ML20195B864
| ML20195B864 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/31/1988 |
| From: | Deelsnyder L, Robey R COMMONWEALTH EDISON CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| RAR-88-26, NUDOCS 8806220023 | |
| Download: ML20195B864 (22) | |
Text
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1 QUAD-CITIES NUCLEAR POWER STATION UNITS 1 ANu 2 MONTHLY PERFORMANCE REPORT MAY, 1988 COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 0027H/0061Z 08?2888R8888:,.
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. TABLE OF.. CONTENTS I.
lIntroduction II.
Summary of Operating Experience A.
Unit One B.
Unit Two
.III.
Plant or-Procedure Changes, Tests, Experiments, and Safety Related Maintenance 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 A.
Operating Data Report B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions VI.
- Unique Reporting Requirements A.
Main Steam Relief Vc e Operations B.
Control Rod Drive Scran Timing Data VII.
Refueling Information VIII.
Glossary 0027H/0061Z
I.
INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Hater 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 March 21, 1972, 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 Koselke and Lynne Deelsnyder, telephone number 309-654-2241, extensions 2240 and 2185.
l 0027H/0061Z l
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II.
SUMMARY
OF OPERATING EXPERIENCE A.
Unit One Unit One segan operations for the month of May in Economic Generation Control (EGC). Tae unit remained in EGC with only minor interruptions to perform routine surveillances until May 6.
At 2100, a normal unit shutdown was initiated for a scheduled dual unit outage associated with the Unit Two refuel outage. At 0121 on May 7, the turbine was tripped and at 0141, the reactor was scrammed. At 0715, normal shutdown procedures vere completed.
From May 7 to May 15 battery testing was performed, control rod drive G-7 was replaced, as well as other maintenance activities involved for Unit One.
At 1620 on May 15, the reactor became critical, and at 0553 on May 16, the generator was synchronized to the grid. At 0556, the turbine was tripped to perform an overspeed test.
At 0640, the generator was again synchronized to the grid. A power ascent to full load was begun using control rods and recire pumps. At 0920 on May 17, full load was achieved.
Rod pattern adjust-ments were made while power levels were held constant. On May 18 and 19, routine surveillances were performed. At 0255 on May 19, while performing Main Steam Isolation Valve Closure Monthly Surveillance, the 1C M31V would not go to the 10% closed position. Therefore, a load reduction was taken to 595 MWe. At 0435, the MSIV closure time surveillance for the IC valve was completed. At 0805, a power ascent was begun.
786 MWe was reached at 0932.
On May 20 at 1721, the unit was placed in EGC.
From May 20 to May 24, the unit generated in EGC with only minor interruptions. At 1248, the unit was taken off of EGC to perform a load drop test. A power ascent to full load was taken and held until the test was completed. At 1825, power levels were adjusted and the unit was placed in ECC. The unit operated in EGC until 1032 on May 25 when it was taken off of EGC due to instabilities indicated in the "B" Recirc Pump Drive Water Flow.
Recire pumps were put to Master-Manual per the Shift Control Room Engineer. At 1510, load was increased from 779 MWe to full power. On May 26 at 0055, power level adjust-ments were made and the unit was placed in EGC.
The unit remained in EGC until May 28, when, at 0845 EGC was tripped and a power reduction was taken to 650 MWe to work on the "A" Main Steam Drain Tank Level control. Repairs were completed and the unit was placed in EGC at 1624, and operated in EGC until May 29.
At 0245, the unit was taken off of EGC and a power reduction to 720 MWe was taken.
At 0345, while testing the #4 control valve, the valve did not fast close during the last 10% travel and a B channel 1/2 scram was not received.
Therefore, a manual 1/2 scram on the B channel was taken, and then reset for testing. The manual 1/2 scram was again taken.
Same results occurred and a power reduction was immediately taken. At 0857, 325 MWe was reached. At 1050, another power reduction was taken with control rods at 285 MWe, Power level was held here while Maintenance attempted to repair the #4 control valve 10% open limit switch. At 0115 on May 30, a power reduction was taken to 250 MWe, and at 0220 the unit was placed 0027H/0061Z
in hot standby. Maintenance continued to work on the #4 control valve.
At 1705, repairs were completed, and the mode switch was placed in RUN.
At 1855, the generator was synchronized to the grid. An ascent to full power was begun using control rods and recire pumps.
Full load was achieved at 1100 on May 31 and was maintained through the end of the month.
B.
Unit Two The End of Cycle Nine 2efueling Outage activities continued normally for Unit Two during the month of May. The vessel was flooded, and the core was reloaded beginning at 0530 on May 24 and completed at 1704 on May 27.
Core reload was verified and CRD friction testing was performed on May 28 thru May 30.
I
III.
PLANT OR PROCEDURE CHANGES TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.
Amendments to Facility License or Technical Specifications Technical Specification Amendment No. 106 was issued on March 28, 1988, to Facility Operating License DPR-29.
This amendment incorporates changes to the Limiting Conditions for Operations, Surveillance Requirements and Bases of the 3.../4.4 Technical Specifications for the Unit 1 Standby Liquid Control System 1 compliance with 10CFR50.62.
Technical Specification Amendment Nos. 107 and 102 were issued on May 10, 1988, to Facility Operating Licenses DPR-29 and DPR-30.
These amendments incorporate revisions to applicable Techr.ical Speci-fications Limiting Conditions for Operation, Surveillance Requirements, and Bases which include changes to:
1) the number of HPCI and RCIC steamline high flow instrumentation required operable,
- 3) and high steam flow instrument designation.
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 related maintenance performed on Units One and Two during the reporting period. This summary includes the following: Work Requests Numbers, Licensee Event Report Numbers Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.
UNIT 1 MAINTENANCE
SUMMARY
WORK REQUEST NO.: Q60630 LER NUMBER: NA COMPONENT:
System 1000 - Installed a larger impeller on the main pump and machined down those on the booster pump, 1-1001-65A.
CAUSE OF MALFUNCTION: There was no malfunction.
This was a special tset done to try and reduce excessive vibration of the pump.
RESULTS & EFFECTS ON SAFE OPERATION: There was no safety significance as there were three other pumps available for operation.
ACTION TAKEN TO PREVENT REPETITION: The test was proved successful and will be implemented on the remaining pumps for both units.
UNIT 2 MA'_.IENANCE
SUMMARY
There were no Deviation Reports or License Events Report associated with the Safety Related Work Request Log this month.
IV.
LICENSEE EVENT REPORTS 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 6.6.B.1. and 6.6.B.2. of the Technical Specifications.
UNIT 1 There were no Licensee Event Reports for Unit 1 for the month of May.
UNIT 2 Licensee Event Report Number Date Title of Occurrence 88-008 5-4-88 RWCU System Pipe Crack 88-009 5-7-88 125 VDC Battery Failed Discharge Test 88-010 5-10-88 U2 DW Structural Ste<4 Outside FSAR 88-011 5-22-88 Scram Signal Mate Sw.'.:ch Moved to S/U 88-012 5-24-88 Pipe Supports on RWCU drain line doesn't meet FSAR requirements88-013 5-26-88 Improperly installed SJAE suction valve i
0027H/0061Z
V. _ DATA TABULATIONS The following. data tabulations are presented in this report:
A.
Operating Data Report B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions 0027H/0061Z
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APPENDlX C OPERA 71NG DATA REPOR7 00CKET NO.
50-254 UNIT one DATE June 7, 1988 COMPLETED BY tvnne Deelsnyder l
TELEPHONE 309-654-2241 l
OPERATING STAM 0000 050188 744 2400 053188 Gross HOURS IN REPORTING PSR100,
- 1. REPORTING PERICO:
2511 MAX. OEPEND. CAPACITY (MvWesti:
769
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWil:
DESIGN ILECTRICAL RATING IMWe= Net):
7x9 N/A
- 3. POWER LEVEL TO WHICH RESTRICTED (IP ANY) (WWe=Not):
- 4. REASONS POR RESTRICTION llP ANYl THIS MONTM YR TO DATE CUMULATIVE 3440.4 112504.7_
- 5. NUMSGR OF HOURS REACTOR WAS CRITICAL.............. 5 3 7. 4 0.0 0.0 3421 1
- 8. REACTOR R ESERVE SHUT 00WN HOURS...................
3345.2 108803.4
- 7. HOUR $ GENER ATOR 0N LINE......................... 5 0 8. 9 0.0 0.0 909.2 E. UNif RESERVE SHUT 00WN HOURS,.....,,...........,,,,
- 9. GROSS THERMAL ENERGY GENER ATED (MWM).............. I133162 7002731 2312434RR 364610 2574669 74998171
- 10. GROSS ELECTRICAL ENERGY GENER ATED (MWHI.............
346653 2459338
,70362627
- 11. NET ELECTRICAL ENERGY GENERATED (MWM) 72.2 94.3 79.9
- 12. 8' EACTOR SE RV ICE P ACTOR..........................
72.2 94.3 82.4_
- 13. R EACTOR AV AILA tlLITY P ACTOR......................
68.4 91.7 77.3
- 14. UNIT SERVIC E P ACTOR........................
68.4 91.7 78.0
- 15. UNIT AV AI LAti LITY P ACTOR..........................
60,1 87.7 65.0 it. UNIT CAPACITY PACTOR (Udng MOC) 59.1 85.5 63.4
- 17. UNIT CAPACITY P ACTOR (Unane Deswi MWel.................
I1.5 3.8 5.4_
- 18. UNIT PORCE D OUTACT RATE........................
- 19. SHUT 00WNS SCHEDULEO OVER NEXT 5 MONTHS (TYPE. DATE, AND OURATION QP E ACHit
- 20. IP SHUT DOWN AT END OP REPORT PERICO. ESTIMATED DATE OP STARTUP:
- 21. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPERATION):
FORECAST ACHIEVED INITI AL CRITICALITY INITI AL E LECTRICITY COMMERClAL OPEP ATION l.169
c.
APPENDIX C OPERATING DATA REPORT DOCKET NO. 50-265 UNIT Two DATE June 7, 1988 COMPLETED iiY I.vnne Deelsnyder l
TELEPHONE 309-654-2241 OPER ATING 87ATL*4 0000 050188 744
- 1. REPORTINO PERIOD:
2400 053188 GRo:s HOUR $ 1N REPORTING PERiOO:
- 2. CURRENTLY AUTHORIZu3 POWER LEVEL (MWt):_2 5 I I M AX. DEPENO. CAPACITY (MWe Ned: 769 DESIGN ELECTRICAL RATING (MWeNet):
E N/A
- 3. POWGM LEVEL TO WHICH RESTRICTED llP ANY) (WW,Not):
- 4. REAEONS POR RESTRICTION llP ANY):
THIS MONTH YR TO Daft CUMULATIVE 0.0 2289.8_
106946.9
- 5. NUMSER 08 HOURS REACTOR WAS CRITICAL................
0.0 0.0 2985.8
- 8. REACTOR R ESERVE SHUTDOWN HOUPIS....................
0.0 2261.9 103797.2
- 7. HOURS G E N E R ATOR ON LI NE..........................
0.0 0.0 702.9 E. UNIT RESE RVE SHUTDOWN HOURS...................... -
0 5138743 222509310
- 9. GROSS THERMAL ENERGY GENERATED (MWM) 0 1669730 71227514
- 10. GRO$$ ELECTRICAL ENERGY GENER ATED (MWM)...........
- 11. NET ELECTRICAL ENERGY GENERATED (MWH)..............-2322 1597023 67157048 0.0 62,8 7A.5
- 12. r E ACTOR SE RVIC E P ACTOR...........................
0.0 62.8 78.6
- 13. R EACTOR AV AILAElLITY P ACTOR.......................
0.0 62.0 74.2
C.0 62.0 74.7
- 15. UNIT AV AILABILITY P ACTOR.............
-0.4 56.9 62.4
- 16. UNIT CAP ACITY P ACTOR (Udng MDC1.....................
-0.4 _
5 5. 5 __
60.8
- 17. UNIT CAPACITY P ACTOR (Uwns Doogn MWel.................
0.0 6.2 8.3
- 19. SHUT 00FN$ SCHEDULED QVER NEXT E MONTHS LTYPE. DATE. AND DURATION OF EACHl:
- 20. IP SMUT 00WN AT END OF REPORT PERIOD. ESTIMATED DATE OP STARTUP;
- 21. UNITS IN TEST STATUS IPRIOR TO COMMERCI AL OPERATION):
PORICAST ACHfEVED INITI AL CRITICALITY
?NITI AL E LECTMICITY MOMMERCI AL OPERAT1088 1.16 9
APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCXET NO.
50-254 UNIT ONE DATE Jt'NF 7.
1988 COMPLETED BY tvnne neelsnyder TELEPHONE 309-654-2241 MONTH MAY' 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe Net) j 690 gy 695 738 781 2
gg 735 723 3
741 779 4
y 733 743 8
21 710 4
22 725
-6 733 7
23
~
724 8
24
-8 743 g
g
-8 10 26 736 gj
-9 27 733 688 in
-9 as 13
-10 29 477 81 14
-11 30 691 15
-12 31 16 94 INSTRUCTIONS On this form, list the average dady unit power lent in MWe Net for each day in the reporting month. Compute to the neassst whole megawatt.
Thew figures will be used to plot a graph for cwh reporting month. Nute that when max 4 mum dependable capacity is I
uad for the net etestncal rating ut the unit, there may be occasions whern the daily average power levcl eaceeds the 1001 line (or the rntncted power Icut hnc). In such cases, the average daly unit power output sheet should be footnoted to explaua the apparent anomaly.
1.16 4 1
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APPENol;t 5 AVERAGE DAILY UNrr POWER IEVEL DOCKET NO. 50-265 UNIT m DATE JUNE 7.
1988 COMPLETED BY 1,vnne Deelsnyder TEl.EPHONE 309-654-2241 MONTH W.
1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net)
-1 17
-2 1
-2
-2 2
gg
-2
-2 3
gg 4
-1 20
-2
-2
-I 21 5
g 22
-2
-2 y
-3 23
-2
-2
-2 8
24
-2 23
-2 g
-2
-2 10 26
-2 27
-2 11
-2 12
~
28 i
-2 29
-2 13 14 30
-2
-2
-2
-2 15 33
-2 14 INSTRUCTIONS On this form. list the average daily unit power level in MWeffet for each day in the reporting month. Compute to the l
Dealgst whole megawatt.
These figures will be used to plot a gr4ph for cash reporting month. Note iliat when maxamum dependable capacity is uwd for the net eteetncal rating ut the umt, there may be oscasions wheri the daily average power level exceeds the 100r# line (or the rntncied power lesel hnc). In such cases, the average dait, unat power output sheet should be footnoted to caplaua the apparent anomaly.
1.16-4 s
i ID/SA APPENDIX D QTP 300-S13 UNIT SHITTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.50-25A August 1982 UNIT NAME QUAD CITIES UNIT ONE COMPLETED BY LYNNE DEEL5!YDER DATE JUNE 8, 1988 REPORT MONTH MAY, 1938 TELEPHONE 309-654-2241 m
5 Et E
m x
=
h LICENSEE w
DURATION R
Sii F/ENT o
o NO.
DATE (HOURS)
REPORT 110.
u g
CORRECTIVE ACTIONS / COP 91ENTS 88-4 880507 S
220.5 B
1 ZZ ZZZZZZ Dual Unit Outage 88-5 880516 S
0.8 B
9 HA TURBIN Turbine Tripped for Overspeed Test 88-6 880528 F
13.8 A
9 88-036 HA VALVEX Turbine Tripped due to #4 Turbine Fast Close Valve Failure
~
APPROVED AUG161982 (final) 9 g, g 3 g
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ID/SA APPENDIX D QTP 300-S13 UNIT $NUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.
50-265 August 1982 UNIT NAME QUAD CITIES UNIT TWO COMPLETED BY LYNNE DEELSNYDER DATE JUNE 8, 1988 REPORT HONTH MAY, 1988 TELEPHONE 309-654-2241 w et g
w z
$w w
o o
g w
g@
}
E LICENSEE m@
g@
O EVENT
'/2 "
e" w
DURATION ii2 "g
NO.
DATE (HOURS) t u
REPORT NO.
j CORRECTIVE ACTIONS /COPMENTS g
88-5 880501 S
744.0 C
1 RC FUELXX End of Cycle Nine Refueling Outage I,
1 APPROVED AUG161982 (final) y c.o g g
VI.
UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments to the commission:
A.
Main Steam Relief Valve Operations Relief valve operations during the reporting period are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.
Unit: Two Date: May 16, 1988 Valves Actuated No. 6 Type of Actuation 2-203-3A 1 Manual 2-203-3B 1 Manual 2-203-3C 1 Manual 2-203-3D 1 Manual 2-203-3E 1 Manual riant Conditions: Reactor Pressure - 920 psig Description of Events:
QOS 201-1 Technical Specification 4.5.D.l.b B.
Control Rod Drive Scram Timing Data for Units One and Two The bases for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifications 4.3.B.1 and 4.3.C.2.
The following table is a complete summary of Units One and Two Control Rod Drive Scram Timing for the reporting period. All scram timing was performed with Reactor pressure greater than 800 PSIG.
RESULTS OF SCRAM TI'llNG MEASUREMENTS PERF0lWED ON UNIT I & 2 CONTROL ROD DRIVES, FROM l-1-88 TO 12-31-88 l
AVERAGE TIME IN SECONDS AT %
MAX. TIME l
INSERTED FROM FULLY WITHDRAWN FOR 90%
1 INSERTION DESCRIPTION NUlEER S
20 50 90 Technical Specification 3.3.C.1 &
i DATE OF RODS 0.375__
0.900 2.00 3.5 7 sec.
3.3.C.2 (Average Scram insertion Time) 5-16-88 89 0.29 0.67 1.45 2.56 3.07 Unit 1, Hot Scram Timing A Sequence (C-II) 0027H/0061Z
VII.
REFUELINGINFORMATIQ1 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. lleed, et al., titled "Dresden, Quad-Cities, and Zion Station--NRC Rtiquest for Refueling Information", dated January 18, 1978.
i 0027H/00612
QTP 300-S32 Revision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST 1.
Unit 01 Reload:
9 Cycle:
'O 2.
Scheduled date for next refueling shutdown:
6-24-89 3.
Scheduled date for restart following refueling:
9-17-89 4.
Will refueling or, resumption of operation thereaf ter require a technical specification change or other license amendewnt:
NOT AS YET DETERMINED.
5 Scheduled date(s) for submitting proposed licensing action and supporting information:
MARCH 24, 1989 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, 7
The number of fuel assemblies.
a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
1773 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:
Licensed storage capacity for spent fuel:
3657 a.
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 APPROVED APR 2 01978 Q.C.O.S.R.
QTP 300-S32 Revision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST 1.
Unit:
02 Reload:
a Cycle:
o 2.
Scheduled date for next refueling shutdown:
4-9-88 3.
Scheduled date for restart following refueling:
6-18-88 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 [UEL TYPES (MAPHLGR CURVES).
CHANGE TO MCPR LIMIT AND OPERATION AT INCREASED CORE FLOW / FINAL FEEDWATER TEM 5.
Scheduled date(s) for submitting proposed licens'ng action and supporting In forma tion:
March 4, 1988 6.
Important licensing considerations associated with refyeling, 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 GENERAL ELECTRIC, GE8E FUEL WITH 4 WATER-RODS AND LHCR LIMIT OF 14.4 KW/FT.
7.
The number of fuel assemblies.
a.
Number of assemblies in core:
724 b.
Number of assemblies In spsnt fuel pool:
1475 8.
The present IIcensed 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:
Llcensed storage capacity for spent fuel:
a.
3897 b.
Planned increase in licensed storage:
o 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
2008 APPROVED APR 2 01978 C). C1 C). S. R.
L 4..
.VIII.
GLOSSARY The following. abbreviations which may have been used in the Monthly Report, are defined below:
ACAD/ CAM Atmospheric Containment Atmospheric Ollution/ Containment
' Atmospheric Monitoring ANSI American National Standards Institute APRM Average Power Range Monitor ATHS Anticipated Transient' Hithout Scram Bolling Water Reactor BWR CR0 Control Rod Drive EHC
~ Electro-Hydraulic Control System EOF Emergency Operations facility Generating Stations Emergency Plan GSEP High-Efficiency Particulate filter HEPA HPCI.
High Pressure Coolant Injection System High Radiation Sampling System HRSS IPCLRT Integrated Primary Containment Leak Rate Test Intermediate Range Monitor IRM ISI-Inservice Inspection Licensee Event Report LER LLRT Local Leak Rate Test LPCI Low Pressure Coolant Injection Mode of RHRS Local Power Range Monitor LPRM Maximum Average Planar Linear Heat Generation Rate MAPLHGR Minimum Critical Power Ratio MCPR Maximum Fraction Limiting Critical Power Ratio MFLCPR MPC Maximum Permissible Concentration MSIV Main Steam Isolation Valve National Institute for Occupational Safety and Health NIOSH Primary Containment Isolation PCI Preconditioning Interim Operating Management Recommendations PCIOMR Reactor Building Closed Cooling Water System RBCCW RBM Rod Block Monitor Reactor Core Isolation Cooling System RCIC Residual Heat Removal System RHRS RPS Reactor Protection System RHM Rod Worth Minimizer Standby Gas Treatment System j
SSGTS Standby Liquid Control SBLC Shutdown Cooling Mode of RHRS SDC Scram Discharge Volume SOV SRM Source Range Monitor Turbine Building Closed Cooling Water System TBCCW Traversing Incore Probe TIP Technical Support Center TSC 0027H/0061Z
.o O' Commonwealth Edison Quad Cities Nuclear Power Station 22710 200 Avenue North Cordove, Illinois 61242 Telephone 309/654 2241 RAR-88-26 May 31, 1988 Director of Nuclear Reactor Regulations U.S. Nuclear Regulatory Com:nission Mail Station P1-137 i'ashington, D.C.
20555 Enclosed for your information is the Monthly Performance Report covering tl:e operation of Quad-Cities Nuclear Power Statien, Units One and Two, during the month of May, 19o8.
Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION R.A. Ro ey Services Superintendent RAR/vk Enclosure j6Y I
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