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l QUAD-CITIES NUCLEAR POWER STATION UNITS I AND 2 4
l QUAD-CITIES NUCLEAR POWER STATION UNITS I AND 2 4
MONTHLY PERFORMANCE REPORT FEBRUARY 1984-COMMONWEALTH EDIS0N COMPANY AND IOWA-ILLINOIS GAS & ELECTi'IC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 2
MONTHLY PERFORMANCE REPORT FEBRUARY 1984-COMMONWEALTH EDIS0N COMPANY AND IOWA-ILLINOIS GAS & ELECTi'IC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 2
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TABLE OF CONTENTS I.       Introduction i
TABLE OF CONTENTS I.
j           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-
Introduction i
                                        ~
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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 4
Summary of Operating Experience A.
V.     Data Tabulations A. Operating Data Report
Unit One B.
Unit Two III. Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A. -Amendments to Facility License or Technical. Specifications-
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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 4
V.
Data Tabulations A.
Operating Data Report
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B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions VI.       Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information VIII.       Glossary t
B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions VI.
Unique Reporting Requirements A.
Main Steam Relief Valve Operations B.
Control Rod Drive Scram Timing Data VII. Refueling Information VIII.
Glossary t
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I. INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company.
INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company.
The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent &
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.
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.
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 Becky Brown and Alex Misak, telephone number 309-654-2241, extensions 127 and 194.
This report was compiled by Becky Brown and Alex Misak, telephone number 309-654-2241, extensions 127 and 194.


II.
II.


==SUMMARY==
==SUMMARY==
OF OPERATING EXPERIENCE A. Unit One Febr uary 1-11 : Unit One began the month operating at full power and continued at this level until 0030 hours on February 5 when the unit dropped load to 700 MWe for weekly Turbine tests. Following the tests, the unit increased load to full power and maintained that load until February 7 when the unit began experiencing fuel depletion deratings due to end of cycle coastdown.
OF OPERATING EXPERIENCE A.
February 12-26: At 0001 hours on February 12, the unit dropped load to 700 MWe for weekly Turbine tests. Following the tests, the unit dropped load to 660 MWe for control rod pattern adjustments.
Unit One Febr uary 1-11 : Unit One began the month operating at full power and continued at this level until 0030 hours on February 5 when the unit dropped load to 700 MWe for weekly Turbine tests.
Following the tests, the unit increased load to full power and maintained that load until February 7 when the unit began experiencing fuel depletion deratings due to end of cycle coastdown.
February 12-26: At 0001 hours on February 12, the unit dropped load to 700 MWe for weekly Turbine tests.
Following the tests, the unit dropped load to 660 MWe for control rod pattern adjustments.
Following these adjustments, the unit began a normal load increase.
Following these adjustments, the unit began a normal load increase.
On two other occasions, February 19 and February 26, weekly Turbh~
On two other occasions, February 19 and February 26, weekly Turbh~
tests were performed which necessitated load reductions to 700 MWe.
tests were performed which necessitated load reductions to 700 MWe.
February 27-29: At 2215 hours on February 28, the unit dropped load to 650 MWe in preparation for an Economic Generation Control (EGC) system test. At 1230 hours on February 29, the unit increased load to 740 MWe and maintained this load until 1550 hours when the unit dropped load to 700 MWe in preparation for an EGC system test.         -
February 27-29: At 2215 hours on February 28, the unit dropped load to 650 MWe in preparation for an Economic Generation Control (EGC) system test.
B. Unit Two February 1-20: Unit Two began the month shutdown for End of Cycle Six Refueling and maintenance. At 0045 hours on February 18, unit startup commenced. At 0303 hours, the Reactor was critical, and the unit was on line at 1957 hours. At 2033 hours, the Turbine was manually tripped due to high Turbine vibration. At 0348 hours on February 19, the unit was placed on line with a load of 160 MWe, This load was ma'ntained until 1000 hours when the unit was shutdown to repair various valve packing leaks. The unit remained shutdown until 1820 hours on February 20 when the Generator was placed on line with a load of 150 MWe.
At 1230 hours on February 29, the unit increased load to 740 MWe and maintained this load until 1550 hours when the unit dropped load to 700 MWe in preparation for an EGC system test.
February 21-29: At 1730 hours on February 21, the unit began increasing load to 350 MWe by pulling control rods. Load was maintained at 350 MWe due to the 2B Recirculation Pump Motor-Generator Set being out of service for repairs. At 1405 hours on February 23, the unit was placed in Hot Standby due to high Turbine vibration. The unit was placed on line at 0210 hours on February 25 with a load of 180 MWe. At 1700 hours, the unit began increasing load to 500 MWe. At 1830 hours, the unit began a nornel shutdown to replace the notor on the 'B' Recirculation Pump Suction Valve. The unit was of f line from 2205 hours on February 25 to 0608 hours on February 27 when the Generator was placed on line, and a normal load increase was initiated.
B.
Unit Two February 1-20: Unit Two began the month shutdown for End of Cycle Six Refueling and maintenance. At 0045 hours on February 18, unit startup commenced. At 0303 hours, the Reactor was critical, and the unit was on line at 1957 hours.
At 2033 hours, the Turbine was manually tripped due to high Turbine vibration.
At 0348 hours on February 19, the unit was placed on line with a load of 160 MWe, This load was ma'ntained until 1000 hours when the unit was shutdown to repair various valve packing leaks. The unit remained shutdown until 1820 hours on February 20 when the Generator was placed on line with a load of 150 MWe.
February 21-29: At 1730 hours on February 21, the unit began increasing load to 350 MWe by pulling control rods.
Load was maintained at 350 MWe due to the 2B Recirculation Pump Motor-Generator Set being out of service for repairs. At 1405 hours on February 23, the unit was placed in Hot Standby due to high Turbine vibration. The unit was placed on line at 0210 hours on February 25 with a load of 180 MWe.
At 1700 hours, the unit began increasing load to 500 MWe.
At 1830 hours, the unit began a nornel shutdown to replace the notor on the 'B' Recirculation Pump Suction Valve.
The unit was of f line from 2205 hours on February 25 to 0608 hours on February 27 when the Generator was placed on line, and a normal load increase was initiated.
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III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY
III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE-i A.
,                          RELATED MAINTENANCE-i                           A. Amendments to Facility License or Technical Specifications On January 24, 1984, the NRC issued Amendment 80 to License DPR-30. This Amendment established new actuation setpoints for the Target Roc.k Safety Relief Valve and two Electromatic Relief Valves,       i t also defined new Minimum Critical Power Ratio limits for steady state operation at ' rated core flow. The Amendment also shows the new Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Planar Average Exposure curve for the new Unit Two core.
Amendments to Facility License or Technical Specifications On January 24, 1984, the NRC issued Amendment 80 to License DPR-30. This Amendment established new actuation setpoints for the Target Roc.k Safety Relief Valve and two Electromatic Relief Valves, i t also defined new Minimum Critical Power Ratio limits for steady state operation at ' rated core flow. The Amendment also shows the new Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Planar Average Exposure curve for the new Unit Two core.
B. Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure changes requiring NRC approval for the reporting period.
B.
C. Tests and Experiments Requiring NRC Approval There were no Tests- cr Experiments requiring _ NRC approval for the reporting period.
Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure changes 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 i and Unit 2 during the reporting period. This summary includes the following headings: Work Request Numbers, LER Numbers, Components, Cause of Mal functions, Results and Ef fects on Safe Operation,- and Action Taken to Prevent Repetition.
C.
Tests and Experiments Requiring NRC Approval There were no Tests-cr 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 i and Unit 2 during the reporting period. This summary includes the following headings:
Work Request Numbers, LER Numbers, Components, Cause of Mal functions, Results and Ef fects on Safe Operation,- and Action Taken to Prevent Repetition.
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UNIT OrlE     MAINTENANCE  
UNIT OrlE MAINTENANCE  


==SUMMARY==
==SUMMARY==
 
CAUSE RESULTS & EFFECTS W.R.
CAUSE                   RESULTS & EFFECTS W.R. LER                               OF                                                 ON                         ACTION TAKEN TO NUMBER NUMBER   COMPONENT             MALFUNCTION                 SAFE OPERATION                                       PREVENT REPETITION Q31892       1-3999-515A RilR     Rust and dirt froze         The valve leaked through                               The valve was dis-Service Water         the plunger,                 but the vault sump pump                                 assembled, cleaned, Vault Sump Dis-                                   maintained the integrity                               lapped, reassembled, charge Check Valve                                 of the vault.                                           and LLRT'd. An investigation was started concerning the vavle reliability.
LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q31892 1-3999-515A RilR Rust and dirt froze The valve leaked through The valve was dis-Service Water the plunger, but the vault sump pump assembled, cleaned, Vault Sump Dis-maintained the integrity lapped, reassembled, charge Check Valve of the vault.
  -Q31893       1-3999-516A RiiR     Rust and dirt froze         The valve leaked through                               The valve was dis-Service Uater         the plunger.                 but the vault sump pump                               assembled, cleaned, Vault Sump Dis-                                   maintained the integrity                               lapped, reassembled, charge Check Valve                                 of the vault.                                         and LLRT'd. An investigation was started concerning the valve reliability.
and LLRT'd.
An investigation was started concerning the vavle reliability.
-Q31893 1-3999-516A RiiR Rust and dirt froze The valve leaked through The valve was dis-Service Uater the plunger.
but the vault sump pump assembled, cleaned, Vault Sump Dis-maintained the integrity lapped, reassembled, charge Check Valve of the vault.
and LLRT'd.
An investigation was started concerning the valve reliability.
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UNIT                               TWO                             MAINTENANCE  
UNIT TWO MAINTENANCE  


==SUMMARY==
==SUMMARY==
 
CAUSE RESULTS & EFFECTS
CAUSE               RESULTS & EFFECTS
.W.R.
    .W.R.       LER                                                                                         OF                         ON                           ACTION TAKEN TO NUM8ER     NUMBER     COMPONENT                                                                   MALFUNCTION               SAFE OPERATION                   PREVENT REPETITION Q25817   83-6,'03L 2-203-2B tiSIV                                                 The               'B' channel       The ittiv failed to                   The limit switch Limit Switch                                                     10% closure limit                   ini tiate a hal f-scram               was replaced.
LER OF ON ACTION TAKEN TO NUM8ER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q25817 83-6,'03L 2-203-2B tiSIV The
switch failed.                       during testing. The half-scram was initiated mancally.
'B' channel The ittiv failed to The limit switch Limit Switch 10% closure limit ini tiate a hal f-scram was replaced.
    - Q27288             2-5401B SJAE                                                   ilorizontal position                 The valve did not                     The valve internals Suction Valve                                                 of valve.                             close. It was                         were cleaned. The manually assisted                     valve has a person closed.                               stationed near it to assist it, and is always, otherwise, kept closed. The valve has since been replaced.
switch failed.
Q28869'             2-54010 SJAE                                                 The valve was                           The valve failed to                   The SJAE suction Suction Valve                                                   improperly                           close on an                           valve has since been installed.                           isolation signal. It                   replaced with a is normally kept                       Butterfly valve.
during testing. The half-scram was initiated mancally.
- Q27288 2-5401B SJAE ilorizontal position The valve did not The valve internals Suction Valve of valve.
close. It was were cleaned. The manually assisted valve has a person closed.
stationed near it to assist it, and is always, otherwise, kept closed. The valve has since been replaced.
Q28869' 2-54010 SJAE The valve was The valve failed to The SJAE suction Suction Valve improperly close on an valve has since been installed.
isolation signal. It replaced with a is normally kept Butterfly valve.
closed.
closed.
Q28972   83-15/03L FCV 2-8802C-                                                 The valve internals                       .
Q28972 83-15/03L FCV 2-8802C-The valve internals The seat was lapped were worn.
The seat was lapped were worn.                               The valve leaked                       and the disc was substantially auring                   cleaned.
The valve leaked and the disc was substantially auring cleaned.
LLRT.
LLRT.
Q29176   83-15/03L CV 2-1301-41                                                 The valve internals                     The valve leaked                       The seat was lapped we re worn.                             s6bstantially during                   and the hinge pin, LLRT.                                 disc, and all seats
Q29176 83-15/03L CV 2-1301-41 The valve internals The valve leaked The seat was lapped we re worn.
                                                            ._.                                                                                                      and gas'kets were replaced.
s6bstantially during and the hinge pin, LLRT.
disc, and all seats and gas'kets were replaced.
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UNIT TU0   MAINTENANCE  
UNIT TU0 MAINTENANCE  


==SUMMARY==
==SUMMARY==
 
CAUSE RESULTS & EFFECTS W.R.
CAUSE             RESULTS & EFFECTS W.R.             LER                             OF                     ON               ACTION TAKEN TO NUMBER               NUMBER     COMPONENT           MALFUNCTION           SAFE OPERATION       PREVENT REPETITION Q30316                     Various Mechanical         Wear.           Various Mechanical       The Snubbers that Snubbers                                   Snubbers were             failed the functional functionally tested. test were sent to 9481, 7327, 7732,       Wyle Laboratories 16565, 16558, 12700,     to be overhauled.
LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q30316 Various Mechanical Wear.
Various Mechanical The Snubbers that Snubbers Snubbers were failed the functional functionally tested.
test were sent to 9481, 7327, 7732, Wyle Laboratories 16565, 16558, 12700, to be overhauled.
and 1488 failed.
and 1488 failed.
Q31102                     2-2301-5 had         The control and       The valve tripped during The cables were control and rnotor   motor cable had.     logic testing. It was   replaced and cables cable replaced.     failed due to a       not required ope rable   in the area and on small steam leak. at the time. The valve   Ul were inspected.
Q31102 2-2301-5 had The control and The valve tripped during The cables were control and rnotor motor cable had.
logic testing. It was replaced and cables cable replaced.
failed due to a not required ope rable in the area and on small steam leak.
at the time. The valve Ul were inspected.
would fail open to -
would fail open to -
provide llPCI service and the in-line 2-2301-4 valve would provide isolation.
provide llPCI service and the in-line 2-2301-4 valve would provide isolation.
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i IV. LICENSEE EVENT-REPCRTS a
i IV.
The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two_ occurring during the reporting
LICENSEE EVENT-REPCRTS a
,t period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.I. and 6.6.B.2. of the Technical Specifications.
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
l UNIT ONE i           Licensee Event
,t as set forth in sections 6.6.B.I. and 6.6.B.2. of the Technical Specifications.
;          Report Number                       Date             Title of Occurrence There were no Licensee Event Reports, for Unit One, for the reporting pe riod.
l UNIT ONE i
I l                                             UNIT TWO l           84-03/03L                           2-11-84           Loss of Rus.28 & 29 j           84-04/03L                           2-15-84           Reactor Scram While t                                                               Shutdown 2
Licensee Event Report Number Date Title of Occurrence There were no Licensee Event Reports, for Unit One, for the reporting pe riod.
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84-03/03L 2-11-84 Loss of Rus.28 & 29 j
84-04/03L 2-15-84 Reactor Scram While t
Shutdown 2
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V. DATA TABULATIONS The following data tabulations are presented in this report:
V.
A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions l
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 l
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r-                   _
r-9 OPERATING DATA REPORT DOCKET NO.
9 OPERATING DATA REPORT DOCKET NO.         50-254 UNIT       ONE DATEFebruarv 7 COMPLETED BYAlex Misok TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 020184
50-254 UNIT ONE DATEFebruarv 7 COMPLETED BYAlex Misok TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 020184 1.
: 1. Reporting period 2400 022984 Gross hours in reporting period:                                     696
Reporting period 2400 022984 Gross hours in reporting period:
696
: 2. Currently authorized power lev,, (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical '.nting (MWe-Net): 789
: 2. Currently authorized power lev,, (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical '.nting (MWe-Net): 789
: 3. Power level to which restricted (if any)(MWe-Net): NA
: 3. Power level to which restricted (if any)(MWe-Net): NA
: 4. Reasons for restriction (if any):
: 4. Reasons for restriction (if any):
This Month       Yr.to Date   Cumulative
This Month Yr.to Date Cumulative
: 5. Number of hours reactor was critical                                     696.0         1440.0       84995.6
: 5. Number of hours reactor was critical 696.0 1440.0 84995.6
: 6. Reactor reserve shutdown hours                                               0.0           0.0       3421.9
: 6. Reactor reserve shutdown hours 0.0 0.0 3421.9 7.
: 7. Hours generator on line                                                 696.0         1440.0       81787.9
Hours generator on line 696.0 1440.0 81787.9
: 8. Unit reserve shutdown hours.                                                 0.0           0.0         909.2
: 8. Unit reserve shutdown hours.
: 9. Gross thermal energy generated (MWH)                                   1643681         3406884     168513590
0.0 0.0 909.2
: 10. Gross electrical energy generated (MWH)                                   545050       1129512     54380128
: 9. Gross thermal energy generated (MWH) 1643681 3406884 168513590
: 11. Het electrical energy gencroted(MWH)                                     517997'       1073371     50679338
: 10. Gross electrical energy generated (MWH) 545050 1129512 54380128
: 12. Reactor service factor                                                     100.0         100.0           82.1
: 11. Het electrical energy gencroted(MWH) 517997' 1073371 50679338
: 13. Reactor avo11ob111ty factor                                                 100.0         100.0           85.4
: 12. Reactor service factor 100.0 100.0 82.1
: 14. Unit service factor                                                         100,30         100.0         79.0
: 13. Reactor avo11ob111ty factor 100.0 100.0 85.4
: 15. Unit availobility factor                                                   100.0         100.0           79.9 63.7
: 14. Unit service factor 100,30 100.0 79.0
                              ~
: 15. Unit availobility factor 100.0 100.0 79.9 L6. Unit capacity factor (Using MDC) 96.8 96.9 63.7
L6. Unit capacity factor (Using MDC)                                             96.8         96.9 L7. Unit capacity factor (Using Des.MWe)                                         94.3         94.5         62.1
~
: 18. Un it forced outage rate                                                       0.0           0.0           6.2
L7. Unit capacity factor (Using Des.MWe) 94.3 94.5 62.1
: 18. Un it forced outage rate 0.0 0.0 6.2
: 19. Shutdowns scheduled over next 6 nonths (Typa,Date,and Duration'of each):
: 19. Shutdowns scheduled over next 6 nonths (Typa,Date,and Duration'of each):
: 20. If shutdown at end of repcrt period, estimated dote of startup __"___________                       ^
: 20. If shutdown at end of repcrt period, estimated dote of startup __"___________
IThe MDC ney be lower then 769 MWe dering perleds of high onbient temperatore det to the tlwrm1 performece of tra sprey comd.                                                                         I i
^
sWOFFICIAL COMPANY NWBERS ARE USED IN THIS REPORT                                                                   )
IThe MDC ney be lower then 769 MWe dering perleds of high onbient temperatore det to the tlwrm1 performece of tra sprey comd.
I i
sWOFFICIAL COMPANY NWBERS ARE USED IN THIS REPORT
)


r __
r l
l                                              OPERATING DATA REPORT DOCKET NO.           50-265 UNIT         TWO DATEFebruarv 7 COMPLETED BYAlex Misok TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 020184
OPERATING DATA REPORT DOCKET NO.
: 1. Reporting period 2400 022984 Gross hours in reporting period:                                     696
50-265 UNIT TWO DATEFebruarv 7 COMPLETED BYAlex Misok TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 020184 1.
Reporting period 2400 022984 Gross hours in reporting period:
696
: 2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical roting (MWe-Net): 789
: 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-Net): NA
: 3. Power level to which' restricted (if any)(MWe-Net): NA 4.
: 4. Reasons for restriction (if any):
Reasons for restriction (if any):
This Month       Yr.to Date     Cumulative
This Month Yr.to Date Cumulative
: 5. Number of hours rinctor was critical                                       245.5         245.5         78163.0
: 5. Number of hours rinctor was critical 245.5 245.5 78163.0
: 6. Reactor reserve shutdown hours                                                 9.0           0.0       2985.8
: 6. Reactor reserve shutdown hours 9.0 0.0 2985.8
: 7. Hours generator on line                                                     160.3         160.3         75370.1
: 7. Hours generator on line 160.3 160.3 75370.1
: 8. Unit reserve shutdown hours.                                                   0.0           0.0         702.9
: 8. Unit reserve shutdown hours.
: 9. Gross thernal energy generated (MWH)                                     193783       193783     155575871-
0.0 0.0 702.9 9.
: 10. Gross electrical energy generated (MWH)                                     58218         58 rib     49493998
Gross thernal energy generated (MWH) 193783 193783 155575871-
: 11. Net electrical energy generated (MWH)                                       53862         53338       46307398
: 10. Gross electrical energy generated (MWH) 58218 58 rib 49493998
: 12. Reactor service factor                                                         35.3         17.0           76.2
: 11. Net electrical energy generated (MWH) 53862 53338 46307398
: 13. Reactor avullobility factor                                                   35.3         17.0           79 i
: 12. Reactor service factor 35.3 17.0 76.2
: 14. Unit service factor                                                           23.0         11.1           73.5 LS. Unit avo11ob111ty factor                                                     23.0         ii.i           '< 4. 2
: 13. Reactor avullobility factor 35.3 17.0 79 i
                                                          ~
: 14. Unit service factor 23.0 11.1 73.5 LS. Unit avo11ob111ty factor 23.0 ii.i
: 16. . Unit capacity factor (Using MDC)                                           10.1           4.8         58.8-
' 4. 2
                                                                                                      ~
~
L7. Unit capacity factor (Using Des.HWe)                                           9.8           4.7         57.3
: 16.. Unit capacity factor (Using MDC) 10.1 4.8 58.8-
: 18. Unit forced outage rate                                                       40.2         40.2'             B '.' 7
~
L7. Unit capacity factor (Using Des.HWe) 9.8 4.7 57.3
: 18. Unit forced outage rate 40.2 40.2' B '.' 7
: 19. Shutdowns schedule.d over next 6 months (Typc,Date,and Duration of each):1
: 19. Shutdowns schedule.d over next 6 months (Typc,Date,and Duration of each):1
: 20. If shutdown at end of teport p er i o d ,e st ina t ed dat e o f. s t ar t up , ___jiA______,.3 SThe 19C ney be lever then 769 mit dering per   7 of high onblent tenperstere det to the thernal perfernance of the grey cenei.
: 20. If shutdown at end of teport p er i o d,e st ina t ed dat e o f. s t ar t up, ___jiA______,.3 SThe 19C ney be lever then 769 mit dering per 7 of high onblent tenperstere det to the thernal perfernance of the grey cenei.
    $W10FFICIAl. ColtAIN lluleERS ARE USED H WIS REPORT
$W10FFICIAl. ColtAIN lluleERS ARE USED H WIS REPORT


i-APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.             50-254
i-APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
'                                                                                              UNIT           ONE DATEFehroorv 7 COMPLETED BYAlex Misok TELEPHONE 309-654-2241x194 MONTH             February 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL                                                                 (MWemlet)
50-254 UNIT ONE DATEFehroorv 7 COMPLETED BYAlex Misok TELEPHONE 309-654-2241x194 MONTH February 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWemlet)
(MWe-Net)
(MWe-Net) 1.
: 17.                         749.4
779.8 17.
: 1.                                779.8 768,3                                     18,                         746.8 2.
749.4 2.
: 19.                           737.9
768,3 18, 746.8 3.
: 3.                                 780.7
780.7 19.
: 20.                           744.5 4,                                  790.8
737.9 4,
: 21. .                         737.7
790.8 20.
: 5.                                  619.0 22,                         745,7
744.5 737.7 5.
: 6.                                 870.5 23,                         737.5
619.0
: 7.                                  783.1
: 21..
: 24.                         708.4
6.
: 8.                                 783.0 2F                           732.8
870.5 22, 745,7 7.
: 7.      __
783.1 23, 737.5 8.
777.7 780.8                                     26,                           713.8 10, 763,6                                   27.                           719.9 li.
783.0 24.
672.6                                     28,                         710.0 L2, 784.4                                     29.                         637.8 L3.
708.4 7.
L4,                                   749.0
777.7 2F 732.8 10, 780.8 26, 713.8 li.
: 15.                                 760.0
763,6 27.
: 16.                                 762.0 INSTRUCTIONS Cn this forn, list the overage daily unit power level in 1%ie-Net for each day in the reporting nonth Conpete to the nearest Whelt negawatt.
719.9 L2, 672.6 28, 710.0 L3.
These figures Will be ssed to plat a graph for each reporting conth. Note that when notinin dependable used 1981 line for the (or net the electrical restricted rating power of theline).
784.4 29.
level  init,In sich cases,the average daily snit power entpst sheet sheeld be festnetad to esplein the apperent onenaly I
637.8 L4, 749.0 15.
760.0 16.
762.0 INSTRUCTIONS Cn this forn, list the overage daily unit power level in 1%ie-Net for each day in the reporting nonth Conpete to the nearest Whelt negawatt.
These figures Will be ssed to plat a graph for each reporting conth. Note that when notinin dependable used for the net electrical rating of the init,In sich cases,the average daily snit power entpst sheet sheeld be 1981 line (or the restricted power level line).
festnetad to esplein the apperent onenaly I
I I
I I


APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.             50-265 UNIT           TWO DATEFebroorv 7 COMPLETED BYAlex Misak TELEPHONE 309-654-2241x194 HONTH             Febroorv 1984 DAY AVERAGE DAILY POWER LEVEL                                                   DAY AVERAGE DAILY P014ER LEVEL (MWe-Net)                                                                     (MWe-Net)
APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
: 1. _
50-265 UNIT TWO DATEFebroorv 7 COMPLETED BYAlex Misak TELEPHONE 309-654-2241x194 HONTH Febroorv 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY P014ER LEVEL (MWe-Net)
                                      -4.3                                         17.                             -7.8
(MWe-Net) 1.
: 2.                               -5.0                                         18.                           -11.0
-4.3 17.
: 3.                               -7.2                                         19,                             32.5
-7.8 2.
'    4.                               -7.4                                         20,                             17.6
-5.0 18.
: 5.                               -7.0                                         21,                           185.7
-11.0 3.
: 6.                               -7.4                                         22,                           330.0
-7.2 19, 32.5 4.
: 7.                               -7.7                                         23.                           147.7
-7.4 20, 17.6 5.
: 8.                               -6.3                                         24.                           -14.2
-7.0 21, 185.7 6.
: 9. _
-7.4 22, 330.0 7.
                                      -6.1                                         25.                           155.9 to.                               -6.0                                         26.                             -9.8
-7.7 23.
: 11.                               -6.0                                         27.                           276.2-
147.7 8.
: 12.                               -6.9                                         28.                         506.9
-6.3 24.
: 13.                               -6.6           _
-14.2
E9.                         617.9
-6.1 25.
: 14.                               -7.1
155.9 9.
: 15.                               -2.7
to.
: 16.                             -11.5 INSTRUCTIONS On this Fern, list the estrege dolly snit i,wer level in IGit ilet for each day in the reporting nenth. Compete to the nearest whole negewett.
-6.0 26.
These figeres ulll be esed to plot a graph for each reporting nenth. Note that when notinen dependable copecitt is esed for the net electrical reting of the enit there ney le eccesiens when the dellt eserege peer level exceeds the .
-9.8 11.
iHI line (or the restricted peer level line),.In suh cases,the estrega daily enit power setpet sheet should he festnoted to explain the apperant enently                                                                             ,
-6.0 27.
J
276.2-12.
-6.9 28.
506.9 13.
-6.6 E9.
617.9 14.
-7.1 15.
-2.7 16.
-11.5 INSTRUCTIONS On this Fern, list the estrege dolly snit i,wer level in IGit ilet for each day in the reporting nenth. Compete to the nearest whole negewett.
These figeres ulll be esed to plot a graph for each reporting nenth. Note that when notinen dependable copecitt is esed for the net electrical reting of the enit there ney le eccesiens when the dellt eserege peer level exceeds the.
iHI line (or the restricted peer level line),.In suh cases,the estrega daily enit power setpet sheet should he festnoted to explain the apperant enently J


O M       M     M     M               M   M       M       M     M     M     M   M       M       M     M       M       M                                 p ID/5A                                                         APPENDIX D                               QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS                   Revision 6 DOCKET NO. 050-254                                                                                   August 1982 UNIT NAME   Quad-Cities 1                                                                 COMPLETED BY Alex Misak DATE       March 6, 1984                       REPORT HONTil   FEBRUARY 1934           TELEPileNE         309-654-2241 w    $                          g
O M
  .                        w"                $    o hw       $w
M M
                              $              Q         d     LICENEEE   m@         @
M M
V w   DURATION  M    -'
M M
g"g         EVENT      $U      o u
M M
NO.     DATE           (Il0URS)                 REPORT NO.                           CORRECTIVE ACTIONS / COMMENTS g
M M
84-6   840205     5         0,0   B       5                     HA   XXXXXX   Reduced load to perform weekly Turbine tests 84-7   840212     S         0.0   8       5                     RB   COUROD   Reduced load for Control Rod Pattern adjustments 84-8   840215     S         0.0   B       5                     HA   XXXXXX   Reduced load to perform weekly Turbine tests 84-9   840276     5         0.0   B       5                     HA   XXXXXX   Reduced load to perform weekly Turbine
M M
                                                                                            +ests 84-10   840228     5         0.0   B       5                     CB   INSTRU   Reduced load in preparation for an Economic Generation Control System test 84-11   840229   5         0.0   B       5                     C8   INSTRU   Reduced Icad in preparation for an Economic Generation Control System test APPROVED i
M M
AUG 1 G 1982 i
M M
                                                                    -I-(final)                                             ygg3g
p ID/5A APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.
050-254 August 1982 UNIT NAME Quad-Cities 1 COMPLETED BY Alex Misak DATE March 6, 1984 REPORT HONTil FEBRUARY 1934 TELEPileNE 309-654-2241 g
w hw
$w w"
o Q
d LICENEEE m@
DURATION M
EVENT
$U V
w
-' " g g
ou NO.
DATE (Il0URS)
REPORT NO.
CORRECTIVE ACTIONS / COMMENTS g
84-6 840205 5
0,0 B
5 HA XXXXXX Reduced load to perform weekly Turbine tests 84-7 840212 S
0.0 8
5 RB COUROD Reduced load for Control Rod Pattern adjustments 84-8 840215 S
0.0 B
5 HA XXXXXX Reduced load to perform weekly Turbine tests 84-9 840276 5
0.0 B
5 HA XXXXXX Reduced load to perform weekly Turbine
+ests 84-10 840228 5
0.0 B
5 CB INSTRU Reduced load in preparation for an Economic Generation Control System test 84-11 840229 5
0.0 B
5 C8 INSTRU Reduced Icad in preparation for an Economic Generation Control System test APPROVED AUG 1 G 1982 i
i
-I-(final) ygg3g


o R                             R   R       R       M           M         -    M     M                 M       M       M     R       R     R ID/5A                                                                     APPENDIX D                                 QTP 300-SI3 UNIT SIIUTDOWNS AND POWER REDUCTIONS                     Revision 6 DOCKET NO.                   050-265                                                                                   August 1982 UNIT NAME                   Quad-Cities 2                                                               CorfPLETED BY   Alex ttisak DATE                         tiarch 6, 1984                   REPORT HONTil FEBRUARY 1984               TELEPil0NE           309-654-2241 w    5                           g w"               E   aS$                     go       !d w
o R
                                                  $            y        M     LICENSEE   m@          @
R R
w  DURATION   E EVENT     $        o NO. DATE             (Il0URS)               REPORT NO.                           CORRECTIVE ACTIONS /C0titlENTS 83-66 830901:     s     428.0     C     4                     RC   FUELXX     Unit Two remains shutdown for End of Cycle Six Refueling and ttaintenance 84-1 840218     F         7.2   B     1                     HA   ZZZZZZ     Unit Two placed in Hot Standby due to high Turbine vibration 84-2 840219     F     32.3     B     1                     ZZ   VALVEX     Unit Two shutdown to repair r..f acellaneous valve packing leaks 84-3 840223     F     36.1     B     1                     IIA ZZZZZZ     Unit Two placed in Hot Standby due to high Turbine vibration 84-4 840225     F     22.0     B     1                     CB   tiOTORX   Unit Two shutdown to replace the motor on the 'B' Recirculation pump suction valve APPROVED AUG 1 G 1982 (final)                                             gjgg3g
R M
M M
M M
M M
R R
R ID/5A APPENDIX D QTP 300-SI3 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.
050-265 August 1982 UNIT NAME Quad-Cities 2 CorfPLETED BY Alex ttisak DATE tiarch 6, 1984 REPORT HONTil FEBRUARY 1984 TELEPil0NE 309-654-2241 5
g w
w" E
aS$
go
!d w y
M LICENSEE m@
DURATION E
EVENT w
o NO.
DATE (Il0URS)
REPORT NO.
CORRECTIVE ACTIONS /C0titlENTS 83-66 830901:
s 428.0 C
4 RC FUELXX Unit Two remains shutdown for End of Cycle Six Refueling and ttaintenance 84-1 840218 F
7.2 B
1 HA ZZZZZZ Unit Two placed in Hot Standby due to high Turbine vibration 84-2 840219 F
32.3 B
1 ZZ VALVEX Unit Two shutdown to repair r..f acellaneous valve packing leaks 84-3 840223 F
36.1 B
1 IIA ZZZZZZ Unit Two placed in Hot Standby due to high Turbine vibration 84-4 840225 F
22.0 B
1 CB tiOTORX Unit Two shutdown to replace the motor on the 'B' Recirculation pump suction valve APPROVED AUG 1 G 1982 (final) gjgg3g


VI. UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments to the commission:
VI.
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.
UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments to the commission:
Valves     No. & Type     Plant     Description Unit     Date       Actuated     Actuations   Co,nditions of Events 2     2-18-84     2-203-38       1 Manual   Rx Press     Surveillance 2-203-3C       1 Manual       920       T.S. 4.5.D.I.b 2-203-3D       1 Manual                 (Post Maintenance) 2-203-3E       I Manual                 Replaced Valve 2-203-3A       1 Manual l
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.
Valves No. & Type Plant Description Unit Date Actuated Actuations Co,nditions of Events 2
2-18-84 2-203-38 1 Manual Rx Press Surveillance 2-203-3C 1 Manual 920 T.S. 4.5.D.I.b 2-203-3D 1 Manual (Post Maintenance) 2-203-3E I Manual Replaced Valve 2-203-3A 1 Manual l


l l
l l
B. CONTROL ROD DRIVE SCRAM TINING DATA FOR UNITS ONE AND TWO The basis for reporting this cata to the Nuclear Regulatory Commission are specified in the surveillance requireraents of Technical Specifications 4.3.C.1 and 4.3.C.2.
B.
CONTROL ROD DRIVE SCRAM TINING DATA FOR UNITS ONE AND TWO The basis for reporting this cata to the Nuclear Regulatory Commission are specified in the surveillance requireraents of Technical Specifications 4.3.C.1 and 4.3.C.2.
The following table is a complete summary of Units On3 and Two Control Rod Drive Scram Timing for the reporting period. All scram t.iming was performed with reactor pressure greater than 800 psig.
The following table is a complete summary of Units On3 and Two Control Rod Drive Scram Timing for the reporting period. All scram t.iming was performed with reactor pressure greater than 800 psig.


RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2                 CONTROL 4
RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL 4
ROD DRIVES, FROM l-1               TO 12-31-04 AVERAGE TIME IN SECONDS AT %       Max. Time INSERTED FROM FULLY WITHDRAWN       For 90%
ROD DRIVES, FROM l-1 TO 12-31-04 AVERAGE TIME IN SECONDS AT %
insertion                                   DESCRIPTION NUMBER               5         20   50       90                                     Technical Specification 3.3.C.I &
Max. Time INSERTED FROM FULLY WITHDRAWN For 90%
DATE OF RODS           0.375   0.900   2.00     3.5     7 sec.                         3.3.C.2 (Average Scram Insertion Time) 2-21     177           0.31     0.69     1.47   2.59     3 25                           unit 2 Hot Scram Timing (J-10)                         A & B Sequence l
insertion DESCRIPTION NUMBER 5
20 50 90 Technical Specification 3.3.C.I &
DATE OF RODS 0.375 0.900 2.00 3.5 7 sec.
3.3.C.2 (Average Scram Insertion Time) 2-21 177 0.31 0.69 1.47 2.59 3 25 unit 2 Hot Scram Timing (J-10)
A & B Sequence l
l l
l l
l
l


l VII. REFUELING INFORtfATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E. O'Brien to C. Reed, et al. , titled "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Information",
VII. REFUELING INFORtfATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E. O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Information",
dated January 18, 1978.
dated January 18, 1978.


QTP 300-S32 R: vision 1 QUAD-CITIES REFUELING           M::rch 1978
QTP 300-S32 R: vision 1 QUAD-CITIES REFUELING M::rch 1978
(-                                                     INFORMATION REQUEST
(-
: 1.           Unit:       Q1         Reload:       7         Cycle:     8
INFORMATION REQUEST 1.
: 2.             Scheduled date for next refueling shutdown:                 3-11-64     -
Unit:
3            Scheduled date for restart following refueling:             5-21-84
Q1 Reload:
: 4.           Will refueling or resumption of operation thereafter require a technical specification change or other IIcense amendment: Yes. Preparatory Technical Specification changes will be submitted to include MAPLHGR curve for one of the reload fuel types and extending MAPLHGR curve for BLTA to 45,000 MWD /t.
7 Cycle:
: 5.           Scheduled date(s) for submitting proposed licansing accion and supporting informa tion:
8 2.
Scheduled date for next refueling shutdown:
3-11-64 3
Scheduled date for restart following refueling:
5-21-84 4.
Will refueling or resumption of operation thereafter require a technical specification change or other IIcense amendment: Yes.
Preparatory Technical Specification changes will be submitted to include MAPLHGR curve for one of the reload fuel types and extending MAPLHGR curve for BLTA to 45,000 MWD /t.
5.
Scheduled date(s) for submitting proposed licansing accion and supporting informa tion:
Tec,nical Specification change will be submitted February 15, 1984.
Tec,nical Specification change will be submitted February 15, 1984.
: 6.           Important licensing considerations associated with refueling, e.g., new or
6.
                          ' different fuel design or suppIIer, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
Important licensing considerations associated with refueling, e.g., new or
: 1) All new fuel assemblies will be GE7B-type (barrier clad, extended exposure design).
' different fuel design or suppIIer, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
: 2)   A generic methodology was used for the analysis of the Control Rod Drop Accide.nt and Rod Withdrawal Error events.
1)
: 3) The two Zirconium Barrier Lead Test Assemblies will be re-inserted to gather Information on the ef fects of extended exposures.
All new fuel assemblies will be GE7B-type (barrier clad, extended exposure design).
7           The number of fuel assemblies.
2)
: a. Number of assemblies in core:                                     724
A generic methodology was used for the analysis of the Control Rod Drop Accide.nt and Rod Withdrawal Error events.
: b. Number of assemblies in spent fuel pool:                       1730
3)
: 8.           The present Itcensed 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:
The two Zirconium Barrier Lead Test Assemblies will be re-inserted to gather Information on the ef fects of extended exposures.
: a. Licensed storage capacity for spent fuel:                       3657 l
7 The number of fuel assemblies.
: 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 I
a.
[-                                                                                               APPROVED APR 2 01978 Q.C.C.S.R.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
1730 8.
The present Itcensed 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 l
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
[-
APPROVED I APR 2 01978 Q.C.C.S.R.


QTP 300-S32 R: vision 1 QUAD-CITIES REFUELING                         March 1978
QTP 300-S32 R: vision 1 QUAD-CITIES REFUELING March 1978
(-                                                                             INFORMATION REQUEST
(-
: 1. Unit:                     Q2   Reload:               6         Cycle:               7
INFORMATION REQUEST 1.
: 2. Scheduled date for next refueling shutdown:                                               9-5-83 3   Scheduled date for restart following refueling:                                           11-12-83
Unit:
: 4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment:
Q2 Reload:
6 Cycle:
7 2.
Scheduled date for next refueling shutdown:
9-5-83 3
Scheduled date for restart following refueling:
11-12-83 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment:
No, however, a change to the Technical Specifications is being submitted (see below).
No, however, a change to the Technical Specifications is being submitted (see below).
: 5. Scheduled date(s) for submitting proposed licensing action and supporting information:
5.
June 14, 1983 (Scheduled)
Scheduled date(s) for submitting proposed licensing action and supporting information:
: 6. In.portant licensing considerations associated with refueling, e.g., new or
June 14, 1983 (Scheduled) 6.
                                      ' ditferent fuel desigit or supplier, unreviewed design or performance analysis methods, significant changas in fuel design, new operating procedures:
In.portant licensing considerations associated with refueling, e.g., new or
: 1) All new fuel assemblies will be of barrier design; MAPLHGR curves will be relabe.ed to include the barrier designation.
' ditferent fuel desigit or supplier, unreviewed design or performance analysis methods, significant changas in fuel design, new operating procedures:
l
1)
: 2)   The use mf impr'ved   o          assumptions in the load reject wi thout bypass analysis                 '
All new fuel assemblies will be of barrier design; MAPLHGR curves will be relabe.ed to include the barrier designation.
resulted in e much improved MCPR operating limit. Technical Specifications l                                             are being changed to provide this adc. Ional operating margin.
l 2)
7   The number of fuel assembites.
The use mf impr'ved assumptions in the load reject wi hout bypass analysis o
: a. Number of assemblies in core:                                                           724
t resulted in e much improved MCPR operating limit.
: b. Number of assemblies in spent fuel pool:                                                 412
Technical Specifications l
: 8. The present licensed spent fuel pool storage capacity and the size of any increase in IIcensed storap capacity that has been requested o,- is planned in number of fuel assemblies:
are being changed to provide this adc.
: a. Licensed storage capacity for spent fuel:                                               3897
Ional operating margin.
: b. Planned increase in IIcensed storage:                                                       O l                                 9     The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present IIcensed capacity: 2003 (7                                                                                                                             4PPROVED
7 The number of fuel assembites.
                                                                                                                          ,        APR 2 01978 Q.C.C.S.R.
a.
                                                                                                                              .\
Number of assemblies in core:
                                                                                                                            /
724 b.
L                                           _                                                                  -- - - - - --
Number of assemblies in spent fuel pool:
412 8.
The present licensed spent fuel pool storage capacity and the size of any increase in IIcensed storap capacity that has been requested o,- is planned in number of fuel assemblies:
a.
Licensed storage capacity for spent fuel:
3897 b.
Planned increase in IIcensed storage:
O l
9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present IIcensed capacity: 2003 (7
4PPROVED,
APR 2 01978 Q.C.C.S.R.
.\\
/
L


    .    . . . . . ___        _..        . _ . _ _ _ - . _              _    _ _ _.            ._  .      . _ .. _ m J.
m J.
i i
i i
,                                                                VIII. GLOSSARY 2
VIII. GLOSSARY 2
3 The following abbreviations which may have been used in the Monthly Report, are defined below:
3 The following abbreviations which may have been used in the Monthly Report, are defined below:
ACAD/ CAM       -
ACAD/ CAM Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI American National Standards Institute APRM Average Power Range Monitor ATWS Anticipated Transient Without Scram i
Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI           -
BWR Boiling Water Reactor CRD Control Rod Drive EHC Electro-Hydraulic Control System j
American National Standards Institute APRM           -
EOF Emergency Operations Facility GSEP Generating Stations Emergency Plan HEPA High-Efficiency Particulate Filter HPCI-High Pressure, Coolant Injection System -
Average Power Range Monitor ATWS           -
HRSS High Radiation Sampling System IPCLRT Integrated Primary Containment Leak Rate Test i
Anticipated Transient Without Scram                                           i BWR           -
IRM Intermediate Range Monitor
Boiling Water Reactor                                                       !
'ISI Inservice Inspection LER Licensee Event Report LLRT Local Leak Rate Tert LPCI Lcw Pressure Coolant Injection Mode of RHRS LPRM Local Power Range Monitor MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MFLCPR M:ximum Fraction Limiting Critical Power Ratio 1-MPC Maximum Permissible Concentration MSIV Main Steam Isolation Valve l
CRD           -
NIOSH National Institute for Occupational Safety and Health PCI Primary Containment Isolation i
Control Rod Drive EHC           -
PCIONR Preconditioning Interim Operating Management Recommendations RBCCW Reactor Building Closed Cooling Water System RBM
Electro-Hydraulic Control System j                         EOF           -
- Rod Block Monitor RCIC Reactor Core Isolation Cooling System RHRS Residual Heat Removal System RPS
Emergency Operations Facility GSEP           -
: Reactor. Protection System RWM Rod Worth Minimizer SBGTS Standby Gas Treatment System SBLC Standby Liquid Control SDC
Generating Stations Emergency Plan HEPA           -
. Shutdown Cooling Mode of RHRS i
High-Efficiency Particulate Filter HPCI-         -
SDV.
High Pressure, Coolant Injection System -
' Scram Discharge Volume SRM
HRSS           -
~ Source Range Monitor.
High Radiation Sampling System IPCLRT         -
TBCCW-Turbine Building Closed Cooling Water System-
Integrated Primary Containment Leak Rate Test i                         IRM           -
- TIP
Intermediate Range Monitor
-Traversing Incore Probe TSC Technical Support Center
                        'ISI           -
Inservice Inspection
.                        LER           -
Licensee Event Report
;                        LLRT           -
Local Leak Rate Tert LPCI           -
Lcw Pressure Coolant Injection Mode of RHRS LPRM         -
Local Power Range Monitor                     .
MAPLHGR       -
Maximum Average Planar Linear Heat Generation Rate MCPR           -
Minimum Critical Power Ratio MFLCPR         -
M:ximum Fraction Limiting Critical Power Ratio 1-                       MPC           -
Maximum Permissible Concentration
:                        MSIV           -
Main Steam Isolation Valve                   .
l                        NIOSH         -
National Institute for Occupational Safety and Health
!                      PCI           -
Primary Containment Isolation i
PCIONR         -
Preconditioning Interim Operating Management Recommendations RBCCW         -
Reactor Building Closed Cooling Water System
,                        RBM                - Rod Block Monitor RCIC           -
Reactor Core Isolation Cooling System RHRS           -
Residual Heat Removal System
,                        RPS           -
: Reactor. Protection System RWM           -
Rod Worth Minimizer SBGTS         -
Standby Gas Treatment System SBLC           -
Standby Liquid Control SDC           -
                                                . Shutdown Cooling Mode of RHRS i                       SDV.           -
                                                ' Scram Discharge Volume SRM         --
                                              ~ Source Range Monitor.                    .        .
TBCCW-         -
Turbine Building Closed Cooling Water System-
                      - TIP           -
                                              -Traversing Incore Probe TSC           -
Technical Support Center
?,
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Coramonwealth Edison l
Coramonwealth Edison C.
C.     Quad Citits Nuchar Powar Station
Quad Citits Nuchar Powar Station l
:- ,      22710 206 Avenue North Cordova. Illinois 61242 Telephone 309/654-2241 NJK-84-80 March 8, 1984 Director, Office of Inspection & Enforcement i
22710 206 Avenue North Cordova. Illinois 61242 Telephone 309/654-2241 NJK-84-80 March 8, 1984 Director, Office of Inspection & Enforcement i
United States Nuclear Regulatcry Commission Washington, D. C. 20555 Attention: Document Control Desk Gentlemen:
United States Nuclear Regulatcry Commission Washington, D. C.
20555 Attention: Document Control Desk Gentlemen:
Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Fower Station, Units One and Two, during the month of February 1984.
Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Fower Station, Units One and Two, during the month of February 1984.
Very truly yours, COMMONWEALTH EDISON COMPANY-QUAD-CITIES NUCLEAR POWER STATION N. J. Kalivianakis Station Superintendent bb Enclosure                                                           l
Very truly yours, COMMONWEALTH EDISON COMPANY-QUAD-CITIES NUCLEAR POWER STATION N. J. Kalivianakis Station Superintendent bb Enclosure
[
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                                                                ,    .}}
.}}

Latest revision as of 23:16, 13 December 2024

Monthly Operating Repts for Feb 1984
ML20087D382
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 02/29/1984
From: Kalivianakis N, Misak A
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NJK-84-80, NUDOCS 8403130382
Download: ML20087D382 (24)
v • d • e


Text

.

o O

l QUAD-CITIES NUCLEAR POWER STATION UNITS I AND 2 4

MONTHLY PERFORMANCE REPORT FEBRUARY 1984-COMMONWEALTH EDIS0N COMPANY AND IOWA-ILLINOIS GAS & ELECTi'IC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 2

l i

PDR l

l r

l i

__m

t i

TABLE OF CONTENTS I.

Introduction i

j 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 4

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 Valve Operations B.

Control Rod Drive Scram Timing Data VII. Refueling Information VIII.

Glossary t

i o

(

4

l I.

INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company.

The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent &

Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors. The Mississippi River is the condenser cooling water source. The plant is subject to license numbers DPR-29 and DPR-30, issued October 1, 1971, and 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 Becky Brown and Alex Misak, telephone number 309-654-2241, extensions 127 and 194.

II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Febr uary 1-11 : Unit One began the month operating at full power and continued at this level until 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> on February 5 when the unit dropped load to 700 MWe for weekly Turbine tests.

Following the tests, the unit increased load to full power and maintained that load until February 7 when the unit began experiencing fuel depletion deratings due to end of cycle coastdown.

February 12-26: At 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> on February 12, the unit dropped load to 700 MWe for weekly Turbine tests.

Following the tests, the unit dropped load to 660 MWe for control rod pattern adjustments.

Following these adjustments, the unit began a normal load increase.

On two other occasions, February 19 and February 26, weekly Turbh~

tests were performed which necessitated load reductions to 700 MWe.

February 27-29: At 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br /> on February 28, the unit dropped load to 650 MWe in preparation for an Economic Generation Control (EGC) system test.

At 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> on February 29, the unit increased load to 740 MWe and maintained this load until 1550 hours0.0179 days <br />0.431 hours <br />0.00256 weeks <br />5.89775e-4 months <br /> when the unit dropped load to 700 MWe in preparation for an EGC system test.

B.

Unit Two February 1-20: Unit Two began the month shutdown for End of Cycle Six Refueling and maintenance. At 0045 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> on February 18, unit startup commenced. At 0303 hours0.00351 days <br />0.0842 hours <br />5.009921e-4 weeks <br />1.152915e-4 months <br />, the Reactor was critical, and the unit was on line at 1957 hours0.0227 days <br />0.544 hours <br />0.00324 weeks <br />7.446385e-4 months <br />.

At 2033 hours0.0235 days <br />0.565 hours <br />0.00336 weeks <br />7.735565e-4 months <br />, the Turbine was manually tripped due to high Turbine vibration.

At 0348 hours0.00403 days <br />0.0967 hours <br />5.753968e-4 weeks <br />1.32414e-4 months <br /> on February 19, the unit was placed on line with a load of 160 MWe, This load was ma'ntained until 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> when the unit was shutdown to repair various valve packing leaks. The unit remained shutdown until 1820 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.9251e-4 months <br /> on February 20 when the Generator was placed on line with a load of 150 MWe.

February 21-29: At 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> on February 21, the unit began increasing load to 350 MWe by pulling control rods.

Load was maintained at 350 MWe due to the 2B Recirculation Pump Motor-Generator Set being out of service for repairs. At 1405 hours0.0163 days <br />0.39 hours <br />0.00232 weeks <br />5.346025e-4 months <br /> on February 23, the unit was placed in Hot Standby due to high Turbine vibration. The unit was placed on line at 0210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br /> on February 25 with a load of 180 MWe.

At 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />, the unit began increasing load to 500 MWe.

At 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />, the unit began a nornel shutdown to replace the notor on the 'B' Recirculation Pump Suction Valve.

The unit was of f line from 2205 hours0.0255 days <br />0.613 hours <br />0.00365 weeks <br />8.390025e-4 months <br /> on February 25 to 0608 hours0.00704 days <br />0.169 hours <br />0.00101 weeks <br />2.31344e-4 months <br /> on February 27 when the Generator was placed on line, and a normal load increase was initiated.

1 1

t i

III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE-i A.

Amendments to Facility License or Technical Specifications On January 24, 1984, the NRC issued Amendment 80 to License DPR-30. This Amendment established new actuation setpoints for the Target Roc.k Safety Relief Valve and two Electromatic Relief Valves, i t also defined new Minimum Critical Power Ratio limits for steady state operation at ' rated core flow. The Amendment also shows the new Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Planar Average Exposure curve for the new Unit Two core.

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-cr 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 i and Unit 2 during the reporting period. This summary includes the following headings:

Work Request Numbers, LER Numbers, Components, Cause of Mal functions, Results and Ef fects on Safe Operation,- and Action Taken to Prevent Repetition.

i e

a 4 - m

~

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UNIT OrlE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q31892 1-3999-515A RilR Rust and dirt froze The valve leaked through The valve was dis-Service Water the plunger, but the vault sump pump assembled, cleaned, Vault Sump Dis-maintained the integrity lapped, reassembled, charge Check Valve of the vault.

and LLRT'd.

An investigation was started concerning the vavle reliability.

-Q31893 1-3999-516A RiiR Rust and dirt froze The valve leaked through The valve was dis-Service Uater the plunger.

but the vault sump pump assembled, cleaned, Vault Sump Dis-maintained the integrity lapped, reassembled, charge Check Valve of the vault.

and LLRT'd.

An investigation was started concerning the valve reliability.

t

)

UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS

.W.R.

LER OF ON ACTION TAKEN TO NUM8ER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q25817 83-6,'03L 2-203-2B tiSIV The

'B' channel The ittiv failed to The limit switch Limit Switch 10% closure limit ini tiate a hal f-scram was replaced.

switch failed.

during testing. The half-scram was initiated mancally.

- Q27288 2-5401B SJAE ilorizontal position The valve did not The valve internals Suction Valve of valve.

close. It was were cleaned. The manually assisted valve has a person closed.

stationed near it to assist it, and is always, otherwise, kept closed. The valve has since been replaced.

Q28869' 2-54010 SJAE The valve was The valve failed to The SJAE suction Suction Valve improperly close on an valve has since been installed.

isolation signal. It replaced with a is normally kept Butterfly valve.

closed.

Q28972 83-15/03L FCV 2-8802C-The valve internals The seat was lapped were worn.

The valve leaked and the disc was substantially auring cleaned.

LLRT.

Q29176 83-15/03L CV 2-1301-41 The valve internals The valve leaked The seat was lapped we re worn.

s6bstantially during and the hinge pin, LLRT.

disc, and all seats and gas'kets were replaced.

O A

t

UNIT TU0 MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q30316 Various Mechanical Wear.

Various Mechanical The Snubbers that Snubbers Snubbers were failed the functional functionally tested.

test were sent to 9481, 7327, 7732, Wyle Laboratories 16565, 16558, 12700, to be overhauled.

and 1488 failed.

Q31102 2-2301-5 had The control and The valve tripped during The cables were control and rnotor motor cable had.

logic testing. It was replaced and cables cable replaced.

failed due to a not required ope rable in the area and on small steam leak.

at the time. The valve Ul were inspected.

would fail open to -

provide llPCI service and the in-line 2-2301-4 valve would provide isolation.

ma e

b I

m

I 4

i IV.

LICENSEE EVENT-REPCRTS a

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

,t as set forth in sections 6.6.B.I. and 6.6.B.2. of the Technical Specifications.

l UNIT ONE i

Licensee Event Report Number Date Title of Occurrence There were no Licensee Event Reports, for Unit One, for the reporting pe riod.

I l

UNIT TWO l

84-03/03L 2-11-84 Loss of Rus.28 & 29 j

84-04/03L 2-15-84 Reactor Scram While t

Shutdown 2

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i-4 i

i-i 3

a 5

4 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 l

[

1 t

r-9 OPERATING DATA REPORT DOCKET NO.

50-254 UNIT ONE DATEFebruarv 7 COMPLETED BYAlex Misok TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 020184 1.

Reporting period 2400 022984 Gross hours in reporting period:

696

2. Currently authorized power lev,, (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical '.nting (MWe-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

5. Number of hours reactor was critical 696.0 1440.0 84995.6
6. Reactor reserve shutdown hours 0.0 0.0 3421.9 7.

Hours generator on line 696.0 1440.0 81787.9

8. Unit reserve shutdown hours.

0.0 0.0 909.2

9. Gross thermal energy generated (MWH) 1643681 3406884 168513590
10. Gross electrical energy generated (MWH) 545050 1129512 54380128
11. Het electrical energy gencroted(MWH) 517997' 1073371 50679338
12. Reactor service factor 100.0 100.0 82.1
13. Reactor avo11ob111ty factor 100.0 100.0 85.4
14. Unit service factor 100,30 100.0 79.0
15. Unit availobility factor 100.0 100.0 79.9 L6. Unit capacity factor (Using MDC) 96.8 96.9 63.7

~

L7. Unit capacity factor (Using Des.MWe) 94.3 94.5 62.1

18. Un it forced outage rate 0.0 0.0 6.2
19. Shutdowns scheduled over next 6 nonths (Typa,Date,and Duration'of each):
20. If shutdown at end of repcrt period, estimated dote of startup __"___________

^

IThe MDC ney be lower then 769 MWe dering perleds of high onbient temperatore det to the tlwrm1 performece of tra sprey comd.

I i

sWOFFICIAL COMPANY NWBERS ARE USED IN THIS REPORT

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r l

OPERATING DATA REPORT DOCKET NO.

50-265 UNIT TWO DATEFebruarv 7 COMPLETED BYAlex Misok TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 020184 1.

Reporting period 2400 022984 Gross hours in reporting period:

696

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-Net): NA 4.

Reasons for restriction (if any):

This Month Yr.to Date Cumulative

5. Number of hours rinctor was critical 245.5 245.5 78163.0
6. Reactor reserve shutdown hours 9.0 0.0 2985.8
7. Hours generator on line 160.3 160.3 75370.1
8. Unit reserve shutdown hours.

0.0 0.0 702.9 9.

Gross thernal energy generated (MWH) 193783 193783 155575871-

10. Gross electrical energy generated (MWH) 58218 58 rib 49493998
11. Net electrical energy generated (MWH) 53862 53338 46307398
12. Reactor service factor 35.3 17.0 76.2
13. Reactor avullobility factor 35.3 17.0 79 i
14. Unit service factor 23.0 11.1 73.5 LS. Unit avo11ob111ty factor 23.0 ii.i

' 4. 2

~

16.. Unit capacity factor (Using MDC) 10.1 4.8 58.8-

~

L7. Unit capacity factor (Using Des.HWe) 9.8 4.7 57.3

18. Unit forced outage rate 40.2 40.2' B '.' 7
19. Shutdowns schedule.d over next 6 months (Typc,Date,and Duration of each):1
20. If shutdown at end of teport p er i o d,e st ina t ed dat e o f. s t ar t up, ___jiA______,.3 SThe 19C ney be lever then 769 mit dering per 7 of high onblent tenperstere det to the thernal perfernance of the grey cenei.

$W10FFICIAl. ColtAIN lluleERS ARE USED H WIS REPORT

i-APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254 UNIT ONE DATEFehroorv 7 COMPLETED BYAlex Misok TELEPHONE 309-654-2241x194 MONTH February 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWemlet)

(MWe-Net) 1.

779.8 17.

749.4 2.

768,3 18, 746.8 3.

780.7 19.

737.9 4,

790.8 20.

744.5 737.7 5.

619.0

21..

6.

870.5 22, 745,7 7.

783.1 23, 737.5 8.

783.0 24.

708.4 7.

777.7 2F 732.8 10, 780.8 26, 713.8 li.

763,6 27.

719.9 L2, 672.6 28, 710.0 L3.

784.4 29.

637.8 L4, 749.0 15.

760.0 16.

762.0 INSTRUCTIONS Cn this forn, list the overage daily unit power level in 1%ie-Net for each day in the reporting nonth Conpete to the nearest Whelt negawatt.

These figures Will be ssed to plat a graph for each reporting conth. Note that when notinin dependable used for the net electrical rating of the init,In sich cases,the average daily snit power entpst sheet sheeld be 1981 line (or the restricted power level line).

festnetad to esplein the apperent onenaly I

I I

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO DATEFebroorv 7 COMPLETED BYAlex Misak TELEPHONE 309-654-2241x194 HONTH Febroorv 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY P014ER LEVEL (MWe-Net)

(MWe-Net) 1.

-4.3 17.

-7.8 2.

-5.0 18.

-11.0 3.

-7.2 19, 32.5 4.

-7.4 20, 17.6 5.

-7.0 21, 185.7 6.

-7.4 22, 330.0 7.

-7.7 23.

147.7 8.

-6.3 24.

-14.2

-6.1 25.

155.9 9.

to.

-6.0 26.

-9.8 11.

-6.0 27.

276.2-12.

-6.9 28.

506.9 13.

-6.6 E9.

617.9 14.

-7.1 15.

-2.7 16.

-11.5 INSTRUCTIONS On this Fern, list the estrege dolly snit i,wer level in IGit ilet for each day in the reporting nenth. Compete to the nearest whole negewett.

These figeres ulll be esed to plot a graph for each reporting nenth. Note that when notinen dependable copecitt is esed for the net electrical reting of the enit there ney le eccesiens when the dellt eserege peer level exceeds the.

iHI line (or the restricted peer level line),.In suh cases,the estrega daily enit power setpet sheet should he festnoted to explain the apperant enently J

O M

M M

M M

M M

M M

M M

M M

M M

M M

p ID/5A APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.

050-254 August 1982 UNIT NAME Quad-Cities 1 COMPLETED BY Alex Misak DATE March 6, 1984 REPORT HONTil FEBRUARY 1934 TELEPileNE 309-654-2241 g

w hw

$w w"

o Q

d LICENEEE m@

DURATION M

EVENT

$U V

w

-' " g g

ou NO.

DATE (Il0URS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS g

84-6 840205 5

0,0 B

5 HA XXXXXX Reduced load to perform weekly Turbine tests 84-7 840212 S

0.0 8

5 RB COUROD Reduced load for Control Rod Pattern adjustments 84-8 840215 S

0.0 B

5 HA XXXXXX Reduced load to perform weekly Turbine tests 84-9 840276 5

0.0 B

5 HA XXXXXX Reduced load to perform weekly Turbine

+ests 84-10 840228 5

0.0 B

5 CB INSTRU Reduced load in preparation for an Economic Generation Control System test 84-11 840229 5

0.0 B

5 C8 INSTRU Reduced Icad in preparation for an Economic Generation Control System test APPROVED AUG 1 G 1982 i

i

-I-(final) ygg3g

o R

R R

R M

M M

M M

M M

R R

R ID/5A APPENDIX D QTP 300-SI3 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.

050-265 August 1982 UNIT NAME Quad-Cities 2 CorfPLETED BY Alex ttisak DATE tiarch 6, 1984 REPORT HONTil FEBRUARY 1984 TELEPil0NE 309-654-2241 5

g w

w" E

aS$

go

!d w y

M LICENSEE m@

DURATION E

EVENT w

o NO.

DATE (Il0URS)

REPORT NO.

CORRECTIVE ACTIONS /C0titlENTS 83-66 830901:

s 428.0 C

4 RC FUELXX Unit Two remains shutdown for End of Cycle Six Refueling and ttaintenance 84-1 840218 F

7.2 B

1 HA ZZZZZZ Unit Two placed in Hot Standby due to high Turbine vibration 84-2 840219 F

32.3 B

1 ZZ VALVEX Unit Two shutdown to repair r..f acellaneous valve packing leaks 84-3 840223 F

36.1 B

1 IIA ZZZZZZ Unit Two placed in Hot Standby due to high Turbine vibration 84-4 840225 F

22.0 B

1 CB tiOTORX Unit Two shutdown to replace the motor on the 'B' Recirculation pump suction valve APPROVED AUG 1 G 1982 (final) gjgg3g

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.

Valves No. & Type Plant Description Unit Date Actuated Actuations Co,nditions of Events 2

2-18-84 2-203-38 1 Manual Rx Press Surveillance 2-203-3C 1 Manual 920 T.S. 4.5.D.I.b 2-203-3D 1 Manual (Post Maintenance) 2-203-3E I Manual Replaced Valve 2-203-3A 1 Manual l

l l

B.

CONTROL ROD DRIVE SCRAM TINING DATA FOR UNITS ONE AND TWO The basis for reporting this cata to the Nuclear Regulatory Commission are specified in the surveillance requireraents of Technical Specifications 4.3.C.1 and 4.3.C.2.

The following table is a complete summary of Units On3 and Two Control Rod Drive Scram Timing for the reporting period. All scram t.iming was performed with reactor pressure greater than 800 psig.

RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL 4

ROD DRIVES, FROM l-1 TO 12-31-04 AVERAGE TIME IN SECONDS AT %

Max. Time INSERTED FROM FULLY WITHDRAWN For 90%

insertion DESCRIPTION NUMBER 5

20 50 90 Technical Specification 3.3.C.I &

DATE OF RODS 0.375 0.900 2.00 3.5 7 sec.

3.3.C.2 (Average Scram Insertion Time) 2-21 177 0.31 0.69 1.47 2.59 3 25 unit 2 Hot Scram Timing (J-10)

A & B Sequence l

l l

l

VII. REFUELING INFORtfATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E. O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Information",

dated January 18, 1978.

QTP 300-S32 R: vision 1 QUAD-CITIES REFUELING M::rch 1978

(-

INFORMATION REQUEST 1.

Unit:

Q1 Reload:

7 Cycle:

8 2.

Scheduled date for next refueling shutdown:

3-11-64 3

Scheduled date for restart following refueling:

5-21-84 4.

Will refueling or resumption of operation thereafter require a technical specification change or other IIcense amendment: Yes.

Preparatory Technical Specification changes will be submitted to include MAPLHGR curve for one of the reload fuel types and extending MAPLHGR curve for BLTA to 45,000 MWD /t.

5.

Scheduled date(s) for submitting proposed licansing accion and supporting informa tion:

Tec,nical Specification change will be submitted February 15, 1984.

6.

Important licensing considerations associated with refueling, e.g., new or

' different fuel design or suppIIer, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

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 Accide.nt and Rod Withdrawal Error events.

3)

The two Zirconium Barrier Lead Test Assemblies will be re-inserted to gather Information on the ef fects of extended exposures.

7 The number of fuel assemblies.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

1730 8.

The present Itcensed 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 l

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

[-

APPROVED I APR 2 01978 Q.C.C.S.R.

QTP 300-S32 R: vision 1 QUAD-CITIES REFUELING March 1978

(-

INFORMATION REQUEST 1.

Unit:

Q2 Reload:

6 Cycle:

7 2.

Scheduled date for next refueling shutdown:

9-5-83 3

Scheduled date for restart following refueling:

11-12-83 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment:

No, however, a change to the Technical Specifications is being submitted (see below).

5.

Scheduled date(s) for submitting proposed licensing action and supporting information:

June 14, 1983 (Scheduled) 6.

In.portant licensing considerations associated with refueling, e.g., new or

' ditferent fuel desigit or supplier, unreviewed design or performance analysis methods, significant changas in fuel design, new operating procedures:

1)

All new fuel assemblies will be of barrier design; MAPLHGR curves will be relabe.ed to include the barrier designation.

l 2)

The use mf impr'ved assumptions in the load reject wi hout bypass analysis o

t resulted in e much improved MCPR operating limit.

Technical Specifications l

are being changed to provide this adc.

Ional operating margin.

7 The number of fuel assembites.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

412 8.

The present licensed spent fuel pool storage capacity and the size of any increase in IIcensed storap capacity that has been requested o,- is planned in number of fuel assemblies:

a.

Licensed storage capacity for spent fuel:

3897 b.

Planned increase in IIcensed storage:

O l

9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present IIcensed capacity: 2003 (7

4PPROVED,

APR 2 01978 Q.C.C.S.R.

.\\

/

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i i

VIII. GLOSSARY 2

3 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 ATWS Anticipated Transient Without Scram i

BWR Boiling Water Reactor CRD Control Rod Drive EHC Electro-Hydraulic Control System j

EOF Emergency Operations Facility GSEP Generating Stations Emergency Plan HEPA High-Efficiency Particulate Filter HPCI-High Pressure, Coolant Injection System -

HRSS High Radiation Sampling System IPCLRT Integrated Primary Containment Leak Rate Test i

IRM Intermediate Range Monitor

'ISI Inservice Inspection LER Licensee Event Report LLRT Local Leak Rate Tert LPCI Lcw Pressure Coolant Injection Mode of RHRS LPRM Local Power Range Monitor MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MFLCPR M:ximum Fraction Limiting Critical Power Ratio 1-MPC Maximum Permissible Concentration MSIV Main Steam Isolation Valve l

NIOSH National Institute for Occupational Safety and Health PCI Primary Containment Isolation i

PCIONR Preconditioning Interim Operating Management Recommendations RBCCW Reactor Building Closed Cooling Water System RBM

- Rod Block Monitor RCIC Reactor Core Isolation Cooling System RHRS Residual Heat Removal System RPS

Reactor. Protection System RWM Rod Worth Minimizer SBGTS Standby Gas Treatment System SBLC Standby Liquid Control SDC

. Shutdown Cooling Mode of RHRS i

SDV.

' Scram Discharge Volume SRM

~ Source Range Monitor.

TBCCW-Turbine Building Closed Cooling Water System-

- TIP

-Traversing Incore Probe TSC Technical Support Center

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,*t

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I,'-v 1

a r e 3

+

Coramonwealth Edison C.

Quad Citits Nuchar Powar Station l

22710 206 Avenue North Cordova. Illinois 61242 Telephone 309/654-2241 NJK-84-80 March 8, 1984 Director, Office of Inspection & Enforcement i

United States Nuclear Regulatcry Commission Washington, D. C.

20555 Attention: Document Control Desk Gentlemen:

Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Fower Station, Units One and Two, during the month of February 1984.

Very truly yours, COMMONWEALTH EDISON COMPANY-QUAD-CITIES NUCLEAR POWER STATION N. J. Kalivianakis Station Superintendent bb Enclosure

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