ML20138J205
| ML20138J205 | |
| Person / Time | |
|---|---|
| Site: | Point Beach |
| Issue date: | 11/30/1985 |
| From: | Kay C, Krause C WISCONSIN ELECTRIC POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-85-129 VPNPD-85-550, NUDOCS 8512170458 | |
| Download: ML20138J205 (9) | |
Text
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OPERATING DATA REPORT DOCKET NO. 50-266 DATE December 9, 1985 COMPLETED BY C. U. KRAUSE TELEPHONE 414 277 2001 OPERATING STATUS
(
- 1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 1
. NOTES-
- 2. REPORTING PERIOD: NOVEMBER 1985 I
- 3. LICENSED THERMAL POWER (MWT): 1518.
- 4. NAMEPLATE RATING (GROSS MWE):
523.8
- 5. DESIGN ELECTRICAL RATING (NET MWE): 497.
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 509.
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 485.
- 8. IF CHAN6ES 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 720 8,016 132,096
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 6,230.4 106,729.0
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 4.7 634.4
[
- 14. HOURS GENERATOR ON LINE 720.0 6,175.3 104,162.8
(
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 1.5 804.0 i
- 16. 6ROSS THERMAL ENER6Y GENERATED (MWH) 1,090,719 9,099,101 142,048,078
- 17. GROSS ELECTRICAL ENER6Y GENERATED (MWH) 374,450 3,122,720 47,767,960 l
18.. NET ELECTRICAL ENERGY GENERATED (MWH) 358,496 2,984,387 45,450,535 l
- 19. UNIT SERVICE FACTOR 100.0 77.0 78.9
- 20. UNIT AVAILABILITY FACTOR 100.0 77.1 79.5
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 102.7 76.8 70.4
- 22. UNIT CAPACITY FACTOR (USING DER NET) 100.2 74.9 69.2
- 23. UNIT FORCED OUTAGE RATE 0.0 0.1 2.3 l
- 24. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)
None
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: NOT SHUTDOWN 66-a
~
o' DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DAIED SEPTEMBER 22, 1977
a UNIT SliUTDOWNS AND POWER REDUCTIONS DOCKET MO. 50-266 UNIT NAME point Beach Unit 1 DATE December 9, 1985 REPORT MONTil NOVEMBER COMPLETED BY C.
W.
Krause TELEPl!ONE 414/277-2001 m
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o4o Licensee Event mo ot Cause and Corrective Action N
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Report No.
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$0 To Prevent Recurrence Q-M gmg 8
oD F: Forced Reason:
3 Method:
Exhibit G-Instruc-S: Scheduled A-Equipment Failure (explain) 1-Manual tions for Prepar-B-Maintenance or Test 2-Manual Scram ation of Data Entry C-Refueling 3-Automatic Scram Sheets for IER File D-Regulatory Restriction 4-Other (explain)
E-Operator Training & License Exam F-Administrative 5 Exhibit I-Same
\\D-28B G-Operational Error (explain)
Source (01-78)
II-Other_ JexFplain)
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DOCKET'NO.
50f266 7 Point' Bead}j Unit 1 UNIT NAME.
,,2 DATE December 9, 1985 W."'KYa6sc
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COMPLETED BY C.
TELEPHONE 414/277-2001 f'.
'AVERhGE DAILY UNIT POWER LEVEL MONTII November, 1985 t
AVERAGE AVERAGE AVERAGE
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DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1
501 11 aqq 21 497 2
494 12 497 22 499 3
499 13 498 23 502 4
495 14 497 24 492 5
498 15 499 25 497 6
497 16 499 26 499 497 17 496 27 499 7
499 18 499 28 499 8
496 i
9 19 498 29 499 497 lo 20 497 30 498 31 N/A s
1 EQR-28a (01-79)
1 l
NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE Docket No.
50-266 l
Unit Name Point Beach, Unit 1 Date December 9, 1985' Completed By C.
W.
Krause Telephone 414/277-2001 i
Unit 1 operated at approximately 498 MWe net throughout the period with no significant reductions in load.
4 There,were no significant operating events and no LERs were issued for Unit 1 during this period.
l l
Safety-related maintenance included a check valve replacement modifi-cation to the auxiliary feed pump.
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OPERATING DATA REPORT DOCKET NO. 50-301 DATE December 9, 1985 COMPLETED BY C. W. KRAUSE TELEPHONE 414 277 2001 OPERATING STATUS
- 1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 2
. NOTES
- 2. REPORTING PERIOD: NOVEMBER 1985
- 3. LICENSED THERMAL POWER (MUT): 1518.
- 4. NAMEPLATE RATING (GROSS MWE):
523.8 5.-DESIGN ELECTRICAL RATING (NET MUE): 497.
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 509.
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 485.
- 8. IF CHANGES DCCUR IN CAPACITY RA7INGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
NOT APPLICABLE e
- 9. POWER LEVEL TO UHICH RESTRICTED, IF ANY (NET MUE): NOT APPLICABLE
- 10. REASONS FOR RESTRICTIONS, (IF ANY): NOT APPLICABLE THIS MONTH YR TO DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 720 8,016 116,881
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 192.0 6,846.0 102,818.4
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 207.1
- 14. HOURS GENERATOR ON LINE 145.0 6,795.0 101,104.4
- 15. UNIT RESERVE SHUTDOWN HOURS 35.0 35.0 233.1
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 95,661 10,093,567 141,846,539
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 32,290 3,432,390 48,072,530
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 26,963 3,275,302 45,786,707
- 19. UNIT SERVICE FACTOR 20.1 84.8 86.5
- 20. UNIT AVAILABILITY FACTOR
'25.0 85.2 86.7
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 7.7 84.2 79.8
- 22. UNIT CAPACITY FACTOR (USING DER NET) 7.5 82.2 78.8
- 23. UNIT FORCED OUTAGE RATE 0.0 0.0 1.3
- 24. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
NONE
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: NOT SHUTDOWN DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977
UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 DATE December 9, 1985 REPORT MONTil November. 1985 COMPLETED BY C.
W.
Krause TELEPilONE 414-277-2001 m
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Date g
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851005 S
573.3 C
1 N/A ZZ ZZZZZ:
Refueling Shutdown 2
851125 S
2.1 B
4 N/A ZZ ZZZZZ:
Unit removed from service for turbine overspeed testing F: Forced Reason:
3 4
Method:
Exhibit G-Instruc-S: Scheduled A-Equipment Failure (explain) 1-Manual tions for Prepar-B-Maintenance or Test 2-Manual Scram ation of Data Entry C-Refueling 3-Automatic Scram Sheets for LER File D-Regulatory Restriction 4-Other (explain)
E-Ocerator Training & License Exam F-Administrative 5 Exhibit I-Same 4D-28B G-Operational Error (explain)
Source (01-78) m-c6nhere (cmpRmAm)
__.~ __
DOCKET NO.
50-301 UNIT NAME Point Beach Unit 2 j
DATE December 9, 1985 COMPLETED BY-C.
W.
Krause TELEPHONE 414/277-2001 AVERAGE DAILY UNIT POWER LEVEL MONTH November, 1985 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
-10 2
-2 12
-2 22
-12 3 13
-2
'23
-14 4
-2 14
-2 24
-9 5
-2 15
-1 25 86 6
-2 16
-3 26 126 7
-2 17
-4 27 127 8
-2 18
-8 28 135 9
-2 19
-9 29 317
-2 20
-12 30 441 10 31 N.i A.
4 EQR-28a 4
(01-79)
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- NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE Docket No. 301-Unit Name Point Beach, Unit 2 Date December 9, 1985 l
Completed By C. W.
Krause Telephone 414/277-2001 At the beginning of-the period, the unit was shut down undergoing j
a scheduled refueling and maintenance outage.
The outage was completed and on November 22, the reactor was taken critical.
On November 24, the generator was placed on line.
The following day, the generator was taken off line temporarily for overspeed testing.
At the end of the period, power output was limited to 88% due to standard post-refueling new fuel conditioning, t
Steam generator eddy _ current testing during the outage revealed that 10 tubes of the "A" steam generator and 44 tubes of the "B" steam generator required plugging.
LER-85-003 was written to document the circumstances of the condition.
i As mentioned in the October monthly report, a failed fuel rod was i
found in two fuel assemblies (L56 and L59).
It is believed that
- fuel. failure was' caused by fuel rod vibration resulting in fretting wear at the fuel rod grid supports.
The fuel rod vibration was caused by water jetting through several core baffle plate joint openings impinging upon the failed fuel rods.
A visual inspection of the lower core support plate revealed pieces of fuel pellets which had come from the failed fuel rods.
Actions were taken to remove loose fuel pieces.
LER 85-004 has been written for this incident.
l
- Safety-related maintenance included a modification to the incore
[
detector system that changed the cover gas from carbon. dioxide to helium in an effort to minimize detector tube corrosion.
- Also, additional. manual reactor trip pushbuttons were installed and main control board cabling was rerouted to' provide train separation for manual reactor trip.
Reactor' trip bypass breaker indications l
were also installed on the main control board.
Other safety-related maintenance included the' replacement of four split pins and the repair of a' loose instrument guide tube.found at the bottom nozzle of a fuel assembly.
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r Msconsin Electnc eona couraur 231 W. MICHIGAN, P.0, 8012046. MILWAUKEE, WI 53201 VPNPD-85-550 NRC-85-129 December 10, 1985 Director of Nuclear Regulatory Operations U. S. NUCLEAR REGULATORY COMMISSION Washington, D.
C.
20555 Gentlemen:
MONTHLY OPERATING REPORTS POINT BEACH NUCLEAR PLANT Attached are monthly operating reports for Units 1 and 2, Point Beach Nuclear Plant, for the calendar month of November 1985.
Very truly yours, Ou)'h, y
C. W.
Fay Vice President Nuclear Power Attachments Copies to R.
S. Cullen, PSCW J.
G. Keppler, NRC Region III NRC Resident Inspector 6
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