ML20097F620
| ML20097F620 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/31/1992 |
| From: | Cialkowski M, Diederich G COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9206150418 | |
| Download: ML20097F620 (26) | |
Text
-
Commonwealth Edison LaSalle County Nuclear Station 2001 N. 21st. Rd.
Marseilles, Illinois 61341 Telephone 815f357 0761 June 10, 1992 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Hall Station PI-137 Washington, D.C.
20555 ATTN: Document Control Desk Gentlemen:
Enclesed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for Hay, 1992.
Very truly yours,
~~
T G. J.
lederich YorStationHanager LaSalle County Station GJD/MJC/djf Enclosure xt:
A. B. Davis, NRC, Region III D. E. Hills, NRC Resident Inspector LaSalle J. L. Roman, IL Dept. of Nuclear Safety B. Siegel, NRR Project Manager D. P. Galle, CECO D. L. Farrar CECO lhPO Records Center D. R. Eggett, NED P. D. Doverspike, GE Resident T. J. Kovach, Manager of Nuclear Licensing T. A. Rieck, Hurlear fuel Services Manager J. E. Lockwood
.91rtory Assurance Supervisor J. H. Giesekee w.hnical Staff Supervisor M. M. Servos >. QA/NS Off Site Review Station File I
-ZCADTS/5 9206150418 920531 i
.ADOCK 0500 3
gDR
LASALLE NUCLEAR POWER STATION UNIT MONTHLY PERFORMANCE REPORT MAY 1992 C00MONNEALTH' EDISON COMPANY l'
NRC DOCKET NO. 050-373 LICENSE NO. NPF-11:
ZCADTS/51
TABLE OF CDN1ENTS (UNIT 1) 1.
INTRODUCTION II. REPORT A.
SUMARY OF OPERA 11NG EXPERIENCE B.
AMEN 0MENTS TO FACILITY LICENSE OR TECHNICAL i?ECIFICATION-C.
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT D.
LICENSEE EVENT REPORTS E.
DATA TABULATIONS 1.
Operating Data Report 2.
Average Daily Unit Power Level 3.
Unit Shutdcsns and Power Reductions F.
UNIQUE REPORTING REQUIREMENTS 1.
Main Steam Relief Valve Operations 2.
ECCS-System Outages 3.
Off-Site Dose Calculation Manual Changes 4.
Major Changes to Radioactive Maste Treatment System 5.
Indications of failed Fuel Elements 3y l
ZCADTS/S
4 I.
INTRODUCTION (Unit-1)
The LaSalle ' County Nuclear Power Station is a two-unit facility owned-by Commonwealth Edison Company and located near Marseilles. Illinois, Each unit is a Boiling Water Reactor-with a' designed net viectrical' output of 1078 Negawatts.
Maste heat is rejected to a. man-made cooling pond using the Illinois-River for make-up and blowdown.- The architect-engineer was -
Sargent and Lundy and the primary construction contractor was=
Commonwealth Edison Company.
Unit One was issued operating Ilcense number NIT-11.on April 17, 1982.
Initial criticality was achieved on June '21,1982 and ' commercial - power operation was commenced on January 1,1984.
This report was compiled by Michael J.
Cialkowski, telephone -number (815)357-6761, extension 24M.
l ZCADTS/S
II. HONTHLY REPORT A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 1)
DAY Ihnf Event 1
0000 Reactor critical, Generator on-line at 850 Hwe.
0600 Increased power level to 1000 Hwe (power level held due to the 'B' Turbine Driven Reactor feed Pump out of service).
2 1400 Increased power level to 1125 Hve.
3 0130 Reduced power level to 950 Hwe due to system load.
2330 Reduced power level to 850 Hwe due to system load.
4 1200 Increased power level to 1120 Hwe.
5 0100 Reduced power level to 850 Hve to perform weekly arid monthly surveillances.
1100 Increased power level to 1125 Hwe.
7 0100 Reduced power level to 1085 Hwe due to the 'B' Reactot Recirculation Flow Control Valve drifting.
1130 Increased power level to 1120 Hwe.
10 0400 Reduced power level to 1085 Hwe due to the 'B' Reactor Recirculation Flow Control Valve drifting.
1000 Increased power level to 1110 Hwe.
12 0100 Reduced power level to 800 Hwe for rod pattern adjustment.
1200 Increased power level to 1118 Hwe.
13 0030 Reduced power level to 1000 Hwe to transfer the Condensate / Condensate Booster Pumps.
0900 Increased power level to 1115 Hwe.
14 0100 Reduced power level to 850 Hwe due to system load.
0800 Increased power level to 1080 Hwe.
15 0200 Reduced power level to 850 Hwe due to system load.
0500 Increased power level to 1090 Hwe.
17 1400 Increased power level to 1115 Hwe.
ZCADTS/S
4 II. MONTHLY REPORT (CONTINUED)
A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 1)
QAy Ilme Event 18 0100 Reduced power level to 950 Mwe due to system load.
0300 Increased power level to 1090 Mwe.
2300 Reduced power level to 850 Mwe due to system load.
19 1100 Increased power level to 1100 Mwe.
20 1800 Reduced power level to 1000 Mwe for Main Turbine performance test.
2200 Increased power level to 1100 Mwe.
22 0200 Reduced power level to 1000 Mwe for Main Turbine performance test.
0600 Increased power level to 1120 Mwe.
1700 Reduced power level to 1000 Mwe due to cooling problems with the Main Power Transformer.
23 0630 Increased power level to 1115 Mwe.
25 1800 Reduced power level to 1075 Mwe to transfer the Condensate / Condensate Booster Pumps.
26 0800 Incr(ased power level to 1100 Mwe..
0900 Reduced power level to 1000 Mwe due to cooling problems with the Main Power Transformer.
2200 Increased power level to 1125 Mwe.
c 27 2330 Reduced power level to 900 Mwe for scheduled maintenance on the '1B' Turbine Driven Reactor Feed Pump.
28 0430
-Increased power level to 950 Mwe.
0730 Increased power level to 1015 Mwe (power level held due to the '1B' Turbine Driven Reactor Feed Pump off-line).
31 0000 Reduced power level to'960 Mwe to place the
'1B' Turbine Driven Reactor-Feed Pump back_in service.
1300 Increased power Icvel to-1125 Mwe.
2300 Reduced power level to 850 Mwe to perform scram timing and rod set.
2400 Reactor critical, Generator on-line at 850 Mwe.
4 ZCADTS/S
__-_-_a
B.
AMENDMENTS TO THE FACILITY LICENSE-OR TECHNICAL SPECIFICATION Addition of refuel platform hoist interlock setpoints to Technical Specification 4.9.6 for the cylindrical mast modification.
C.
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED ' EQUIPMENT (including SOR differential pressure switch failure reports).
(See Table 1)
D.
LICENSEE EVENT REPOR',; (Unit 1)
LER Nu_ber DAtg Qtscriotion a
92-007-00 05/31/92 Auto-start of the
'B' Control Room / Auxiliary Electric Equipment Roon Ventilation-Emergency.
Make-up Train.
E.
DATA TABULATIONS (Unit 1) 1.
Operating Data Report (See Table 2) 2.
Average Daily Unit Power Level (See Table 3) 3.
Unit Shutdowns and Significant Power Reductions (See Table A) k i
l ZCADTS/5 l
C.
TABLE 1 (Unit 1)
MAJOR CORRECTIVE MAINTENANCE TO
~
SAFETY-RElATED EQUIPMENT HORK REQUEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L14435 Electrical Switchgear Alare relay.
Improper indication.
Replaced alarm relay.
Heat Removal System Fan IVXO6C.
L15077 Low Power Range Low power range monitor No downscale indication.
Replaced low power range Monitor 32-178 card. '
monitor card.
L15345 Control Room Servo motor.
Unable to obtain accurate Replaced servo motor.
Ventilation Radiation readings.
Monitor Recorder-1D18-R800 L15525 Reactor Building Air Solenold.
Valve failed to close.
Replaced solenoid.
Equipment Drain Valve 1RE026 L15762 Control Room Tape drive.
Tape not advancing.
Replaced. tape drive motor.-
Ventilation System Ammonia Detector OXY-VC125B L15819 Residual Heat Removal Baseplate gasket leakage.
None.
Replaced baseplate gasket.
Pump Seal. Cooler 1E12-C002B L15820
' Residual Heat Removal' Baseplate gasket leakage.
None.
Replaced baseplate gasket.
Pump Seal Cooler.
lE12-C002C L15898 Average Power. Range Upscale alarm relay.
Abnormal alarms.
Replaced relay.
Monitor Channel 'A' (No SOR Failures this month.)
ZCADTS/5+
+
TABLE 2
+
E.1 OPERATING DATA REPORT DOCKET -110. 050 37 3 -
UNIT LASALLE ONE-DATE June 10,1992 COMPLETED BY M.J.CIALKOWSKI-TELEPilONE (815) 357 6761 OPERATING STATUS 1.
REPORTING PERIOD:-
-Hay 1992 GROSS IlOURS IN REPORTING PERIOD:
744 2.
CURRENTLY AUTilORIZED POWER LEVEL (Mwt):
3,323 MAX DEPCNDABLE CAPAC17T (Mwe-Net) -
1,036 DESIGN ELECTRICAL RATING (Mwe-Net):
1,078 3.
POWER LEVEL TO WHICH RESTRICTED (IF ANY):
N/A 4.
REASON FOR RESTRICTION (IF ANY):
Tills MONTil YEAR-TO-DATE CUMULATIVE-5.
REACTOR CRITICAL TIME (l!OURS) 744.0 3,585.5 50,942.0-6.
REACTOR RESERVE SHUTDOWN TIME (llOURS) 0.0 0.0 11,641.2=
7.
GENERATOR ON-LINE TIME (llOURS) 744.0 3,552.8 49,931.1 8.
UNIT RESERVE SHUTDOWN TIME (llOURS)
- 0. 0_
0.0 1.0 9.
TIIERMAL ENERGY GENERATED (HWitt) 2,360,801 11,459,638. 146,616,617
- 10. ELECTRICAL ENERGY GENERATED (MWile-Gross) 796,712
'3,904,944-48,991,716
- 11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 769,848 3,783,919-46,979,064
- 12. REACTOR SERVICE FACTOR (%)
100.0
'98.3 69.0-
- 13. REACTOR AVAILABILITY FACTOR (E) 100.0' 98.3 71.3
- 14. UNIT SERVICE FACTOR (%)
100.0 97.4
-67.7
- 15. UNIT AVAILABILITY FACTOR-(%)
100.0 97.4 67.7
- 16. UNIT CAPACITY FACTOR (USING MDC) (%)-
99.9
=100.1 61.4
- 17. UNIT CAPACITY FACTOR (USING DESIGN MWe)-
96.0 96.2 59.1
- 18. UNIT FORCED OUTAGE FACTOR-(%)-
0.0
- 2. 6 -_
7.3
- 19. SHUTDOWHS SCl!EDULED OVER TIIE NEXT 6 MONTHS (TYPE, DATE AND DURATION OF- -
EACH):~ Refuel Outage, 09/26/92,112. Weeks
- 20. - IP S!!UTDOWN AT END OF REPORT PERIOD, - ESTIMATED DATE OF STARTUP -
.]
ii -
....__d
TABLE 3 E.2 AVERAGE DAILY LINIT POWER LEVEL _ (MWa-Net)
DOCKET NO, 050-373 UNIT LASALLE.ONE DATE June. 10,1992:
COMPLETED BY.M.J.CIALKONSKI TELEP110NE (815) 357 6761 REPORTING PERIOD May 1992 DAY POWER DAY POWER 1
928 17 1,035 2
1,032 18 1,033 3
931 19 996 4
1,022 20
-1,066-5 1,019.
21-
-1,076 6
1,088 22 1,044 7
1,075 23 1,073 8
1,078
'24 1,083.
9 1,078 25 1,074-10 1,075 26-1,034=
11 1,075 27.
1,077-12 1,017 28
'957 13 1,049 29
~ 988:
14 1,008.30-986 15 1,021 31' 13021 16 1,038-
TABLE 4 l
E.3 UNIT SHUTDONNS AND POWER REDUCTIONS > 201 (Unit 1)
METHOD OF.
CORRECTIVE YEARLY TYPE SHUTTING DONN ACTIONS /CODMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (YYD000) S: SCHEDULED (HOURS)
REASON REDUCING PONER applicable)
(None.)
SUPO4ARY OF OPERATION:
The-unit remained'on line at high power throughout the month. Several minor power reductions were required due to system-l loading and maintenance activities.
t I
L LZCADTS/5
,f.
UNIQUE REPORTING REQUIREMENTS (Un't 1) i 1.
Safety / Relief valve operations (None.)-
2.
ECCS System Outages (See Table 5)-
3.
Changes to the Off-Site Dose Calculation Manual
-(None.)
4.
Major changes to Radioactive Maste Treatment Systems.
(None.)
5.
Indications of failed Fuel Elements.
(None.)
4 s
l
'ZCADTS/5
(Unit 1)
Table 5 F.2 ECCS System Outages Note: The year and unit data has been removed from the outage number.
00TAGE NO.
EQUIPMENT
. PURPOSE _
(U-0) 0394 ODG08CA Air compressor inspection.
0395 00G08CB Air compressor inspection.
0397 00G0lP Coupling lubrication.
0398 ODG01K Change soak back oil filters.
0399 ODG0lK Transducer calibration.
0400 00G0lK Rewire annunciator logic. -
0402 ODG0lP Replace feed breakers.
(U-1) 0319 1E51-C001 Coupling lubrication.
0320 lE51-F010 V0TES testing.
0321 1E51-C003 Motor replacement 0336 0340 1E22-C302A Inspection.
0344 1E22-C302B Inspection.
0345 1E22-S001 Conduit repair.
0355 IE22-C302A Repair air dryer.
0365 IE12-C0028-Relay calibration.
0366 1E12-C002C.
Relay. calibration.
0370 1E12-C002B Megger motor.
j 0371 1E12-C002C Megger motor.
0372
--IE12-F040B
.EQ inspection.
i 0373 IE12-C300C Megger motor.-
ZCADTS/5+
l I --
Ni (Unit 1)
Table 5 (Continued) f.2 ECCS System Outages Note:
The year and unit data has been removed from the outage number.
0374 1E12-C3000 Hegger motor.
0381 1DG01K Breaker inspection.
0385 1DG01K Transducer calibrations.
0395 1E12-C0028 Repair seal leakage.
1E12-C002C 0415 1E51-C004 Motor inspection.
IE51-C005 i
ZCADTS/5+
l
e LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT MAY 1992 COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 ZCADTS/7
TABLE OF CONTENTS (Unit 2)
I.
INTRODUCTION II. REPORT A.
SUMARY OF OPERATING EXPERIENCE B.
AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C.
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EWIPMENT D.
LICENSEE EVENT REPORTS E.
DATA TABULATIONS 1.
Operating Data Report 2.
Average Daily Unit Power Level 3.
Unit Shutdowns and Power Reductions D
F.
UNIQUE REPORTING REQUIREMENTS 1.
Safety / Relief Valve Operations 2.
ECCS System Outages 3.
Off-Site Dose Calculation Manual Changes 4.
Major Changes to Radioactive Maste-Treatment System 5.
Indications of Failed Fuel Elements l
ZCADTS/7
I.
INTRODUCTION (Unit 2)
The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois.
Each unit is a Boiling Hater Reactor with a designed net electrical output of 1078 Hegawatts. Haste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was Consonwealth Edison Company.
Unit Two was issued operating license number NPF-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and commercial power operation was commenced on June 19, 1984.
This report was compiled by Michael J. Cialkowski, telephone number (815)357-6761 extension 2427.
ZCADTS/7 l
_.m_____
II. MONTHLY REPORT A.
SlM4ARY Of OPERATING EXPERIENCE (Unit 2)
QAy lin Event 1
0000 Reactor critical, Generator on-line at 1000 Mwe (power level held due to the '2A' Turbine Driven Reactor feed Pump being off-line).
2 0400 Increased power level to 1135 Mwe.
1900 Reduced power level to 1070 Mwe due to low discharge pressure of the Condensate pump.
3 0300 Increased power level to 1135 Mwe.
7 0200 Reduced power level to 940 Mwe due to system load.
1200 Increased power level to 1135 Mwe.
15 2100 Reduced power level to 545 Mwe due to Feedwater Heater high level, placed the.'28' Turbine Driven Reactor Feed Pump off-line.
2300 Increased power level to 702 Mwe.
16 2100 Increased power level to 993 Mwe.
18 1400 Increased power level _to 1130 Mwe.
19 0100 Reduced power level to 980 Mwe due to system load.
1100 Increased power level to 1135 Mwe.
20 0530 Reduced power level to 950 Mwe to place the Circulating Mater pump off-line.
1130 Increased power level to 1125 Hwe.
23 1800 Reduced power level to 950 Mwe due to system load.
2330 Reduced power level to 850 Mwe due to' system load.
24 1100 Increased power level-to 970 Mwe.
25 0100 Reduced power level'to 850 Mwe due to system load.
1500 Increased power level to 1100 Mwe'(power level held due to high vibration on the #11 Main Turbine bearing).
26 0500 Reduced power-level to 960 Mwe due to system load.
0900' Increased power level to 1115 Mwe.-
27 0100 Reduced power level to 1060 Mwe due to system load.
i 1400 Increased power level to 1115 Mwe.
31 2400 Reactor critical, Generator on-line at 1115 Mwe.
ZCADTS/7
B.
AMENDMENTS TO THE FACILITY LICENSE.0R TECHNICAL SPECIFICATION Addition of refuel platform hoist interlock setpoints to Technical Specification 4.9.6 for the_ cylindrical mast modification.
C.
MAJOR CORRECTIVE MAINTENANCE TO SAFE 1Y RELATED EQUIPMENT-(including SOR differential pressure switch failure reports).
(See Table 1)
D.
LICENSEE EVENT REPORTS (Unit 2)
LER Number Qaig Description (None.)
E.
DATA TABULATIONS (Unit 2) 1.
Operating Data Report.
(See Table 2) 2.
Average Daily Unit Power Level.
(See Table 3) 3.
Unit Shutdowns and Significant Power Reductions.
(See Table 4)
ZCADTS/7
C.
b 'LE 1 (Unit 2)
MAJOR CORRLCTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT RESULTS AND EFFECTS MORK REQUEST
. NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION
'L11672 Auxiliary Electric 011 temperature switch.
Incorrect teg erature indication. Replaced temperature switch.
Equipment Room
' Ventilation Compressor OVE04CB L15423 Average Power Range Thermal trip unit card.
Thermal trip unit failed Replaced thermal trip unit Monitor Channel 'E' calibration.
card.
L15580
. Control Room Ink wheel capacitor.
Slow indication response.
Replaced capacitor.
Ventilation Radiation
-Recorder L15765 Main Steam Line Leak Setpoint drir..
Switch tripped below rejection Replaced switch.
Detection High Flow limit.
Differential Pressure Swltch 2E31-N011A (Sea attached SOR Failure Report.)
ZCADTS/7 L _
SQLdti.EWITcil FAlwnLDATLslignT Equipment Piece Number 2E31-llD11A_
Model Number 1D2-AS D3D5:lLRTIX6 Serial Number.85-1-1119 Application: Main _Elenm_11l91LEinwln91AtioJLDitter.ential htssure Date and Time of Discovery: 05/19192 D20.Q hours Reactor Mode: LIRual Power Levels 1QQ_%
Calibration Tolerance: 102J - 10L D P81d Nominal Setpoints lQ3xQ psid Action Liinits:
<_9L 2 or >10L1 psid Reject Limits:
( 94.8 or >11122 paid Technical Specification Limits:
11620 +/- D1.0 psid As Found Setpoints
_912Q psid Date and Time of Return to Service: 05/22/92 0115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br /> Model Number of Replacement Switch 1Q2-AS-B(Ql:NK_JdTIKA Serial Number of Replacement Switch: 36-10-560 DVR Number: 1-2-02 Q56 Causes Switch waE_Launi_out of calibration d parent cause is instrument agtp.gint drift.
Corrective Action: The switch was replaced.
d l
TABLE 2
-E.1 OPERATING-DATA REPORT DOCKET NO. 050-373 UNIT LASALLE'TWO DATE June 10,1992 COMPLETED BY M.J.CIALKOWSKI TELEPHONE (815) 357-6761 OPERATING STATUS 1.
REPORTING PERIOD:
May 1992 GROSS HOURS IN REPORT.Nd PEPIOD:
744-2.
CURRENTLY AUTHORIZED POWER LEVEL (Mwt):
3,323 MAX DEPENDABLE CAPACITY (Mwe-Net):
1,036 DESIGN ELFCTRICAL RATING (Mwe-Net):
1,078 3.
POWER LEVEL TO WHICH RESTRICTED (IF ANY):
N/A 4.
REASON FOR RESTRICTION (IF ANY):
THIS MONTH YEAR-TO-DATE CUMULATIVE 5
REACTOR CRITICAL TIME (HOURS) 744.0 1,297.2 46,233.1 6.
REACTOR RESERVE SHUTDOWN TIME (HOURS)
' O 0' O.0; 1,716.9 7.
GENERATOR ON-LINE TIME (HOURS) 744.0 1,135.4 45,339.9 i
8.
UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0-9.
THERMAL ENERGY GENERATED (MWEt) 2,375,735 3,224,677 135,467,076-
- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 806,618 1,093,624 44,983,374
- 11. ELECTRICAL ENERGY GENERATED (MWHe-Net!
779,823l 1,026,568 43,158,072-12.' REACTOR SERVICE-FACTOR (%)
-100.0 35.6-69.'2
- 13. REACTOR AVAILABILITY FACTOR-(%)
100.0-35.6-71'. 8 -
4
- 14. UNIT SERVICE FACTOR (%)
100.0 31.1 67.9L
- 15. UNIT AVAILABILITY FACTOR (%)-
100.0 31.1
-67.9
- 16. UNIT CAPACITY FACTOR (USING MDC)i(%)~
101.2 27.2 62.4
- 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 97.2 26.1 59.9 18.- UNIT FORCED OGTAGE FACTOR (%)-
0.0
-8.2' 13.0 19.-SHUTDCHNS-SCHEDULES OVER THE NEXT 6 MONTHS (TYPE, DATE AND DURATION OF--
]
EACH):
20..IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE'Or STARTUP:
1 1
TABLE 3-E.2 AVERAGE DAILY UNIT POWER LEVEL (MWa-Net)
DOCKET NO. 050 373 UNIT LASALLE TWO DATE June 10,1992 COMPLETED BY M.w.CIALKUWSKI TELEP110NE -(815) 357-6701 REPORTING PERIOD: May 1992 DAY POWER
. DAY- - POWER 1
997
.7 946 2-1,079-18 1,03b?
3 1,092 19 1,045 4-1,092 12 0 1,064-5 1,09<
21 1,075 6
1,094 22 1,081-i
't 1,043 23 1,026 8
1,088 24
-901 9
1,088 25:
973 10 1,090 26-1,039 11 1,094 27
.1,059 12 1,087 28 1,065 13 1,086-
'29 1,067 14 1,088 30' 1,071 15 987 L31 1,071 16 879 c:
TABLE 4 E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS >20%
(UNIT 2)
METHOD OF CORRECTIVE YEARLY
-TYPE SHUTTING DOWN ACTIONS /COpegurII.
' SEQUENTIAL DATE
.F: FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (YY)MDD1 St SCHEDULED
-(HOURS)
REASON REDQCING POWCR applicable)
C6 920615 F
0.0 H
4 Power level reduced due to feedwater beatet high level..
- SUte4ARY OF OPERATION:
The unit remained on line at high power throughout the month. 'Several minor power reductions were required due to system 10ading, maintenance activities, and a feedwater heater transient.
ZCADTS/7 l
m.
~
F.
UNIQUE REFORTING REQUIREMENTS (Unit 2)
'l.
Safety /Re11of Valve Operations (None.)
2.
ECCS System Outages (See Table 5.)
3.
Changes to the Off-Site Dose Calculation Manual.
(None.)
4.
Major changes to Radioactive Haste Treatment Systems.
(None.)
5.
Indications of Failed Fuel Elements.
(None.)
)
sE 1
ZCADTS/7
l l
(Unit 2)
Table 5 F.2 ECCS System Outages Note:
The year and unit data has been removed from the outage number.
QUJAGE N0.
[QQIPMENT_
PURPOSE 1702 2DG08DA Repair air dryer compressor.
1703 1732 2DG090A Replace air dryer compressor.
1733 1735 2E22-S001 Replace cylinder thermocouples.
1744 2DG09DB Recalibrate temperacire switches.
1754 2E51-C003 Coupling lubrication.
ZCADTS/7
_. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.. _ _ _ _ _ _ _ _. _ _ _ _ _ _. _