ML20097E709
| ML20097E709 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/31/1992 |
| From: | Link B, Peterson D WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-92-058, CON-NRC-92-58 VPNPD-92-211, NUDOCS 9206120325 | |
| Download: ML20097E709 (9) | |
Text
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4 Wisconsin Electnc POWER COMPANY 231 w Metem PO fo 20e Mawoukee3n3?a1 14141225 234's VPNPD-92-211 NRC-92-058 June 9, 1992 I
U.
S. NUCLEAR REGULATORY COMMISSION Document Control Desk Mail Station Pl-137 Washington, D.
C.
20555 Gentlemen!
DOCKETS 50-266 AND 50-301 MONTHLY OPERATING REPORTS POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Attached are monthly operating reports for Units 1 and 2, Point Beach Nuclear Plant, for the calendar month of May 1992.
Sincerely, Q. s 7 '(
.j },y -
Bob Link Vice President Nuclear Power
-Attachments L
Copies to L.
L. Smith, PSCW NRC Regional Administrator, Region III l
NRC Resident Inspector l
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i OPERATING DATA REPORT
' DOCKET NO. 50-266 -
DATE:. Juae 2',
1992 COMPLETED BY: Don C.
Peterson 4
2 TELEPHONE:
414-755-2321 ext. 361 OPERATING STATUS 1
j
.1. UNIT NAME:.
. POINT BEACH NUCLEAR PLANT - UNIT 1
. NOTES 1
-2.-REPORTING PERIOD: May - 1992
- 3. LICENSED THERMAL POWER (MWT):
1518.5
- 4. NAMEP' ATE RATING (GROSS MWE):
523.8
)
- 5. DESIGN ELECTRICAL RATING.(NET MWE):-,497.0 6.= MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
509.0.
I
- 7. MAXIMUM DEPENDABLE CAPACITY (NET HWE):
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 i
- 10. REASONS FOR RESTRICTIONS, (IF ANY):
l NA THIS *iONTH YEAR TO DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD.
744 3,647 189,071
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 29.0 2,460.3 155,850.8
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 2.4 655.1
- 14. HOURS GENERATOR ON LINE O.0 2,428.9 152,857.6
- 15. UNIT RESERVE-SHUTDOWN HOURS 0.0 0.0 846.9 i
- 16. GROSS THERMAL ENERGY GENERATED (MWH)
O 3,637,967 214,287,970 i
- 17. GROSS ELECTRICAL ENERGY GENERATED 0
1,249,950 72,353,680 l
- 18. NET.*i:LECTRICAL ENERGY GENERATED (MWH) 0 1,196,458 68,946,231
)
- 19. UNIT SERVICE FACTOR O.0%
66.6%
80.8%
- 20. UNIT AVAILABILITY FACTOR O.0%
66.6%
81.3%
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0%
67.6%
74.8%
)
I
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.0%
66.0%
73.4%
- 23. UNIT FORCED OUTAGE RATE O.0%
0.0%
1.7%
- 24. SHUTIXMNS SCHEDULED OVER NEXT 6 MONTFS (TYPE, DATE, AND DURATION OF EACH):
NA
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
j June 4, 1992
)
DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977 4
i
POINT BEACH NUCLEAR PIANT DOCKET NO.
50-266
' AVERAGE DAILY UNIT PO%TR LEVEL UNTT NAME
.Peint Beach. Unit l'
- MONTH hfAY - IW2 DATE June 5.IM COhtPLETED BY D.' C. Peterson TELEPHONE 414n55-2321 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY NfWe NET DAY.
htWe NET DAY MWe NTT 1
-1 11
-2 21
-2 2
-1 12
-2 22
-2 3
-1 13
-2 23
-2 4
-2 14
-2 24
-3 5
-2 15
-2 25
-6 6
-2' 16
-2 26
-13 7
-2 17
-2 27
-9 8
-2 18
-2 28
-14 9
-2 19
-5 29
-13 10
-2 20
-7 30
-14 l
l 31
-13 rnransa (0190)
A g
. POINT BEACli NUCLEAR PLANT Docket No.
50-2M Unit Name Point Beach. Unit 1 UNIT SiliJTDOWNS AND POWER REDUCTIONS Date June i 11n2 Compicted By D. C. Petersee REPORT MONTil MAY - IW2 Telephone No.
414/755-232L Ext 361_
Method of l -
Shutting Date Twpe' Duratam.
Reason TAmn thensee Event 5 stem Cornponent Cause and Correctrve Actum 2
1 92f>tli 5
744 C
1 Scheduled re'ucting and etai:vvenance catage U1R19. Majnr work itens include inspection and eddy current testeg of the steam generators, installatum of Isil fkm test lenes kw residual heat removal, safety injection and ewi_.....;.,; spray pumgs. A capacity increase of the steam driven auntiary feedwater pump recirculatum ime. Contvot power separation for the 480 volt tvuses, kw pressure tuttine work and as-bails electrical drwwing wo kdoums of the r
teactor pentettion and safeguards system.
. Ultrasonic testing of au feel st=2s Recondition and testing of the mani steam isolation valves i
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'F: Forced
'Reasorr
' Method:
' Exhibit G - Instructions S: Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of 8 - Maintenance or Testing 2 - Manual Scram data entry sheets C - Refueling 3 - Automatic Scram LER file (NUREG-0161)
D - Regulatory Restriction 4 - Continuation of i '
E - Operator Training &
Previous Shutdosi i
Licensing Exam 5 - Reduced load F-Administrative 6 - Other (explain)
'ExhNt I - Same Source G - Operational Error (explain)
II - Other (explain) i f
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DOCKET NO.
50-266 UNIT NAME point B3ach Nuclear Plant, Ursit 1 DATE June 9, 1992 COMPLETED BY D.
C.
Peterson TELEPHONE 414-755-2321, Extension 361 Unit 1 was in a refueling outage during the month of May with zero electrical output.
During this report period, LER 266/92-003 was submitted covering the deenergization of 1A05 resulting in ESF uctuation which occurred April 28, 1992.
Safety-related maintenance included the following:
1.
Replaced the gasket ring, belleville warhers, disc seat, and assembly of the auxiliary feed pump discharge check valve.
2.
Replaced lugs with QA lugs and crimped wiring in reactor protection relay-logic cabinets and eliminated dropped rod turbine runback.
3.
Realigned limit switches for correct operation of personnel access air lock.
4.
Replaced excess letdown heat exchanger shell side outlet valve operator solenoid.
5.
Replaced red 12b volt DC/120 volt AC inverter.
6.
Calibrated faulty low reading auxiliary foodwater flow indicator.
7.
Repacked, relagged, and refurbished the main steam isolation valves.
8.
Replaced and calibrated intermediate range channel log current amplifier.
9.
Replaced containment spray pump seals.
10.
Replaced safety injection pump seal sleeves and throttle bushi;.y and aligned coupling.
11.
Increased torque on jacking studs to stop indicated leak from conoscal.
12. - Replaced switches on reactor vessel head vent solenoids per Service Bulletin 8801A.
13.
Installed anti-rotation modification on safety injection discharge check valves to prevent back icakage.
14.
Replaced studs in body-to-connect bolts of containment spray pump suction valve from residual heat removal due to evidence of corrosion.
15.
Replaced and adjusted several safeguards sequenced time delay relays.
OPERATING DATA' REPORT DOCKET NO. 5@-301 4
DATE: June 3, 1992-COMPLETED BY: Don C. Peterson i
l TELEPHONE:
414-755-2321 ex.361 OPERATING STATUS I
- 1. UNIT NAME: POINT BEACL NUCLEAR PLANT - UNIT 2 NOTES 1
j
- 2. 'tEPORTING ' PERIOO: May 1992 3-G CENSED THERMAL POWER (MWT): 1518.5
- 4. NAMEPLATE RATING (CROSS MWE):
523.8
- 5. DESIGN ELECTRICAL MATIMG (NET MWE):. 497.0
- 6. MATINUM DEPENDABLE CAPACITY (CROSS MWE):
509.0.
i 4
- 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 I
- 9. POWER LEVEL TO WHICM RESTRICTED, IF ANY (NET MWE): na
- 10. REASONS FOR RESTRICTIONS, (IF ANY):
na THIS MONTH YEAR TO DATE CUNULATIVE L
- 11. HOURS IN REPORTING PERIOD 744 3,647 173,856
}
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 3,647.0 152,376.8
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 11.6 228.3
- 14. HOURS GENERATOR ON LINE 744.0 3,635.4 150,124.9
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 302.2
- 16. GROSS THEIWE.2. ENERGY GENERATED (MWH) 1,126,747 5,446,402 214,913,559
- 17. GROSE ELECTRICAL ENERGY GEsERATED 386,350 1,881,920 73,041,300
- 18. NET ELECTRICAL ENERGY GENERATED (MWM) 369,295 1,801,144 69,620,922
- 19. UNIT SERVICE FACTOR 100.0%
99.7%
86.4%
- 20. UNIT AVAILABILITY FACTOR 100.0%
99.7%
86.5%
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 102.3%
101.8%
81.9%
- 22. UNIT CAPACITY FACTOR (USING DER NET) 99.9%
99.4%
80.6%
- 23. UNIT FORCED OUTAGE RATE O.0%
0.01 1.1%
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 NONTHS (TYPE, DATE. AND DURATION OF EACH):
4
).
Unit 2 Refteling Id iS scheduled for 9/25/92 through 11/13/92 for a total duration of 49 days.
i
- 25. IF SHUTDOWN-AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
I na j
DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977 6
1 i
i i
s, POINT BEACII NUCLEAR PLANT DOCKET NO.
50-301 Point Beach. kinit 2 AVERAGE DAfLY UNIT POWER LEVEL UNIT NAME MONTil MAY-IW2 DATE
- June 5_'1992.
COMPLETED BY D. C. Peterson TELEPHONE 414/755-2321
. AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL Po"'rR LEVEL -
POWERISTL DAY MWe F ET DAY
.'.fWe NET DAY MWe NET 1
49R 11 497 21 J97 2
498 12 498 22 498 3
498 13 498 23 497 4
447 14 493 24 40R 5
477 15 499 25 498 6
497 16 499 26 498 7
498 17 498 27 J98 8
499 18 49S 28 498 9
455 19 497 29 498 10 498 20 495 30 498 31 493 FBF4rega (03-90)
POINT BEACil NUCLEAR P1 ANT Docket No.
_ 50-301-Unit Name Point Beach. Unit 2 UNITSHUTDOWNS AND POWER REDUCTIONS Date
_) m i 1902 Completed By D. C. Petein REPORT MONTH MAY-1*r2 Telephone No.
414/75_t2.121 Ert M1 Method of Shettmg Duration 1xensee sent system Gwponent Cause end Grnrtne Actum A
Date Type' (llars)
Reasm:
peg Report M
' G**
Cd To Frewat Reew nnre t
~
'F: Forced
'Reasoir
' Method-
' Exhibit G - Instructions S: Scheduled A - Equipment Fdlare (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 i
E - Operator Training &
Psevious Shutdown licensing Exam 5 - Reduced load F-Administrative 6 - Other (explain)
Txinht I - Same Source G - Operational Error (explain)
H - Other (explain)
PDF oo2sb (0190) 1 w
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i DOCKET No.
50-301 UNIT 1,1AME Point Beach Nucicar Plant, Unit 2 DATE' June 9, 1992 i
COMPLETED BY D.
C.
Peterson TELEPHONE 414/755-2321, Extension 361 Unit 2 operated at approximately 496 MWo not throughout this report period.
Safety-related maintenance included the following:
1.
Replaced the 125 volt station battery distribution bus, changing fromia thermal trip breaker to a fused disconnect switch.
2.
Replaced bolts on turbo-charger exhaust flange of the emergency diesel generators.
3.
Changed low alarm level setpoint to 49 percent for the boric acid storage tanks.
4.
Recharged electrical containment penetration to 15 psi.
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