ML20235J557
| ML20235J557 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/30/1987 |
| From: | Robey R, Schmidt K COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RAR-87-31, NUDOCS 8707150636 | |
| Download: ML20235J557 (24) | |
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QUAD-CITIES NOCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JUNE, 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 I
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TABLE OF CONTENTS y
I.
Introduction 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
'a B.
Facility or Procedure Changes Requiring NRC Approval C.
Tests and Experiments Requiring NRC Approval 6
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 i
VI.
Unique Reporting Requirements A.
Main Staam Relief Valve Operations B.
Control Rod Drive Scram Timing Data VII.
Refueling Information 1
VIII.
Glossary 1
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INTRODUCTION Quad-Cities Nuclear Power Station is composed of.two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 HWe Net, located in Cordova, Illinols. 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 Arc'itect/ Engineer was Sargent & Lundy, Incorporated, and the primary n
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 j
initial Reactor criticalities'for Units One and Two, respectively'were October 18, 1971, and April. 26, 1972. Commercial generation of power began on l
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.
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II.
SUMMARY
OF OPERATING EXPERIENCE l
A.
Unit 1 June 1-15 The month of June began with the unit slowly ascending to full power. At 0530 on June 1, full power was reached and held until June 3 at 0343, when power was reduced for EGC.
The unit was operated in EGC until June 8, except during surveillance and control rod movements.
The unit was taken off of EGC at 0730 on June 8 and raised to full power by 0745. At 0110 on June 9, power was reduced and the unit placed in EGC at 0120. The unit operated in EGC with only short, routine interruptions until 1233 on June 12.
On June 10, a GSEP unusual event was declared at 1907 and terminated at 2030 due to an earthquake in Southeastern Illinois.
On June 12 beginning at 1237, power was slowly increased.
Full power was reached at 1550 and held until 0422 on June 13.
The unit was operated in EGC from 0447 until 2300.
Power was. reduced for a turbine generator test and power held at 650 MWe from 0015 to 0200 on June 14.
A slow load increase was started, the unit raised to full power at 1230 on June 15, and held the rest of the day.
June 16-30 June 16 was begun with the unit holding full load. At 0800 on June 16, power was reduced for EGC which ran from 0855 until 0820 on June 17.
The unit was increased to full load at 1145 and held until 1950. At that time, a load drop was begun for maintenance. The unit was held at 413 MWe from 2207 until 0555 on June 18.
Power was increased to 700 MWe by 0655 and then slowly returned to full load by 1717. On June 19, power was reduced to 750 MWe from 0330 to 0610 to allow for movement of control rods.
Full power was held until 1155 on June 20, when power was again reduced for control rod movements. At 1300, a slow increase from 770 MWe to full power was begun.
A lightning strike at 1505 caused numerous alarms, but no damage or trips. The unit reached full power at 2000 and held until 1151 on June 21.
The unit was in EGC at 1211 on June 21 and operated with only brief interruptions until 0817 on June 25.
Power was increased in steps from 734 MWe at 0822 to full power at 1305.
Full power was held until 1840.
The unit was operated in EGC frca 1848 until 2148 when a load reduction was started to facilitate surveillance and maintenance on circu-lating water equipment. At 0515 on June 26, power was raised from 600 to 725 MWe at 0615 and then slowly to full loed at 1745. Full load was held until 0345 on June 27.
At the request of the load dispatcher, power was reduced to 700 MWe and held from 0430 to 0715.
The unit was slowly increased in power and reached full load at 1850.
At 000 on June 28, 0027H/00612
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loud was reduced in steps at the request of the load dispatcher, to a minimum of 400 MWe which was held from 0605 to 0730.
Power was increased, and the unit reached full load at 1330 on June 29.
Full load was held until 1325 on June 30.
The unit was placed in EGC at 1328 and operated for the rest of the day.
B.
Unit 2 June 1-15 Unit Two held full load for the first three days of June and until 0805 on June 4.
The unit.was operated in EGC from 0840 on June 4 until 1328 on June 5.
The unit wao at full power from 1353 until 1845, it then went back in EGC and operated until 1620 on June 7.
The unit held full load from 1637 on June 7 until 0040 on June 13.
On June 10, there was a GSEP unusual event declared at 1907 and terminated at 2030 due to an earthquake in Southeastern'1111nois. On June 13 at 0040, there were control rod insertions to prepare for a flow control line determination.
The load drop for the FCL determination was begun at 0100 and reached a minimum of 408 MWe at 0202. The minimum load was held until 0230.
Power was raised to 750 MWe by 0315 and then slowly to full power by 1320.
Full load uas held.until 0853 on June 16.
June 16-30 June 16 began with the unit holding full load. Power was reduced for EGC at 0853. The unit was operated in EGC from 0932 until 1335, when EGC was
, tripped due to fluctuations in the reactor water level. The unit was increased to full load at 1424 and held load until 0105 on June 21.
At 1505 on June 20, there was a lightning strike which caused numerous alarms, but no damage or trips. At 0105 on June 21, there was a load reduction to facilitate testing of the turbine stop and control valves. Load was held l
at 750 MWe from 0130 to 0445 and returned to full power at 0520. At 0535, a load reduction was begun at the request of the load dispatcher.
The load reached a minimum of 707 MWe at 0640 and the unit was returned to full power by 0740. Full load was held until 0015 on June 23.
Following reversal of condenser flow, power was reduced to a minimum of 500 MWe at 0215 and held I
until 0530. Power was increased and the unit reached full load at 0950.
Full load was held until 0400 on June 26, when a power reduction was begun at th2 request of the load dispatcher. Load reached a minimum of 650 MWe j
at 0500 and was held until 0530. Power was slowly increased and the unit reached full load at 1607. On June 27, there was a slight load reduction j
from 0730 to 0855 in order to switnh condensate pumps. The unit continued j
to operate at full load until June 29.
At 0050 a rapid load reduction was
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performed as part of a special test of the units load following ability j
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while using barrier fuel. The load reached a minimum of 400 MWe, which was held from 0240 until 0510.
Power was increased and the unit reached full load at 0715. Full load was held until the next day, June 30.
At 0020, another rapid load reduction was performed for a load following test.
Power reached a minimum of 420 MWe at 0220 and was held until 0510.
Power was increased and at 0730 the unit reached full load, which it held for the rest of the day.
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k III.- PLANT OR PROCEDURE CHANGES TESTS EXPERIMENTS, AND SAFETY
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RELATED MAINTENANCE l
A.. Amendments to Facility License or Technical Specifications There were no Amendments to the Facility License or Technical
' Specifications for the reporting period.
t 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 Request Numbers, Licensee' Event Report Numbers, Components, Cause of Malfunctions, Results
'and Effects on. Safe Operation, and Action Taken to Prevent Repetition.
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I UNIT 1 MAINTENANCE
SUMMARY
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WORK REQUEST No.:
Q55741
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1 LER NUMBER:
N/A j
i COMPONENT:
System 1200 - Installed control transformer on Clean-Up Return
{
Isolation Valve 1-1201-80.
CAUSE OF MALFUNCTION: The cause of malfunction was current overload to Control Transformer MO-1-1201-80, due to end-of-life failure of relay 595-135.
1 RESULTS & EFFECTS ON SAFE OPERATION:
Operating personnel subsequently isolated f
the RWCU system.
The event did not jeopardize the health and safety of the public or affect safe plant operation.
ACTION TAKEN TO PREVENT REPETITION:
Both the relay and the control transformer were replaced.
The RWCU system was filled, vented, and returned to operation.
j No further corrective action is deemed necessary.
WORK REQUEST No.: Q56958 LER NUMBER: N/A COMPONENT:
System 7500 - Replaced bearings and greased with Chevron SRI 1/2-7506A.
CAUSE OF MALFUNCTION: There was no malfunction, but there was the possibility that two different greases had been used on the 1/2-7506A fan motor.
RESULTS & EFFECTS ON SAFE OPERATION: There was no effect on safe operation as a visual inspection was done indicating no bearing or grease problems.
ACTION TAKEN TO PREVENT REPETITION:
The action taken to prevent repetition was the implementation of signs to contact Electrical Maintenance before greasing the motor.
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1 WORK REQUEST _NO.: -Q57013.
LER NUMBER: li/A COMPONENT:
System 7500 - Replaced bearings and greased with Chevron SRI for 1/2-7506B.
CAUSE OF MALFUNCTION: There was no malfunction, but there was the possibility that two different greases had been used on the-1/2-7506B fan motor.
RESULTS & EFFECTS ON SAFE OPERATION: There was no effect on safe operation as a visual inspection was done indicating no bearing or grease problems.
ACTION TAKEN TO PREVENT REPETITION: The action taken to prevent repetition was I
the impicmentation of signs to contact Electrical Maintenance before greasing the motor.
WORK REQUEST No.: Q57387 LER NUMBER: N/A COMPONENT:
System 6600 --No problem found.
CAUSE OF MALFUNCTION: No problems were found with the relays associated with the lock out of the 1/2 Diesel Generator.
The prcbable'cause for the relay trip is attributed to vibration.
RESULTS & EFFECTS ON SAFE OPERATION:
The 1/2 Diesel Generator was made operable before any Technical Specification actions could be performed. The Unit One and Unit Two Diesel Generators were available to provide power if necessary. Also, the 1/2 Diesel Generator had just been successfully tested 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> earlier.
ACTION TAKEN TO PREVENT REPETITION: The immediate corrective action was to investigate and reset the "A" phase differential relay. A modification had been initiated prior to this event to replace all the Diesel Generator differential relays with ones less susceptible to vibration.
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UNIT 2 MAINTENANCE
SUMMARY
WORK REQUEST No.: Q52739 LER NUMBER:
86-15 COMPONENT:
System 1600 - Installed new gasket on U-2 DW Head Access Hatch, j
2-1600-X4.
1 CAUSE OF MALFUNCTION: The cause of the ILRT Failure was deterioration in the sealing ability of the drywell head flange seal material.
l RESULTS & EFFECTS ON SAFE OPERATION: The leakage, while it exceeded the limit for an ILRT, was still well below a value that would have caused serious impact to public safety in the unlikely event of a design basis accident.
ACTION TAKEN TO PREVENT REPETITION: The immediate corrective action was to replace the gasket with a type manufactured by Garlock.
Further investigation of a better i
choice of a seal material is continuing.
WORK REQUEST No.:
Q56878 LER NUMBER: N/A COMPONENT:
System 1600 - Replaced solenoid in A0 2-1601-56.
CAUSE OF MALFUNCTION: The cause of valve 2-1601.-56 to exceed its maximum stroke time was due to normal wear and dirt accumulation on the solenoid.
RESULTS & EFFECTS ON SAFE OPERATION:
Safety implications were minimal as the valve did close and the other "in-line" isolation valves were operable and closed ensuring that primary containment integrity was maintained at all times.
ACTION TAKEN TO PREVENT REPETITION: The immediate corrective action was to replace the solenoid. The valve 2-1601-56 was cycled three times and closure time was
-acceptable.
1 IV.
LICENSEE EVENT REPORTS The folloEing 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 Licensee Event Report Number Date-
-Title of Occurrence 87-011 6-12-87 RHR Embedment Plate Beyond-Design Stress.87-012 6-24-87 Relay 1-1701-100B Failure 87-013 6-29-87 Control Room HVAC.
. Toxic Gas Analyzer Trip UNIT 2 87-008 6-30-87 U2 Cable Tunnel Sprinkler 00S1P_14 Days I
0027H/0061Z-1
l 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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id' OPERATING DATA REPORT DOCKET NO.
50-254, UNIT.
DNE DATE7 JULY i '? B'7 _
COMPLETED DYK,A. SCHMIDT s'
1 C L F P H O N E 3 0 9 - 6 5 4 - 2 2 4_ 1_
OPERATING STATUS 0000 060187 1,
Reporting period:240.0 063087 Gross hours in reporting period: _.720 2.
Currently authorized power level (MWt): 2511 Mox, Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789
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3.
Power level to which restricted (if any)(MWe-Net): NA 4.
Reasons for restriction (if any):
lhis Month Yr,to Date Cumulotive S.
Number of hours reactor was critical 7&R.jl 4280.6 107093.3 6.
Reactor reserve shutdown hours 0.0 0,0 3 4 R.i. 9 0 7.
Hours generator on line 7RO.0 4264.6 113._5f31.1 8.
Unit reserve shutdown hours,
.,0. 0 0.0 909,2 9.
Gross thermal energy generated (MWH) 1699082 i_Qi4h3Jii
,_2112.04172
- 10. Gross electrical energy generated (MWH) 551694
- 3343420,
..._2.1096804
,6644651 ii. Net electricc1 energy generated (MWH) 527_1.ft.,
3197448 6
0
- 12. Recctor service factor 100.0 9 8 _._ft 80.7
- 13. Reactor ovollobility f ut' t or
..10 Q2 0 98.6 83.3
- 14. Unit service factor 100.0 9EL. a 78.1 15, Unit ovallobility factor f.90.0 98.2 78.7
- 16. Unit copocitv foctor (Uning MDC)
,,._ _ _. 95.2 95,7 65.3_
- 17. Unit copocity factor (Us.ing Des,MWe)
_ j2 R
_.._.93.3 63 2 2
- 10. Unit forced outage rate 0.0
.6 5.5 l
- 19. Shutdowns scheduled over next 6 months (Type,Date,and Duration of coch):
- 20. If shutdown at end of report period,estimoted date of startup. _ _. _.
tUNDFFICIAL COMPANY NU M ERS ARE USED IN THIS REPORT o
OPERATING DATA REPORT DOCKET NO.
50-265, UNIT.
TWO.
DATE7 JULY 1987..__
COMPLETED BYli.1 A S C H M I D _...
T TELEP HONE;LO(7-654-2241 OPERATING STATUS 0000 060187 1.
Reporting period:2400 0(1;3087 Gross hours in reporting period 720 2.
Currently authorized power 1cvel (MWt): 2511 Max, Depend capacity (MWe-Net): 769* Design electrical roting (MWe-Net): 789 3.
Power level to which restricted (if any)(MWe-Net): NA 4.
Reasons for restriction (if any)i lhis Month Yr.to Date Cumulotive S.
Number of hours reactor was critical 720.0 3715.7 101431.4 6.
Reactor reserve shutdown hours
, _ 0. J1 0.0 2985.8 7.
Hours generator on line 7E0.0 3662.7 98361.8 8.
Unit reserve shutdown hours.
... () d!.
0.0 702 2.
9.
Gross thermal energy generoted(MWH) 1 7 6 2.1 8 9 86.'/3033
_Ei_0038732
- 10. Gross electrical energy generated (MWH) 566140 281M53
_ 67173245
- 11. Het electrico) energy generated (MWH) 541814 2691432 63288469
- 12. Reactor service factor 100.0 85.6 77.0 13 Reactor ovallobility factor 100.0
.__85.6 79.2
- 14. Unit service factor 100.0 84.3 74.6
- 15. Unit avo11obility factor 100.0 84.3 75.2
- 16. Unit capacity factor (Using MDC) 97.9 80.6 67 5
- 17. Unit capacity Factor (Uning Des.MWe) 9 5. _ 41 78.5 60,9
- 18. Unit forced outage rate
]) 0 4.3 7.6 l
- 19. Shutdowns scheduled over next 6 nonths (Type,Date,ond Duration of coch):
- 20. If shutdown at and of report period,estinated date of startup
$UNDFFICIAL. COMPANY NUMBERS ARE USED IN THIS REFORT
APPENDIX B AVERACE DAILY UNIT POWER LEVEL DOCKET NO.
50-254 UNIT ONE DATE7 JulJ _1987. _.
(:OMPLETED BY!(.. &
SCHrilDT..
TELEP HONE;5 09;-654-2341 MONTH June 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) i.
772.7 17.
(>.B 3.. 3 2.
790.7 10.
644.5 3.
754 O 19.
7k_2 _.0 4,
727.2 20, 776.5 5,
752.3
- 21..
731.4 6,
727.5 22, 726.5 7.
723.5
- 23.,_
7 0 8._R.
8.
777.8 24.
75J).,_9 9.
734.0
- 25. _
712.6 10.
,__, 7i7.8 26.
7i5.0 ii.
720.6 27.
734.8 12.
750.0 28.
630._0_ _
13.
749.3 29, 766.4 14, 6f> 6. 0 30.
741.3 l
15, 762.2 16, 749.3 INSTRUCTIONS On this forn, list the overage dolly unit power level in tiWe-Net for each day in the reporting nonth.Cenpote to the nearest whole negawatt.
These figures will be used to plot a graph for enth reporting nonth. Note that when noxinen dependable capacity is used for the net electrical rating of the Unit there nup be occasions when the daily overage power level exceeds the 1901 line ter the rutricted power level line),.In soth costs,the overage daily unit power output sheet sheeld be festnoted to explain the apparent enonely
APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-265 UNIT.
TWO.._
DATE7_ JULY 1987 COMPLETED BYK_.A.._
SCHMIDT TELEPHONE;50E-654-2g4i..
i MONTH June 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1.
759.3 17.
749.9 2.
775.3
- 18. _
762...l.,
3.
759.7
- 19..__.
7622 4,
754.1 20.
782.#
5.
756.6 21.
738J 6.
_._725.8 22.
7 8.6 1. __
7.
726.4
- 23. _..
691.fa 8.
780.5 24.
770.i 9.
748.7 25, 746.5 10.
159.5 26.
757.H ii.
76i 9 27.
760_.1 760.3 12.
772.3 28.
13.
7_36.0 29.
72L 9 14.
761.2 30.
598..jl l
15.
7.'77.8 16, 76_0_.4 INSTRUCTIONS nearest whole, list the overage daily unit power level in MWe-Net for each day in the reporting nenth Compute to the On this forn necowett.
Thesefigureswillbeusedtoplotagraphforeachreportingnonth.Noteihotwhennoxinendependablecapacityis used for the net electrical rating of the unit,there may be occasions when the dail? overage power level exceeds the iHI line (or the restricted power level line).In soth cases,the overage daily unit power evtput sheet should be footnoted to explain the apparent anonaly
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i 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 There were no Main Steam Relief Valve Operations for the reporting period.
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.
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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.
0'Brien to C. Reed, et al., tf tied "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Information", dated January 18, 1978.
I 0027H,/0061Z l
l VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined below:
ACAD/ CAM Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI American National Standards Institute APRM Average Power Range Monitor Anticipated Transient Without Scram ATHS BWR Boiling Water Reactor CRD Control Rod Drive EHC Electro-Hydraulic Control System EOF Emergency Operations Facility Generating Stations Emergency Plan GSEP HEPA High-Efficiency Particulate Filter HPCI High Pressure Coolant Injection System HRSS High Radiation Sampling System IPCLRT Integrated Primary Containment Leak Rate Test IRM Interniediate Range Monitor ISI Inservice Inspection LER Licensee Event Report LLRT Local Leak Rate Test LPCI Low Pressure Coolant Injection Mode of RHRS Local Power Range Monitor LPRM MAPLHGR Maximum Average Planar Linear Heat Generation Rate 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 Primary Containment Isolation PCI Preconditioning Interim Operating Management Recommendations PCIOMR Reactor Building Closed Cooling Water System RBCCW RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System Residual Heat Removal System RHRS RPS Reactor Protection System RHM Rod Worth Minimizer Standby Gas Treatment System SBGTS Standby Liquid Control SBLC Shutdown Cooling Mode of RHRS SDC Scram Discharge Volume SDV Source Range Monitor SRM TBCCW Turbine Building Closed Cooling Water System TIP Traversing Incore Probe Technical Support Center TSC 0027H/0061Z
QTP 300-S32 1
Revision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST 1.
Unit:
01 Reload:
8 Cycle:
9 2.
Scheduled date for next refueling shutdown:
9-14-87 3.
Scheduled date for restart following refueling:
12-7-87 4.
Wl11' refueling or resumption of operation thereafter 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 AMENDKENT TO MOVE SINGLE LOOP OPERATION INTO TECHNICAL SPECIFICATIONS.
5 Scheduled date(s) for submitting proposed licensing action and supporting information:
AUGUST 21, 1987 6.
Important IIcensing considerations associated with refueling, e.g., new or
' different fuel design or supplier, unreylewed 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 LHGR LIMIT OF 14.4 KW/FT.
7 The number of fuel assemblies.
a.
Number of assemblies in core:
724 l
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 fuel:
3657 1
b.
Planned increase in licensed storage:
0 I
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 C3. <:. C). s. Ft.
t*
e QTP 300-S32-Revision 1
-QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST i
1., Unit:
02-Reload:
8 Cycle:
9 2.
Scheduled date for next refueling. shutdown:
3_14_88 3
Scheduled date for restart following refueling:
5-22-88 4.
Will refueling or resumption of operatloa thereaf ter require a technical i
specification change or other license amendment:
NOT AS YET DETERMINED.
5 Scheduled date(s) fo~r submitting proposed IIcensing action and supporting information:
DECEMBER 14, 1987 6.
Important licensing considerations associated with refueling, e.g., new or
' dif ferent 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:
1311 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 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 Ilcensed capacity: 2008 XPPROVED i
- APR 2 01978 j
CD. C:. C). S. R.
l Commonwealth Edison
- n..
ound Cities Nuclzar Power Station
,.I'
- 22710 206 Avenue North 1
Cordova, Illinois 61242 j
Telephone 309/654 2241
]
l
'I l
J
-RAR-87-31 i
July 2, 1987' i
U.S. Nuclear Regulatory Commission-Attn:. Document Control Desk Office'of Nuclear Reactor Regulation
' Washington, D. C.
20555
' 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 June, 1987.
Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES. NUCLEAR POWER STATION f, h.R.A.Robey}-
Services Superintendent yk l
Enclosure I
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