ML20133F647

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Monthly Operating Repts for Dec 1996 for Point Beach Nuclear Plant,Unit 1 & 2
ML20133F647
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 12/31/1996
From: Patulski S, Vander Velde B
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PBL-97-0010, PBL-97-10, NUDOCS 9701140308
Download: ML20133F647 (10)
v • d • e


Text

. . . . . . . - -

l Wisconsin Electnc \

POWER COMPANY i i

l Point Beoch Nuclear Plant (414) 755-2321 6610 Nuclear Rd.. Two Rivers. WI 54241 j l

l PBL 97-0010 January 7,1997 Document Control Desk U. S. NUCLEAR REGULATORY COMMISSION Mail Station Pl-137 Washington, DC 20555 i

Gentlemen:

DOCKETS 50-266 AND 50-301 MONTHLY OPERATING REPORTS  !

POINT BEACH NUCLEAR PLANT. UNJTS 1 AND 2 l Attached are monthly operating reports for Units 1 and 2 of the Point Beach Nuclear Plant for the calendar month of December 1996.

Sincerely, i

l l

l . A. Patulski General Manager Nuclear Operations smb i

l Attachments \l

\

14011

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l cc: L. L. Smith, PSCW NRC Regional Administrator, Region III NRC Resident inspector ,]/[

9701140308 961231 PDR ADOCK 05000266 R PDR A sukskn ornomin Dryrmxath>n ,

OPERATING DATA REPORT -

DOCKET NO. 50-266 DATE: 01/06/97 COMPLETED BY: B. J. Vander Velde TELEPHONE: 414-755-6681 i OPERATING STATUS i

1. UNIT NAME: POINT BEACH NUCLEAR PLANT - UNIT 1 . NOTES .
2. REPORTING PERIOD: December - 1996 . .
3. LICENSED THERMAL POWER (MWT): 1518.5 .
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): Power 90%
10. REASONS FOR RESTRICTIONS, (IF ANY):

Self-imposed restriction.

THIS MONTH YEAR TO DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744.0 744.0 229,272.0
12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 744.0 192,873.9
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 667.3
14. HOURS GENERATOR ON LINE 744.0 744.0 189,655.0
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 846.9
16. GROSS THERMAL ENERGY GENERATED (MWH) 1,075,254.0 1.075,254.0 269,494,385.0
17. GROSS ELECTRICAL ENERGY GENERATED 368,290.0 368,290.0 91,091,090.0
18. NET ELECTRICAL ENERGY GENERATED (MWH) 352,505.5 352,505.5 86.856,419.5
19. UNIT SERVICE FACTOR 100.0 % 100.0 % 82.7 %
20. UNIT AVAILABILITY FACTOR 100.0 % 100.0 % 83.1 %
21. UNIT CAPACITY FACTOR (USING MDC NET) 97.7 % 97.7 % 77.8 % ,
22. UNIT CAPACITY FACTOR .'USING DER NET) 95.3 % 95.3 % 76.2 % 6
23. UNIT FORCED OUTAGE RATE O.0% 0.0% 1.4%
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

Refueling, 05/10/97, 50 days

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

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

- _ . _ _ . . . _ _ - _ _ _ __ _. _ _ _ __ .______m ___ _ _ . . _ . . _

POINT BEACH NUCLEAR PLANT -

DOCKET NO. 50-266 AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach Unit 1 MONTH DECEMBER - 1996 DATE 1/6/97 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 1 476 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 8 499 16 449 28 449 9 495 19 446 29 450 10 496 20 447 30 447 31 448

POINT BEACH NUCLEAR PLANT Docket No. 50-266 Unit Nane Point Beach. Unit 1 UNIT SIIUTDOWNS AND POWER REDUCTIONS Date 1/9/97 Completed By B. J. Vander Velde i REPORT MONTII DECEMBER - 1996 Telephone No. 414/755-6681 .

Method of Licensee Event .

Duration Reactor Report No. System Component Cause and Corrective Action j No. Date Type' (Hours) Reason' Shut Down' Code

  • Code' To Prevent Recurrence 3 %I201 S 0 B 5 NA HB VALVEX The unit was reduced to 69% power for turbine stop valve tests, atmosphenc steam dump tears, crossover steam dump tests, and condenser steam dump tests.

4  % I217 5 0 F 5 NA ZZ ZZ7777 'Ihe unit entered a self-inrosed power reduction to 90% power.

'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 Imad F- Administrative 6 - Other (explain) ' Exhibit 1 - Same Source G - Operational Error (explain)

H - Other (explain)

PBF-0028b (03-90),

  • DOCKET NO. 50-266 UNIT NAME Point Beach Unit 1 DATE 1/7/97 COMPLETED BY B. J. Vander Velde TELEPHONE 414/755-6681 Unit 1 operated at an average of 474 MWe net for the December,1996 report 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.
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 genciator air start system headers cleaned and frequency meter replaced.
8. F-137A emergency diesel generator fuel oil pump discharge filters replaced.
9. C-2 personnel access air lock gear replaced.
10. Piping HB-19 rarvice water to engineered safeguards piping replaced.

OPERATING DATA REPORT DOCKET NO. 50-266 ,

DATE: 01/08/97 COMPLETED BY: B. J. Vander Velde TELEPHONE: 414-755-6681 OPERATING STATUS

1. UNIT NAME: POINT BEACH NUCLEAR PLANT - UNIT 2 $ NOTES .
2. REPORTING PERIOD: December - 1996 . .
3. LICENSED THERMAL POWER (MWT): 1518.5 . .
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 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
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
17. GROSS ELECTRICAL ENERGY GENERATED O.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 O.0% 75.8 % 85.7 %
20. UNIT AVAILABILITY FACTOR O.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 O.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 REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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

_ _ _ . . - _ - _ _ . - _ . - - _ _ - , . _ _ . _ _ _ _ _ . _ . _ - . _ - - . . _ . , - . . . _ _ _ _ _ . - - - - - _ _ - . . . - _ _ _ - - _ _ - . _ . _ _ _ _ . _ - . - -.____.--_------------r - _ _ _ . , ,.____a -

- - a . - - ,s

POINT BEACH NUCLEAR PLANT - DOCKET NO. 50-301 '.

AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach. Unit 2 MONTH DECEMBER - 1996 DATE 1/6/97 COMPLETED BY Brian J. Vander Velde TELEPHONE (414)755-6681 4

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 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

_ _ _-_-._._______.____..._m______ _ _ _ _ . _ _ _ _ _ _ . _ - . _ _ _ _ _ _ _ _ _ ___ __ _--_ - _ _ ______.__.___-_ _._____._ _ _ _ _____-_____._-___ - _ _ _ _ _ _ _ _ _ . - ________i____--____________-_____ -

POINT BEACH NUCLEAR PLANT Docket No. 50-301 Unit Name Point Beach. Unit 2 -

UNIT SHUTDOWNS AND POWER REDUCTIONS Date 1/6/97 +

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 Recurtence 4 961005 S 744.0 C 1 NA NA NA Scheduled refueling and maintenance (U2R22). Major work items include: Replacire boeh Unit 2 steem generators; main control board wire separation resolution; repiece 8 main aseem condenser valves; HP turbine crosaunder piping; repair service water west header, replace boric acid and reactor makeup water totalizers; replace oefety irsection accunmistor levei trememitters; modify X02, XO3, and XO4 treneformer metering and relay circuite; and exciter modification.

'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 Imd F - Administrative 6 - Other (explain) Mahibit I - Same Source G - Operational Error (explain)

H - Other (explain) 4 PBF-0028b (0340).

4 4 *

. DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 DATE 1/7/97 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.

Safety-related maintenance included: .

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

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

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

4. LT-00471 steam generator level transmitter shielded extension cab!e installed. '

l

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.

i

9. C-2 personnel air lock o-rings replaced.
10. P-011 A component cooling water pump probe mounting blocks installed.

I1. 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. ~

\

14. HS-36 steam generator north side snubber tested.
15. HS-37 steam generator middle side snubber tested.
16. HS-38 steam generator south side snubber tested.
17. HS-39 steam generator north side snubber tested.
18. B52-328F control power transformer replaced.
19. B52-3210C control power transformer replaced.
20. B52-425C control power transformer replaced.
21. B52-4275 control power transformer replaced.
22. CPP-39 containment cooler supply pipe penetration adapter neplaced.
23. SI-00825A reactor water storage tank outlet cleaned.

e l

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