ML20133N060

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Revised MOR Rept for Dec 1996 for Point Beach Nuclear Plant, Units 1 & 2
ML20133N060
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 12/31/1996
From: Velde B
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20133N020 List:
References
NUDOCS 9701230148
Download: ML20133N060 (9)
v • d • e


Text

i OPERATING DATA REPORT

nma DOCKET NO. 50-266

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y DATE: 01/13/97 DW COMPLETED BY: B. J. Vander Velde we o4 TELEPHONE: 414-755-6681 y

OPERATING STATUS j

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1. UNIT NAME: POINT BEACH NUCLEAR PLANT - UNIT 1 NOTEE l

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2. REPORTING PERIOD: December - 1996 l
3. LICENSED THERMAL POWER (MWT): 1518.5

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4. NAMEPLATE RATING (GROSS MWE): 523.8 I

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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:

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9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE): Power 90%
10. REASONS FOR RESTRICTIONS, (IF ANY):

Self-imposed restriction.

I THIS MONTH YEAR TO DATE CUMULATIVE l -

11. HOURS IN REPORTING PERIOD 744.0 8,784.0 229,272.0 i
12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 8,219.5 192,873.9 f
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 667.3 l
14. HOURS GENERATOR ON LINE 744.0 8,173.6 189,655.0
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 846.9 i
16. GROSS THERMAL ENERGY GENERATED (MWH) 1,075,254.0 12,278,236.0 269,494,385.0

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17. GROSS ELECTRICAL ENERGY GENERATED 368,290.0 4,184,720.0 91,091,090.0 l
18. NET ELECTRICAL ENERGY GENERATED (MWH) 352,505.5 4,003,335.0 86,856,419.5
19. UNIT SERVICE FACTOR 100.0 %

93.1 %

82.7 %

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20. UNIT AVAILABILITY FACTOR 100.0 %

93.1 %

83.1 %

21. UNIT CAPACITY FACTOR (USING MDC NET) 97.7 %

94.0 %

77.8%

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22. UNIT CAPACITY FACTOR (USING DER NET) 95.3 %

91.7 %

76.2%

23. UNIT FORCED OUTAGE RATE 0.0%

0.0%

1.4%

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)

Refueling,05/10/97, 50 days f

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

NA i

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

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POINT BEACH NUCLEAR PLANT DOCKET NO.

50-266 AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach, Unit 1 -

MONTH DECEMBER -

1996 DATE 1/13/97 COMPLETED BY Brian J. Var <'tr Veide TELEPHONE (414)755-6681 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1

476 11 499 21 449 2

497 12 498 22 449 3

498 13 497 23 448 4

498 14 498 24 448 5

498 15 498 25 449 6

498 16 497 26 450 7

498 17 472 27 446 i

8 499 18 449 28 449 9

495 19 446 29 450 10 496 20 447 30 447 31 448 t

i POINT BEACH NUCLEAR PLANT Docket No.

50-266 Unit Name Point Beach. Unit 1 UNIT SHUTDOWNS AND POWER REDUCTIONS Date 1/13/97 Completed By B. J. Vander Velde REPORT MONTH DECEMBER - 1996 Telephone No.

414r755-6681 Method of Licensee Event Duration Reactor Report No.

System Component Cause and Corrective Action No.

Date Type' (Hours)

Reason' Shut Down' Code' Code' To Prevent Recurrence 3

961201 S

0 B

5 NA HB VALVEX The unit was reduced to 695 power for turbine stop valve tests, atmospheric steam dump tests, crossover steam dump tests, and condenser steam dump tests.

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% 1217 5

0 F

NA ZZ 777777 The unit entered a self-imposed power reduction to 905 power.

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'F: Forced Reason:

' Method:

' Exhibit G - Instructions f

2 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)

' Exhibit I - Same Source G - Operational Error (explain)

H - Other (explain)

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t DOCKET NO.

50-266 UNIT NAME Point Beach Unit 1 DATE 1/13/97 COMPLETED BY B. J. Vander Velde I

TELEPHONE 414/755-6681 l

I Unit 1 operated at an average of 474 MWe net for the December,1996 repon period.

The following Licensee Event Reports were submitted to the NRC in December 1996:

Licensee Event Report 50-266/96-010, Emergency Diesel Generator (G-01) Governor Failure.

Licensee Event Report 50-266/96-011, Delta T Trip Setpoints Not Reduced in Accordance with Technical Specifications.

Safety-related maintenance included:

1. C-02 main control board annunciator buzzer replaced.

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2. P-012A spent fuel pool cooling pump flow tested.
3. PI-03368A emergency diesel generator turbo-charger oil pressure indicator calibrated.
4. D-06124 volt DC station battery flash arrestor replaced.
5. 120 volt system multi and/or non numbered equipment receptacle replaced.
6. G-01 emergency diesel generator air start circuit repaired and tested, relay replaced.
7. G-02 emergency diesel generator air start system headers cleaned and frequency meter replaced.

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8. F-137A emergency diesel generator fuel oil pump discharge filters replaced.

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9. C-2 personnel access air lock gear replaced.

10 Piping HB-19 service water to engineered safeguards piping replaced.

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OPERATING DATA REPORT DOCKET NO. 50-301 DATE: 01/13/97 COMPLETED BY: B. J. Vander Velde TELEPHONE: 4?4-755-6681 OPERATING STATUS

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

. NOTES

2. REPORTING PERIOD: December - 1996 i
3. LICENSED THERMAL POWER (MWT): 1518.5
4. NAMEPLATE RATING (GROSS MWE): 523.8 l
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):

i NA THIS MONTH YEAR TO DATE CUMULATIVE f

11. HOURS IN REPORTING PERIOD 744.0 8,784.0 214,057.0
12. NUMBER OF HOURS REACTOR WAS CRITICAL O.0 6,660.5 185,987.6
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 233.9
14. HOURS GENERATOR ON LINE O.0 6,653.9 183,508.3 I
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 302.2
16. GROSS THERMAL ENERGY GENERATED (MWH) 0.0 9,072,854.0 263,605,007.0 j
17. GROSS ELECTRICAL ENERGY GENERATED 0.0 3,100,050.0 89,603,310.0
18. NET ELECTRICAL ENERGY GENERATED (MWH) 0.0 2,946,934.0 85,411,583.5
19. UNIT SERVICE FACTOR 0.0%

75.8 %

85.7 %

20. UNIT AVAILABILITY FACTOR 0.0%

75.8 %

85.9 %

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0%

69.2 %

81.7 %

22. UNIT CAPACITY FACTOR (USING DER NET) 0.0%

67.5 %

80.3 %

23. UNIT FORCED OUTAGE RATE 0.0%

0.3%

0.9 %

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

None

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

02/15/97 DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22,1977

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POINT BEACH NUCLEAR PLANT DOCKET NO.

50-301 l

i AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach, Unit 2 -

MONTH DECEMBER -

1996 DATE 1/13/97 COMPLETED BY Brian J. Vander Velde TELEPHONE (414)755-6681 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1

-2 11

-2 21

-3 2

-2 12

-2 22

-3 3

-2 13

-2 23

-3 1

4

-2 14

-2 24

-3 5

-2 15

-2 25

-4 6

-2 16

-2 26

-4 7

-2 17

-2 27

-3 8

-2 18

-3 28

-3 9

0 19

-2 29

-3 10

-1 20

-2 30

-3 31

-2 I

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POINT BEACH NUCLEAR PLANT Docket Ns.

50-301 Unit Name Point Beach. Unit 2 UNIT SHUTDOWNS AND POWER unUCTIONS Date 1/13/97 Compiceed By B. L Vander Velde REPORT MONTH DECEMBER - 104 -

Telephone No.

414/755-6681 Method of Licensee Event Duration Reactor Report No.

System Component cause and Corrective Action

[

No.

Date Type' (Hours)

Reason

  • Shut Down' Code' Code' To Ptevesa Recurrence i

3 4

961005 5

744.0 C

1 NA NA NA Scheduled refue!isig and snaissenance (U2R22). Mejor work itemme include: Replacing bee Unit 2 steem generators; main control board wire saperation.

. replace 8 main senema i

condenser valves; HP turbine cronounder piping; repair service weser west header, replace boric acid and reactor molteup woner totalizers; replace enfaty ispection accueuslator level tre, i

modify XO2, XO3, and XO4 transformer metenng and relay circuite; and exciter mundificanian i

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'F: Forced

' Reason:

' Method:

Txhibit G -Instructions E

S: Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of B - Maintenance or Testing 2 - Manual Scram data entry sheets l

C - Refueling 3 - Automatic Scram LER file (NUREG-0161)

D - Regulatory Restriction 4 - Continuation of E - Operator Tr ining &

Previous Shutdown i

LW; Exam 5 - Reduced load F-Administrative 6 - Other (explain)

Mbit I hana Sotate G - Operatonal Error (explain)

H - Other (explain)

'60-90).

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DOCKET NO.

50-301 I

UNIT NAME Point Beach Unit 2 DATE 1/13/97 COMPLETED BY B. J. Vander Velde TELEPHONE 414/755-6681 i

Unit 2 was in a refueling outage during the entire December,1996 report period.

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l Safety-related maintenance included:

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1. LT-00461 steam generator level transmitter shielded extension cable installed.
2. LT-00462 steam generator level transmitter shielded extension cable installed.

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3. LT-00463 steam generator level transmitter shielded extension cable installed.

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4. LT-00471 steam generator level transmitter shielded extension cable installed.

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5. LT-00472 steam generator level transmitter shielded extension cable installed.
6. LT-00473 steam generator level transmitter shielded extension cable installed.
7. SC-00955 reactor coolant hot leg sample isolation valve stroke tested.
8. C-1 equipment access air lock (lower) gasket repaired.
9. C-2 p,ersonnel air lock o-rings replaced.
10. P-011 A component cooling water pump probe mounting blocks installed.
11. P-01IB component cooling water pump probe mounting blocks installed.
12. HS-32 steam generator main steam line east snubber tested.
13. HS-33 steam generator main steam line west snubber tested.

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14. HS-36 steam generator north side snubber tested.

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15. HS-37 steam generator middle side snubber tested.

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16. HS-38 steam generator south side snubber tested.

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17. HS-39 steam generator north side snubber tested.

I8. B52-328F control power transformer replaced.

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19. B52-3210C control power transformer replaced.

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20. B52-425C control power transformer replaced.

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21. B52-4275 control power transformer replaced.
22. CPP-39 containment cooler supply pipe penetration adapter replaced.
23. SI-00825A reactor water storage tank outlet cleaned.

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