ML20042A443
| ML20042A443 | |
| Person / Time | |
|---|---|
| Site: | Point Beach |
| Issue date: | 04/08/1981 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20042A440 | List: |
| References | |
| NUDOCS 8203230423 | |
| Download: ML20042A443 (8) | |
Text
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OPERATING DAIA REPOR1 DOCKET NO. 50-266 DATE April 8,'1981 u
i gy COMPLETED BY C. W. FAY 00 TELEPHONE 414 277 2811 tJ OPERATING STATUS ogg oo
- 1. UNIT NAME: POINT BEACH NUCLEAR FLANT UNIT 1
. NOTES 38f 2.
REPORTING PERIOD:
MARCH 1981 ggta
- 3. LICENSED THERMAL POWER (NUT): 1518.
- 4. NAMEPLATE RATING (GROSS MWE):
523.8
- 5. DESIGN ELECTRICAL RATING (NET MWE): 497.
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 519.
- 7. MHAIMUM DEPENDABLE CAPACITY (NET MWE): 495.
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
NOT APPLICABLE 9.' POWER LEVEL TU UHICH RESTRICTED. IF ANY (NET MUE):
390.0
- 10. REASONS FOR RESTRICTIONS. (IF ANY): MMK4RTHEMMggig Power restriction is the result of a self-imposed reduction in core average temperature in an attempt to inhibit corrosion of steam generator tubes within the tubesheet crevice.
THIS MONTH YR TO DATE CUMULAllVE
- 11. HOURS IN REPORTING PERIOD 744 2,160 91,176
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 741.0 2,157.0
/b,591.8
- 13. REACluR RESERVE SHUTDOWN HOURS 0.3 0.3 606.0
- 14. HOURS GENERATOA 04 LINE 735.0 2,151.0 73,287.9
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 144.3
- 16. GROSS THERMAL ENERGY GENERATED (MUH) 885,413 2,576,863 101,415,307
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 287,220 838,240 34,097,960
- 18. NET ELECTRICAL tNERGY GENERATED (NWH) 272,616 795,734 32,463,020
- 19. UNIT SERVICE FACTOR 58.8 99.6 80.4
- 20. UNii AVAILABILITY FACTOR 98.8 99.6 81.2
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 74.0 74.4 7J.0
- 22. UNIT CAFACle r F ACluR (USING DER NET) 73.7 74.1 71.6
- 23. UNIT FORCED OUTAGE RALE
-1.2 0.4 3.2
- 24. SHUTDOLHS SCHEDULED OVER NEXT 6 MONTHS (TYPE, 9 ATE, AND DURATION OF EirH):
Steam generator eddy current inspection June 19, 1981, expected to last from two to four weeks.
- 25. IF bHu DOUN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP: NOT SHUTDOWN A
DATA REe0RTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBEh 22, 1977 l
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e OPERATING DATA REPORT DOCKET NO. 50-301 DATE April 8, 1981 i
COMPLETED BY C. W. FAY TELEPHONE 414 277 2811 UPERATING STATUS
- 1. UNIT NAME: POINT BEACH NUCLEAR PLANT t! NIT 2
. NOTES
- z. REPORTINU PERIOD:
MARCH 1981
- 3. LICENSED THERMAL POWER (MWT): 1518.
- 4. NAMEPLATE RAIING LGh0S$ MWE):
523.8
- 5. DESIGN ELECTRICAL RATING (NET MWE): 497.
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 519.
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 495.
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPURT, GIVE REASONS:
NOT APPLICABLE 9.' POWER LEVEL TO UHICH RESTRICTED, IF ANY (NET MWE): WOT APPLICABLE
- 10. REASONS FOR RESTRICTIONS, (If ANf): NOT APPLICABLE THIS MONTH YR 'TO DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 744 2,160 75,961
- 12. NUMBER OF HOURS REAC1bR WAS CRITICAL 744.0 2,160.0 68,710.0
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 186.3
- 14. HOURS GENERATOR ON LINE 744.0 2,160.0 67,458.5
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 123.9 1.6. GKUSS THERMAL ENERGY GENERATED (MuH) 1,112,552 3,236,340 92,024,086
- 17. DROSS LLECTRICAL ENERGY GENERATED (MWH) 378,350 1,094,120 31.217,970
- 18. NET ELECiRICAL ENERGY GENERATED (MWH) 362,115 1,047,432 29,710,853
- 19. UNIT SERVICE FACTOR 100.0 100.0 88.8
- 20. UNIT AVAILABILITY FACTOR 100.0 100.0 89.0
- 21. UNIT CnrACITY FACTOR (USir4G MDC NET) 98.3 98.0 79.7
- 22. UNIT CAPACITY FACTOR (USING DER NET) 97.9 97.6 78.7
- 23. UNIT FORCED OUTAGE RATE 0.0 0.0 1.5
- 24. SHUTDOWNS SCHEDULED OVER NExi 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
Refueling shutdown April 17, 1981, expected to last approximately five weeks.
- 25. IF SHUTDOWN AT END OF REPORI PERIOD, ESTINATED DATE OF STARTUP: NOT SHUTDOWN DATA REPOR(tD AND FACTORS CALCULATED Ab RLuuESTED IN NRC LETTER DATED SEPfEP.ER 22, 1977 l
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I
DOCKET NOo 50-266 UNIT NAME Point Beach Unit 1 DATE Ap ril 8, 1981
. COMPLETED BY C.
W.
Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH March, 1981 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY
_MWe NET 1
373 11 374 21 176 2
375 12 374 22 179 3
376 13 375 23 177 4
372 14 375 24 177 5
373 15 35 3 25 374 6
374 16 374 26 378 7
376 17 375 27 374 8
375 18 375 28 376 9
375 19 375 29 376 10 375 20 377 30 373 31 128 AD-28A
( 1-7,7 )
i l f
DOCKET NO.
50-301 UNIT NAME Point Beach Unit 2 DATE Acril 8,
1981 COMPLETED BY C.
W.
Fav TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH March. 1981 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1
488 11 487 21 489 2
489 12 486 22 487 3
490 13 482 23 485 4
489 14 476 24 485 5
489 15 487 25 484 6
489 16 488 26 487 7
489 17 488 27 485 8
479 18 490 28 490 9
487 19 491 29 489 10 485 20 489 30 486 31 484 AD-28A i
(1-77) w ra h.
L
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-266 UNIT NAME Point Beach Unit 1 DATE Ac ril 8.
1991 REPORT MONTH March, 1981 COMPLETED BY C.
W.
Fav TELEPHONE 414/277-2811
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o4o Licensee Event mo ot Cause and Corrective Action N
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Report No.
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IO To Prevent Recurrence ca -
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1 810331 F
9 B
3 N/A ED ENSTRO Failure of Unit 1 turbine generator voltage regulator.
Voltage regulator was re'p ai re d.
i p.
I F: Forced Reason:
3 4
Method:
Exhibit G-Instruc-S: Scheduled A-Equipment Failure (explain) l-Manual tions for Prepar-B-Maintenance or Test 2-Manual Scram ation of Data Entry C-Refueling 3-Automatic Scram Sheets for LER File i
l D-Regulatory Restriction 4-Other (explain)
E-Operator Training & License Exam F-Administrative E Exhibit I-Same AD-28B g
Operational Error (explain)
(01-78)
. Source H-Other (explain) i w' A
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UNIT SHUTDOWNS AND POWER' REDUCTIONS DOCKET NCs. 50-301 UNIT NAME Point Beach Unit 2 REPORT MONTH March, 1981 COMPLETED av TELEPHONE 414/277-2811 _
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Date g
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{'g Cause and Corrective Action e
am o
ex Report No.
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8 1 F: Forced Reason:
Method:
Exhibit G-Instruc-S: Scheduled A-Equipment Failure (explain) l-Manual tions for Prepar-B-Maintenance or Test 2-Manual Scram ation of Data Entry; C-RLZueling 3-Automatic Scram Sheets for LER Filef D-Regulatory Restriction 4-Other (explain)
, (NUREG-OlGl)
E-Operator Training & License Exam F-Administrative 5
AD-28B Exhibit Same G-Operational Error (explain)[
! Source (01-78)
H-Other (explain) s t
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NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE Docket No.
50-266 Unit Nane Point Beach Unit 1 Date April 8, 1981 Completed By C. W.
Fay Telephone 414/277-2811 Unit 1 operated at 375 MWe net throughout the period with one reactor trip and two power reductions.
On March 15,19 81, at 0 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, Unit 1 power was reduced to 265 MWe to perform turbine stop valve testing.
After successful completion of turbine stop valve testing, Unit 1 was returned to 375 MWe at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> the same day.
While Maintenance personnel were trying to remedy voltage regulator problens on Unit 1 turbine generator, a reactor trip occurred at 0051 hours5.902778e-4 days <br />0.0142 hours <br />8.43254e-5 weeks <br />1.94055e-5 months <br /> on March 31, 1981.
The reactor trip occurred as a direct result of a generator trip followed by a turbine overspeed trip.
The unit was returned to service after a slight delay while repairing an air leak in the heater drain tank at 0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br /> on March 31, 1981.
At 1248 hours0.0144 days <br />0.347 hours <br />0.00206 weeks <br />4.74864e-4 months <br /> on March 31, 1981, Unit 1 power was reduced to 148 MWe to repair a body-to-bonnet leak on a feedwater heater drain line check valve.
Tha unit was restored to full load at 0150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> on
~
April 1, 1981.
While performing ICP 2.15, Reactor System Logic Periodic Test, prior to reactor startup of Unit 1, a defective reactor trip relay, 1RT7A, was discovered failed in the conservative direction.
The relay was replacei on March 31, 1981.
An investigation into this Westinghouse BFD relay failure is being pursued.
This was not a reportable occurrence.
Following a DC power failure alarm, the field failure alarm relay for 3D Diesel was discovered to be defective at 1120 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.2616e-4 months <br /> on March 28, 1981.
The Diesel was taken out of service at 1120 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.2616e-4 months <br /> to replace the alarm relay and was restored to service at 1658 hours0.0192 days <br />0.461 hours <br />0.00274 weeks <br />6.30869e-4 months <br />.
This occurrence is reportable by a 30 day written report in accordance with Technical Specificatien 15.6.9.2.B.2 as a condition leading to operation in a degraded mode permitted bY a limiting condition of operation.
Safety-related maintenance for this period included rebuilding the spare charging pump varidrive unit, installation of temporary technical support center instrumentation, replacement of reactor trip relay 1RT7A and 3D Diesel field failure alarm relay as described previously.
O
NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE Docket No.
50-301 Unit Name Point Beach Unit 2 Da te April 8, 1981 Completed By C. W.
Fay Telephone 414/277-2811 Unit 2 operated at 490 MWe net throughout the period with two load reductions.
On March 8, 1981, at 0240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />, Unit 2 power was lowered to 320 MWe to perform turbine stop valve testing.
Af ter successful completion of turbine stop valve tes ting, Unit 2 was restored to 495 MWe at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> the same day.
At 2145 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.161725e-4 months <br /> on March 13, 1981, shortly after placing "A"
deborating demineralizer on the line, ave rage reactor coolant tempereture dropped 50F.
Imme diately following the temperature drop, Lait 2 power was lowered to 39 5 MWe,
"A" deborating demineralizer was taken out of service,
and "B"
deborating demineralizer was placed in service.
After a brief investigation, it was de termined that the " A" deborating domineralizer was boron saturated.
Unit 2 power was restored to 4 90 MWe at 0205 hours0.00237 days <br />0.0569 hours <br />3.38955e-4 weeks <br />7.80025e-5 months <br /> on March 14, 1981.
During the performance of ICP 2.1, Periodic Testing of Uni t 2 Reactor Protection and Safeguards Analog Systems, the setpoint of loop " A" steam generator pressure channel 482A was found to be 3.46% lower than that required by Technical Specification Table 15. 3.5-1 on March 24, 1981, at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />.
The channel was deemed inoperable by Technical Specification definition and reportable under Technical Specification
- 15. 6. 9. 2. B.1 as a 30 day report.
The alarm bistable was replaced and the setpoint adjusted on March 24, 1981.
This occurrence will be filed under Licensee Event Report No.
81-001/03L-0.
Sa fe ty-rela te t maintenance included the repair of Unit 2 blowdown radiation monitor and loop " A" steam generator pressure alarm bistable discussed previously.
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