ML20082R917

Monthly Operating Rept for Aug 1991 for Jm Farley Nuclear Plant Unit 1

ML20082R917
Person / Time
Site:	Farley
Issue date:	08/31/1991
From:	Dennis Morey, Woodard J ALABAMA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9109160302
Download: ML20082R917 (6)

Text

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• Docket No. 50-348 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Joseph M. Farley Nuclear Plant Unit 1 Monthly Ooeratina Data Report Attached is the August 1991 Monthly Operating Recort for Joseph M. Farley Nuclear Plant Unit 1, as required by Section 6.9.1.10 of the Technical Specifications.

If you have any questions, please advise.

Respectfully submitted,

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. Woodard AEJ:edb3014 Attachments cc: Mr. S. D. Ebneter Mr. S. T. Hoffman Mr. G. F. Maxwell l

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9109160302 910931

• POR ADOCK 05000348

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-JOSEPil-M. FARLEY NUCLEAR PLANT

. J . UNIT 1-NARRATIVE SUP91ARY OF OPERATIONS August 1991

?There-were two _ reactor _ trips and one major power reduction during the month of

August.-

At 0001 on August 2, the reactor tripped due to personnel error. A systems operator opened the breaker supplying power to the 120. volt regulated panel IE, which provides power to the IC reactor coolant pump (RCP) breaker position contact.- Loss of power to the breaker position contact caused the solid state protection t stem to generate-an RCP breaker reactor trip. .The IC RCP breaker did not ac, 211y open.  ;

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L The 3ersonnel involved have been counseled. Also, this event will be included  !

L in tie next. cycle of licensed and nonlicensed operator retraining. A caution j

label which reads, " Opening this breaker may cause a reactor trip.", has been

placed on the four associated breakers in' Unit I and Unit 2. The unit returned .

to power operation at 0815 on 8-03-91.

5

-At 1720 on August 19, a. lightning induced trip of the IB star _t-up transformer caused the loss of-18 and ~1C RCPs. The loss of RCPs at 100 percent power e caused the reactor to trip. The 1B start-up transformer has been inspected and  !

tested. A_ damaged lightning-arrestor on phase 2 was discovered and replaced. l In addition, an engineering study is being conducted to attempt to prevent i

.further lightning induced trips at FNP.. The unit returned to power operation i at 0921 on 8-21-91.

A major power reduction. occurred on 8-5-91 when a broken condenser line from  ;

number four-. turbine' gland _ caused a loss of vacuum, requiring a reduction in -j

; power.to 68 percent. The line was subsequently plugged, and the_ unit returned  :

to 100 percent power on 8-5-91'.

The following major safety-related maintenance was performed during the month: j j, 1) .There was a .1-2A diesel generator outage for quarterly preventive maintenance tasks and various other maintenance.  ;

2) A new thrust bearing was~ installed in the turbine driven auxiliary feedwater pump (TDAFWP)-after the thrust bearing-temperature went out  !

of. specification high during the _ quarterly Surveillance Test. Procedure  :

(FNP-0-STP-22.16). -The TDAFWP was declared inoperable on 8-22-91 at-l 0513 and returned to service on 8-23-91 at 0510. i o .

.3) ' Miscellaneous corrective and preventive maintenance was performed on  !

the diesel generators.

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. OPERATING DATA REPORT DOCKET NO. 50-348 DATE September 5, IMT COMPLETED BY D. N. Herey TELEPil0NE (205)899-3156 OPERATING STATUS i Notes

.1. Unit Namet Joseph H. Parley - Unit 1 1) Cumulative data since

, 2. Reporting Periods. August 1991 12-1-77, date of

3. Licensed Thermal-Power (HVt): 2,652 commercial opetation.

4. Nameplate Rating (Gross MVe): 860

5. Design Electrical Rating (Net HVe): 829

6. Maximum Dependable Capacity (Gross MVe): 856.4

7. Haximum Dependable Capacity (Net Hve): 814.0

8. If Changes Occur in Capecity P.atings (ltems Number 3 Through 7) Since Last Report,

Give Reasons

N/A f

9. Power Level To Vhich Restricted, IF Any (Net HVe): N/A

10. Reasons For Restrictions, If Any N/A This Month Yr-to-Date Cumulative 2

11. Hours In Reporting Period 744 5831 120,527

12. Number Of Hours Reactor Vas Critical 690.7 ~ 4043.5 92,997.8

, '13. Reactor Reserve Shutdown Hours 0.0 0.0 3,650.0

-14. Hours Generator On-Line 671.8 3968.5 91,360.2 4' 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Cross Thermal Energy Generated (HVH) 1,725,229 10,129,439 233,763,420

17. Gross Electrical Energy Generated (HVH) 55^,762 ._3,258,130 75,308,468

18. Net-Electrical Energy Generated (HVH) 519,150 3,061,488 71,065,020

19. Unit Service Factor 90.3 68.1 75.U~

-20. Unit-Availability Factor 90.3 68.1 75.8

21. Unit-Capacity Factor (Using HDC Net) 85.7 64.5 78.7

22. Unit Capacity Factor (Using DER Net) 84.2 63.3 71.1

- 23. Unit Forced Outage Rate 9.7 3.3 7.3

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

N/A

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

?6. Units In Test Status (Prior to Commercial Operation): Forecast Achieved 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 L ,

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DOCKET No. 50-348 UNIT 1  ;

DATE September 5, 1991 COMPLETED BY D. N. Morey TELEPHONE (205)899-5156 MONTH August DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POVER LEVEL (MVe-Net) (HVe-Net) l' 807 17 -606

-2 0 18 803 >

3 309 19 578 l 4- 803 20 0 5 709 21 140 6 805 22 611

7. 805 23 810 '

8 805- 24 810 9 805 25 806 .

10 804 26 807 11- 807' 27 805 i

12 806 -28 806 i

13 807 29 804 >

-_14 808 30 804 15 811 31 807 5 L -16 809- . .!

r INSTRUCTIONS ,'

1 1

• his format, list the average daily unit power level in HVe-Net for each day in un reporting month. Compute to the nearest whole megavatt. ,

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DOCRET 30.53-348 UNIT SUITIl OWNS JCD POWE2 REDUCTIONS UNIT ENTE J. L FARLET - t(NIT 1 DATE Se,te.ne, s,in! -

COMPLETED BY D. N. MORET REPORT MONTH AUGUST TEI2 PHONE (2056099-5156 l CAOSE & CORRECTIVE l l l l l l l METHOD OF l LICENSEE l l l ACTION TO l l l DURATION l l SHUTTING l EVENT l SYSTEM l COMPONENT l l FRE7ENT RECURRENCE l l REPORT S l CODE

• l CODE l lNO. l DATE l TTPE l (HOURS) l REASON l DOWN REACTOR' 32.23 G 3 l 91-00s l JG l site lA systems operater opened a breaker supplying power l l 9108*2 F l l l l007 l lto 120 volt regulated panel IE, which provides l l l l l l l l l l l l l l power to the 1C reactor coolant pump (RCP) breaker l l l l l l l l l position contact. Loss of power to the breaker l l l l l l l l l

l l l l position contact caused solid state protection to l l l l l l l l l l l generate an RCP breaker reactor trip. The 1C RCP l l l l l l l l l breaker did not actually open. l l l l l l l l l I I I I I I 1 1 I I I Also, l l l l lThe perscanet involved have been counseled.

l l l l l l

l l l l lthis event will be included in the next cycle of l l l l l l l l l l licensed and nonlicensed operator retraining. l l l l l l l I I I I I I I l 1 1 I l l l lA caution label which reads, " Opening this breaker l l l l l l l

l l lmay cause a reactor trip *, has been placed on the l l l l l l l l lfour associated breakers in Unit 1 and Unit 2. l l l l l l l l l i

! I I I l i l 1 I I I I I I I I i l I I I i l i I I i i i 1 i I

I i l i I I I I I I l i i l l I I i l i i l I I I I I I I l i I I i

i I I i i l I I i i I I I I I I i l l I I i 1

! I I I I i i I i 1

Method: Exhibit G-Instructions F: Forced Reason:

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 (1.ER) File (NUREG-C-Refueling 4-Other (Explain) 0161)

D-Regulatory Restriction E-operator Training & License Examination Exhibit I -Same 3ource F-Administrative l G-operational Error (Explain)

H-Other (Emplain)

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UNIT SHUTDOWNS AND POWER CEDUCTIONS DOCEET NO. 50-348 UNIT NAME J. M. FARLEY - WNIT 1 DATE September 5, 19D1 COMPLETED RY D. N. MORET s REPORT MONTN AUGUST TELEFRONE (2051899-51$6 _

l2.ICENSEE l l l CAUSE 6 CORRECTITE l l l l l l l METHOD OF ACTION TO l l l l l DURATION j l SHUTTING l EVENT l SYSTEM l COMPOWENT l l REPORT 5 l CODE

• l CODE l PREVENT RECURRENCE l lNO. l DATE l YYPE l (HOURS) l REASON l DOWN REACTOR F l 40.02 H 3 l 91-009 l EA l 2FMR lA lightning induced trip of the 18 start-up l l 008 l 910819 l l l l l l transformer caesed the loss of 18 6 1C Reactor l l l l l l l l l l l l Coolant Pumps (RCPs). The loss of RCPs at 100 l l l l l l l l l l l l percent power caused the reactor to trip. l l l l l l I I l 1 1 I I I I I I l l l l l lThe 15 start-up transformer has been inspected and l l l l l l l l l l l tested. A damaged lightning arrsstor on phase 2 l I l l l l l l l l l lvas discovered and replaced. An engineering study l l l l l l l l l l l lis being conducted to attempt to prevent further l l l l l l l l l l l1ightning induced trips at FNP. l l l l I I I l l l l l 1 1 l

F 7.22 A W/A l N/A l SH l COND lA broken condenser return line from number four l l 009 l 910805 l l l l l l l l l l turbine gland caused a loss of vacuum, requiring a l l l l l l l l l l l reduction in power to 68%. The line was l l l l l l l l l l l l subsequently p1 ragged; and the unit returned to l l l l I I i 1100s. I l 1 I I I I I l i I I I I I I I I I I I I I i I I I I I I I l i I 1 1 I I I I I I I I I I I I i 1 1 1 I I I I I I I l l l Reason: Method: Eahibit G-Instructions F: Forced A-Equipment Failure (Emplain) 1-Manual for Preparation of Data l S: Scheduled B-Maintenance or Test 2-Manual Scram. Ent ry Sheets for Licensee l

C-Refueling 3-Automatic Scram. Event Report (LER) File (RUREG-l D-Regulatory Restriction 4-Other (Esplain) 0161)

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

(9/77) H4ther (Explain)

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