l l l l l l l l l aamiliary feedwater to main.feedwater during , l ..

l l l l l l l 'l l l plant startup. The perwonnel: involved have been l..

, l l l l l l l l l l counseled concerning improper feedwater' ,j i l i i i l i I I I tr=nsfer. I I I I  ! I i i i i I .I I I I I I I I I I i 1.

I I I I I I I I I I i I I I I I I I i 1 I I-l 1 1 I I I I i .I I I 4 I I i i i i I I i 1 1 I I I I I I I 'l i I ~l t* : Forced Reason: Method: Exhibit G-Iestructions S: Scheduled A-Equipment Failure (Explain) 1-Manual .for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 44ther (Explain) 0161)

E-Operator Training E License Examination F-Administrative ' Exhibit I -Same source G-Operational Error (Explain)

(9/77) H-Other (Explain) mn axm v2

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