ML20134J871
| ML20134J871 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| 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) | |
Text
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' Electnc POWER COMPANY Point Beoch Nuclear Plant 6610 Nuclear Rd.Two Rivers.WI 54241 2
(414) 755-2321 PBL 97-0041 l
l 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
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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 REPORT MONTH JANUARY - 1997 Telephone No.
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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
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5 NA XX XXXXXX The unit commenced a load reduction to allow plant conditions to support steam generator loop l
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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 G - Operational Error (explain) t H - Other (explain) t I
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PBF-C328b (03-90)
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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.
The following Licensee Event Reports were submitted to the NRC in January 1997:
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.
Licensee Event Report 50-266/96-015-00, Main Steam Safety Valve Lift Setpoints Exceed Design Basis Values.
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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-..m 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 REPORT MONTH JANUARY - 1997 Telephone No.
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.
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% I005 S
744.0 C
1 NA NA NA Scheduled refueitug and maintenance (U2R22). Major work items include: Replacing both
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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 2
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 Licensing Exam 5 - Reduced lead F - Administrative 6 - Other (explain)
' Exhibit I - Same Source l
G - Operational Error (explain)
H - Other (explain)
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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.
- 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.
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- 21. B-03 480V safeguards load center changed.
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- 22. HS-34 main steam line east snubber replaced.
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- 23. HS 35 main steam line west snubber replaced.
- 24. HS-36 steam generator north side snubber replaced.
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- 25. HS-37 steam generator middle side snubber replaced.
- 26. HS-38 steam generator south side snubber replaced.
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- 27. P-001B-M reactor coolant pump motor hose replaced.
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- 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.
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- 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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