ML20094S579
| ML20094S579 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/31/1992 |
| From: | Michael Benson, Tietz G COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GCT-92-016, GCT-92-16, NUDOCS 9204150176 | |
| Download: ML20094S579 (24) | |
Text
_ - _ _ - _ - _ _ _ _ _
Commonwealth Edison oaad Citios Nuclear Power Station 22710 206 Avenue North Corcova, Illinois 61242 Telephone 309/654-2241 GCT-92-016 April 2, 1992 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555
SUBJECT:
Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report NRC Docket Nos. 50-254 and 50-265 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 March 1992.
Respectfully,
. COMMONWEALTH EDIS0N COMPANY QUAD-CITIES NUCLEAR POWER STATION
$dC-db Gerald C,. Tietz U Technical Superintendent GCT/CALS/dak Enclosure cc:
A. B. Davis, Regional Administrator T. Taylor, Senior Resident Inspector o
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9204150176 920331
\\v PDR ADOCK 05000254
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QUAD-CITIES NUCLEAR P0HER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT MARCH 1992 COMMONHEALTH EDISON COMPANY AND IOHA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 r
N TS 14
TABLE OF CONTENTS I.
Introduction II.
Summary of Operating Experience A.
Unit One B.
Unit Two i
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 Repart B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions VI. Unique Reporting Requirements A.
Main Steam Reitef Valve Operations B.
Control Rod Drive Scram Timica r,ta VI' Refueling Information VIII. Glossary TS 14
i r
I.
1HIRODUCILON 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 & riectric Company.
The Nuclear Steam Supply Systems are General Electric Company Bolling Hater Reactors.
The Architect / Engineer sas 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, respective;y 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 Matt Benson and Debra Kelley, telephone number 309-654-2241, extensions 2995 and 2240.
TS M
1 II. SUMMARLDL0EER&UNG EXPERIENCE A.
UniL0ne L0n March 1, Unit One dropped to 450 HKe for "B" Gland Steam Exhaust Repairs.
Load drops occured on March 8 to 650 MWe-and March 15 to 328 MWe. - These_ drops were for CIV testing and Feedwater Heater maintenance respectively.
A final load drop occured or March 22 to 450 MWe for-1B Gland Steam Condenser level Control Valve repairs, l1 B.
Unit Two; Unit Two continued scheduled refuel outage.
i 1
70 14
l III. P1 ANT OR PROCEDURE _C11ANGE1 E II. EXPERIMENTS, AND_ SAFETY RELAIED_tBIRIEILANCE A.
Amendments to Facility License or Tetbattal_Specificatloni Tcchnical Specification Admendment No. 130 was issued on February 21, 1992 to facility Operating License No. DPR-30 for Quad Cities Nuclear Power Station, Unit 2.
This amendment revises the Technical Specifications to reflect the addition of 2 containment isolation valves, and a change in logic, to the HPCI System.
B.
fatllity_or Pratedure ChangeLRequitlag_HBC_Approyal There were no facility or Procedure changes requiring NRC approval for the reporting period.
C.
Inittand_ExpatimentLRequiring NRC..Anar_oNAl o
There were no Tests or Experiments requiring NRC approval for the reporting pe:ciod.
D.
Cortertfle MainttDAnte of S&Le.ty_ Belated Equipmen.t 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 Evant Peport Numbers, Components, Cause of Malfunctions, Results and Effects on SLfe Operaticm, and Action Taken to Prevent Repetition, i
TS 14
UNIT 1 MAINTENANCE
SUMMARY
WORK REQUESI SYSIIB EID DESCRIPTION HORK PERFORMED Repair soak back oil pump As Found:
Small piece of insulation and tape 1
l Q98670 6600 contactor on 1/2 Diesel Generator. stuck by contractor hinge caused the contactor to chatter. As Left: Removed foreign material from contactor then energized it.
Contactor cperated normally.
Q90500 6600 Repair cracked insulation near As Found:
Found brittle insulation around lugs on heater coil 1HC on the conductor. As left: Removed old wiring from 1/2 Diesel Generator control TRF10-X2, 1HC-HC and HD, and TB25C-11.
Replaced the internal wiring with 515 wire ar.d relabled the panel.
wiring.
Q98377 6700 Replace secondary disconnects on As Found:
Found broken phenolic on SBM switch and 4 KV breaker #35.
magnetic field side secondary disconnect.
There was scarfed insulation on several wire runs. As Left: Removed magnetic fleid side secondary disconnect and installed new disconnect.
Replaced l
wire from MF2-SBMB and HR4-SBMG. -Removed old SBM switch and installed new SBM switch.
l l
Q98890 7300 Repair breaker in Bus 29 cross As Found:
Found terminal Al sticking in contact tie has a defective secondary block. As Left: Disassembled secondary contact block and remove defective Al contact assembly.
disconnect.
i Replace assembly with a new contact assembly.
J 1
097082 7500 Repair leak on the glove port As Found:
Found cover gasket badly worn and not l
opening for rough prefilter.
enough adjustment left in clamos. As Left:
Caulked around opening before reinstalling cover and replaced adjustment screws in clamps.
Q84416 0020 Install aux. steel grating As Found:
Found grating in bad condition. As support brackets per ECN Left: Angles welded to beam and grating supported 04-00087H.
by same.
TS 15 y,
UNIT 1 MAINTENANCE
SUMMARY
HORK REOUEST SYSTEM EID DESCRIPTION HORK PERFORMEL Q83650 0030 Repair Cable jackets.foundl EHC damaged cable
> Sets repaired-using 3 half damaged during cleaning removal lapped layers of scc;ch 130c and I half lapped of EHC fluid.
.layerLof scotch.33t.
Q82801 0030 Inspect and repair as necessary, Cleaned. tray,' cleaned and inspected all cables.
cables damaged by EHC. fluid at Temporarily ID'ed damaged cables for future. repair.
Cable Tray 94713.
Q82802 0030 Inspect and repair as necessary-Cleaned cable tray Node 947H5 and repaired 3 cable damaged by EHC Fluid at damaged cables..
cable tray 947MS.
082803 0030 Inspect and repair as necessary Cleaned cables and tray, also repaired 2 damaged cable damaged by EHC fluid at cables.
cable tray 947M2.
Q82804 0030 Inspected and repair as necessary Cleaned cables and tray'in 947M1 Temporarily.
l cables damaged by EHC fluid at labeled damaged cables for future repair.
cable tray 947M1.
j TS 15
UNIT 2 MAINTENANCE
SUMMARY
HORK REQESI SYSTEM EID DESCRIPIJ')]f HORK PERFORMED 097739 0260 Repair APRM 4-6 Flow Converter.
As Found:
found converter damaged and zero adjustment not working. While converter was being tested the circuit board began to smoke. As Left: Replaced converter with one from Dresden which was calibrated in IM shop. Rejected old converter to vendor for refurbishment under Work l
Request Q98716.
098710 0261 Repair U2 MSIV Temperature switch Replaced fitting with 3/4 in. conduit Pulling 90.
conduit fitting.
Q98149 0261 Repair RHR Recirc Pump As Found:
Found torque tube on bellows assembly differential pressure switch.
was binding no repeatability on instrument. As Left: Replaced switch assembly and bellows assembly. Also calibrated switches and indicator.
098233 0261 Replace RHR Recirc pump As Found: Switch lock screw was broken and unable differential pressure loop select to secure switch. As Left: Removed old switch logic 2-261.
and installed replacement, installed new test fittings on low and high side, installed new caps i
and new tubing adapters. Calibrated switch and Indication and restored to orig 1 rial condition.
Q97602 0263 Investigate and repair supply' Voltage is within acceptable tolerance when the voltage found to be out of range, transmitter is unloaded. 0AD to remove 200 OHM on Reactor vessel level upper 400. resistor from input card under Work Request 098903 to adjust card for signal in a 10-50 MA loop.
TS 15
I UNIT 2 MAINTENANCE
SUMMARY
E.RK REQUESI SYSTEM EID DESCRIPTION HORK PERFORMED 098949 0300 Repair leak on accumulator foi As Found:
Fotnd 0-Rings to be flat and pliable, valve 2-0305-111.
some minor dirt. As Left:
Hiped clean and installed new 0-Rings and valve.
Lubricated and hand tighten torquing to 50 ft. Ibs.
Q97387 0750 Investigate and repair LPRM As Found:
LPRM is bypassed, and no longer reads24-49C which has hard hi signal.
upscale when not in bypass. As Left: Did TDR traces, appears problem could be under pot or detector.
Replaced connector under pot using Work Request Q92438.
LPRM is now reading zero.
099033 0902 Trouble shoot push button on As Found:
Found relay was loose in its socket.
902-5 panel.
As Left:
Replaced relay and tested good.
Q98251 1000 Repair limitorque for RHR torus As Foand:
Found motor pinion gear had walked of dump valve, Unit will not its shaft, oil seal on motor shaft leaking, and declutch.
bearings were bad. As left:
Put limitorque in manual three times worked fine. Rejected motor and new motor to be installed on Q92529.
l 098702 1000 Repair contacts 12 & 12C on As Found:
Found terminal #12 and #13 to be open l
limitorque valve for 2B RHR and wires 12 and 12C were crimped on insulation.
l suction valve.
As left: Crimped new lugs on 12 and 12C cable is
- 14 ANG.
Terminals #12 and #13 now read 1.0 OHMS. Control successfully stroked the valve.
Q98790 2400 Investigate and repair Channel A At X-20 used bias pot to adjust reading to 10R/hr monitor reading 3 times higher (per checked exposure rate). At X-2 used slope than source or Channel B.
pot to adjust reading down to 100 R/hr. (per checked exposure rate). Hent back to the minimum and took "As lefts".
Q98536 3900 Investigate and repair valve As found:
Found valve handwheel and top of stem 1
handwheel which broke off RHR broken off. As left: Replaced valve bonnet Service Water low pressure piping. assembly with new one.
TS 15
UNIT 2 MAINTENANCE
SUMMARY
HORK RE00EST SYSTEM EID DESCRIPTION HORK-PEPFORMED Q98535
.5200 Repair fuel oil leak.
As Found:
Nipple leaking on fuel pump diese1' line. Down stream brass 1/2 inch pipe nipple was cracked. As left:
Replaced both nipples where leak was detected.
Found leak at brazed "T" nipple.
New nipple was fabricated and installed by ENC under Work Request Q98560.
Q90858 5700 Disassemble 2A RHR Room Cooler As found: Cooler plugged with mud. As left:
for inspection by system engineer. Cleaned cooler ar.d reassembled it.
Q99216 6600 Remove thermocouple which is As Found:
Thermocouple.had been removed from #8 broken of in #8 cylinder for U2 cylindar exhaust' chamber but thermocouple fitting Diesel Generator.
was seized in place. As left: Strong backs were fabricated and placed over the remaining piece of the thermoc< ple fitting to seal off the exhaust.
Q98252 6600 Investigate why U2 Diesel As Found: Visual inspection of voltage regulator Generator voltage regulator KVARS found no problems. As Left: After visual swung excessively with Diesel inspection U2 Diesel Generator was run loaded and Generator loaded.
performed properly on 2-19-92 ind 2-29-92.
Q98736 6700 Relug and reland white-black As Found:
Found wire was in lug but pulled right conductor to terminal ZX-2, Cable out.
As Left:
Relugged the white-black conductor 20661 on Cubicle 8 Bus 23.
to terminal 2W-2 in Cubicle 8, Bus 23.
Removed to ty-raps and replaced with new.
097890 6700 Repair breaker on Bus 23-1 Adjusted jack nut in Cubicle 3 for proper breaker Cubicle 3.
operation and cleaned up cable side covers for cables so breaker can be installed properly.
Q98243 0830 Replace breaker for MCC 2A compt. As Found: Old breaker failed trip check. As t
on RHCU Recirc shutoff.
Left:
Installed new breaker and tested good.
i TS 15
. ~. - -
IV. LLCENSEE_LVERLREPORIS 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, i
UNIT 1 Licensee Event Report _Rudet DfLtg Title of Occuttence 92-007 02-28-92 CR Vent Isolation from CL detector 92-008
'03-11-92 1A & IB RHR. Room Coolers plugged.
This happened on 11/24/90 and 1/5/91.
Utill_2 92-007 03-04-92 2B RHR Hx Cooler tubes plugged.
92-008-03-16-92 ESF Actuation'while conducting RCIC logic test (ECCS Initiation) 92-009-03-26-92 Auto start of 2C and 2D RHR pumps.92-010 03-29-92 Low temperature on RPV' bottom head during hydro test.
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I l-TS 14
- i 1
V.
DAIA TABUL&Il0NS 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 I
l TS 14 V:
APPENDIX C OPERA 71NG DA1A REPORT DOCKET NO 50-254 UNIT QDe DATE April 2. 1991.
COMPLETED BY. tia.Lt_BtD8_on TELEPHONE 110.91,_654-2241 OPERATING STATUS 0000 030192-
- 1. REPORTING PERIOD: 2400 OL\\l2L GROSS HOURS IN REPORTING PERIOD: 744
- 2. CURRENTLY AUTHORIZED POWER LEVEL (HWt): 2511 MAX. DEPEND CAPAtliY: 769 DESIGN ELECTRICAL RATING (HWe-Net): 789
- 3. POWER LEVEL TO WHICH PEifRICTED (If ANY) (HWe-Net): N/A a
- 4. REASONS FOR RESTRICTION (IF ANV):
THIS HONTH YR TO DATE CUHULATIVE
- 5. NUMBER OF HOURS REACTOR WAS CRITICAL...........
744.0 1911.3 138422 1
- 0. REACTOR RESERVE SHUTDOWN HOURS..................
0.0 QA_
3421.9
- 7. HOURS GENERATOR ON LINE.........................
744.0 1B22 1 134123.1
- 8. UNIT RESERVE SHUTDOWN HOURS.....................
0.0 0.0 90h2._
- 9. GROSS THERHAL ENERGY GENERATED (HWH).........
1789300.0 4598294.4 288648324.4
- 10. GROSS ELECTRICAL ENERGY GENERATED (HWH)..........
J87483. 0_ _
,,J525DfBJ
.93579404.0
- 11. NET ELECTRICAL ENERGY GENERATED (HWH)..........<.
565454 1
_141 L Q
_B81H398.0
- 12. REACTOR SERVICE FACT 0R...........................
1004Q 87.51 79.07 i
- 13. REACTOR AVAILABILITY. FACT 0R.,....................
100JQ 81J1 81.03
.-_14. UNIT SERVICE FACTOR.............................
100.0A 86.63 76.62
'15. UNIT AVAILABILITY FACTOR........................
10DdQ 86d3
-77 14
-16. UNIT CAPACITY FACTOR (Using HDC)................
9AE3 87.35_
65.5g.
- 17. UNIT CAPACITY FACTOR (Using Design HWe)
_,_.9fn33 85.14 63.84
- 18. UNIT FORCED OU1 AGE RATE.........................
0.D_
13.31 5.84
- 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MON 1HS (TYPE DATE. ANu DURATION OF EACH):
- 20. IF SHUTDOWN AT END OF REPORT PERIOD ESTINATED DATE OF STARTUP:
- 21. UNIT 3 IN TEST STATUS (PRIOR TO CONHERCIAL OFERATION):
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION is u 1.16-9 1
1:
l-APPENDIX C OPERATING DATA REPORT DOCKET NO 50-165 1
UNIT Iwo
+
DATE ApriLZ 1992 COMPLETED BY Hatt Bensmt.
TELEPHONE - 1309L614-2141 OPERATING STATUS 0000
.030192
- 1. REPORT!NG PERIOD _.:
2400 033192_ GROSS HOURS IN REPOPTING PERIOD:
744
- 2. CURRENTLY AUTHORIZED POWER LEVEL (HWt): 2511 MAX. DEPEND. CAPACITY: 169 DESIGN ELECTRICAL RATING (HWe-Net): 289
- 3. POWER LEVEL TO WHICH RESTRICTED (If ANY) (HWe-Net): HLA
- 4. REASLNS FOR RESTRICT'ON (IF ANY):
THIS HONTH YR TO DATE CUHULATIVE
-5.
NUMBER OF HOURS REACTOR WAS CRITICAL............
0.0 0 25
- 133482d5
- 6. REACTOR RESERVE SHUTDOWN HOURS'..................
0.0 0.0 2985.8
- 7. HOURS GENERATOR ON LINE.........................
0.0
- 0. 2.5
_. 130020.415
- 8. UNIT RESERVE SHUTDOWN HOURS.....................
0.0 0.0 702.9.
- 9. GROSS THERHAL ENERGY GENERATED (HWH).............
0.0 175.2_
30Q84062.20
- 10. GROSS ELECTRICAL ENERGY GENERATED (PfdH)..........
0.0 50.0 89930240.0
__1977.0..
.350H9J 851183ffuD.
- 11. NET ELECTRICAL ENCRGY GENERATED (HdH).....,......
- 12. REACTOR SERVICE FACT 0R...........................
- 0. _
0 01 76.94
- 13. REACTOR AVAILABILITY FACTOR..................
0.Q,
0.01 78.66 14.' UNIT' SERVICE FACTOR.............................
0.0 0.Q1 74.94
- 15. UNIT AVAILABILITY FACTOR........................
0.0 0.01 75.35
- 16. UNIT CAPACITY. FACTOR (Using HDC)................
-ld4_
-0.94 63.BA
- 17. UNIT CAPACITY FACTOR (Using Design HWe).........
-1. 0Z[
QJZ 62.18
- 18. UNIT. FORCED OUTAGE RATE.........................
0.0 0 Q_
8.09
- 19. SHUTDOWNS. SCHEDULED OVER NEXT 6 HONTHS (TYPE. DATE, AND DURATION OF EACH):
- 20. IF SHUTDOWN AT END OF REPORT PERIOD. ESTD%TED DATE r STARTUP:
April 10. 1992
- 21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COHHERCIAL OPERATION 1.16-9 TS 14 -
APPENDIX B AVERAGE DAILY UNIT POWER LEVEL
-DOCKET N0 10-254 UNIT One DATE April 2._1992 COMPLETED.BY MittLBenson-
-TELEPHONE (309) 654-2241 MONTH March 1992 DAY AVEREAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MHe-Net)
(MHe-Net) 1.
560 17, 793 2.
791 18.
794 3.
793 19.
793 4.-
,92 20.
793
-5.
793 21.
784 I
6.
794 22.
638 7.
794 23.
791 8.-
759 24.
791 9.
793 25, 792 10.
791 26, 791 11.
791 27, 790 12.
793 28.
786 13, 795 29, 718 14.
794 30.
786 15.
334 31, 787 16.
685 INSTRUCTIONS On this form, list the average daily unit power level in MHe-Net for_ each day in the reporting month. Compute to the nearest whole megawatt.
These figures will be used to plot a graph for each reporting month.
Notti that when maximum dependable capacity is used for the net electrical rating of the~ unit, there may be occasions when the daily average power level exceeds t
the 1007. line (or the restricted power level line).
In such cases, the average daily unit _ power output sheet should be footnoted to explain the apparent anomaly.
Ts u 1.16-8
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APPENDIX B AVERAGE DAILY UNIT P0HER LEVEL l
DOCKET NO 50d65 UNIT Iwo DATE Apr_i L L _1192 COMPLETED BY MatLBftnion -
TELEPHONE 13_09) 654-2241 MONTH Jarch 1992 DAY AVEREAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MHe-Net)
(MHe-Net) 1.
-8
- 17. _
-8 2.
-8 18.
-8 3.
-8 19.
-8 4.
-8 20.
-8 5.
- - 8.
21.
- L__.
6.-
-8 22.
-8 7.
-8 23.
-8 8.
-8 24.
-8 j
9.
-8 25.
-8 10.
-8 2 6. __.
-8 11.
-8 27.
-8 12.
-8 28.
-8 13.
-8 29.
-8 14.
-8 30.
-8 15.
-8 31.
-8 16.
-8 INSTRUCTIONS On this form, list the average daily unit power level in MHe-Net for each day in_the reporting month. Compute to the nearest whole megawatt.
These figures will be used to plot a graph for each reporting month.
Note that when maximum dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line).
In such cases, the i
average daily unit power output sheet should be footr.oted to explain the
,g apparent anomaly.
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4 VI. -UNIQULREEDRUNLREQUIREMENIS 1
The following items are included in this report based on prior commitments to the comm1551on:
A.
Main _SteAHLRe11ef Valyl 0pertilous 1
There were no Hain Steam Relief Valve Operations for the reporting period.
B.
ConirOLRotDr.l.ye_SctaRLilm1Dg_Qata for UM1LQneJad_In There was no Control Rod 9 rive scram tim'ng data for Units One and Two for j
the reporting period.
(:
1.
71 14
d 4
VII. REEUIuliLINE0RM&Il01i 4
The following information about future reloads at Quad-Citivs 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 i
Station--NKC Request for Refueling Information", dated January 18, 1978.
-j e
TS 14 -
-j
~_
QTP 300-532 Revision 2 OUAD CITIES REFUELING October 1989 INFORMATION RE0 VEST 1.
Unit:
41 Reload:
11 Cycle: -
12 2.
Scheduled date for next refueling shutdown:
9-5-92 3.
Scheduled date for restart following refueling:
12-5-92 4.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:
NOT AS YET DE1E1011NED.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
NOT AS YET DETElO!!NED.
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 fort assemblies.
a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
1405 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.
Licens storage capacity for spent fuel:
3657 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:
2009 1
APPROVED OCT 3 01989 14/0395t O.C.O.S.R.
QTP 300 032 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST 1.
Unit:
02 Reload:
10 Cycle:
11 2.
Scheduled date for next refueling shutdown:
01/01/92 3.
Scheduled date for restart following refueling:
04/12/92 4.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:
Yes, as listed below:
- 1. Remove Table 3.7-2
- 2. Modification to turbine control valve fast actina, solenoid valve.
- 3. Modification to 11PCI turbine exhaust steam line.
- 4. HPC1/RCIC 24-hour shutdown action provision.
S.
Scheduled date(s) for submitting proposed licensing action and supporting /92information:
- 1. 01/15
- 2. 04/18/91
- 3. 06/28/91 4.
12/31/91 6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or per'ormance analysis methods, significant changes in fuel design, new operating procedures:
NONE AT PRESENT TIME.
7.
The number of fuel assemblies.
I a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
2439 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 I
planned in number of fuel assemblies:
l-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:
2009 APPROVED 14/0395t I
OCT 3 01989 0.C.O.S.R.
VIII.
GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined below:
ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Almospheric Honitoring ANSI
- American National Standards Institute APRH
- Average Power Range Monitor ATHS
- Anticipated Transient Hithout Scram CHR
- Boiling Hater Reactor CR0
- Contros (tod Drive EHC
- Electro-Hydraulic Control System EOF
- Emergency Operations facility GSEP
- Generating Stations Emergency Plan HEPA-
- High-Efficiency Particulate filter HPCI
- High Pressure Coo! ant Injection System HRSS
- High Radiation Sampling System IPCLr<T
- Integrated Primary Containment Leak Rate Test IRH
- Intermediate Range Honitor ISI
- Inservice Inspection LER
- Licensee Event Report LLRT
- Local Leak Rate Test LPCI
- Low Pressure Coolant Injection Mode of RHRs LPRH
- Local Power Range Honitor HAPLHGR - Maximum Average Planar Linear Heat Generation Rate HCPR
- Minimum Critical Power Ratio HFLCPR
- Maximum Fraction Liiniting 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 RBCCH
- Reactor Building Closed Cooling Water Systein RBH
- Rod Block Honitor RCIC
- Reactor Core Isolation Cooling System RHRS
- Residual' Heat Removal System RPS
- Reactor Protection System RWH
- Rod Horth Minimizer SBGTS
- Standby Gas Treatment System SP,LC
- Shutdown Cooling Mode of RHRS SDV-
- Source Range Monitor.
SRH
- Turbine Building Closed Cooling Hater System TBCCH-TIP
- Traversing Incore Probe TSC
L
~ TS 14 j
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