ML20095D677
| ML20095D677 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 07/31/1984 |
| From: | Kalivianakis N, Kimler D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NJK-84-233, NUDOCS 8408230435 | |
| Download: ML20095D677 (24) | |
Text
,
4 QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JULY 1984 C(M10NWEALTH EDIS0N 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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s TABLE OF CONTENTS 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 B.- Facility or Procedure Changes Requiring NRC Approval C.
Tests and E:tperiments 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 J
VI. Unique Reporting Requirements A.
Main Steam Relief Valve Operations B.
Control Rod Drive Scram Timing Data VII.
Refueling Infomation VIII. Glossary
- a I.
INTRODUCTION Quad-Cities Nuclear Power Station 'is camposed 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 Systens are General Electric Campany 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. Camercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 forUnitTwo.
This report was campiled by Becky Brown and Dave Kimler, telephone number 309-654-2241, extensions 127 and 192.
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II.
SUMMARY
OF OPERATING-EXPERIENCE A.
Unit One
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Unit One remained shutdown throughout the month for End of Cycle
.Seven Refueling and Maintenance.
B.
Unit Two July 1-6i Unit Two began the month in a reduced load state for weekly t
Turbine tests. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> the unit began a normal load increase to full power. At 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />, on July 3, load was dropped to 730 MWe for a Condensate - Demineralizer changeover. At 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> the unit began a normal load increase to full ;x)wer. -At 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />, on July 4, and 2
0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br />, on July 6, load was reduced for high Local Power Range Monitor (LPRM) indication.
.e
. July 7-17: At 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, on July 7, load was dropped to 550 MWe for weekly Turbine tests.
During this reduction, a Control Rod pattern adjustment was initiated also. At 0520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> the unit began normal increase to full power. At 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, on July 15, load was' dropped i
to 700 MWe for weekly Turbine tests. At 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> the unit began a normal load increase to full power. At 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br />, on July 17, load
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was dropped to 700 MWe for testing on the 2B Reactor Feedwater Pump.
At 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br /> the unit began a normal load increase to full power.
July 18-31: At 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br />, on July 22, load was dropped to 700 MWe for weekly Turbine tests. At 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> the unit began a normal load
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increase to full power. At 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, on July 29, load was dropped to 700 MWe for weekly Turbine tests. At 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br /> the unit began a 1
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normal load increase to full power.
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III.
PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.
Amendments to Facility License or Technical Specif! cations On July 13, 1984, the NRC issued Amendments 77 and 86 to License DPR-29 Amendment 77 updates tables regarding instrumentation that initiates or controls core and containment cooling systems and the minimum test and calibration f requency for this instr umentation based on an undervoltage condition on the 4KV emergency buses.
Amendment 77 also updates Auxiliary Electrical Systems Surveillance requirements for the Emergency Diesel Generators. Amendment 86 updates the Auxiliary Electrical Systems Surveillance Requirements, Limiting Conditions for Operation Bases, and Surveillance Requirements Bases for the Reactor Protection Bus Power Monitoring System.
B.
Facility or Procedure Changes Requiring NRC Approval j
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 Unit One and Unit l
Two during the reporting period. This summary includes the following headings: Work Request Numbers, LER Numbers, Components, Cause of Halfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.
UNIT ONE MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R.
LER OF ON ACTION.TAKEN TO NUMBER NUMBER COMPONENT MALFUNCT10N SAFE OPERATION PREVENT REPETITION Q32294 Thermostat on Thermostat tripped The 1/2.'ASBGTS The thermostat was 1/2 'B' Standby when the 1/2 'B' was started and ran
, reset, and did'not Gas Treatment SBGTS was started.
. satisfactorily; thus, trip when 1/2
'B' System lleater minimizing the con-SBGTS was' restarted,
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sequences of this
~ Reference Modifica-deviation. Reference tion M-4-l/2-83-21'
' Deviation Report for further corrective 4-1-84-40, action.
Q32779 Breaker tripped Loose terminal at The valve was opened Checked all termina-While Operating Motor Control manually immediately, tions at the valve land Valve MO l-1402-
- Center, and the in-line 1402-Motor Control Center.
258 248.was' shut. The' Also, took current.
Other loop of Core
. reading, which showed Spray was available, no excessive current.
I as was all other during valve operation.
ECC systems. The safety' implications were minimal.
Q33755 84-2 Valve 50 1-2499-Valve did not seat
. Reference LER 84-2.
The leakage rate'was 4B Leaks completely..
The in-line valve reduced to an Excessively 50 1-2499-3B would acceptable value for.
have provided PCI
.startup, function.
Q33756 84-2 Valve S0 1-2499-
-Valve did not seat The in-line valve The leakage rate was 4A Leaks completely.
S0 l-2499-3A would' reduced to an Excessively have provided PCI acceptable value for
-function. Reference startup.
LER 84-2.
Q35138 84-2 A0 1-8803 Leaks incomplete seating Reference LER 84-2.-
The leakage was Excessively of valve.
A0.1-8804 would have reduced to an provided PCI function.
acceptable value for i.
startup.
UNIT ONE MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R.
LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q35257 84-2 Shear Lug Degraded 0-ring Leak was 8.5% of La.
Replaced 0-rings on Inspection Hatch seals.
Reference LER 84-2.
all shear lug
- 1 Leaks inspection hatches.
Q35428 84-2
'B' inboard 0-ring seating Reference LER 84-2.
The leakage was Feedwater Check imp rope rl y, reduced to an Valve Leaks acceptable value for startup.
Q35586 84-2 Drywell Head Bad gasket.
Reference LER 84-2.
Leakage was reduced to Access Hatch an acceptable level by Leaks replacing gasket.
Q35842 RilR Service Water Dirt accumulation Reference Deviation Valve was cleaned and Vault Sump Pump in lift-check valve.
Report 4-1-84-33 tested satisfactorily.
Discharge Check Valve Leaks Q35843 RHR Service Water Dirt accumulation Reference Deviation Valve was cleaned and Vault Sump Pump in lift-check valve.
Report 4-1-84-33 tested satisfactorily.
Discharge Check Valve Leaks Q35913 CRD 34-51 uill uncoupling rod Unit was shutdown for Uncoupling rod was Not Latch-Up inserted off refueling. No safety installed correctly centering hole.
implications and tested satisfac-associated with this
- torily, defect.
Q36038 84-2 HPCI Steam Exhaust Not seating properly. The in-line 1-2301-74 A new valve was Check Valve Leaks valve would have installed to bring provided the necessary leakage to an PCI function. Reference acceptable value before LER 84-2.
startup.
O e
ONE UNIT MAINTENANCE
SUMMARY
t CAUSE RESULTS & EFFECTS W.R.
LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION l
Q36212 Corroded Leads Broken wire in in the unlikely event Reconnected wire.
on Condenser switch mechanism, of a condenser pit Tested satisfactorily.
Pit 5 Ft. Level cyclic fatigue.
flooding, the other This is first failure Switch 1-4441-switches would have of these switches.
25A provided an alarm No other corrective and a circulating action deemed necessary, water pump trip.
Reference Deviation Report 4-1-83-13 Q36248 RHR Service Water Dirt accumulation Reference Deviation Valve was cleaned and Vault Sump Pump in lift-check valve. Report 4-1-84-38.
tested satisfactorily.
Discharge Check Valve Leaks Q36396 ID RilR Service Latch stops out of Leak was very small.
Adjusted latch stops.
Vater Vault adjustment.
The sump pump inside Submarine Door could handle the Leaks flow incurred in the unlikely event of condensate pit fl ooding.
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UNIT M
MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R.
LER OF ON ACTION TAKEN TO NUMSER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITI0II Q25444 83-18 Reactor Water Unknown. Suspect Indication was 20%
Line was replaced Clean-up Line IGSCC induced thru-wall, and 11 from line 2-1025-20" Pipe Cracks indications, inch long.
to MO 2-1201-2. Short i
(2-1202-6"A) downstream of MO 2-1201-2 replaced also.
Q36070 84-8 Valve 110 2-Unknown.
All other ECC systems Failure could not be 2301-48 available. Valve was reproduced. Current Breaker Tripped immediately re-opened.
reading does not l
HPCI was unavailable indicate a problem, for only a short period of time.
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IV. LICENSEE EVENT REPORTS 4
The following is a tabular sumary of all licensee event reports for Quad-Cities Units.One and Two occurring during the reporting period, pursuant to the reportable occurrence reportinq requirements as set forth in sections 6.6.8.1. and 6.6.B.2. of the Pechnical Specifications.
UNIT ONE There were no Licensee Event Reports for Unit One for the reporting period.
UNIT TWO Licensee Event Report Number Date Title of Occurrence 84-8 7-4-84 HPCI 2-2301-48 Valve Inoperable 1
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V.
DATA TABULATIONS The following data tabulations are presented in this report:
j A.
Operating Data Report B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions
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OP R AT$kG DbTE REP 0ttT' Ts e,
DOCKET NO.
50-254
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,s UNIT ONE DATEAunust 8 CbMPLETED BYDAVE KIMLER TELEPHONE 309-654-224iXi92 OPERATING STATUS j
0000 070184,-
1.
Reporting period:2400 073184 Gross hours in reporting period:
744
- 2. Currently authorized power level (MWt):f2bii Max. Depend capacity
-(MWe-Net):.769* Design electrical rating (MWc-Net): 789 3.
Power level to which restricted (if any)(MWe-Net): NA
,4. Reasons for restriction (if any):
'~^
This Month Yr.to Date Cumulative
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5.
Number of hours reactor was criticol 0.0 1562.i-85117.7
- 6. Reactor reserve shutdown hours 0.0 0.0 3421.9 i
7.
Hours generator on line 0.0 1561.2 81909.i 8.
Unit reserve shutdown hours.
0.0 0.0 909.2 9-Gross thermal energy generated (MWH) 0 3659732 168766438
- 10. Gross electrical energy generated (MWH)'
0 1213148 54471764'
- 11. Net electrical energy generated (MWH)
-3423' 1144207 50750174
- 12. Reactor service factor 0.0 30.6 79.4
-g.
- 13. Reactor ovallobility factor 0.' O 30.6 82.6
- 14. Unit service factor 0.0 30.5 76.4
- 15. Unit avo11obility factor 0.0 30.5 77.3 16.-Unit copocity factor (Using MDC)
.6 29 i 61.6
- 17. Unit capacity factor (Using Des.MWels
,6 28.4 60,0 o
- 18. Unit forced. outage rate 0.0 0.0 6.1
- 19. Shutdowns scheduled over next 6 months (Type.,Date,and Duration of each):
20.'If shutdown at end of report period, estimated date ofstartup__0YI_0b_______
- The 19C nay be lever than 769 IWe during perleds of high onbient tenpdrotere due y te the therml' perforwace of the spray cual.
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- t310FFICIAL CollPANY Mul9ERS ARE USED IN THIS REPORT
OPERATING DATA REPORT DOCKET NO.
50-265 UNIT TWO DATEAuaust 8 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241Xi92 OPERATING STATUS 0000 070184 1.
Reporting period:2400 073184. Gross hours in reporting period:
744
- 2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical roting (MWe-Net): 789 3.
Power level to which restricted (if any)(MWe-Nat): NA 4.
Reasons for restriction (if any):
This Month Yr.to Date Cumulative 5.
Nunber of hours reactor was critical 744,0 3565.1 81482.6 6.
Reactor reserve shutdown hours 0.0 0.0 2985.8 7.
Hours generator on line 744,0 3455.0 78664.8 8.
Unit reserve shutdown hours.
0.0 0.0 702,9 9.
Gross thernal energy generated (MWH) 1820040 8100023 io3482iii
- 10. Gross electrical energy generated (MWH) 580384 2619090 52054870
- 11. Net electrical energy generated (MWH) 554452 2494629 48828689
- 12. Reactor service factor 100.0 69.8 76.7
- 13. Reactor ovallobility factor 100.0 69.8 79.5
- 14. Unit service factor
_100.0 67.6 74.0
- 15. Unit ovallobility factor 100.0 67.6 74.7
- 16. Unit capacity factor (Using MDC) 96.9 63.5 59.8
- 17. Unit capacity factor (Using Des.MWe) 94.5 61.9 58.3
- 18. Unit forced cutoge rate 0.0 4.1 8.4
- 19. Shutdowns scheduled over next 6 months (Type, Dote,and Duration of each):
- 20. If shutdown at end of report period,estinated date of startup _____NA______
$The MDC ncy be lower than 769 MWe during perleds of high anblent tenperatsre due to the thernal perfernance of the sprop canal.
$UN0FFICIAL COMPANY HUMBERS ARE USED IN THIS REPORT U
APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-254 UNIT ONE DATEAuaust P COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241Xi92 MONTH July 1984' DAY AVERAGE DAILY POWER LEVEL-DAY AVERAGE DAJLY POWEN LEVEL (MWe-Net)
(MWe-Net) 1.
-3.6 17.
-5.3 2.
-4,5 18.
-6.7 3.
-4.3 19.
-6.5 4.
-4.2 20.
-6.4 5.
-4.0 21.
-6.6 6.
-2.0 22.
-6.8
.7.
-3.5 23.
-7.3 8.
-4.8 24.
-6.2 9.
-4.8 25.
-6.5 10.
-4.5 26.-
-7.0 11.
-5.3 27.
-6.4 12. -
-4.9 28.
-6.4 13.
-6.3 29.
-6.6 P
14.
-5.6 30.
-6.5 15.
-5.8 31.
-7.4 16..
-6.1 INSTRUCTIONS neerest whole, list the neerage daily snit power leoel in blie-Wet for each day in the reporting nonth Conpete to the On this forn negawatt.
-These figeres ulIl be esed to plot a graph for each reporting nenth. Note that when notinen dependable capacite is
- esed for the net electrical rating of the unit there may be occasions when.the daily seerage power level exceeds the
-illI line (or the restricted power leetl line),In such cases,the estrage daily snit power output sheet sheeld be festnoted to explain the apparent onenely s
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- APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET'NO.
50-265 UNIT TWO DATE&yaust 8 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241Xi92 MONTH' -
Julv'i984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) i 1.
740.5 17.
736.9 2.
772.4 18.
773.8 3.
734.2 19, 764.8 4.
762.6 20, 770.8 5.
739.6 21, 758.5 6.
750.6 22, 730.9 7,
571.6 23.
754.0 8.
671.1 24.
760.3 9.
757.3 25.
772.3 10.
758.9 26, 742.9 1.
ii.
764.1 27.
'766.5 12.
758.9 28.
764.3 J
13.
762.4 29.
740.8 14, 753.6 30, 760.3 15.
720.0 31, 760.7 16.
764.2 INSTRUCTIONS On this forn, list the coeroge daily snit power level in Nie-Net for each day in the reportine penth.Conpete to the nearest whole negewett.
-These figeres will be esed to plot a graph for each reporting month. Note that when notinen dependable capacity is used for the net electritet rating of the enit there noy be occasions when the daily everage power level exceess the 1HI line (or the restricted power level line).,In such cases,the average daily snit power setpet sheet sheeld be festnoted to explain the opperent onenely w
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ID/SA APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET No.
050-265 August 1982 UNIT NAME Quad-Cities Unit 2 CORRECTED COPY COMPLETED BY D Kimler DATE August 6, 1984 REPORT HONTil JUNE 1984 TELEPil0NE 309-654-2241 5
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DURATION M
EVENT o
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DATE (IlOURS)
REPORT NO.
CORRECTIVE ACTIONS / COMMENTS O
84-19 840601 S
0.0*
B 5
RC CONROD Reduced load for rod maneuver in preparation for unit shutdown 84-20 840602 S
57.8 8
2 ED TRANSF Manually scrammed unit to repair oil leak on Transformer 21 84-21 840606 S
0.0*
H 5
RC CONROD Reduced load to perform Control Rod maneuver per Nuclear Engineer 84-22 840610 S
0.0*
B 5
CD VALVEX Reduced load to perform bi-weekly Main Steam Isolation Valve test 84-23 840610 F
18.1 A
3 CC VALVEX Reactor scram due to ' FAST' closure of
- 4 Control Valve during testing 84-24 840611 S
0.0*
B 5
CH VALVEX Reduced load to allow Maintenance to work on Feedwater Heater Valve 84-25 840613 S
0.0*
H 5
RC CONROD Reduced load to perform Control Rod maneuver per Nuclear Engineer
- CORRECTE D FIC URES F0P JUNE 1984 r EPORT APPROVED AUG 1 G 1982
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ID/SA APPENDIX D QTP 300-S13 UNIT SilUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.
050-265 August 1982 UNIT NAME fiuad-Ci ties Unit 2 CORRE CTE') COPY COMPLETED BY D Kimler DATE August 6, 1984 REPORT HONTil JUNE 1984 TELEPil0NE 309-654-2241 5
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DURATION d
EVENT o"
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DATE (lf0URS)
REPORT NO.
CORRECTIVE ACTIONS / COMMENTS o
84-26 840616 s
0.0*
B 5
HA TURBIN Reduced load to perform weekly Turbine tests 84-27 840624 s
0.0*
B 5
HA TURBIN Reduced load to perform weekly Turbine tests 84-28 840630 s
0.0*
B 5
HA TURBIN Reduced load to perform weekly Turbine tests
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ID/5A APPENDIX D QTP 300-S13 UNIT SilUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.
050-254 August. 1982 UNIT NAME Quad-Cities Unit I COMPLETED BY D Kimler DATE August 2, 1984 REPORT MONTil JULY 1984 TELEPIIONE 309-654-2241 N
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M EVENT U"
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NO.
DATE (IIOURS)
REPORT NO.
CORRECTIVE ACTIONS / COMMENTS A
84-14 840306 S
744 C
1 RC FUELXX Unit One remains shutdown for End of Cycle Seven Refueling and Maintenance J
APPROVED AUG 1 G 1982
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ID/SA APPENDIX D QTP 300-S13 UNIT SilUTDOWNS AND PCWER REDUCTIONS Revision 6 DOCKET NO.
050-265 August 1982 UNIT NAME Quad-Cities Unit 2 COMPLETED BY D Kimler DATE August 2, 1984 REPORT HONTil JULY 1984 TEI.EP110NE 309-6S4-2241 H
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No.
DATE (IIOURS)
REPORT NO.
CORRECTIVE ACTIONS / COMMENTS o
84-29 840703 S
0.0 B
Cll DEMINX Reduced load to perform Condensate Demineralizer changeover.
84-30 840704 S
0.0 H
1B INSTRU Reduced load due to high LPRM reading 84-31 840706 S
0.0 H
IB INSTRU Reduced load due to high LPRM reading 84-32 840707 S
0.0 B
HA TURBIN Reduced load to perform weekly Turbine tests 84-33 840715 S
0.0 B
HA TURBIN Reduced load to perform weekly Turbine tests 84-34 840717 S
0.0 B
CH PUMPXX Reduced load to perform test on 2B Reactor Feedwater Pump 84-35 840722 S
0.0 8
HA TURBIN Reduced load to perform weekly Turbine tests 84-36 840729 5
0.0 B
HA TURBIN Reduced load to perform weekly Turbine tests APPROVED AUG 1 G 1982
, (final) yCUbH
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.
4 4
4
VI I.
REFUELING INFORMATION The following infonnation about future reloads at Quad-Cities Station was requested in a January (78-24).from D. E. O'Brien to C. Reed, et al. licen 26, 1978 ti tled Dre sden, Quad-Cities, and Zion Station--NRC Request for Refueling Infonnation",
dated January 18, 1978.
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QTP 300-S32 l
Rnvision 1 I
QUAD-CITIES REFUELING Harch 1978 INFORMATION REQUEST l
1.
Unit:
Q1 Reload:
7 Cycle:
8 Refueling Outage 2.
Scheduled date for next refueling shutdown:
Currently in Progress t
3 Scheduled date for restart following refueling:
8-11-84 4.
Will refueling or resumption of operation thereaf ter require a technical g-specification change or other IIcense amendment: Yes.
Preparatory Technical Specification changes have been submitted to include MAPLHGR curve for one of s
the reload fuel types and extendi'ng MAPLHGR curve for BLTA to 45,000 MWD /t.
[
5.
Scheduled date(s) for submitting proposed licensing action and supporting Information:
{
Technical Specification change has been submitted February 21, 1984.
6.
Important Ilcensing 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 procedires:
1)
All new fuel assemblies will be GE7B-type (barrier clad, extended exposure design).
2)
A generic methodology was used for the analysis of the Control Rod Drop Accident and Rod Withdrawal Error events.
3)
Four Barrier Lead Test Assemblies will be re-inserted to gather information on the effects of extended exposures.
7 The number of fuel assemblies.
a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
1926 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 b.
Planned increase in IIcensed storage:
0 9
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2003 4PPROVED
. APR 2 01978 Q.C.O.S.R.
( _._. -.. _ _...
L... '
QTP 300-S32 Ravision 1 g
l QUAD-CITIES REFUELING March 1978
[,
INFORMATION REQUEST 7
[
1.
Unit:
Q2 Reload:
7 Cycle:
8 2.
Scheduled date for next refueling shutdown:
3-18-85 3
Scheduled date for restart following refueling:
5-26-85 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:
I#
January 18, 1985, i f licensing action requi red.
7
?
6.
Important licensing considerations associated with refueling, e.g., new or r'
' different fuel design or suppiler, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
1 1)
All new fuel assemblies will be GE7B-type (barrier clad, extended exposure design).
~
2)
A generic methodology was used for the analysis of the Control Rod Drop Accident and Rod Withdrawal Error events.
l
?
7 The number of fuel assemblies.
a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
414 8.
The present licensed spent fuel pool storage capacity and the size of any g
increase in IIcensed 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 IIcensed storage:
0
-d 9
~
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2003 i
XPPROVED APR 2 01978 Q.C.O.S.R.
r-r g
~
VIII. GLOSSARY The following abbreviations which may have been used-in the Monthly Report, are defined below:
Atmospheric Containment Atmospheric Dilution /Contaiment ACAD/ CAM Atmospheric Monitoring ANSI Anerican National Standards Institute Average Power Range Monitor APRM ATWS Anticipated Transient Wi thout Scram Boiling Water Reactor BWR CRD Control Rod Drive EHC Electro-Hydraulic Control System E0F Emergency Operations Facility Generating Stations Emergency Plan GSEP HEPA High-Efficiency Particulate Filter High Pressure Coolant Injection System HPCI HRSS High Radiation Sampling System Integrated Primary Containment Leak Rate Test IPCLRT Intennediate Range Monitor IRM Inservice Inspection ISI LER Licensee Event Report LLRT Local Leak Rate Test Low Pressure Coolant Injection Mode of RHRS LPCI LPRM Local Power Range Monitor MAPLHGR Maximum Average Planar Linear Heat Generation Rate Miniraum Critical Power Ratio MCPR Maximum Fraction Limiting Critical Power Ratio MFLCPR Maximum Pennissible Concentration MPC MSIV Main Steam Isolation Valve National Institute for Occupational Safety and Health NIOSH PCI Primary Containment Isolation PCIOMR Preconditioning Interim Operating Management Recommendations Reactor Building Closed Cooling Water Systen RBCCW Rod Block Monitor RBM Reactor Core Isolation Cooling System RCIC RHRS Residual Heat Removal Systen Reactor Protection System RPS Rod Worth Minimizer RWM Standby Gas Treatment System SBGTS SBLC Standby Liquid Control Shutdown Cooling Mode of RHRS SDC Scram Discharge Volume SDV SRM Source Ringe Monitor Turbine Buildin!1 Closed Cooling Water System TBCCW TIP Traversing Incore Probe Technical Support Center TSC
i i
q e
O Commonwealth Edison Quad Cities Nucle:r Power St:ti:n 22710 206 Avenue North Corcova, Illinois 61242 i
Telephone 309/654-2241 NJK-84-233 August 1,1984 Director, Office of Inspection & Enforcenent United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Document Control Desk Gentlemen:
Enclosed for your infonnation is the Ibnthly Perfonaance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of July 1984.
Very truly yours, COMMONWEALTH EDIS0N COMPANY QUAD-CITIES NUCLEAR POWER STATION
/h N. J. Kalivianakis Station Superintendent bb Enclosu re 9
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