L-97-211, Monthly Operating Repts for July 1997 for Tps
| ML17354A605 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point |
| Issue date: | 07/31/1997 |
| From: | Hovey R, Knorr J FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| L-97-211, NUDOCS 9708140077 | |
| Download: ML17354A605 (16) | |
Text
~.q CATEGORY 1 REGULATORIINFORMATION DISTRIBUTION WEM (RIDE)
ACCESSION NBR:9708140077 DOC.DATE: 97/07/31 NOTARIZED:
NO DOCKET FACIAL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH.NAME AUTHOR AFFILIATION KNORR,J.E.
Florida Power
& Light Co.
HOVEY,R.J.
Florida Power S Light Co.
RECIP.NAME RECIPIENT AFFIl IATION
SUBJECT:
Monthly operating repts for July 1997 for TPS.W/970806 ltr.
DISTRIBUTION CODE:
IE24D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Monthly Operating Report (per Tech Specs)
NOTES:
RECIPIENT ID CODE/NAME PD2-3 PD INTERNAL: AEOD/SPD/RRAB NRR/DRPM/PECB RGN2 EXTERNAL: LITCO BRYCE,J H
NRC PDR COPIES LTTR ENCL 1
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1 1
1 1
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OC/DBA NOAC COPIES LTTR ENCL 1
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AUG 61997 L-97-211 10 CFR 550.36 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re:
Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 hl eai R
In accordance with the requirements ofTurkey Point Units 3 and 4 Technical Specification 6.9.1.5, and the guidance ofGeneric Letter 97-02, attached are the July 1997 Operating Status and Summary ofOperating Experience Reports for Turkey Point Units 3 and 4.
V
- yours,
> Sun~~
R. J. Hovey Vice President Turkey Point Plant Attachments cc:
L. A. Reyes, Regional Administrator, Region II, USNRC T. P. Johnson, Senior Resident Inspector, USNRC, Turkey Point Plant A (j <g 97083,40077 9707GX PDR ADQCK 05000250 R
PDR an FPL Group company Illlllllllllllllllllllllllllllllllllllll I
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DOCKET NO.
UNITNAME DATE COMPLETED BY TELEPHONE 50-250 U
E P
I U
I u
u 4
997 J E~(~nrr REPORTING PERIOD
~ul
'L999 (Month/Year)
- 1. Design Electrical Rating (MWe-Net) 720
- 2. Maximum Dependable Capacity (MWe-Net) 693
- 3. Number of Hours Reactor Was Critical
- 4. Number of Hours Generator Was On Line
- 5. Unit Reserve Shutdown Hours
- 6. Net Electrical Energy (MWH) hLt be 699.9 3993.3 149444.8 680.2 3917.3 147304.4 0.0 0.0 121.8 445499.0 2657032.0 93817238.0
AVERAGE DAILY IT POWER LEVEL DOCKET NO.
50 - 250 UNIT Turkey Point ¹3 DATE Aug 05, 1997 COMPLETED BY J. E. Knorr TELEPHONE I305) 246 - 6757 MONTH July, 1997 DAY 07/01/97 07/02/97 07/03/97 07/04/97 07/05/97 07/06/97 07/07/97 07/08/97 07/09/97 07/10/97 07/11/97 07/12/97 07/13/97 07/14/97 07/15/97 07/16/97 07/17/97 07/18/97 07/19/97 07/20/97 07/21/97 07/22/97 07/23/97 07/24/97 07/25/97 07/26/97 07/27/97 07/28/97 07/29/97 07/30/97 07/31/97 AVERAGE DAILY POWER LEVEL IMWe.Net) 696 699 703 702 701 695 696 696 697 699 697 696 698 696 694 696 696 612 350 420 516 358 0
393 698 702 705 702 701 430 141
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
REPORT MONTH Mo.
Date Duration (Hours)
Reason*
Method of Shutting Down Reacto&
Cause
& Corrective Action Comments 1045 7/18/97 0.0 Reduce load to repair heat exchanger 1048 7/21/97 0.0 Reduced load while repairing stop valve controls 1049 7/22/97 39.5 Manual reactor trip due to 12 dropped control rods 1050 7/30/97 13.3 Automatic reactor trip due to failed MSIV seal-in relay 1051 7/31/97
- 11. 0 Remained in Mode 2 to trouble-shoot 'A'FW pump trip F - Forced S - Scheduled Reason A - Equipment Failure E - Maintenance or Test C - Refueling D - Regulatory restriction E - Operator Training a License Examination F - Administrative G - Operational Error (Explain)
H - Other Nxplain)
Method 1 - Manual 2 - Manual Scram 3 - Automatic Scram 4 - Continued 5 - Load Reduction 9 - Other (Explain)
A Y F
PFR TI F.
PF.
IF F.
DOCKET NO.
2L2~
UNIT.
~E DATE:
COMPLETED BY:
J E Knorr TELE HONE:
REPORT MONTH~I Y 1~
Unit 3 operated at essentially 100% power until July 18, 1997, when power was reduced to perform a turbine valve test and clean and eddy current test the Turbine Plant Cooling Water heat exchangers.
A number oftubes were plugged on the heat exchangers to eliminate leaks.
The plant was returned to approximately 87 % power on July 21. Later that day, power was again reduced to allow repair ofthe controls for a reheat stop valve. Power was then returned to 100 % on July 21. On July 22, 12 control rods dropped into the core, due to failed power supplies in a rod control cabinet, and the reactor was manually tripped. Power was returned to 100% on July 24. On July 30 an automatic trip from 100% power occurred due to a failed relay in the B main steam isolation valve. The unit was restarted and reached 100% power on July 31.
1(
OPERATING DATAREPORT DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE kOD25 E
0 T
N uu 4
99
~J(~o iMLuu!E REPORTING PERIOD JUI 99 (Month/Year)
- 1. Design Electricai Rating (MWe-Net) 720
- 2. Maximum Dependable Capacity (MWe-Net) 693
- 3. Number of Hours Reactor Was Critical
- 4. Number of Hours Generator Was On Line
- 5. Unit Reserve Shutdown Hours 744.0 744.0 0.0 5013.0 4999.8 0.0 146466.0 142165.8 577.2
- 6. Net Electrical Energy (MWH) 509388.0 3515042.0 91564120,0
I~
AVERAGE DAILY IT POWER LEVEL DOCKET NO.
50-251 UNIT Turkey PeInt P4 DATE Aug 04. 1997 COMPLETED BY J. E. Knorr TELEPHONE (305) 246-6757 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 07/01/97 07/02/97 07/03/97 07/04/97 07/05/97 07/06/97 07/07/97 07/08/97 07/09/97 07/10/97 07/11/97 07/12/97 07/13/97 07/14/97 07/15/97 07/16/97 07/17/97 07/18/97 07/19/97 07/20/97 07/21/97 07/22/97 07/23/97 07/24/97 07/25/97 07/26/97 07/27/97 07/28/97 07/29/97 07/30/97 07/31/97 698 697 693 692 497 694 696 695 699 696 694 692 685 695 697 696 695 694 693 696 694 694 695 691 690 690 689
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
REPORT MONTH Mo.
Date Type'uratio n
(Hours)
Reason'ethod of Shutting Down Reactor'ause
& Corrective Action to Prevent Recurrence 1043 7/0/97 0.0 RCS flow instrumentation replacement 1044 7/9/97 0.0 Water box cleaning F - Forced S - Scheduled Reason A - Equipment Failure B - Maintenance or Test C - Refueling D - Regulatory restriction E - Operator Training &
License Examination F - Administrative G - Operational Error (Explain)
H - Other (Explain)
Method 1 - Manual 2 - Manual Scram 3 - Automatic Scram 4 - Continued 5 - Load Reduction 9 - Other (Explain)
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~
~
M ARY F
ER TI PERIF E
DOCKET NO.
UNIT:
DATE:
COMPLETE BY:
TELEPHONE:
g-2'i 1 it 1
~K~n REPORT MONTHQJIY~
Unit 4 operated at essentially 100% power until July 8. On July 8, power was reduced to allow replacement ofthe B reactor coolant system loop flowinstrument. and clean water boxes.
Power was returned to 100% on July 9 and remained at essentially that level for the remainder of the month.
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