ML20011D138

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Monthly Operating Rept for Nov 1989 for Jm Farley Unit 1.W/ 891214 Ltr
ML20011D138
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 11/30/1989
From: Hairston W, Dennis Morey
ALABAMA POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8912210013
Download: ML20011D138 (5)


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- Alabama Power Company ..-

. 40 inverness Center Parkcay -

/' t '. - i. Post Offce Box 1295

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Birmingham, Alabama 35201 -

i ~! ' Telephone 205 068-5581 -

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, W. G. Hairston, til

- Senior Vice President Nuclear Operations Alabama Power:

the Southern eleC!nc Systern . .,

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December 14, 1989  ;

. Docket No. 348 :

U.' S. Nuclear Regulatory Comission r ATIN: Document Control Desk

-Washington, D. C.' 20555 ,.

Joseph M. Farley. Nuclear Plant

1. Unit 1 Monthly Operating Data Report i

Attached is the November 1989 Monthly Operating Report for Joseph M. Farley Nuclear Plant Unit 1, required by Section 6.9.1.10 of the Technical Specifications.

If you have any questions, please advise.

Respectfully submitted,

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.JGS:sme/1.6 Attachment cc: Mr. S. D. Ebneter Mr. E. A. Reeves-Mr. G. F. Maxwell l:

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-8912210013 891130

.PDR R ADOCK 0500034G l

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~' - JOSEPH k FARLEY NUCLEAR PIANT

. UNIT l' c-' r NARRATIVE SltNARY OF. OPERATIONS o November, 1989L

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, , gThe ' Cycle 9N 10 refueling outage continued into the month of November.  !

t- - ' L. Power operation began at 2345 on November 9.

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-l'Ihe' generator was' taken off line .at 1055 on November 10 to perform the . ,

y  : turbine overspeed; trip test'.. The unit returned to power operation at'1854:-

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orf November 10. -

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'LAt 1658 on November.12, a safety injection- and reactor trip' were initiated :

p idue. toilow steam line ' pressure. '1he low steam line pressure .resulted from j 7 personnel error ~during naintenarce on the digital electro-hydraulic control:

[ system. The. unit returned to= power-operation atL1502'on November.14.

h At.1855 on November 19,-- the generator was removed from the grid to recouple; h

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ithe governor. valve. stems to their actuators.. The unit returnedito power.

Loperation 'at 0258 on November 21.

l[ (Thel f6110 wing major safety- related nnintenance was perfomed in the month  ;

4 Lof November: 4

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~1. .A water leak was repaired on the 1C containment cooler.

~ 2. flhe turbirie driven auxiliary feedwater pump was rebuilt.

3. : Repairs were made to .the notor driven auxiliary feedwater pump

-breaker circuitry.

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4'. - The -1B service water pump was replaced.

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5. lA leak was repaired ~on the 10 charging pump room cooler.
  • 6. Some high energy line break sensors were recalibrated, f- 7'. A;1esking diaphragm on the normal -letdown valve actuator was
y. replaced.
8. MiscelJaneous corrective and preventive maintermnce was performed on d j lthe'dieaal generators.

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OPERATING m'm REPORT

. i DOCKET NO. 50-34ft MTE 12/6/89 CCMPLEND BY D. N. Morey TELEPHCNE (205)899-5156

'1PERATING S'm'IUS Notes

1. Urit Name: Joseph M. Farley - Unit 1
2. Reporting Period: November, 1989 1) Cumulative data since

-3. Licensed Thermal Power (MWt): 2,652 12-1-77, date of i

4. Nameplate Rating (Gross MWe): 860 comercial operation  !

.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 (Items 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 l

'Ihis Month Yr-to-Date Cumulative

. 11. Hours In Reporting Period 720 8,016- 105,192

12. Number Of Hours Reactor Was Critical 510.2 6,869.4 79,514.4
13. Reactor Reserve Shutdown Hours 0.0 0.0 3,650.0 M.. Hours Generator On-Line 418.2 6,777.1 77,966.2 15 Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal ~ Energy Generated (MWH) 855,994 17c602,592 199,185,814  ;
17. Gross Electrical Energy Generated (MWH) 271,574 5,709,108---

64,115,456

18. Net Electrical Energy Generated (MWH) 244,044 5,400,208 60,477,618 t
19. Unit Service Factor 58.1 84.5 74.1
20. Unit Availability Factor 58.1 84.5 74.1
21. Unit Capacity Factor (Using MDC Net) 41.1 81.8 71.2
22. Unit Capacity Factor (Using DER Net) 40.9 81.3 69.4

- 23.. Unit Forced Outage Rate 15.7 1.1 8.2

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 r INITIAL CRITICALITY 08/06/77 08/09/77 INITIAL ELECTRICITY 08/20/77 08/18/77 COMMERCIAL OPERATION 12/01/77 12/01/77 Form 2/34

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DOCKET NO. 50-348  ;

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UNIT- 1 ,

MTE DECEMBER 6,1989 COMPLETED BY D. N. Morey TELEPHONE (205)899-5156

'i MONDI NOVEMBER' DAY AVERAGE MILY POWER LEVEL MY AVERAGE DAILY POWER LEVEL (MWe-Net) (PMe-Net)

1. 0 17 _

605 2 0- 18 653 3 0- 19 423 4 0 20 0 5 0 21 334 6- 0 22 762 7 0 23 830

'8 0 24 834

. 9: 0 25 832 10 27 26 829 11 200 27 828

' 12 107 28 824 13 0 29 836 14 20 30 837 15 321 31 5

~ 16 386

.- INSTRUCTIONS L 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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  • UNIT SHUTDOWNS A*? *%"Q REDUCTIONS DOCKET NO. 50-348 UNIT NAME J. M. FARLET - UN*T 1 'J DATE DECEMBER 6, 1989 ** '

COMPLETED BY D. N. MORET REPORT MONTH NOVEMBER TELEPHONE (2051899-5156 l l METHOD OF l LICENSEE l l l CAUSE & CORRECTIVE l l l l l l E7ENT l 3YSTEM l COMPONENT l ACTION TO l l l l l DURATION l l SEUTTING ,

l REPORT #. l CODE l CODE l FREVENT RECURRENCE l lNO. l DATE l TYPE l (HOURS) l REASON l DOWN REACTOR I I I I I I 1 1 I I I S 215.7 C l 1 l N/A l N/A l N/A l The Cycle 9-10 refueling outage continued l l001 l891101 l l l l l l l l l l from 9-22-89. l l l l l002 l 891110 l 5 l 8.0 l B l NA* l N/A l N/A l N/A l The generator was taken off-line for the l' l l l l l turbine overspeed trip test. l l l l l l l003 l 891112 l F l 46.1 l H l 3 l 89-006-00 l JJ l CPU l A safety injection and reactor trip were l l l l l l l l l l l initiated due to low steam line pressure. l l l l l l l l l l During troubleshooting of an oscillation l l

l l l l l l l l l l in the #3 governor valve, the circuit card that l l l l l l l l l l -l controls this valve was replaced with l l l l l l l l l l l an improperly configured card. This caused l l l l l l l l l l l the digital electro-hydraulic control (DEHC) -l l l l l l l l l l l to open all three of the other governor valves. l l l l l l l l l l l This in turn resulted in a decrease in steam l l l l l l l l l line pressure. The person involved has been l l l l l l l l l l l l counseled. As a further enhancement,'when l l

l l l l l l l l troubleshooting the DEHC system during power l l l l l l l l l l l l 'l operation,'the governor valve position l' l l l l l l l l l l limiter will be restricted to limit the amount l l l l l l l l l l l of valve opening. l l004 l 891119 l F l 32.0 l B l NA* l N/A l TA l FCV l The generator was removed from the grid to l l l l l l l l l l recouple a governor valve stem to its actuator l l

l l l l l l l l and make repairs on other governor l l l l l l l l l l l l v31ve couplin;c. l l

F: Forced Reason: ' Method: Exhibit G-Instructions 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. Evert Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-operator Training & License Examination 5

F-Administrative Exhibit I -Same' Source G-Operational Error (Explain)

  • Generator was taken off H-Other (Explain) line While reactor remained (9/77)

'IEDI Ebtm 1/2 critical.

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