ML20215A881
| ML20215A881 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/31/1987 |
| From: | Robey R, Schmidt K COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 0027H, 0061Z, 27H, 61Z, RAR-87-28, NUDOCS 8706170125 | |
| Download: ML20215A881 (23) | |
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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT MAY, 1987 COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 8706170125 870531 ~
PDR ADOCK 05000254 R
pag.
O JES t,I 0027H/00612
4 4
TABLE OF CONTENTS I.
Introduction i
II.
Summary of Operating Experience A.
Unit One B.
Unit Two III.
Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance i
A.
Amendments to Facility License or Technical Specifications B.
Facility or Procedure Changes Requiring NRC Approval C.
Tests and Experiments Requiring NRC Approval D.
Corrective Maintenance of Safety Related Equipment IV.
Licensee Event Reports V.
Data Tabulations j
A.
Operating Data Report 8.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions VI.
Unique Reporting Requirements A.
Main Steam Relief Valve Operations
)
B.
Control Rod Drive Scram Timing Data VII.
Refueling Information VIII.
Glossary 0027H/0061Z
L I.
INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois.
The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company.
The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors.
The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors.
The Mississippi River is the condenser cooling water source.
The plant is subject to license numbers DPR-29 and DPR-30, issued October 1, 1971, and Marcn 21, 1972, J
respectively; pursuant to Docket Numbers 50-254 and 50-265.
The date of initial Reactor criticalities for Units One and Two, respectively were October 18, 1971, and April 26, 1972. Commercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 for Unit Two.
This report was compiled by Verna Koselka and Kurt Schmidt, telephone number 309-654-2241, extensions 2240 and 2147.
0027H/0061Z
f l-II.
SUMMARY
OF OPERATING EXPERIENCE A.
Unit 1 May 1-15 The month of May began with Unit One holding full load. A load drop to 740 MWe for surveillances was started at 0213.
Following the surveillances, full power was restored by 0720. At 0905 load was dropped for EGC and the unit placed in ECC at 0920. At 2310 the unit went out of EGC and a load drop was begun to facilitate a rod pattern change.
Following the control rod position changes,'at 0510 on May 2, a slow power ascent was begun. The ascent was interrupted at 0815 by the need for a rod pattern adjustment and resumed at 0835.
Full power was reached on May 5 at 0500 and held until 0800 on May 7 when load was reduced for EGC.
The unit was placed in EGC at 0830, and operated until 0730 on May 9 when the EGC was tripped due to a reserve emergency.
Starting at 0740 on May 9 the unit was brought to full power at 1020 and held until 1800.
Power was reduced and the unit placed in EGC at 1819.
EGC was off for surveillances from 0000 to 0055 on May 10 and from 0823 to 0849 on May 11.
At 1000 on May 11, a half scram occurred during weekly instrument surveillances. The half scram caused rod G-7 to be inserted.
EGC was tripped and load reduced to 600 MWe to allow recovery of the rod.
Following special rod maneuvers for recovery, the unit was returned to full power starting at 1030 and completed by 1124.
Full load was held until 1905 on May 12.
Rod G-7 was fully inserted for control system repairs and at 2230 a load reduction to 600 MWe was started to facilitate recovery of rod G-7.
On May 13, special rod maneuvers were performed from 0012 to 0053 and at 0130 an ascent to full power was begun.
Full power was reached at 1315 and held until 0300 on May 15.
Power was reduced and the unit run in EGC from 0315 to 0710. At 0715 the unit was returned to full power where it was held for the rest of the day.
May 16-31 The 16th started with the unit holding full load.
At 0947, load was dropped and the unit placed in EGC at 1003.
EGC was operated until 0515 on May 19 with 4 short interruptions for surveillances and change of limits.
At 0720 on May 19, the unit was brought to full power and held until 0050 on May 20.
The unit was placed tn EGC and operated until 0655 on May 21.
The unit was brought to full load by 0715 and held until May 22 at 0720.
Power was reduced to allow for control rod movements and then returned to full by 0950.
Full power was held until 2205 when it was reduced and the unit placed in EGC at 2223. The unit ran in EGC until 0723 on May 26.
The unit was brought to full power by 0735 and held until May 27 at 0215 when power was reduced.for ECC. EGC 0027H/00612
. ~,
j was operated from 0220 to 0705 and the unit returned to full power at 0715. On May 28, EGC was operated from 0027 to 1005. The unit held full power from 1125 on May 28 to 2256 on May 29 when a load drop was started l
for rod pattern adjustments.
The load drop was completed at 0156 on May 30.
The control rod pattern adjustment was performed from 0230 to j
0343. At 0500, a slow power ascent was begun from 600 MWe.
The load ascent continued for the rest of the month and was completed at 0530 on June 1.
B.
Unit 2 May 1-15 The month of May began with the unit operating in EGC. At 0617 EGC was tripped due to a reserve emergency and the unit raised to full power by 0635.
Full power was maintained until 0030 on May 3 when load was reduced to facilitate a feed pump change over. The pump chang' over was completed at 0350 and the unit returned to full power by 0705.
Full power was held until 0045 on May 5.
The unit ran in EGC from 0110 to 0930 and at full power from 1005 to 1120. The unit was placed back in EGC at 1133, r m until 1328, and then went back to full load at 1340.
Full load was held until 0025 on May 6 when it was reduced for EGC.
The unit was placed in.EGC at 0033. At 0230, four rapid trips of EGC were experienced due to input failures.
EGC was left off and power held at 740 MWe until 0335 when it was increased to 750. At 0340 EGC was reset and ran until 0555 when it again tripped on input failure. The unit was raised to full load by 0620, which it j
held until 1618. The unit was placed in EGC and ran until 0020 on May 7.
j EGC was off for turbine surveillances from 0020 to 0158. At 0318, EGC was tripped because power had dropped below the lower limit of EGC.
Power was raised back to the control band and the unit returned to EGC.
EGC was off again from 0840 to 0900 to switch Reactor Vessel level controllers.
EGC ran until 0600 on May 8 when power was raised.
Full load was held from 0605 to 0130 on May 9.
The unit was operated in EGC from 0142 until 0730 when it was tripped because of a reserve emer-gency. The unit held full load from 0741 until 2150.
The unit was placed in EGC at 2205 and operated until 1600 on May 11.
The unit held full load from 1610 until 2300 and was put back in EGC at 2310.
EGC was tripped at 0209 on May 12 because of a reserve emergency.
The unit held full load from 0218 until May 15 at 0315.
The unit ran in EGC from 0335 until 0715.
Full load was held from 0730 until 2350 when load was reduced to prepare for EGC.
May 16-31 The 16th began with the unit preparing to operate in.EGC.
EGC was run from 0015 until 0240 on May 17.
At the request of the load dispatcher, load was reduced in steps, to 575 MWe at 0550.
This load was held until 0615 and then the unit raised back to full power by 0815.
Full load was held until May 18 at 1425.
At that time, a malfunction of the recire MG
speed control required a load reduction to correct.
The speed control was returned to normal at 1550 and the unit raised to full power.
Full power j
was maintained from 1616 until 0030 on May 19.
The unit was operated in EGC from 0040 until 0820.
Full load was held from 0835 until 0255 on j
May 20, when the unit was placed in EGC.
At 0350, EGC tripped on input I
failure. Also, at 0350, bus 28 was lost with the cause believed to be due to a lightning strike.
The loss of bus 28 caused a 1/2 scram, 1/2 isolations on Group I and II, and various other equipment trips.
By 0405,
)
bus 28 had been recovered, the scram and isolations reset and loads returned 1
to normal. At 0715 a power increase was begun.
Full power was reached at j
0820 and held until 1952.
EGC was operated from 2010 to 2335.
EGC was
-]
off for surveillances until 0112, and then ran until 0700 on May 21.
Full load was held from 0720 until 0130 on May 22.
The unit was operated'in j
EGC from'0200 until 1034.
From'1034 until 1235 EGC was off for surveillances.
j The unit was then operated in EGC until May 26 at 0725.
The unit was raised to full power and held from 0745 until 0217 on May 27.
EGC was operated from 0227 until 0704 when the unit was taken to full power.
Full power was maintained from 0725 until 0000 on May 28 when it was reduced for EGC.
The unit was operated in EGC from 0022 until 0827, when power was raised.
The unit ran at full load from 0850 on May 28 until 0145 on May 30.
EGC was operated until 1712 when it was tripped due.to a problem with computer inputs. The unit was returned to EGC at 1905 and operated until 1125 on May 31.
The unit was raised to full load by 1140 and finished the day holding full load.
I j
III.
PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.
Amendments to Facility License or Technical Specifications There were no Amendments to the Facility License or Technical Specifications for the reporting period.
B.
Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure changes requiring NRC approval for the reporting period.
C.-
Tests and Experiments Requiring NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period.
D.
Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the major safety re.'.ated maintenance performed on Units One and Two during the reporting period. This summary includes j
the following: Work Request Numbers, Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.
0027H/00612
t UNIT 1 MAINTENANCE
SUMMARY
WORK REQUEST No.:
Q55169 LER NUMBER: N/A COMPONENT: System 1600 - Replaced power supply to indicators 1-1640-10B & 11B.
l CAUSE OF MALFUNCTION: The cause of malfunction of the containment pressure (PI-1-1640-11B) and the suppression chamber level (PI-1-1640-10B) instrumen-tation was the high voltage condition of their power supply.
RESULTS & EFFECTS ON SAFE OPERATION: As alternate indications ror this l
instrumentation gave normal readings, safety implications were minimal.
ACTION TAKEN TO PREVENT REPETITION: The power supply was replaced with the voltage regulator allowing only 40 volts and 0.5 amps instead of 72 volts at 0.3 amps. This should preclude similar high voltage conditions in the future.
'\\
l WORK REQUEST No.:
Q55243 i
LER NUMBER: N/A 1
C0HPONENT:
System 261 - Repaired acoustic monitor sensor cable to meet E.Q. requirements.
CAUSE OF MALFUNCTION: The cause of this event was improper documentation.
The EQ document at the Station make no mention of how the acoustic monitors are to be spliced at the drywell penetrations.
RESULTS & EFFECTS ON SAFE OPERATION:
Station Nuclear Engineering detertined
[
that the monitors would function properly in the event of an accident. There-fore, the safety consequences were minimal.
ACTION TAKEN TO PREVENT REPETITION: The Station informed the Station Nuclear E
Engineering Department of the EQ document discrepancies so they may be j
corrected. Also, the cable has been repaired to meet EQ requirements.
's
.lE].;g.,,
j.
4.. t.. -
- .f /-
UNIT 2 MAINTENANCE
SUMMARY
- l
'\\t.y 4
/.
1 There were no Deviation Reports or License Events Report associated with'the j
. Safety Related Work Request Log this month.
I. '
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4 IV.
LICENSEEEVENTREPORTd-n The following is a tabular summary of all licensee, event' reports for Quad-Cities Units One and Two occurring during the' reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 1
6.6.B.'i.' and 6.6.B.2. of the. Technical Specifications.
?
UNIT 1 I
1 Licensee Esc.it Report Numbee Date Title Occurrence 87-08 5-26-87 1C RHRSW pump - piping
's, i
exceeds allowable stress
(.
87-09 5-26-87 Cable Spread Room Fire Protection 00S 87-10 5-19-87 Control Room HVAC on Recirc UNIT 2 87-07 5-20-87 Group III Isolation CU high temperature s
0027H/006t2
e V.
DATA TABULATIONS i
The following data tabulations are presented in this report:
A.
Operating Data' Report B.
Average Daily Unit Powe; Level C.
Unit Shutdowns and Power Reductions i
i l
l 0027H/0061Z
OPERATING DATA REPORT DOCKET NO.59-254 UNIT.
O N E _,,_,
.l DATEJUt{E 4 1987 COMPLETED BYK.MRT A.
SCljMIDT l
T ELEP HONE 3])9 _654-2241 OPERATING STATUS 0000 050187 1.
Reporting periodi2400 05318Z, Gross hours i n r er..s r t in g periodt__ 744 2.
Currently authorized power. level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical rating'(MWe-Net): 789 3.
Power level to which restricted (if any)(MWe-Net): NA 4.
Peosons fcr restriction (if any):
1his Month Yr,to Date CunulotIve 5.
Number of hours reactor was critical 7 4,0 3560.6 106373.3 4
6.
Reactor reserve shutdown hours 0,0 0.0 3421.9 7.
Hours generator on line 744,0 3544.6 102861.1 8.
Unit reserve shutdown hours.
._0 0,
0. j)_
909.2 9.
Gross thermal anergy generated (MWH) i'w.y.t.d.
8446472
_RiE,04290
- 10. Gross electrical eneroy generated (MWH),,_,_,5 7 7 2 5 4
_229_1ZRb 70545110 ii. Net electricc1 energy generoted(MWH) 55222.j.,
2670288
,_.6,6117490
- 12. Reactor service factor 100.0 9 8. ~f 80,_,6.
13, Reactcr availability factor iq.0.0 98.'3 83.2
- 14. Unit service factor 100.0 97.8
],.LP
- 15. Unit availability factor i_00.0 97.8 78.6
- 16. Unit capacity factor (Using MDC) 2.6,_.5 95.8 65.1
- 17. Unit capacity factor (Using Des.MWe) 94.1 93,4 63.5
- 18. Unit forced outage rate
.0.A
.7 5.6
- 19. Shutdowns scheduled over next 6 Months (Type,Date,and Duration of each):
- 20. If shutdown at end of report period, estimated date of.stortup __,._,_,,___ _,_
1
- UN0FFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT
APPENDIX B AVERAGE DAILY UNIT-POWER LEVEL 1
DOCKET NO,50-25L,,_
UNIT._
OtJE DATEJUNE_4 1987 COMPLETED BYKURT A.
SCHMIPL TELEP HONE 3_0 87-654-2p41 1
MONTH Mov 1907 l
DAY AVERAGE DAILY POWER LEVEL' DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) i.
747,8 17.
Z h,2 -
2.
534.5 10.
773.5, 3,
640.9 19.
756 EL 4,
719.0 20, 742 5 1
5, 791.8 21, 772 E _.
6.
764.5 22.
781.9 7.
753.8 23.
7p_6.3 8.
770.7 24, 736.E 9.
761.8
- 25. _
738.5 10.
763.4 26, 778.,2.
1i.
764.2 27.
764_.3..,
12.
773.5 28.
759d..
1 13.
729.7 29.
768J_
14.
778.8 30, 61,4,.6 15.
786.5 31.
703._3 16.
752,,,,,,3 INSTRUCTIONS On this forn nearest whole, list the average daily unit power level in MWe-Net for each day in the reporting nonth. Compute to the negawatt.
These figures will be used to plot a graph for each reporting nonth. Note that when noxinen dependable capacity is used fer the net electrical rating of the unit,there may be occasions when the daily overage power level exceeds the 100% line (or the restricter' power level line).In such cases,the overage daily voit power cetput sheet should be footnoted to explain the apparent anonaly
j OPERATING DATA REPORT-j DOCKET NO.
50-265
- UNIT, T W 0._
DATEJUt{E 4 1987,.,,.
COMPLETED BYKURT-A. SCHMIDT._,,
TELEP HONE 10 9-654-2R41.,_.,,
OPERATING STATUS 0000 050187-1.
Reporting period: 0400 0_53_1RZ GrorT hours in reporting periodt 744 2.
Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical' rating-(MWe-Net): 789 3.
Power level to which restricted (if any)(MWe-Net): NA 4.
Reasons for restriction (if any):
lhis Month Yr,to Date CumulotIve 5.
Number of hours reactor was critical 74.L.Q 2995.7
,_ 1QO.711'4 6.
Reactor reserve shutdown hours
_.,j).3J),
0.0 2985.8 7.
Hours generator on line 744__q 2942.7
,._. 97641.8
~
8.
Unit reserve shutdown hours.
0,0 0.0 7.0.23E 9.
Gross thermal energy generated (MWil) 18p h'.e
.6930044 20 02Z.0 E43,
- 10. Gross electrical energy generated (MWH) 582729 2247813 66607105
,ii. Net electrical energy generated (MWH) 558022 2149618 62746655
- 12. Reactor service factor 10.j),3J1.
82.7 76a2
- 13. Reactor avullability factor 100._0 82.7 79.1
- 14. Unit service factor i () 0. 0 81.2 74.5
- 15. Unit availability factor 100.0 81.2 75.0
- 16. Unit capacity factor (Using MDC) 97.5 77.2 62 ;3 t
- 17. Unit capacity factor (Using Des.MWe) 95.,1
_._. Z5._ 2 6]L. Z
- 18. Unit forced outage rate 0.0 5.3 7.!;
- 19. Shutdowns scheduled over next 6 months (Type,Date,and Duration of each):
- 20. If shutdown at end of report period, estimated date of startup
- WOFFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT
il APPENDIX B I
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO, 50-265
{
UNIT.
TWO l
DATEJUNE'4 1987 COMP LETED BYKLlR T A,_SCliMI_D.,LT,,,,,,
Lj t
TELEPHONE 309-654-2241 MONTH Mqy_i_287 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1, 769,4 17, 719,0 2,
758,2 18, 7,# 0,,A 3,
702J 1(7,
737,,'/
j 4,
783,5 20, 732,5 5,
770,0 21.
7 5 ft.,,,3 6.
738.5 22, 735.9 7,
735,5 23, 707.,_0 8,
777,4 24,,
714,1 9,
767.3 25,,,.
717,6 10.
754 5 26.
791.9 t
1i.
757,4 27, 727.,t,3.,
12, 774,0 28.
74 8. t_
13.
775,8 29.
765,7 14,
_767,2 30,
'722,i 15, 770,7 3i,,,,,..,
7 32.,,,7 16, 735,0 INGTRUCTIONS Dn this forn,last the overage daily unit power level in fiWe-Net for enth day in the reporting month,Conpete to the nearest whole negawatt, These figures will be used to plot a graph for each reporting month. Note that when noximin dependable copocity'Is used for the net electrical rating of the unit,there not be occasions when the daily overage power level exceeds the 1001 line (or the restricted power level line),In soth cases,the overage dolly e.... Jewer output sheet should be feetnoted to explain the apparent anonaly l
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l VI.
UNIQUE REPORTING REQUIREMENTS The followirg items are included in this report based on prior commitments to the commission:
j A.
MAIN STEAM RELIEF VALVE OPERATIONS There were no Main Steata Relief Valve Operations for the reporting period.
j B.
CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO There was no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.
1 l
0027H/0061Z
VII. REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E.
O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Information", dated January 18, 1978.
0027H/00612
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l QTP 300-S32 Revision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST i
i 1.
Unit:
Q1 Reload:
8 Cycle:
9 l
2.
Scheduled date for next refueling shutdown:
9-14-87 3.
Scheduled date for restart following refueling:
12-7-87
)
4.
Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment: YES.
TECHNICAL SPECIFICATION CHANGES WILL BE REQUIRED FOR NEW FUEL TYPES (MAPHLGR CURVES) AND A LICENSE AMENDMENT TO MOVE SINGLE LOOP OPERATION INTO TECHNICAL SPECIFICATIONS.
l S.
Scheduled date(s) for submitting proposed licensing action and supporting information:
AUGUST 21, 1987 4
6.
Important licensing considerations associated with refueling, e.g., new or
' different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
FIRST RELOAD OF GEN,ERAL ELECTRIC, GE8E FUEL WITH 4 WATER-RODS AND LHGR
)
LIMIT OF 14.4 FW/FT. FIRST CYCLE" UTILIZING A DIFFUSION BASED CORE MONITORING CODE.
j 7
1 7
The number of fuel assemblies.
a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
1573 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:
a.
Licensed storage capacity for spent fue!:
3657 b.
Planned increase in licensed storage:
0 1
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2008 30 F* P Ft () \\/ E [> APR 2 01978 Q.C.O.S.R.
qTP 300-S32 Revision 1.
QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST i
i 1.
Unit:
Q2 Reload:
8 Cycle:
9 2.
Scheduled date for next refuel!,g shutdown:
3-14-88 3
Scheduled date for restart following refueling:
5-22-88 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment:
NOT AS YET DETERMINED.
5.
Scheduled date(s) for submitting proposed licensing action and supporting Information:
DECEMBER 14, 1987 6.
Important licensing considerations associated with refueling, e.g., new or
' different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
NONE AT PRESENT TIME.
1 7
The number of fuel assemblies, a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
1308 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned i
in number of fuel assemblies:
a.
Licensed storage capacity for spent fuel:
3897 b.
Planned increase in licensed storage:
0 9
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2008 WPPROVED APR 2 01978 Q.C.O.S.R.
j
1 4
- VIII, GLOSSARY The following abbreviations which may have been used in the Monthly Report,-
l are defined below:
ACAD/ CAM Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI American National Standards Institute APRM Average Power Range Monitor ATHS Anticipated Transient Without Scram BWR Boiling Water Reactor L
CRD Control Rod Drive EHC Electro-Hydraulic Control System EOF Emergency Operations Facility GSEP Generating Stations Emergency Plan HEPA High-Eff_iciency Particulate Filter HPCI High Pressure' Coolant Injection System HRSS High Radiation Sampling System IPCLRT Integrated Primary Containment Leak Rate Test IRM Intermediate Range Monitor ISI-Inservice Inspection LER Licensee Event Report LLRT Local Leak Rate Test LPCI Low Pressure Coolant Injection-Mode of RHRS LPRM Local Power Range Monitor 1
MAPLHGR Maximum Average Planar Linear Heat Generation Rate 1
MCPR Minimum Critical Power Ratio MFLCPR Maximum Fraction Limiting Critical Power Ratio MPC Maximum Permissible' Concentration MSIV Main Steam Isolation Valve NIOSH National Institute for Occupational Safety and Health PCI Primary Containment Isolation PCIOMR Preconditioning Interim Operating Management Recommendations RBCCW Reactor Building Closed Cooling Water System RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System i
RHRS Residual Heat Removal System RPS Reactor Protection System RWM Rod Worth Minimizer SBGTS Standby Gas Treatment System SBLC Standby Liquid Control SDC Shutdown Cooling Mode of RHRS SDV Scram Discharge Volume SRM~
Source Range Monitor TBCCW Turbine Building Closed Cooling Water System TIP Traversing Incore Probe TSC Technical Support Center 0027H/006IZ 1
Comm:nwealth Edison
'ouad Citiss Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241-RAR-87-28 June 5, 1987 Director, Office of Inspection & Enforcement United' States Nuclear Regulatory Commission Washington, D. C.
20555 j
Attention: Document Control Desk l
Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of May, 1987.
Respectfully, COMMONWEALTH EDISON COMPANY l
QUAD-CITIES NUCLEAR POWER STATION I
R.'A.Robey@
i Services Superintendent vk 4
Enclosure 4
0027H/0061Z
E
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