L-97-127, Monthly Operating Repts for April 1997 for Tps

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Monthly Operating Repts for April 1997 for Tps
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)
v • d • e


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 ID CODE/NAME PD2-3 PD INTERNAL: AEOD/SPD/RRAB NRR/DRPM/PECB RGN2 COPIES LTTR ENCL 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME CROTEAU,R lAI+SAl FILE CENTER 0

O~CDBA/PAD COPIES LTTR ENCL 1

1 1

1 1

1 EXTERNAL: LITCO BRYCE,J H

NRC PDR 1

1 1

1 NOAC 1

1 D

0 N

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

C

!.. (

NAY12 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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P 4

AVERAGE DAIL NIT POWER LEVEL MONTH April, 1997 DOCKET NO.

50 - 250 UNIT Turkey Point 43 DATE May 07, 1997 COMPLETED BY J. E. Knorr TELEPHONE I305) 246 - 6757 DAY 04/01/97 04/02/97 04/03/97 04/04/97 04/05/97 04/06/97 04/07/97 04/08/97 04/09/97 04/10/97 04/11/97 04/12/97 04/13/97 04/14/97 04/15/97 04/16/97 04/17/97 04/18/97 04/19/97 04/20/97 04/21/97 04/22/97 04/23/97 04/24/97 04/25/97 04/26/97 04/27/97 04/28/97 04/29/97 04/30/97 AVERAGE DAILY POWER LEVEL (MWe.Net) 0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 96 46 244 299 455 699 71 'I 707 712 715 715 713 710 711 708

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH APRIL 1997 DOCKET NO.

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50- 250 Turkey Point ¹ 3 May 07, 1997 J. E. Knorr (305) 2466757 No.

Date Type 1

Duration (Hours)

Reason 2

Method of Licensee Shutting Event Down 3

Report ¹ Reactor System Code 4

Component Code 5

Cause and Corrective Action to Prevent Recurrence:

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 S Scheduled
2. A-Equipment Failure (Explain)

B - Maintenance or test C - Refueling D - Regulatory Restriction E - Operator Training Jicense Examination F - Administraitive G - Operational Error (Explain)

H - Other (Explain)

3. 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continued 5-Load Reduction 9-Other (Explain)
4. Exibit G - Instructions for Preperation of Data Entry Sheets Licensee Event Report (LER) File (NUREG4161)

Exibit I - Same Source

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

1. UNIT NAME:

TURKEY POINT UNIT3

2. REPORTING PERIOD:

ApriI, 1997

3. LICENSED THERMALPOWER (MWT):

2300

4. NAMEPLATERATING (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:
11. HOURS IN REPORT PERIOD:
12. NUMBER OF HOURS REACTOR WAS CRITICAL
13. REACTOR RESERVE SHUTDOWN HOURS
14. HOURS GENERATOR ON-LINE
15. UNIT RESERVE SHUTDOWN HOURS
16. GROSS THERMALENERGY GENERATED (MWH)
17. GROSS ELECTRICAL ENERGY GENERATED (MWH)
18. NET ELECTRICAL ENERGY GENERATED (MWH)
19. UNIT SERVICE FACTOR
20. UNIT AVAILABILITYFACTOR
21. CAPACITY FACTOR

( USING MDC NET )

22. CAPACITY FACTOR

( USING DER NET )

23. UNIT FORCED OUTAGE RATE
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS:

MONTHLY 719.0 387.0 0.0 338.7 0.0 651515 209139 192150 47.1 47.1 38.6 37.1 0.0

- YTD -

CUMULATIVE 2879.0

'1829.4 0.0 1773.0 0.0 213920.0 144619.9 844.4 142533.0 121.8 1244151 1177294 61.6 61.6 59.0 56.8 1.9 95671947 90586722 66.6 66.7 64.4 61.9 10.3 3825487 297819913

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 MONTH April, 1997 DAY AVERAGE 04/01/97 04/02/97 04/03/97 04/04/97 04/05/97 04/06/97 04/07/97 04/08/97 04/09/97 04/10/97 04/11/97 04/12/97 04/13/97 04/14/97 04/15/97 04/16/97 04/17/97 04/18/97 04/19/97 04/20/97 04/21/97 04/22/97 04/23/97 04/24/97 04/25/97 04/26/97 04/27/97 04/28/97 04/29/97 04/30/97 DOCKET NO.

50 - 251 UNIT Turkey Point 44 DATE May 07, 1997 COMPLETED BY J. E. Knorr TELEPHONE 1305) 246 - 6757 DAILY POWER LEVEL (MWe Net) 712 718 721 721 720 717 714 707 706 709 715 713 708 702 704 710 714 720 724 720 717 711 309 0

0 26 534 706 708 708

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH APRIL 1997 DOCKET NO.

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50- 251 Turkey Point r/ 4 May 09, 1997 J. E. Knorr (305) 2466757 No.

Date Type 1

Duration (Hours)

Reason 2

Method of Shutting Down Reactor Licensee Event Report 0 System Code 4

Component Code 5

Cause and Corrective Action to Prevent Recurrence:

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 S Scheduled
2. A-Equipment Failure (Explain)

B - Maintenance or test C - Refueling D - Regulatory Restriction E - Operator Training Jicense Examination F - Administraitive G -Operational Error (Explain)

H - Other (Explain)

3. 1-Manual 2 - Manual Scram 3 - Automatic Scram 4 - Continued 5 - Load Reduction 9-Other (Explain)
4. Exibit G - Instructions for Preparation of Data Entry Sheets Licensee Event Report (LER) File (NUREG4161) 5 Exibit I - Same Source

OPE NG DATA REPORT OPERATING STATUS

1. UNIT NAME:

TURKEY POINT UNIT 4 DOCKET NO DATE PREPARED BY TELEPHONE 50- 251 05I07/97 J. E. Knorr (305) 246-6757

2. REPORTING PERIOD:

April, 1997

3. LICENSED THERMALPOWER (MWT):
4. NAMEPLATERATING (GROSS MWE):
5. DESIGN ELECTRICALRATING (NET MWE):
6. MAXIMUMDEPENDABLE CAPACITY (GROSS MWE):
7. MAXIMUMDEPENDABLE CAPACITY (NET MWE):
8. IF CHANGES OCCUR IN CAPACITY RATINGS ( ITEMS GIVE REASONS:

2300 760 720 726 693 NUMBER 3 THROUGH 7 ) SINCE LAST REPORT,

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)
10. RESONS FOR RESTRICTION, IF ANY:

MONTHLY

- YTD -

CUMULATIVE

11. HOURS IN REPORT PERIOD:
12. NUMBER OF HOURS REACTOR WAS CRITICAL
13. REACTOR RESERVE SHUTDOWN HOURS
14. HOURS GENERATOR ON-LINE
15. UNIT RESERVE SHUTDOWN HOURS
16. GROSS THERMALENERGY GENERATED (MWH)
17. GROSS ELECTRICAL ENERGY GENERATED (MWH)
18. NET ELECTRICAL ENERGY GENERATED (MWH)
19. UNIT SERVICE FACTOR
20. UNIT AVAILABILITYFACTOR
21. CAPACITY FACTOR

( USING MDC NET )

22. CAPACITY FACTOR

( USING DER NET )

23. UNIT FORCED OUTAGE RATE
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS Refueling Outage Scheduled for September 719.0 645.0 0.0 640.2 0.0 1446847 469838 446835 89.0 89.0 89.7 86.3 11.0 2879.0 2805.0 0.0 2791.8 0.0 6349380 2074975 1980722 97.0 97.0 99.3 95.6 3.0 207652.0 142243.8 166.6 138009.1 577.2 292841 575 93713361 88775863 66.5 66.7 65.0 62.5 9.8
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.

~1

~

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