ML20125E188
| ML20125E188 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 11/30/1992 |
| From: | Cialkowski M, Diederich G COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9212160235 | |
| Download: ML20125E188 (27) | |
Text
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O'. Commonwzith Edlan LaSalle County Nuclear Station 2601 N. 21r.t. R1 Marseilles, Illino!s 61341 Telephone 815/357-6761 l
1 December 10, 1992 i
i
. : rector of Nuclear Reactor Regulation united States Nut. lear Regulatory Commission Mail Station Pl-137 Hashington, D.C.
20555 ATTN: Document Contr(,1 Desk Gentlemen:
Enclrsed for your information is the monthly. erformance report covering LaSalle County Nuclear Power Station for November 1992.
Very truly yours, G. J. Diederich I Station Manager LaSalle County Station GJD'HJC/djf 4
i En;1osure xc:
A. B. Davis, NRC, Region III D. E. Hills, NRC Resident Inspector LaSalle J. L. Roman, IL Dept. of Nuclear Safety C. Singel, ERR Project Manager D. P. Galle, CECO D. L. Farrar, CECc INP0 Records Center D. R. Eggett, NED-P. D. Doverspike,.GE Resident 2
T. J. Kovach, Manager of Nuclear Licensing.
i T. A. Rieck, Nuclear Fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor M. P. Pietryga, QA/NS Off Site Review Station File 9212160235 921130
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LASALLE NUCLEAR PONER STATION UNIT 1 MONTHLY PERFORMANCE RFRRT NOVEMBER 1992 COMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 i
)
1 ZCADTS/5
9 TABLE OF CONTENTS.
(UNIT 1)
I.
INTRODUCTION II. REPORT A.
SUMARY OF OPERATING EXPERIENCE B.
AMENDMENTS TO FACILITY UCENSE OR TECHNICAL SPECIFICATIONS 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 Shutdowns 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 j
5.
Indications of Failed Fuel Elements 1
1 1
).
i 4
i ZCADTS/5 o
4 I.
INTRODUCTION (Unit 1)
The laSalle County Nuclear Power Station is a two-unit facility owned by Comonwealth Edison Company and located near Marseilles, Illinois.
Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts.
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 Commonwealth Edison Cogany.
Unit One was issued operating license number NPF-ll en April 17, 1982..
Initial criticality was achieved on June 21, 1982 and commercial power operation was comenced on January 1,1984.
This report was compiled by Michael J.
Cialkowski, telephone number (815)357-6761, extension 2427.
-ZCADTS/S l
1 a
II. MONTHLY REPORT k.
SLM MRY OF OPERATING EXPERIENCE (Unit 1) 1 l
QAy Time Event 1
i 1
0000 Reactor sub-critical, Generator off-line, refuel. outage
{
(LIR05) in progress.
30 2400 Reactor sub-critical, Generator off-line, refuel outage (L1R05) in progress.
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. B.
ANENDMENTS TO THE FACILITY LICENSE OR TECHNICAL SPECIFICATION (None.)
C.
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT (including SOR differential pressure switch failure reports).
(See Table 1)
D.
LICENSEE EVENT REPORTS (Unit 1)
LER Number Qaig Description 92-012-00 11/02/92 Missed fire watch for. inoperable fire detection zone 1-15.
92-013-00 11/14/92 Automatic-start of the
'1A' Diesel Generator due to instrument spike during performance of a Reactor high pressure response time test.
92-014-00 11/11/92 Violation of a high radiation area boundry.
E.
DATA TABULATIONS (Unit 1) 1.
Operating Data Report (See Table 21 2.
Average Daily Unit Power Level (See Table 3) 3.
Unit Shutdowns and Significant Power Reductions (See Table 4)
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TABLE 1 (Unit 1)
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT MORK REQUEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION LO4716 Residual Heat Removal Leakage past bonnet gasket. None.
Manual Discharge Valve 1E12-F098C L17916 Containment Monitoring Indication sticking at Inaccurate temperature Replaced indicator.
0 System Drywell Air 200 F.
indication.
Temperature Indicator 1TI-CM058 4
L18375 Residual Heat Removal Dual indication when valve Inaccurate indication.
Adjusted limit switches.
Shutdown Down Cooling was closed.
1 Manual Stop Valve 1E12-F0908 L18552 Diesel Fuel Oil Pump oiler leaking.
None.
Replaced oiler.
Transfer-Pump 00001P L18559 Reactor Vessel Low Level Transmitter
-Greater than 11 shift during Replaced transmitter.
Mater Level'3 'A' 1821-N403A.
Transmitter Calibration.
Logic L18706 Main Stream Line High Excessive electrical noise None.
Replaced switch.
Flow Switch IE31-N011A in switch.
L18775 Reactor' Building Damper binding when cycled. Redundant damper available.
AJied additional supports Exhaust Isolation
- Jamper structure.
l Damper IVR05YB L18776-Reactor Building Air hoses leaking.
None.
Replaced air hoses.
Ventilation Exhaust Isolation Damper IVR05YB (No SOR Failures this month.)
.i.
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TABLE 1 (Unit 1)
PAGE 2 i
MAJOR 00RRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT MORK REQUEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L18777 Reactor Building Air hose leaking.
None.
Replaced air hose.
Ventilation Supply Isolation Damper IVR04YA L18869 Diesel Generator Broken sensing line.
Improper pressure indication.
Replaced union, reconnected
. Scavenging Air tubing.
Pressure Indicator OPI-DG086 L18905 High Pressure Core Pump breaker failed to Mone.
Replaced breaker.
Spray Pump 1E22-C001 insert fully into cubicle.
L18909 High Pressure Core ~
Pressure indicator snubber. Improper indication.
Replaced snubber.
Spray Diesel Generator Crankcase Pressure Indicator IE22-RS46 L19033 High' Pressure' Core.
Overspeed trip relay None.
Replaced relay.
Spray Diesel Generator failed to operate.
Overspeed Trip L19039 Control Rod Drive Accumulator leaking.
None.
Replaced accumulator Hydraulic Control 0-ring.
Unit 38-31 L19043 Control Rod Drive.
Nitrogen leaking from None.
Repl&ced drain cap.
Hydraulic Control drain cap.
Unit 42-11 ZCADTS/5+
C.
TABLE I (Unit 1)
PAGE 3 MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT MORK REQUEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L19071 Control Rod Drive Nitrogen charging valve None.
Replaced valve cartridge.
Hydraulic Control leaking.
Unit 18-51 4
.L19097 Control Rod Driva Nitrogen charging valve None.
Replaced valve cartridge.-
1 Hydraulic Control leaking.
Unit 18 :
L19098 Control Rod Drive Nitrogen charging valve None.
Replaced valve cartridge.
l Hydraulic Control leaking.
t Unit 26-07 (No SOR Failures this month.)
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i TABLE 2 2
E.1 OPERATING _ DATA REPORT 1-DOCKET NO. 050-373
_ UNIT.LASALLE ONE-l 1
DATE December 10,1992 COMPLETED BY M.J.CIALKOWSKI OPERATING'CTA*IUS TELEPHONE (815) 357-6761 4
1-1 j
1.
REPORTING PERIOD:
November 1992 l
GROSS HOURS IN REPORTING PERIOD:
720 l
2.
CURRENTLY AUTHORIZED POWER LEVEL (MWt):
3,323-l MAX DEPENDABLE CAPACITY (MWe-Net):
1,036 DESIGN ELECTRICAL RATING (MWe-Net):
1,078 3.
POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):
N/A 1
4.
REASON FOR RESTRICTION (IT ?JY):
I THIS MONTH YEAR TO DATE CUMULATIVE 5.
REACTOR CRITICAL TIME (HOURS) 0.0 6,568.3 53,924.8 i
6.
REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2 i-l 7
GENERATOR ON-LINE TIME (HOURS) 0.0-6,529.3 52,907.6~
l 8
UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0 1
9.
THERMAL ENERGY GENERATED (MWHt) 0
.19,903,179 ' 155,060,158
- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 0 6,702,577-51,792,349 1-l
- 11. ELECTRICAL ENERGY GENERATED (MWHe-Net)
- -8,026 6,461,252 49,656,397 I
i
-'12. REACTOR SERVICE FACTOR (%)
0.0-
'81.7 69.0 4
[.
- 13. REAC7Gu AVAILABILITY FACTOR (%)
0.0 81-7 71.1
- 14. *JNIT SERVICE FACTOR (%)
0. 0_
-81.2_
67.7 i
'15. UNIT AVAILIBILITY FACTOR (%)
0.0
=81.2 67.7 i
- I6. UNIT CAPACITY FACTOR (USING MDC) (%)
-1.1 77.6
= 61.3 i
' 17. UNIT CAPACITY FACTOR.(USING DESIGN MWe)
-1.0
-74.5
' 58.9 j
- 18. UNIT FORCED OUTAGE FACTOR (%)'
O.0
-1.4 6.9
- 19. SHUTDOWNS. SCHEDULED OVER THE NEXT 6 MONTHS.- (TYPE, ' DATE, AND DURATION OF EACil) :
1 l
' 20. IF ' SHUTDOWN AT END OF REPORT PERIOD,. ESTIMATED DATE OF STARTUP: '
01/08/93 I
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TABLE 3 E.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net)
DOCKET NO. 050-373 UNIT LASALLE ONE DATE December 10,1992 COMPLETED BY M.J. CIALKOWSKI TELEPHONE (815)-357-6761-REPORT PERIOD: November 1992 DAY POWER DAY POWER 1
-11 17
-11 2
-11 18
-13 3
-11 19
-12 4
-11 20
-11 5
-11 21
-11 6
-11 22
-11 7
-11 23
--11 8
-11 24
-11 j
j' 9
-11 25
-11 i
10
-11 26
-11 11
-11 27
-11 12
-11 28
-11 j
13
-11 29
-11 l-14
-12 30
-11 i'
15
-11 31 i.
16
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TABLE 4 E.3 UNIT SHUTDONNS AND PONER REDUCTIONS > 201 i
(Unit 1)
METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DONN ACTIONS /COMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # 1f NUMBER (YYMDD) S: SCHEDULED (HOURS)
REASON REDUCING POWER applicable) 4 921003 S
720.0 C
1 Refuel outage (LlR05)
SUMARY OF OPERATION:
The unit entered a scheduled refueling outage on 10/03/92. Scheduled return to service is 01/08/93.
1 ZCADTS/S i
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UNIQUE REPORTING REQUIREMENTS (Unit 1) i 1.
Safety / Relief valve operations j
(None.)
i 2.
ECCS System Outages (See Table 5) 3.
Changes to the Off-Site Dose Calculation Manual j
(None.)
4.
Major changes to Radioactive Maste Treatment Systems.
l (None.)
i 1
5.
Indications of Failed Fuel Elements.
(None.)
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(Unit 1)
Table 5 F.2 ECCS System Outages Note: The year and unit data has been removed from the-outage number.
OUTAGE NO.
EOUIPMENT PURPOSE (0-0) 0597 00G01K Replace air start, tubing, general 0632 maintenance.
0844 0831 00G01K Installation of quick disconnects 0845 on the lube oil circulation pump.
0833 00G01K Inspection.
0848 00G01K Cooling water strainer inspection cable repair.
0859 00G01K Heat exchanger maintenance.
(U-1) 0676 1DG01K General diesel generator maintenance.
0709 1DG01K Relay inspection.
0751 1DG01K Cooling water strainer inspection.
1650 1DG01K Inspection.
1655 1DG01K Modify mounting of the lube oil circulation pump motor.
1658 1DG049A Troubleshoot and repair check valve.
1659 IDG01K Administrative control.
1678 1DG035 Troubleshoot and repair motor operated valve.
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LASALLE NUCLEAR PONER STATION UNIT 2 MONTHLY PERFORMANCE REPORT NOVEMBER 1992 CO WONNEALTH EDIS0N COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18
' ZCADTS/7 i
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TABLE OF CONTENIS (Unit 2)
I.
INTRODUCTION i
1 i
j II. REPORT A.
SIM4ARY OF OPERATING EXPERIENCE B.
AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C.
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT f
D.
LICENSEE EVENT REPORTS E.
DATA TABULATIONS 1.
Operating Data Report 3
2.
Average Daily Unit Power Level 3.
Unit Shutdowns and Power Reductions i
F.
UNIQUE REPORTING REQUIREMENTS l
1.
Safety / Relief Valve Operations 2.
ECCS System Outages i
3.
Off-Site Dose Calculation Manual Changes i
4.
Major Changes to Radioactive Mast 9 Treatment System l
S.
Indications of Failed Fuel Elements l
l l
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i ZCADTS/7
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I.
INTRODUCTION (Unit 2) j The LaSalle County Nuclear Power Station is a two-unit facility owned by j
Commonwealth Edison Company and located near Marseilles, Illinois.
Each unit is a Boiling Mater Reactor with a designed net electrical output of l
1078 Megawatts. Maste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was 2
i Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company.
i 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 October 19, 1984.
l This report was complied by Michael J. CialkowsL!, telephone number (815)357-6761 extension 2427.
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II. MONTHLY REPORT l
5.
SUHMARY OF OPERATING EXPERIENCE (Unit 2)
I p_gy Ilma Event 1
0000 Reactor critical, Generator on-line at 1130 Hwe.
i 0400 Reduced power level to 990 Mwe due to system load.
2 1300 Increased power level to 1135 Hve.
2 0030 Reduced power level to 940 Mwe due to system load.
1 1300 Increased power level to 1135 Mwe.
4 0030 Reduced power level to 980 Mwe due to system load.
i 1200 Increased power level to 1135 Mwe.
4 i
8 0400 Reduced power level to 945 Mwe due to system load.
i 1100 Increased power level to 1135 Mwe.
9 0100 Reduced power level to 995 We due to system load.
)
1000 Increased power level to 1135 Mwe.
10 2330 Reduced power level to 890 Mwe due to system load.
j 11 1100 Increased power level to 1135 Mwe, i
j 12 0230 Reduced power level to 850 Mwe due to system load, a
l 1100 Increased power level to 1130 Mwe.
13 0300 Reduced power level to 900 Mwe due to system load, i
1100 Increased power level to 1130 Hwe.
)
2330 Reduced power level to 850 Mwe to place the Turbine Driven Reactor Feed Pump out of service for maintenance.
14 1000 Increased power-level to 1030 Mwe.
16 0123 Reactor scram due to loss of the station service /
instrument air system.
18 0450 Reactor critical.
2023 Generator on-line at 80 Mwe.
19 0700 Increased power level to 200 Mwe.
1700 Increased power level to 750 Hve.
2100 Increased power level to 1050 Hve.
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II. MONTHLY REPORT A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 2)
(CONTINUED) 4 l
[)Ay Time Event 21 0030 Reduced power level to 815 Mwe for rod set.
0300 Reduced power level to 630 Mwe for rod set.
[
1600 Increased power level to 1130 Mwe.-
l 23 0100 Reduced power level to 995 Mwe due to system load.
l 0700 Increased power level to 1130 Mwe.
i i
25 1300 Reduced power level to 1100 Mwe due to system load.
j 1800 Increased power level to 1130 Mwe.
l 26 0230 Reduced power level to 850 Mwe ode to system load.
1400 Increased power level to 1125 Mwe.
l l
27 0100 Reduced power level to 850 Mwe due to system loaa.
l 1000 Increased power level to 1130 Mwe.
l 28 0100 Reduced power level to 850 Mwe due to system load.
1100 Increased power level to 1135 Mwe.
29 0300 Reduced power level to 895 Mwe due to system load.
l 1700 Increased power level to 1135 Mwe.
2300 Reduced power level to 980 Mwe due to system load, i
30 0300 Reduced power 1svel to 910 Mwe due to system load.-
l 1000 Increased power level to 1135 Mwe.
1 2400 Reactor critical, Generator on-line at-1140 Mwe.
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. B.
AMENDMENTS TO THE FACILITY-LICENSE OR TECHNICAL SPECIFICATION i
(None.)
I i
C.
MAJOR CORRECTIVE MAINTENANCE TO SAFETY RELATED EQUIPMENT. (including i
SOR differential pressure switch failure reports).
(See. Table 1)
)
0.
LICENSEE EVENT REPORTS (Unit 2)
LER Number Qaig Description i
92-016-00 11/16/92 Reactor scram due to loss of Service Air.
i i
j E.
DATA TABULATIONS (Unit 2)
}
1.
Operating Data Report.
j (See. Table _2)
I' 2.
Average Daily Unit Power Level.
l
'(See-Table 3) i 3.
Unit Shutdowns.and Significant Power Reductions.
(See Table.4) f f
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TABLE 1 (Unit 2)
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT HORK REQUEST RESl!LTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L17682 Control Rod Drive Directional control valve Double notching of control rod. Replaced' directional Hydraulic Control 122 sticking open.
control valve Unit 18-43 L18120 Local Power Range LPRM card.
LPRM failed 1/2 scram received. Cleaned card connector.
Monitor 48-098 L18793 Average Power Range Power supply voltage None.
Replaced power supply.
Monitor A oscillating.
(See attached SOR Failure Report.)
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SQLdp SWITCH FAILURE DATA SHEET 1
Equipment Piece Number: 1E11-Ital 2HB Model Number: 103-AS-B203-NX-JJT1XS l
Serial Number: 85-1-2131 Application: Residual 1[tulLt_ Removal Shutdown Cooling _linc_bItak switch (alarml Date and Time of Discovery: 11/10/92 1745 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.639725e-4 months <br /> 4
~
Reactor Mode: 1 (Run)
Power Levels 100%
Calibration Tolerance: 167.4 - 169.4 "WC 3
Hominal Setpoints 168.4 "WC Action Limits:
< 163tQ or >11318 "WC J
Reject Limits:
< 158.8 or >178.0 "WC Technical Specification
]
Limits:
N/A "WC I
As Found Setpoint N/A_ "WC 4
Date and Time of Return to Service: N/A hours 1
Model Number of Replacement Switch: N/A Serial Number of Replacement Switch: _F/A i
DVR Number 1-2-92-08Q 1
Causes Switch,was found out of calibration during_ monthly functional test.
Switch failure was attributed to a torn diaphraam.
Corrective Action: The switch was taken out.of setyine pending removal d.urina refuel outace L2R05 per modification M01-2-88-060.
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TABLE 2 E.1 OPERATING DATA REPORT DOCKET NO. 050-373 3
UNIT LASALLE TWO I
DATE December 10,1992 COMPLETED DY M.J.CIALKOWSKI OPERATING STATUS TELEPHONE (815) 357-6761 1
1.
REPORTING PERIOD:
November 1992 GROSS HOURS IN REPORTING PERIOD:
720 2.
CURRENTLY AUTHORIZED POWER LEVEL (MWt):
3,323 l
MAX DEPENDABLE CAPACITY (MWe-Net):
1,036
]
DESIGN ELECTRICAL RATING (MWe-Net):
1,078 4
3.
POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe_Het):
N/A i
j 4.
REASON FOR RESTRICTION (IF ANY):
THIS MONTH YEAR TO DATE CUMULATIVE 5.
REACTOR CRITICAL TIME (HOURS) 692.6 5,333.7 50,269.5 6.
REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9 7.
GENERATOR QN-LINE TIME (HOURS) 653.0 5,107.8 49,312.4 f
8.
UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0 i
9.
THERMAL ENERGY GENERATED (MWHt) 2,034,654 15,378,284 147,620,683 i
- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 689,387 5,194,685 49,084,435-
- 11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 670,277 4,987,675 47,119,179 4
i l
- 12. REACTOR SERVICE FACTOR (%)
96.2 66.3 70.6 i
l
- 13. REACTOR AVAILABILITY FACTOR (%)
96.2 65.3 73.0
- 14. UNIT SERVICE FACTOR (%)
90.7 63.5 69.3 l
- 15. UNIT AVAILIBILITY FACTOR (%)
90.7 63.5 69.3
- 16. UNIT CAPACITY FACTOR (USING MDC) (%)
89.9 59.9 63.9 i
- 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 86.4 57.5 61.4 l
. 18. UNIT FORCED OUTAGE FACTOR (%)
9.3 9.5 12.8 4
- 19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
i j'
j
- 20. IF SEUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUPt l
- -+ -, _. -,,,,
n
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-.... =. -. _ -
.... -. _ ~.... -. -.
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TABLE 3 j,
E.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) j.
DOCKET NO. 050-373 i
UNIT LASALLE TWO j
DATE December 10,1992 COMPLETED BY M.J. CIALKOWSKI l-TELEPHONE (815)-357-6761-1 i
j j
f 4
l REPORT PERIOD: November 1992 l
DAY POWER DAY POWER 1
1,063 17
-11 l
2 1,056 18 6
3 1,099 19 499 4
1,062 20 987 j
5 1,100 21 990 e
i i
6 1,101 22 1,095 l
7 1,103 23 1,078 4
l 8
1,083 24 1,097 h
l' 9
1,073 25 1,088 i-l 10 1,089 26 997 11 1,038 27 1,033 12 1,037 28 1,034 I
13 1,048 29 1,002 i.
14 967 30 1,054 l
15 1,008 31' 16 53 g
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TABLE 4 E.3 UNIT SHUTD00nIS AND POWER REDUCTIONS >20%
(UNIT 2)
(
.j METHOD OF CORRECTI YEARLY TYPE' SHUTTING DONW ACTIONS / COB 9 EDITS SEQUENTIAL DATE F: FORCED DURATIoK THE REACTOR OR (LER/DVR # if
.f NUMBER (YY)S4DD) St SCHEDULED (HOUFS)
REASON REDUCING POWER applicable) f 9
921116 F
67.0 G
3 Reactor scram due to a transient caused by loss of station air.
{
SUMMARY
OF OPERATION:.
The unit remained on line at high power..throughout the month. Several minor power reductions.were required due to system load and maintenance activities. The'unf t experient.ed a forced outage on 11/16/92, the unit was returned to service on 11/18/92.
ZCADTS/7 i
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F.. UNIQUE REPORTING REQUIREMENTS (Unit 2) 1.
Safety / Relief Valve Operations Valves No & Type Plant QAlg Actuated Actuations Condition Descriotion of Event 11/16/92 2821-F013U Automatic 1
Scram (LER#92-016-00) 2.
ECCS System Outages (See Table 5.)
3.
Changes to the Off-Site Dose Calculation Manual.
(None.)
4 4.
Major changes to Radioactive Naste. Treatment Systems.
-(None.)-
5.
Indications of Failed Fuel Elements-.
t (None.)
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(Unit 2) i Table 5 F.2 ECCS System Outages Note: The year and unit data has been removed from the outage number.
OUTAGE NO.
EOUIPMENT PURPOSE-i 2218 2E51-D003 Repair steam trap.
f.
2220 2E22-C003 Coupling lubrication.
2228 2E22-S001 Install temporary _ pressure gauge.
f 2229 2E51-C004 Replace brushes.
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