ML20077P121
| ML20077P121 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/31/1991 |
| From: | Fay C, Peterson D WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-91-081, CON-NRC-91-81 VPNPD-91-275, NUDOCS 9108150260 | |
| Download: ML20077P121 (9) | |
Text
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, WISCONSIN 1Electnc POWER COMPAtJY nt w Mengan to b 2045.Musee wurci term i23e VPNPD-92-275 NRC-91-081 August 12, 1991 U.
S.
NUCLEAR REGULATORY COMMISSION Document Control Desk Mail Station F1-137 Washington, D.
C.
20555 Gentlement DOCKETS 50-266 AND 50-301 MONTIILY OPERATING REPORTH POINT BEAQI NUCLEAR PIANT, UNITS 1 AND 2 Attachod are monthly operating reports for Units 1 and 2, Point Beach Nuclear Plant, for the calendar sonth of July 1991.
Very truly yours, ff:
i C. W. Fay Vice President-Nuclear Power Attachments Copies to L.
L.
Smith, PSCW NRC Regional Admini'..ator, Region III NRC Resident Inspector
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i
s POINT BEACH NUCLEAR PIANT DOCKETNO.
R)-266 AVERAGE DAILY UNIT POWTR LEVEL UNIT NAAfE Peid Beach. Unit I ~
5 MONTH JULY - 1991 DATE Auctst 7.1 31 ~
CO5tPLETED BY J. T. Fdrc%n TFI FFHONE
_414 M S-2221 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY SfWe NET DAY SfWe NET 1
As7 11
- 7 21 495 2
495 12 ASR 22 493 3
495 13 4S5 23
- 24 4
496 14 495 24
- C 5
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495 16 4M 26 455 7
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- 32 19 494 29 485 10 493 20 4'11 30 444 31 493 PBF4X72Sa (03-90)
A POINT BEACH NUCLEAR PLANT Docket No.
% 266 Unit Name Point Beadt Unit 1 UNIT SHITTDOWNS AND POWER REDUCTIONS Date Atwee 7. LW1 Completed By D. C Petersen REPORT MONTH JULY - 191 Telephone No.
414n55222L Ext. MI Method of Shumng No.
Date Type' Duratme Reason Down Innsee Exat System Cw ponent Came and Comctree Actme
'F: Forced Reason-
' Method:
' Exhibit G - Instructions 2
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 Trainmg &
Presions Shutdm Licensing Exam 5 - RMuced Load F-Administratim 6 - Other (explain)
' Exhibit I - Same Source G - Operational Error (explain)
H - Other (explain)
PBF-632Sb (EU)
4 DOCKET NO.
50-266 UNIT NAME Point Beach Unit i DATE August 8, 1991 COMPLETED BY D.
C.
Peterson TELEPHONE 414/755-2321, Ext. 361 1
Unit 1 operated at approximately 489 MWe not throughout this report period with no rignificant load reductions.
Unit 1 experienced a reportable event in accordance with 10CFR50.73 (1 LER 91-009).
On July 27, a nuclear instrumentation power chonnel 1N44 spiked high, then returned to normal causing a turbine 7/unback with associated reactor protection rod drop rod stop signal.
1N44 was removed from service, checked, no fault found, and returned to service.
Safety-related maintenance included calibration, filling and venting of the electric auxiliary feedwater pumps discharge flow transmitters FI-4007 and FI-4014; reple. ed gasket to stop body to bonnet leak on auxiliary feedwater pumi overspeed trip valve 1MS-2002; inspecting the main feedwater pump 1P-29 outboard bearing.
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OPERATING DATA REPORT DOCKET No. 50-301 DATE: August 7, 1991 COMPLETED BY:
D. C. Peterson TELEPHONE 414/755 2321, Ext. 361 OPERATING GTATUS
- 1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 2
. NOTES
- 2. REPORTING PERIOD:
JULY 1991
- 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.
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):
485.
- 8. IF CHANGC Am 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 I
- 11. HOURS IN REPORTING PERIOD 744 5,087 166,536 f
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 5,087.0 146,171.5
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 216.7
- 14. HOURS GENERATOR ON LINE 744.0 5,087.0 144,C06.4
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 302.2 i
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1,118,149 7,690,607 205,855,016 1
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 379,970 2,637,360 69,934,620
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 362,933 2,523,606 66,655,672
- 19. UNIT SERVICE FACTOR 100.0 100.0 86.5
+
- 20. UNIT AVAILABILITY FACTOR 100.0 100.0 86.7
- 22. UNIT CAPACITY FACIDR (USING DER NET) 98.2 99.8 80.5
- 23. UNIT FORCED OUTAGE RATE O.0 0.0 1.1
- 24. SHUTDOWNS SCHEDULED CVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
42-day Refueling and Maintenance Shutdown to start September 27, 1991.
i 4
- 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
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POINT BEACH NUr'T FAR PLAST Docket No.
_50-3D1
~
Unit Name Feint Beach. Unit 2 HIT SIILTDOWNS AND POWER REDt'CTIONS Date Jerust 7_1991 Completed By D. C Petersen PORT MONTH JULY - IW1 Telephone No.
414/755-212L Ext _ }il
\\fettrA cf Shuning Csuse and Correctne Actre No.
Date Tvpe' Durstne Reau,2 Dt=n Ixersee Dent System Com;vant 5
To P_..a R.m. _ _ _
filexM Reed Re~m M Code' CeSe 1
910714 5
20 B
5 NA EB CET BRK Satfur liezannonde (SF.) ps leak re;wir on 3*5 KV Greurt Breaker.
I
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2 l
I
'Afethod-
' Exhibit G - Instructions
'F: Forced Reason-S: Scheduled A - Equipment Failure (explain)
I - Manual for preparation of B - Alaintenance or Testing 2 - Nianual Scram data entry sheets C - Refueling 3 - Automatic Scram LER file (NUREG-0161) 4 - Cont' uation of m
D - Regulatory Restriction Presions Shutdown E - Operator Training &
Licensing Exam 5 - Reduced Load F - Administrative 6 - Other (explain)
' Exhibit I-Same Source G - Operational Error (epiain)
II - Other (explain)
PBFR]2Sb (03-W)
e.
- O DOCKET NO.
50-301 UNIT NAME Point Beach Unit 2 DATE August 7, 19'.
COMPLETED BY D.
C.
Peterson TELEPHONE 414/755-2321, Ext. 361 Unit 2 operated at approximately 487.7 MWe not throughout this report period with one significant load reduction.
The load reduction was caused by a gas leak in a switchyard circuit breaker.
Repair of the circuit breaker aligned Unit 2 with only one outgoing 345 KV line.
Power was reduced to less than 50 percent during the attempted repair in accordance with 3
Technical Specification 15. 3.'/.b.1.a.
Unit 2 experienced a reportable event in accordance with 10CFR50.73 (2 LER 91-001).
A reactor protection system rod stop i
signal was generated on July 30, while performing a reactor protection system logic surveillance test.
Safety-related maintenance included verifing drawings associated
~
wit the reactor protection system logic.
_ _ _ _ _ _ _ _ _ _, _ _ _ _ _ _ _ _,