ML20134J871

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Monthly Operating Repts for Jan 1996 for Point Beach Nuclear Plant,Units 1 & 2
ML20134J871
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 01/31/1997
From: Dante Johnson, Vander Velde B
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PBL-97-0041, PBL-97-41, NUDOCS 9702120378
Download: ML20134J871 (12)
v • d • e


Text

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Wisconsin

' Electnc POWER COMPANY Point Beoch Nuclear Plant 2 6610 Nuclear Rd.Two Rivers.WI 54241 (414) 755-2321 PBL 97-0041 .

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February 6,1997 Document Control Desk U. S. NUCLEAR REGULATORY COMMISSION Mail Station Pl-137 Washington, DC 20555 Gentlemen:

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

POINT BEAC11 NUCLEAR PLANT. UNITS 1 AND 2  !

l Attached are monthly operating reports for Units I and 2 of the Point 13each Nuclear Plant for the

, calendar month of January 1997.

Sincerely, D. F. Johnson Manager Regulatory Services & Licensing i

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Attachments cc: L. L. Smith, PSCW e NRC Regional Administrator, Region III ,

NRC Resident inspector

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i 9702120378 970131 PDR ADOCK 05000266 R PDR 120067 A subskhr7 of Hha>nsin Enew Ostpmrth>n ,

OPERATING DATA REPORT DOCKET NO. 50-266 .

DATE: 02/05/97 COMPLETED BY: B. J. Vander Velde TELEPHONE: 414-755-6681 OPERATING STATUS

1. UNIT NAME: POINT BEACH NUCLEAR PLANT - UNIT 1 NOTES .
2. REPORTING PERIOD: January - 1997 ,
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, 'F 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 744.0 744.0 230,016.0
12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 744.0 193,617.9
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 667.3
14. HOURS GENERATOR ON LINE 744.0 744.0 190,399.0
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 846.9
16. GROSS THERMAL ENERGY GENERATED (MWH) 1,014,658.0 1,014,658.0 270,509,043.0
17. GROSS ELECTRICAL ENERGY GENERATED 348,560.0 348,560.0 91,439,650.0
18. NET ELECTRICAL ENERGY GENERATED (MWH) 333,043.0 333,043.0 87,189,462.5
19. UNIT SERVICE FACTOR 100.0 % 100.0 % 82.8%
20. UNIT AVAILABILITY FACTOR 100.0 % 100.0 % 83.1 %
21. UNIT CAPACITY FACTOR (USING MDC NET) 92.3 % 92.3 % 77.8%
22. UNIT CAPACITY FACTOR (USING DER NET) 90.1 % 90.1 % 76.3%
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

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 BEACH NUCLEAR PLANT DOCKET NO. 50-266 __

AVERAGE DAILY UNIT POWER LEVEL UNIT NAME - Point Beach, Unit 1 MONTH JANUARY- 1997 DATE 2/5/97 ,

COMPLETED BY Brian J. Vander Velde TELEPHONE (414)755-6681  ;

AVERAGE AVERAGE AVERAGE I DAILY ,

DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET ,

DAY MWe NET 1 448 11 448 ,

21 448 2 449 12 448 22 450 3 456 13 448 23 449 i

4 443 14 449 24 449 5 449 15 4 d 'd 25 445 l 6 448 16 448 26 449 L 7 449 17 447 27 449 l 8 448 18 448 28 450 i

9 448 19 448 29 450 '

y 10 449 20 450 _

30 450 31 420 l t

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_. _ . _ _ _.m . - - . . . _ . _ - . . . ~ . . . -. _ . . _ . _ - . . . . . _ _ . _ _ _ .. . _ - - .. ~ . , . _., _ _ _

POINT BEACH NUCLEAP ?LANT Docket No. 50-266 -

Unit Name Point Beach. Unit 1 UNIT SHUTDOWNS AND POWER REDUCTIONS Date 2/5/97 Completed By B. J. Vander Velde *

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REPORT MONTH JANUARY - 1997 Telephone No. 414rl55-6681 Method of Licensee Event .

Duration Reactor Report No. System Component Cause and Corrective Action '

No. Date Type' (Hours) Reason' Shut Down' Code' Code' To Prevera Recurrence

+

5 970131 F 0 H 5 NA XX XXXXXX The unit commenced a load reduction to allow plant conditions to support steam generator loop l

entry to support equipment operability determination on steam generator cubicle ductwork. '

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'F: Forced ' Reason: ' Method: ' Exhibit G - Instructions

, 5: 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 t G - Operational Error (explain) >

H - Other (explain) t I

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t I PBF-C328b .

(03-90) I

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' DOCKET NO. 50-266 UNIT NAME Point Beach Unit 1 DATE 2/5/97 COMPLETED BY B. J. Vander Velde TELEPHONE 414/755-6681 Unit 1 operated at an average of 448 MWe net for the January,1997 report period.

l The following Licensee Event Reports were submitted to the NRC in January 1997:

l Licensee Event Report 50-266/96-012-00, EDG Fuel Oil System Tests Not Performed In Accordanc e )

With Technical Specifications. j Licensee Event Report 50-266/96-013-00, Potential Common Mode Failure in 120 VAC.

Licensee Event Repon 50-266/96-014-00, Steam Generator Blowdown Sample Not Performed In Accordance With Technical Specifications.

I Licensee Event Report 50-266/96-015-00, Main Steam Safety Valve Lift Setpoints Exceed Design Basis l

Values.

l Safety-related maintenance included:

1. C-177 white computer mux input processor board replaced.
2. P-002B charging pump plexiglas and tygon tubing replaced.
3. CV-00313 A reactor coolant pump seal water return isolation insulated.
4. G-02 emergency diesel generator air start system header cleaned, skirting plate repaired, insulation fasteners repaired, and air stan motor rebuilt.
5. CS-00476 steam generator feedwater regulator control packing tightened.
6. P-032E service water pump bolts tightened.
7. G-01 air staner motor rebuilt.
8. P-032A-M service water pump motor repaired.
9. Y-31 white instrument distribution temporary power supply installed.

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10. P-032D-M service water pump bearings replaced.

I1. P-032A service water pump packing adjusted.

12. SI-030lR-01 containment spray pump discharge to spray nozzles gasket replaced.

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i OPERATING DATA REPORT DOCKET NO. 50-301 -

DATE: 02/05/97 ,

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: January - 1997 . ,
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 744.0 744.0 214,801.0
12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 185,987.6
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 233.9
14. HOURS GENERATOR ON LINE 0.0 0.0 183,508.3
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 302.2
16. GROSS THERMAL ENERGY GENERATED (MWH) 0.0 0.0 263,605,007.0
17. GROSS ELECTRICAL ENERGY GENERATED 0.0 0.0 89,603,310.0
18. NET ELECTRICAL ENERGY GENERATED (MWH) 0.0 (1,641.0) 85,409,942.5
19. UNIT SERVICE FACTOR 0.0% 0.0% 85.4 %
20. UNIT AVAILABILITY FACTOR 0.0% 0.0% 85.6 %
21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0% -0.5 % 81.5 %
22. UNIT CAPACITY FACTOR (USING DER NET) 0.0% -0.4 % 80.0 %
23. UNIT FORCED OUTAGE RATE 0.0% 0.0% 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:

03/05/97 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 AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach. Unit 2 MONTH JANUARY - 1997 DATE 2/5/97 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 -2 2 -2 12 -2 22 -2 3 -2 13 -2 23 -2 4 -2 14 -2 24 -2 5 -2 15 -2 25 -2 6 -3 16 -2 26 -3 7 -2 17 -2 27 -2 8 -2 18 -2 28 -2 9 -2 19 -2 29 -2 10 -2 20 -2 30 -2 31 -2

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POINT BEACH NUCLEAR PLANT Docket No. 50-301 Unit Name Point Beach. Unit 2 UNIT SHUTDOWNS AND POWER REDUCTIONS Date 2/5/97 Completed By B. J. Vander Velde

Method of Licenace Evers -

Duration Reactor Report No. System Component Cause and conective Action  ;

No. Date Type' (Hours) Reason

  • Shut Down' Code' Code' To Prevent Recurrence .  !

4  % I005 S 744.0 C 1 NA NA NA Scheduled refueitug and maintenance (U2R22). Major work items include: Replacing both Unit 2 aream generators; main control board wire separation resolution; replace 8 main steam ,

condenser valves; HP turbine crossunder piping; repair service water west header; replace boric acid and reactor makeup water totalizers; replace safety injection accumulator level transminers; modify XO2, X03, and XO4 transformer metering and relay circuits; and exciter modification.

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'F: Forced Reason: ' Method: ' Exhibit G - Instructions l

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 .

5 - Reduced lead Licensing Exam F - Administrative 6 - Other (explain) ' Exhibit I - Same Source l G - Operational Error (explain)

H - Other (explain)

PBF-CD28b (0340)

DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 DATE 2/5/97  !

COMPLETED BY B. J. Vander Velde TELEPHONE 414/755-6681 i

Unit 2 was in a refueling outage during the entire January,1997 report period.

Safety-related maintenance included:

1. P/P-00626 reactor heat removal heat exchanger bypass flow control positioner pilot valve replaced.
2. FT-00464 steam generator flow transmitter valve replaced.
3. FT-00465 steam generator flow transmitter valve replaced.
4. FT-00474 steam generator flow transmitter valve replaced.
5. FT-00475 steam generator flow transmitter valve replaced.
6. RC-00502 reactor coolant loop 'a' cold leg piping supports tightened.
7. PT-00468 steam generator pressure transmitter removed from service.
8. PT-00469 steam generator pressure transmitter cable replaced.
9. PT-00478 steam generator pressure transmitter cable replaced.
10. PT-00479 steam generator pressure transmitter cable replaced. )
11. PT-0482 steam generator pressure transmitter cable replaced.
12. PT-00483 steam generator pressure transmitter cable replaced.
13. LT-00461 steam generator level transmitter cable replaced. ,

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14. LT-00462 steam generator level transmitter cable replaced.
15. LT-00463 steam generator level transmitter cable replaced.
16. LT-00471 steam generator level transmitter cable replaced.

- 17. LT-00473 steam generator level transmitter cable replaced.

18. LT-00479 steam generator level transmitter cable replaced.
19. SI-00844A-S safety injection accumulator drain solenoid installed. ,

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20. WL-01003B-O reactor coolant drain tank pump suction valve replaced.

i j 21. B-03 480V safeguards load center changed.

I i- 22. HS-34 main steam line east snubber replaced. ,

i l 23. HS 35 main steam line west snubber replaced.

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24. HS-36 steam generator north side snubber replaced.
25. HS-37 steam generator middle side snubber replaced.
26. HS-38 steam generator south side snubber replaced.

4 l 27. P-001B-M reactor coolant pump motor hose replaced.

i 28. CC-00747B evaporator component cooling outlet reliefvalve rebuilt. ,

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29. MS-00217A steam generator blowdown line drain piping and valves replaced.
30. CC-00814B safety injection pump seal water heat exchanger shell side outlet flange c!eaned.

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31. SI-00834D safety injection accumulator nitrogen inlet check valve replaced. ,
32. B52-427M auxiliary feedwater pump suction from service water control power transformer replaced.

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33. B52-423F refueling water storage tank outlet control power transformer replaced.
34. B52-323F refueling water storage tank outlet control power transformer replaced. L
35. B52-425J safety injection pump suction control power transformer replaced.
36. B52-425F safety injection pump suction control power transformer replaced. >
37. B52-325J volume control tank outlet thermal overboard device replaced.
38. B52-321M containment spray pump control power transformer replaced.

' 39. B52-327J reactor coolant loop control power transforme,r replaced.

40. B52-3210J charging pump control power transformer replaced.
41. B52-421M containment spray pump discharge control power transformer replaced.
42. B52-422M containment spray pump discharge control power transformer replaced.
43. B52-423J containment spray pump suction control power transformer replaced.
44. B52-423M containment spray pump suction control power transformer replaced.
45. SI-00825A refueling water storage tank outlet cleaned.
46. SI-00896A safety injection pump suction cleaned.
47. SI-00878D safety injection pump loop 'a' injection tested.
43. MS-02005 steam generator steam header safety foreign material exclusion inspected.

49.1/RH-00700 reactor heat removal pump suction header control switch replaced.

50. VNPSE-03244 purge supply for discharge valve replaced.
51. A-06 4.16kV bus switchgear foreign material exclusion inspected.
52. Pipe SI-0903R-01 nitrogen supply to accumulator relief valve installed.
53. SI-01425 safety injection accumulator nitrogen header valve packing replaced.
54. SI-00825B refueling water storage tank outlet valve cleaned.
55. SI-00896B safety injection pump suction cleaned.
56. P-015A safety injection pump adjusted.

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