ML20006A506
| ML20006A506 | |
| Person / Time | |
|---|---|
| Site: | Point Beach |
| Issue date: | 12/31/1989 |
| From: | Krause C WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20005G904 | List: |
| References | |
| NUDOCS 9001290046 | |
| Download: ML20006A506 (7) | |
Text
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OPERATING DATA REPORT-i
-DOCKET NO. 50-266.
L DATE January 5,.1990 COMPLETED BY C. W.'KRAUSE TELEPHONE 414 221 2001 OPERATING ST*TUS
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- 1. UNIT NAME:
POINT BEACH NUCLEAR PLANT UNIT 1
. NOTES.
- 2. REPORTING PERIOD:
DECEMBER 1989
- 3. LICENSED THERMAL POWER (MWT):
1518.5.
- 4. NAMEPLATE RATING (GROSS MWE):
523.8
- 5. DESIGN ELECTRICAL RATING (NET MWE):
497.
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MNE}:
509.
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):
485.
8.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
NOT APPLICABLE
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE). NOT APPLICABLE
- 10. REASONS FOR RESTRICTIONS, (IF ANY):
NOT APPLICABLE THIS MONTH
.YR TO DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 744 8,760 167,904
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 7,728.3 138,343.8
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- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 652.7
- 14. HOURS GENERATOR ON LINE 744.0 7,706.8 135,539.3
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 837.9
'I
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1,124,510 11,125,568 188,468,392
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 381,630 3,775,640 63,604,690
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- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 365,895 3,606,223 60,590,691
- 19. UNIT SERVICE FACTOR 100.0 38.0 80.7 i
- 20. UNIT AVAILABILITY FACTOR 100.0 88.0 81.2
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 101.4 84.9 74.0
- 22. UNIT CAPACITY FACTOR (USING DER NET) 99.0 82.8 72.6
- 23. UNIT FORCED OUTAGE RATE O.0 0.0 1.8
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
Fifty day refueling and maintenance outage scNduled to commence March 31, 1990.
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, E.e'tIMATED DATE OF STARTUP:
NOT SHUTDOWN
~l DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977 9001290046 900109 PDR ADOCK 05000266 R
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JhQlI DOCKET NO.. 266
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UNIT NAME~
Point' Beach, Unit li ~
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DATE
' January 5, 1990-i.
COMPLETED BY-C. W. Krause TELEPHONE.
"414/221-2001 AVERAGE DAILY UNIT POWER LEVEL l
l MONTH DECEMBER ~1989 AVERAGE
' AVERAGE AVERAGE DAILY-DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe' NET DAY MWe NET DAY MWe NET 1
496 11 495 21-492-2 495 12 494 22 492 3
475 13 495 23 492 4
495 14 495 24 493 5
496 15 495 25 488-6 496 16 494 26 493 7
495 17 495 27 493 8
494 18 493 28 494 9
496 19 493 29 493 10 471 20 492 30 494 31 473 EQR-28a (04-86)
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UNIT SHUTDOWNS'AND POWER: REDUCTIONS.
DOCKET NO.?
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450 266-O
~ Point Beach Unit'l W UNIT:NAME..
.DATE.
January-5,.1990--
. REPORT MONTH DECEMBER ^1989
- COMPLETED.BY C. W. Krause:
TELEPHONE 414/221-2001 o
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Date 8 $d O$ 0 Licensee Event N3 O'E Cause &" Corrective. Action H
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go go To Prevent Recurrence E.c vs 1F:
Forced 2 Reason:
3 Method:
4 Exhibit F-Instructions, S:
Scheduled A - Equipment Failure (explain) 1 -' Manual for preparation 'of B - Maintenance or Test 2 - Manual Scram data entry. sheets C - Refueling' 3 - Automatic Scram-LER file (NUREG-0161) l D - Regulatory Restriction 4 - Continuation of
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E - Operator Training &
Previous Shutdown l
Licensing Exam 5 - Reduced ~ Load SExhibit H-Same. Source F - Administrative 6 - Other-(explain)-
G - Operational Error (explain)
H --Other (explain)
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SUMMARY
OF OPERATING EXPERIENCE
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Docket!No.
50-266 L
Unit Name Point Beach Unit 1
~Date January 5, 1990
) Completed By C. W. Krause i
Telephone 414/221-2001
. Unit 1 operated at approximately 494 MWe net throughout the D
' period with no significant load reductions.
Primary to secondary leakage was stable at a detectable rate.
'On December 10,-1989, the No. 2 turbine governor valve closed when a relay card in the governor electro-hydraulic system failed.
The valve closing. caused a' change in power which was sensed by the reactor.
This initiated a-false " control rod drop" signal
.and subsequently-turbine power self-adjusted to approximately 410 MWe, o
After seven-hours of investigation and corrective maintenance, the unit returned to full power operations.
Safety related maintenance conducted during the period included:
. packing adjustments to service water pump P-32C; calibration of auxiliary feedwater flow transmitters.FT-4007 and FT-4014; modifications to~DYOC and DYOD inverter transfer switches; repairs.to pressurizer spray valve controller HC-431H; repairs to auxiliary feedwater pump bearing cooling supply solenoid valve;
' repairs 1to a tube-leak on emergency diesel glycol cooler HX-55B; seal and outboard bearing replacement on component water cooling pump P-11B; and the restoration of a yellow bus power supply to residual heat removal controller instrument ~HC-626.
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OPERATING DATA,REPCRT-
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DOCKET! NO.E 50--301 m
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DATE: January 5, 1990
. COMPLETED.BY C. W.
KRAUSE
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TELEPHONE
'414-221 2001 OPERATING STATUS
- 1. UNIT NAME:
POINT BEACH NUCLEAR PLANT UNIT 2
. NOTES
- 2. REPORTING PERIOD:
DECEMBER 1989
- 3. LICENSED THERMAL POWER (MWT):- 1518.5
- 4. NAMEPLATE RATING (GROSS MWE):
'523.8
- 5. DESIGN ELECTRICAL; RATING (NET MWE):- 497.
- 6. MAXIMUM DEPENDABLE CAPACITY-(GROSS MWE):
509.
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- 7. MAXIMUM DEPENDABLE CAPACI'IT (NET MNE):
485.
........................ ~.
8.
IF CHANGES OCCUR IN CAPACITY RATINGS-(ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
NOT APPLICABLE
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
NOT APPLICABLE
- 10. REASONS FOR RESTRICTIONS,-(IF ANY):
NOT' APPLICABLE THIS MONTH YR TO DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 744 8,760
-152,689
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 7,243.6 133,345.8
- 13. REACTOR RESERVE SHUTDONN HOURS 0.0 0.6
-216.7
- 14. HOURS GENERATOR ON LINE 744.0 7,108.7 131,205.3
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 4.8 302.2
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1,123,322 10,637,702 186,583,536
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- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 387,780 3,651,520 63,325,220
- 18. NET ELECTRICAL ENERGY GENERATED (MNH)-
.371,856 3,484,188 60,338,610
- 19. UNIT SERVICE FACTOR 100.0 81.1 85.9 i
- 20. UNIT AVAILABILITY FACTOR 100.0 81.2 86.1 l
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 103.1 82.0 80.7
- 22. UNIT CAPACITY FACTOR (USING DER NET) 100.6-80.0 79.5-
- 23. UNIT FORCED OUTAGE RATE O.0 1.8 1.2
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND' DURATION OF EACH):
l NONE I
i
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
NOT SHUTDONN
- l DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977
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UNIT: SHUTDOWNS AND' POWER REDUCTIONS DOCKET NO.-
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55--301 E C
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E TUNIT NAME J JPoint Beach Unit 2 9
.DATE-January 5,.?.990-
' REPORT MONTH! DECEMBER 1989
- COMPLETED BYa C. -W.
Krause=
TELEPHONE'.
414/221-2001-J.
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Forced 2 Reason:
3 Method:
4 Exhibit F-Instructions S:
Scheduled A - Equipment Failure (explain) 1 Manual for preparation of-B - Maintenance or Test-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 Load.
sExhibit H-Same Source-F - Administrative 6 - Other (explain)
G - Operational' Error (explain)
H -'Other-(explain).
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NARRATIVE-
SUMMARY
OF OPERATING ~ EXPERIENCE
. Docket No.o 50-301
'- /
. Unit,Name
' Point Beach Unit'2 Date January 5, 1990 Completed By-C.'W. Krause Telephone:
414/221-2001 Unit 2 operated at approximately 501 MWe net throughout'the j
period with no-significant load reductions.
Primary to secondary leakage was less than one-gallon per day.
On December 5, 1989; the unit surpassed 63 billion KWh of
+
generation.
'i i On' December 11, 1989, two maintenance workers received first and second~ degree burns from hot 1 water and steam while conducting
~
n corrective maintenance on a: heater drain pump discharge check valve...The workers were transported to a local hospital for
, evaluation and treatment.
-Safety related maintenance conducted during the period included:
L calibration of four " Bank D" rod insertion limit modules; gasket i
replacement of component cooling water check valve 2-724B; tightening.the' flange of CVCS temperature control valve
_2-TCV-130; calibration of reactor coolant loop A flow
-transmitters FT-411 and FT-413; repairs to pressurizer pressure
- bistable'PC-430E/F; limit switch adjustments to safety injection
" valve-motor operator 2-827A; and analysis of a vibration problem
'on~ residual. heat removal pump 2-P-10B.
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