ML20084B487

From kanterella
Jump to navigation Jump to search
Corrected Monthly Operating Repts for Apr 1995 for Point Beach Nuclear Plant,Units 1 & 2
ML20084B487
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 04/30/1995
From: Koudelka M
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20084B480 List:
References
NUDOCS 9505310249
Download: ML20084B487 (10)
v • d • e


Text

.

OPERATING DATA REPORT .

DOCKET NO. 50-266 My DATE: 05/23/95 *

D O O COMPLETED BY
M. B. Koudelka c "o D

ON TELEPHONE: 414 755-6480 Q4 OPERATING STATUS gA Ut 1. UNIT NAME: POINT BFACH NUCLEAR PLANT - UNIT 1 . NOTES h

TOM

2. REPORTING PERIOD: April - 1995
3. LICENSED THERMAL POWER (MWT) :

CMA 1518.5 .

2& 4. NAMEPLATE RATING (GROSS MWE) : 523.8 .

5. DESIGN ELECTRICAL RATING (NET MWE) : 497.0 .
6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) : 509.0 . .
7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) : 485.0 . . . . . . . . . . . . . . . . . .
8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:

NA

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE): NA
10. REASONS FOR RESTRICTIONS, (IF ANY) :

NA THIS MONTH YEAR TO DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 719.0 2,879.0 214,607.0
12. NUMBER OF HOURS REACTOR WAS CRITICAL 341.5 2,001.0 178,840.6
13. REACTOR RESERVE 3HUTDOWN HOURS 0.0 0.0 667.3
14. HOURS GENERATOR ON LINE 329.2 1,987.9 175,700.3
15. UNIT RESERVE SHUIDOWN HOURS 0.0 0.0 846.9
16. GROSS THERMAL ENERGY GENERATED (MWH) 449,547 2,929,580 248,474,577
17. GROSS ELECTRICAL ENERGY GENERATED 153,290 997,210 83,935,860
18. NET ELECTRICAL ENERGY GENERATED (MWH) 144,097 951,410 80,012,061
19. UNIT SERVICE FACTOR 45.8% 69.0% 81.9%
20. UNIT AVAILABILITY FACIOR 45.8% 69.0% 82.3%
21. UNIT CAPACITY FACTOR (USING MDC NET) 41.3% 68.1% 76.5%
22. UNIT CAPACITY FACTOR (USING DER NET) 40.3% 66.5% 75.0%
23. UNIT FORCED OUTAGE RATE 0.0% 0.0% 1.5%
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

NONE

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

NA DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977

POINT BEAC11 NUCLEAR Pl. ANT Docket No. 50-266 -

Unit Name Point Beach. Unit I . .

UNrr SIFJrDOWNS AND POWER REDUCTIONS Date May 8.1995 Completed By M. B. Koudelka .

REPORT MONTH APRIL - 1995 Telephone No. 414n554580 Method of Shutting Wo. Date Type' Disranon Reason' Down t_icensee Event System Component Cause and Correc ive Action 2 3/11/95 S 389.8 C 1 NA NA NA Scheduled refueling and maintenance (UIR22). Major work items include steam generator eddy current testing residual heat removal rotating assembly work, channcIhead blowers duct replacement, reacter vessel head shielding. fuel transfer asbe shickling. 003 emergency diesel generstor Phase 3B tie-in work, modify control rod drive -hani= current order timing change, degraded grid voltage relay work, steam generator blowdowls heat encharger replacement, crossover steam dump pressure switches replacement.1 A05 bus ;J3 loss of voltage logic work, componentcooling small bore pipe seismic upgrades. SC-955 contamment isolation valve retubing. IRC-558 valve replacement, modify service water and component cooling supports as part of contimed Bulletm 79-14 upgrades.

2

'F: Forced Reason: ' Method: ' Exhibit G - Instructions S: Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of B - Maintenance or Testing 2 - Manual Scram data entry sheets C - Refueling 3 - Automatic Scram LER file (NUREG-0161)

D - Regulatory Restriction 4 - Continuation of E - Operator Training & Previous Shutdown Licensing Exam 5 - Reduced 1. cad F - Administrative 6 - Other (explain) 5 Exhibit I - Same Source G - Operational Error (explain)

H - Other (explain)

PBF M 80 (03-Q)

POINT BEACH NUCLEAR PLANT DOCKET NO. 50-266 -

AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach. Unit 1 -

MONTH APRIL - 1995 DATE May 8.1995 COMPLETED BY M. B. Koudelka TELEPHONE (414)755-6480 AVERAGE AVERAGE AVERAGE DAILY DAILY DAM.Y POWER LEVEL POWER LEVEL POWER LEVEL t DAY MWe NET DAY MWe NET DAY MWe NET 1 -2 11 -2 21 456 2 -2 12 -2 22 499 3 -2 13 -9 23 502 4 -2 14 -13 24 499 5 -2 15 -15

, 25 500 i t$ -2 16 -15 26 499 7 . -2 17 57 27 500 "

8 -4 18 199 28 500 9 -8 19 371 29 496 10 -2 20 519 30 490 s

- _ . _ . - _ _ _ _ _ _ _ _ _ - _ _ _ . _ . _ -___m. ___- _ _ _ _ _ _ _ _ _ ____ _ _ _ _ _ _ . - _ m - . _ e -

-e-* _ _ _ _ _ . . _ _ _ _ _ _ _ - _ _ -

DOCKET NO. 50-266 UNIT NAME Point Beach Unit 1 DATE May 8, 1995 COMPLETED BY M. B. Koudelka TELEPHONE 414/755-6480 Unit 1 operated at an average of 200 MWe net for the report period.

Licensee Event Report 50-266/95-002-00, Inadvertent Emergency Piesel Generator Start, was submitted.

Licensee Event Report 50-266/95-003-00, Inadvertent Emergency Diesel Generator Start, was submitted.

Licensee Event Report 50-266/95-004-00, Loss of Voltage Relays Not Calibrated to Technical Specification Limits, was submitted.

While performing low power physics testing, coming out of Unit 1 Refueling 22, a manual reactor trip was initiated because of dropped rods. Neither the physics procedure nor the normal operating procedure allowed a restart with the control rod configuration at that time.

Safety-related maintenance included:

1. 271/A02; 272/A01; 272/A02 Bus A01 and A02 undervoltage relay gaskets replaced.
2. 1A52-60 G01 emergency diesel generator output to 1A05 loose lug crimped.
3. 1A52-84 Bus 1A06 feed to 1X14 station service transformer overcurrent relay setpoint recalibrated.
4. 1B52-21B power to PP-13 pressurizer backup heater Group D power panel amptector retrofit installed.
5. 1C2 personnel access air lock 0-rings replaced.
6. 1CV-371-0 letdown line containment isolation valve diaphragm replaced.
7. 1HX-1A steam generator Furmanite removed and repair of lower south handhole.

l l

8. HX-105A&B primary auxiliary building battery room vent cooler l flushed.

' l 1

9. 1MS-478 HX-1B steam generator steam header PT-478 root valve j packing replaced.  !

I J

10. 1MS-279 HX-18A1&2 steam generator blowdown heat exchanger outlet to T26 tank inlet throttle valve cage and gaskets replaced.
11. 1MS-2016 HX-1A steam generator steam header atmospheric steam dump control valve cage replaced.
12. 1MS-2017A HX-1B steam generator steam header non-return check valve diaphragm replaced.

13, 1MS-2054 main steam dump to condenser dump control valve trim and packing replaced.

14. 1P1B reactor coolant pump #2 seal leak corrected.
15. 1P1B-M reactor coolant pump motor return flanges installed, i
16. IRC-431C T1 pressurizer power-operated relief valve trim, packing, yoke bonnet bolts, and diaphragm replaced.
17. 1RC-570B R1 reactor vessel head vent solenoid valve control switch replaced.
18. 1RC-595 T2 pressurizer nitrogen regulator isolation valve bonnet replaced.
19. 1SC-955 reactor coolant hot leg sample isolation valve packing replaced and operator rebuilt.
20. 1SC-966B pressurizer liquid sample containment isolation valve packing replaced.
21. 1SI-839B-S Train A cold leg safety injection to test line isolation solenoid valve rebuilt, i
22. ISI-866B core deluge injection line isolation valve limit switch wiring modified.
23. 1SI-878C P15B safety injection pump R1 reactor vessel injection valve cleaned and packing adjusted.
24. 1SI-898 T13 refueling water storage tank local sample valve diaphragm replaced.
25. ISW-726B HX-30B cavity cooling coil outlet manifold drain valve cleaned.
26. 1W1A-D1 containment accident recirculation fan accelerometers replaced.
27. Plexiglass covers were removed from 4 reactor trip breakers and anti-operation pins were installed.
28. Unit 1 containment floor liner plate inspected.

+

OPERATING DATA REPORT ~

DOCKET NO. 50-301

  • t DATE: 05/23/95
  • I COMPLETED BY: M. B. Koudelkin
4 1

TELEPHONE: 414 755-6480 OPERATING STATUS

! 1. UNIT NAME: POINT BEACH NUCLEAR PLANT - UNIT 2 . NOTES

2. REPORTING PERIOD: April - 1995 .

l i

3. LICENSED THERMAL POWER (MWT) : 1518.5 .
4. NAMEPIATE RATING (GROSS MWE) : 523.8 .

j

5. DESIGN ELECTRICAL RATING (NET MWE): 497.0 .

I

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) : 509.0 . .

I

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) : 485.0 . . . . . . . . . . . . . . . . . .

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

NA .

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)
NA
10. REASONS FOR RESTRICTIONS, (IF ANY):

NA THIS MONTH YEAR TO DATE CUMi" ATIVE

11. HOURS IN REPORTING PERIOD 719.0 2,879.0 199,392.0-
12. NUMBER OF HOURS REACTOR WAS CRITICAL 719.0 2,733.4 174,785.0
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 233.9
14. HOURS GENERATOR ON LINE 719.0 2,E52.3 172,347.0  ;

i 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 302.2 4

! 16. GROSS THERMAL ENERGY GENEEATED (MWH) 1,080,884 3,976,210 247,958,135 i j 17. GROSS ELECTRICAL ENERGY GENERATED 365,940 1,342,320 84,293,430 j 18. NET ELECTRICAL ENERGY GENERATED (MWH) 3d9,498 1,280,573 80,361,088 i j 19. UNIT SERVICE FACTOR 100.0% 92.1% 86.4%

20. UNIT AVAILABILITY FACTOR 100.0% 92.1% 86.6%
21. UNIT CAPACITY FACTOR (USING MDC NET) 100.2% 91.7% 82.5%
22. UNIT CAPACITY FACTOR (USING DER NET) 97.8% 89.5% 81.1%
23. UNIT FORCED OUTAGE RATE 0.0% 0.0% 0.9%
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

Refueling, 10/07/95, 38 days j 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

! NA ,

DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC Lsnm.x DATED SEPTEMBER 22, 1977 i

. _ _ _ _ . _ ._m_ _ _ , .- . . - . , , , - - , . - - , - . , 4 - - - . - .. .m.-.-

POINT BEACH NUCLEAR PLANT Docket Ns. 50-301

~

Unit Name Point Beach Unit 2 .

UNIT SIIUTDOWNS AND PORTR REDUCTIONS Date May 8.1995

  • Completed By M. B. Koudelka REPORT MONTH APRIL - 1995 Telephone No. 414/755 4480 ,-

Method of Shuning Duration 90 % Licensee Event System Component No. Cause amiCornctive Action Date Type' Olours) Reason Reacto,s Report No. Code

  • Code' To PrevectD-mace NA NA NA NA NA NA NA NA NA NA l

'F: Forced 2 Reason: ' Method:

  • Exhibit G - Instructions S: Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of B - Maintenance or Testing 2 - Manual Scram data entry sheets C - Refueling 3 - Automatic Scram LSR file (NUREG-0161)

D - Regulatory Restriction 4 - Continuation of E - Operator Training & Previous Shutdown Licensing Exam 5 - Reduced Imad F - Administrative 6 - Other (explain) 5 Exhibit I- Same Source G - Operational Error (explain)

II - Other (explain)

F3F-0028b (03-90)

POINT BEACH NUCLEAR PLANT DOCKET NO. 50-301-i AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach. Unit 2 MONTH APRIL - 1995 DATE .May 8,1995 COMPLETED BY M. B. Koudelka TELEPHONE (414)755-6480 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 486 11 484 21 486 2 466 12 488 22 486 3 487 13 483 23 488 4 485 14 486 24 487 5 486 15 484 25 486 6 487 16 486 26 486 7 486 17 485 27 487 8 487 18 486 28 486 9 486 19 486 29 486 10 487 20 486 30 487 t

y e

m._ __ . - _ _ - - _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ - _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . __m u - , - -- - -- -- , ,-

' DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 DATE May 8, 1995 COMPLETED BY M. B. Koudelka ,

TELEPHONE 414/755-6480 Unit 2 operated at an average of 485 MWe net for the report period.

Licensee Event Report 50-301/95-003-00, Reactor Trip Due to Turbine Generator Electrohydraulic Control (EHC) System Oil Leak, was submitted.

Safety-related maintenance included:

1. 2B52-29B power to PP-18 pressurizer backup heater Group D power panel amptector unit installed.
2. 2MS-249 HX-1A steam generator SAX-2023 inlet sample '

isolation valve packing adjusted.

3. 2P2A charging pump O-rings replaced.
4. 2SI-896A&B valves cleaned of boric acid buildup.
5. Harmonic filters installed and 273/A05; 274/A05; and 275/A05 Bus AOS loss of voltage relays calibrated.

I e -

POINT BEACH NUCLEAR PL. ANT Docket No. 50-301 Unit Name Point Beach. Uni? 2 .

UNrr SHUrDOWNS AND POWER REDUCTIONS Date May 2.1995 '

Completed By M. B. Koudelka REPORT MONTri MARCII - 1995 Telephone No. 414/755-6480 ,-

Meiod of Shumng Duration g,, Licensee Event System Component Cause and Corrective Accon No. Date Type' (Hours) Reason' Reactors Repon No. Code' Code' To Prevent Recurrence 1 2125195 5 122.7 H 4 NA EG XXXXXX The unit was =*i=M in hot shutdown because of seal oil inleakage into the Unit 2 generator.

The generator was disassembled. A Westinghouse seal oil expert cammmcd the seal oG package noemg no problems with the component. A sell was replaced and an catra drain instaGed to

Dre excess oil to preclude problems with the generator.

2 3107/95 F 14.3 A 3 301/95 @ 3 @ IIA MECFUN A leak in the main turbine EH control oG system caused a snain steam stop valve to close. This caused an increase in reactor coolant system temperature. The unit automancally responded by reducing turbine load, fonowed by an overtemperature differential temperature reactor trip.

'F: Forced 2 Reason: 3 Method: ' Exhibit G - Instructions S: Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of B - Maintenance or Testing 2 - Manual Scram data entry sheets C - Refueling 3 - Automatic Scram LER file (NUREG-0161)

D - Regulatory Restriction 4 - Continuation of E - Operator Training & Previous Shutdown Licensing Exam 5 - Reduced Lead F - Administrative 6 - Other (explain) 5 Exhibit I - Same Source G - Operational 'S.rror (explain)

II - Other (explain)

PBF-0028b (03-90)

__

Retrieved from "https://kanterella.com/w/index.php?title=ML20084B487&oldid=2744540"