ML17354A507

Monthly Operating Repts for April 1997 for TPS.W/970512 Ltr

ML17354A507
Person / Time
Site:	Turkey Point
Issue date:	04/30/1997
From:	Hovey R, Knorr J FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-97-127, NUDOCS 9705190257
Download: ML17354A507 (16)

Text

CATEGORY 1 REGULAT INFORMATION DISTRIBUTION%STEM (RIDE)

ACC;ySSIPN NBR:9705190257 DOC.DATE: 97/04/30 NOTARIZED: NO DOCKET FACIE: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 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

Monthly operating repts for April 1997 for TPS.W/970512 ltr.

DISTRIBUTION CODE: IE24D COPIES RECEIVED:LTR i ENCL ) SIZE:

TITLE: Monthly Operating Report (per Tech Specs)

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-3 PD 1 1 CROTEAU,R 1 1 lAI+SAl INTERNAL: AEOD/SPD/RRAB 1 1 FILE CENTER 0 1 1 NRR/DRPM/PECB 1 1 O~CDBA/PAD 1 1 RGN2 1 1 EXTERNAL: LITCO BRYCE,J H 1 1 NOAC 1 1 NRC PDR 1 1 D

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NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 10

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NAY 12 tggr L-97-127 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 In accordance with the requirements of Turkey Point Units 3 and 4 Technical Specification 6.9.1.5, and the guidance of NUREG-0020, attached are the April 1997 Operating Status and Summary of Operating Experience Reports for Turkey Point Units 3 and 4.

Very truly yours, R. J. Hove Vice President Turkey Point Plant JEK Attachments cc: L. A. Reyes, Regional Administrator, Region II, USNRC T. P. Johnson, Senior Resident Inspector, USNRC, Turkey Point Plant 9705<90257 970eao PDR ADOCK 05000250 R PDR

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AVERAGE DAIL NIT POWER LEVEL DOCKET NO. 50 - 250 UNIT Turkey Point 43 DATE May 07, 1997 COMPLETED BY J. E. Knorr TELEPHONE I305) 246 - 6757 MONTH April, 1997 DAY AVERAGE DAILY POWER LEVEL (MWe.Net) 04/01/97 0 04/02/97 0 04/03/97 0 04/04/97 0 04/05/97 0 04/06/97 0 04/07/97 0 04/08/97 0 04/09/97 0 04/10/97 0 04/11/97 0 04/12/97 0 04/13/97 0 04/14/97 0 04/15/97 0 04/16/97 96 04/17/97 46 04/18/97 244 04/19/97 299 04/20/97 455 04/21/97 699 04/22/97 71 'I 04/23/97 707 04/24/97 712 04/25/97 715 04/26/97 715 04/27/97 713 04/28/97 710 04/29/97 711 04/30/97 708

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50- 250 UNIT NAME: Turkey Point 3 ¹ DATE: May 07, 1997 COMPLETED BY: J. E. Knorr REPORT MONTH APRIL 1997 TELEPHONE: (305) 2466757 No. Date Type Duration Reason Method of Licensee System Component Cause and Corrective (Hours) Shutting Event Code Code Action to 1 2 Down 3

Report ¹ 4 5 Prevent Recurrence:

Reactor 00001039 03/03/97 S 368.5 97-02 RB INSTRU Manual reactor trip due to rod control urgent failure alarm 00001040 04/17/97 S 12.8 N/A HA INSTRU Shut plant down to perform a turbine overspeed test

1. F Forced 2. A - Equipment Failure (Explain) 3. 1- Manual 4. Exibit G - Instructions for S Scheduled B - Maintenance or test 2- Manual Scram Preperation of Data Entry C - Refueling 3- Automatic Scram Sheets Licensee Event Report D - Regulatory Restriction 4- Continued (LER) File (NUREG4161)

E - Operator Training Jicense Examination 5- Load Reduction F - Administraitive G - Operational Error (Explain) 9- Other (Explain) Exibit I - Same Source H - Other (Explain)

OPE NG DATA REPORT DOCKET NO 50 - 250 DATE 05/07/97 PREPARED BY TELEPHONE OPERATING STATUS

1. UNIT NAME: TURKEY POINT UNIT3

2. REPORTING PERIOD: ApriI, 1997

3. LICENSED THERMAL POWER (MWT): 2300

4. NAMEPLATE RATING (GROSS MWE): 760

5. DESIGN ELECTRICAL RATING (NET MWE): 720

6. MAXIMUMDEPENDABLE CAPACITY (GROSS MWE): 726

7. MAXIMUMDEPENDABLE CAPACITY (NET MWE): 693 B. IF CHANGES OCCUR IN CAPACITY RATINGS ( ITEMS NUMBER 3 THROUGH 7 ) SINCE LAST REPORT, GIVE REASONS:

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)

10. RESONS FOR RESTRICTION, IF ANY:

MONTHLY - YTD - CUMULATIVE

11. HOURS IN REPORT PERIOD: 719.0 2879.0 213920.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL 387.0 '1829.4 144619.9

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 844.4

14. HOURS GENERATOR ON-LINE 338.7 1773.0 142533.0

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 121.8

16. GROSS THERMAL ENERGY GENERATED (MWH) 651515 3825487 297819913

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 209139 1244151 95671947

18. NET ELECTRICAL ENERGY GENERATED (MWH) 192150 1177294 90586722

19. UNIT SERVICE FACTOR 47.1 61.6 66.6

20. UNIT AVAILABILITYFACTOR 47.1 61.6 66.7

21. CAPACITY FACTOR ( USING MDC NET ) 38.6 59.0 64.4

22. CAPACITY FACTOR ( USING DER NET ) 37.1 56.8 61.9

23. UNIT FORCED OUTAGE RATE 0.0 1.9 10.3

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS:

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

DOCKET NO. 59=259.

UNIT:

DATE:

TELEPHONE:

REPORT MONTH Unit 3 started the month of April shut down for a refueling which began on March 3, 1997. The unit began operation on April 16.

The plant shutdown as scheduled the next day for a Turbine overspeed test returning to power the next day. The unit reached 100% power on April 21 and remained at that level for the remainder of the month.

During the filling and venting process for the reactor coolant system after the refueling outage a one minute run of the 3A RCP was conducted. At 1:50 a.m on April 1, 1997, the Overpressure Mitigating System (OMS) High Pressure Alert annunciated at 400 psig. The running charging pump was immediately stopped.

Position indication change or annunciation of a power operated relief valve (PORV) Opening was not observed. However, the operators did hear the relays changing state, indicating an OMS actuation. The OMS system operated as designed, with PORV (or PORVs) lifting at about 415 psig.

AVERAGE DAIL NIT POWER LEVEL DOCKET NO. 50 - 251 UNIT Turkey Point 44 DATE May 07, 1997 COMPLETED BY J. E. Knorr TELEPHONE 1305) 246 - 6757 MONTH April, 1997 DAY AVERAGE DAILY POWER LEVEL (MWe Net) 04/01/97 712 04/02/97 718 04/03/97 721 04/04/97 721 04/05/97 720 04/06/97 717 04/07/97 714 04/08/97 707 04/09/97 706 04/10/97 709 04/11/97 715 04/12/97 713 04/13/97 708 04/14/97 702 04/15/97 704 04/16/97 710 04/17/97 714 04/18/97 720 04/19/97 724 04/20/97 720 04/21/97 717 04/22/97 711 04/23/97 309 04/24/97 0 04/25/97 0 04/26/97 26 04/27/97 534 04/28/97 706 04/29/97 708 04/30/97 708

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50- 251 UNIT NAME: Turkey Point r/ 4 DATE: May 09, 1997 COMPLETED BY: J. E. Knorr REPORT MONTH APRIL 1997 TELEPHONE: (305) 2466757 No. Date Type Duration Reason Method of Licensee System Component Cause and Corrective 1 (Hours) 2 Shutting Event Code Code Action to Down Report 0 4 5 Prevent Recurrence:

Reactor 00001041 04/23/97 F 22.1 97- 02 HA INSTRU Reactor trip due to loss of turbine load, caused by worker bumping a relay 00001042 04/24/97 F 56.8 N/A CB VALVEX Repair of letdown valve leak

1. F Forced 2. A - Equipment Failure (Explain) 3. 1- Manual 4. Exibit G - Instructions for S Scheduled B - Maintenance or test 2 - Manual Scram Preparation of Data Entry C - Refueling 3 - Automatic Scram Sheets Licensee Event Report D - Regulatory Restriction 4 - Continued (LER) File (NUREG4161)

E - Operator Training Jicense Examination 5 - Load Reduction 5 F - Administraitive G -Operational Error (Explain) 9- Other (Explain) Exibit I - Same Source H - Other (Explain)

OPE NG DATA REPORT DOCKET NO 50- 251 DATE 05I07/97 PREPARED BY J. E. Knorr TELEPHONE (305) 246-6757 OPERATING STATUS

1. UNIT NAME: TURKEY POINT UNIT 4

2. REPORTING PERIOD: April, 1997

3. LICENSED THERMAL POWER (MWT): 2300

4. NAMEPLATE RATING (GROSS MWE): 760

5. DESIGN ELECTRICAL RATING (NET MWE): 720

6. MAXIMUMDEPENDABLE CAPACITY (GROSS MWE): 726

7. MAXIMUMDEPENDABLE CAPACITY (NET MWE): 693

8. IF CHANGES OCCUR IN CAPACITY RATINGS ( ITEMS NUMBER 3 THROUGH 7 ) SINCE LAST REPORT, GIVE REASONS:

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)

10. RESONS FOR RESTRICTION, IF ANY:

MONTHLY - YTD - CUMULATIVE

11. HOURS IN REPORT PERIOD: 719.0 2879.0 207652.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL 645.0 2805.0 142243.8

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 166.6

14. HOURS GENERATOR ON-LINE 640.2 2791.8 138009.1

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 577.2

16. GROSS THERMAL ENERGY GENERATED (MWH) 1446847 6349380 292841 575

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 469838 2074975 93713361

18. NET ELECTRICAL ENERGY GENERATED (MWH) 446835 1980722 88775863

19. UNIT SERVICE FACTOR 89.0 97.0 66.5

20. UNIT AVAILABILITYFACTOR 89.0 97.0 66.7

21. CAPACITY FACTOR ( USING MDC NET ) 89.7 99.3 65.0

22. CAPACITY FACTOR ( USING DER NET ) 86.3 95.6 62.5

23. UNIT FORCED OUTAGE RATE 11.0 3.0 9.8

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS Refueling Outage Scheduled for September

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

~

~

'I

DOCKET NO.

UNIT:

DATE:

COMPLETE BY:

TELEPHONE:

REPORT MONTH Unit 4 began the month of April operating at essentially 100%

reactor power and operated at that level until April 23, 1997.

On April 23, due to an inadvertent actuation of the turbine overspeed protection the reactor tripped on over temperature delta T from 100% power. On April 23, maintenance was being performed which disabled turbine stop valve control panel indication. Due to lack of turbine valve position indication at the time of the trip, control room operators procedurally closed the main steam isolation valves(MSIVs). As a result of this trip and the closure of MSIVs, three main steam code safety valves lifted at their set point of 1085 psig and the., two pressurizer power operated relief valves also lifted at 2335 psig. The plant was returned to power operation on April 26 and reached 100%

power on April 27, 1997. Unit 4 remained at essentially 100%

reactor power for the remainder of the month.

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