ML20149G147
| ML20149G147 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/31/1988 |
| From: | Deelsnyder L, Robey R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation |
| References | |
| RAR-88-01, RAR-88-1, NUDOCS 8802180138 | |
| Download: ML20149G147 (29) | |
Text
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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 t
MONTHLY PERFORMANCE REPORT JANUARY, 1988 COMMONHEALTH EDISON COMPANY AND IONA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND OPR-30
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t TABLE OF CONTENTS I.
Introduction II.
Summary of Operating Experience A.
Unit One 8.
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 t
-IV.
Licensee Event Reports V.
Data Tabulations A.
Operating Data Report B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions VI.
Unique Reporting Requirements A.
Main Steam Relief Valve Operations B.
Control Rod Drive Scram Timing Data i
VII.
Refueling Information' VIII.
Glossary i
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4 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 Bolling 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, i
respectively; pursuant to Docket Numbers 50-254 and 50-265.
The date of initial Reactor criticalities for Units One and Two, respectively were October 18, 1971, and April 26, 1972. Commercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 for Unit Two.
This report was compiled by Verna Koselka and Lynne Deelsnyder, telephone number 309-654-2241, extensions 2240 and 2185.
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G II.
SUMMARY
OF OPERATING EXPERIENCE A.
Unit One January 1-31 Unit One began January operating at 600 MWe and was increased to full power on January 1 at 1255.
Full load was. held until 2050 on January 2, when it was reduced due to an EHC leak in the turbine front standard. /s the leak worsened, rods were inserted and load *as decreased to 320 MWe. At 0235 on January 3, the main turbine was tripped and the EHC leak repaired. At 0728 the mode switch was placed in RUN, and at 0857 the generator was synchronized to the grid. From January 4 to January 30 unit load was maintained near full power, or ths unit. operated in Economic Generation control..The only significant load drops were for minimum system demand on weekends.
On January 30 the unit was taken off of EGC and load was. decreased to 580 MWe due to off gas
~high temperature. After correcting an off gas condenser problem, ascent back to full power was begun, and achieved at 0635 on January 30.
Load was again
-decreased to 435 MWe on January 31 because of off gas high temperature problems.
I Further corrective actions were taken to alleviate this problem snd a power i
ascent was begun until full load was reached and held through the remainder-of the month.
B.
Unit Two January 1-15 Unit Two began January in EGC and operated at a minimum power level of 710 MWe until January 4.
At 1835 on January 4 the unit was taken off of EGC and a I
load reduction to 210 MWe was taken to make a drywell entry.
This power level was held while valve packing adjustments were made to correct leakage. On January 5 at 1315, a load increase was begun.
700 MWe was reached at 1915 and full power (823 MWe) was reached on January 7 at 0753.
The unit operated normally until January 11 when at 1055 the unit two reactor scrammed due to a turbine / generator load mismatch. The problem appeared to be a main generator ground and the unit remained shutdown during January 12-15 while inspections vere performed to identify the problem.
On January 15 at 0737, the mode switch was placed in STARTUP, and control rod withdrawal was begun at 0900. The reactor was critical at 1057 on January 15.
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. January 16-31
.At 0126 on January 16, the mode-switch was placed in RUN and the generator was synchronized to the grid at 0300. A power ascent was begun using control rods and recire pumps.
500.MWe was reached at 0843 and power level was held here until January 18 when ful1~ power was achieved.
On January 20 the unit was_placed in EGC and operated in EGC with only minor interruptions until January 30.
A load drop was requested by the load dispatcher due to minimum
' demand problems on January 30.
Unit load was held at 400 MWe until January 31 when a power ascent commenced and full load was achieved thru the remainder-of the month, s,
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III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.
Amendments to Facility License or Technical Specifications There were no Amendments to the Facility _ License or Technical Specifications for the reporting period.
B.
Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure changes requiring NRC
, proval for the reporting period.
C.
ests and Experiments Requiring NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period.
D.
Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the major safety related maintenance performed on Units One and 'iwo during the reporting period. This summary includes the following: Work Request Numbers, Licensee Event Report Numbers, Components,-Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.
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UNIT 1 MAINTENANCE
SUMMARY
WORK REQUEST No.: Q59171 LER NUMBER:
87-015 1
COMPONENT:
Systen1700-Replaceddefectivepart]nonChannelBPdyegSupply Process Monitor.
3 CAUSE OF MALFUNCTION:
ThecauseofthemalfunctUonofthe 1-1705-7B radiation monitor power supply was the result of a failed capscitor in the p'dkar supply due to its end-of-life, s
RESULTS & EFFECTS ON SAFE OPERATI?,: The event on the
'B' channel cauand the Unit I and Unit 2 Reactor Building Vent,ta' tion System to isolate the'1/2AySBGT train to sta:t and the control room ventilation system went on recirculation en deiigned.
Also, the A channel of the process radiation monitors was available at all times.
Therefore, safety implications were minimal.
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, ACTION TAKEN TO PREVENT REPETITION: The failed capacitor Oas replaced like-for-
'.ke.
In addition, two other capacitors, one transistor and 1/4 amp. fuse were replaced for preventive maintenance purposes.
The radiati6n monttors affected were successfully tested and returned to service.
WORK REQUEST NO.: Q59266 LER NDiPg: N/A COMPONENT:
System 6600 - No problem found with Unit One Diesel Generato?.
CAUSE OF MALFUNCTION: The cause of the' malfunction of the Unit One Diesel, Generator was air in the fuel line resulting from an inadequate procedure for installing new fuel filters.
RESULTS & EFFECTS ON SAFE OPERATION: The safety implications are minimal since all systems required operable per Technical Specification 3.9.E.1 were demonstrated to be operable.
ACTION TAKEN TO PREVENT REPETITION: A temporary procedure that will be made perma-nent has been written to clarify steps an how to properly vent a new fuel filter (QMS 200-S3). An inspection by a Western Engine Service Representative was per-formed and no apparent problems were identified.
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WORK REQUEST Nc.: QS9291 LER NUMBER: 87-017
. COMPONENT:
System 2300 -' Replaced transmitter for HPCI steam line high flow, 1-2352.
CAUSE OF MALFUNCTION:' The cause of the malfunction of the differential pressure transmitter DPT 1-2352 is unknown at-this time.
It was sent back to the manu-facturer for failure determination. 'A supplemental report will be written then.
RESULTS & EFFECTS ON SAFE OPERATION: ' The safety implications were minimal since all systems required per Technical Specification 4.5.C.2 were demonstrated to be operable.
ACTION TAKEN TO PREVENT REPETITION:.The immediate corrective action was to replace the transmitter like-for-like.
No further corrective action is deemed necessary at this time.
WORK _ REQUEST NO.: Q60678 LER NUMBER: N/A COMPONENT:
System 1700 - Replaced coil for 1705-106 relay.
l CAUSE OF MALFUNCTION: The failure of the coil for relay 1705-106 was due to its end of life.
_RESULTS & EFFECTS ON SAFE OPERATION: There was no effect on safe operation as it failed in the conservative direction.
It is a two-out-two logic, so the failure did not initiate any system actuation.
ACTION TAKEN TO PREVENT REPETITION: The immediate corrective action was to replace the coil like-for-like.
This, along with the modification (4-1(2)-85-17) to improve reliability, is deemed sufficient at this time.
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WORK REQUEST NO.: Q60791 LER NUMBER:
87-620 COMPONENT:
System 1700 - Replaced relay 1705-106.
CAUSE OF MALFUNCTION: A safety actuation occurred due to an installation error during the previous relay (1-1705-106) coil replacement.
RESULTS 6 EFFECTS ON SAFE OPERATION: The safety of the public and plant was never affected daring this event.
The failure of the relay did not affect the ability of the system to perform its function. Although due to the failure of the relay on the A channel when the B radiation monitor was removed for normal maintenance, the Reactor Building ventilation system isolated and the Standby Gas System started.
ACTION TAKEN TO PREVENT REPETITION: The immediate corrective action was to replace the relay like-for-like.
The event was discussed with Electrical Maintenance Personnel for proper care during installation and adequate post maintenance testing. Also, a modification M4-1(2)-85-17 has already been initiated to replace all CR120A model relays with a suitable replacement to improve reliability.
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UNIT 2 MAINTENANCE
SUMMARY
WORK REQUEST NO.: Q59028 LER NUMBER: N/A COMPONENT:
System 200 - Cleaned connector and adjusted threshold for 2-203-3C.
CAUSE OF MALFUNCTION: After investigation, it was discovered that the malfunction of point II on the Valve Leak Detection Recorder TR-2-260-20, was due to a loose electrical connection in the thermocouple lead.
RESULTS & EFFECTS ON SAFE OPERATION: There was no effect on safe operation as the acoustic monitor for this relief valve was functional and therefore adequate valve position monitoring was available to satisfy Technical Specification Table 3.2-4.
Also, position light indication for the relief valve position was available.
ACTION TAKEN TO PREVENT REPETITION: The corrective action involved replacing both the window splices on the inside and outside of the drywell penetration on two separate occasions. The thermocouple was raplaced at both times also to be conservative. Due to past f ailures, action item record (AIR) 4-87-17 has been initiated to improve the relief valve temperation indication system.
WORK REQUEST NO.:
Q59032 LER NUMBER: N/A COMPONENT:
System 260 - Replaced the thermocouple for recorder 2-260-20.
CAUSE OF MALFUNCTION: After investigation, it was discovered that the malfunction of point II on the Valve Leak Detection Recorder, TR-2-260-20, was due to a loose electrical connection in the thermocouple lead.
RESULTS & EFFECTS ON SAFE OPERATION: There was no effect on safe operation as the acoustic monitor for this relief valve was functional and therefore adequate valve position monitoring was available to satisfy Technical Specification Table 3.2-4.
Also, position light indication for the relief valve position was available.
ACTION TAKEN TO PREVENT REPETITION: The corrective action involved replacing both the window splices on the inside and outside of the drywell penetration on two separate occasions. The thermc. couple was replaced at both times also to be conservative. Due to past failures, action item record (AIR) 4-87-17 has been l
initiated to improve the relief valve temperation indication system.
WORK REQUEST NO.:
Q59612 LER NUMBER: N/A COMPONENT:
System 261 - Replaced temperature switches and inspected mounting supports.
-CAUSE OF MALFUNCTION: The cause of the malfunction of the temperature switch,
'l-261-18D, was due to the switch being grounded to its associated conduit.
This was a result of improper instrument support allowing it to experience excessive vibration.
RESULTS & EFFECTS ON SAFE OPERATION:
Safety implications were minimal since the other area monitors were operating properly and the temperature switch failed in the conservative direction, i.e.,
half a Group I isolation occurred.
ACTION TAKEN TO PREVENT REPETITION:
The failed temperature switch was replaced like-for-like and properly supported.
Other temperature switches will be investi-gated for improper supports during the next refuel outage (Q59612).
WORK REQUEST NO.:
Q60285 LER NUMBER:
87-012 COMPONENT:
System 1600 - Adjusted test cylinder on 2-1601-33E.
CAUSE OF HALFUNCTION: The cause of the malfunction of the vacuum breakers 2-1601-33E and 32A was in the testing portion: when the test cylinder was actuated the valve disc arm was binding on the stuffing box bushing.
Therefore, the test cylinder arm and the valve disc arm were adjusted on both vacuum breakers and for the 33E the test cylinder was rebuilt.
For 2-1601-33A the limits were adjusted because it had been showing dual indication.
RESULTS & EFFECTS ON SAFE OPERATION:
Upon analysis it was determined that the vacuum breakers 2-1601-33E, 32A, and 33A would all have performed as required during a LOCA. Also, the vacuum breakers were tested every 15 days after the event as required by Technical Specification 3.7.A 4.d.
Therefore, the safety implications are minimal.
ACTION TAKEN TO PREVENT REPETITION:
The immediate corrective action for the vacuum breakers was to repair them.
Also due to recurring problems with the vacuum breakers an Action Item Record (AIR) 4-87-15 has been initiated to investigate the problem.
F WORK REQUEST NO.:
Q60288 LER NUMBER:
87-012 COMPONENT: System 1600 - Adjusted limits on 2-1601-33A.
CAUSE OF MALFUNCTION: The cause of the malfunction of the vacuum breakers 2-1601-33E and 32A was in the testing portion: when the test cylinder was actuated the valvo disc arm was binding on the stuf fing box bushing. Therefore, the test cylinder arm and the valve disc arm were adjusted on both vacuum breakers and for the 33E the test cylinder was rebuilt.
For 2-1601-33A the limits were adjusted because it had been showing dual indication.
RESULTS & EFFECTS ON SAFE OPERATION: Upon analysis it was determined that the vacuum breakers 2-1601-33E, 32A, and 33A would all have performed as required during a LOCA. Also, the vacuum breakers were tested every 15 days after the event as required by Technical Specification 3.7.A.4.d.
Therefore, the safety implications are minimal.
ACTION TAKEN TO PREVENT REPETITION: The immediate corrective action for the vacuum breakers was to repair them. Also due to recurring problems with the vacuum breakers an Action Item Record (AIR) 4-87-15 has been initiated to investigate the problem.
WORK REQUEST NJ.:
Q60289 LER NUMBER:
87-012 COMPONENT:
System 1600 - Adjusted test cylinder on 2-1601-32A.
CAUSE OF MALFUNCTION: The cause of the malfunction of the vacuum breakers 2-1601-33E and 32A was in the testing portion: when the test cylinder was actuated the valve disc arm was binding on the stuffing box bushing.
Therefore, the test cylinder arm and the valve disc arm were adjusted on both vacuum breakers and for the 33E the test cylinder was rebuilt.
For 2-1601-33A the limits were adjusted because it had baen showing dual indication.
RESULTS & EFFECTS ON SAFE OPERATION: Upon analysis it was determined that the vacuum breakers 2-1601-33E, 32A, and 33A would all have performed as required during a LOCA. Also, the vacuum breakers were tested every 15 days after the event as required by Technical Specification 3.7.A.4.d.
Therefore, the safety implications are minimal.
ACTION TAKEN TO PREVENT REPETITION:
The immediate corrective action for the v.Scuum breakers was to repair them. Also due to recurring problems with the vacuum breakers an Action Item Record (AIR) 4-87-15 has been initiated to investigate the problen.
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WORK REQUEST NO.:
Q60361 LER NUMBER: N/A COMPONENT:
System 260 - Replaced thermocouple for point II on 2-260-20.
CAUSE OF MALFUNCTION: After investigation, it was discovered that the malfunction of point II on the Valve Leak Detection Recorder, TR-2-260-20, was due to a loose electrical connection in the thermocouple lead.
RESULTS & EFFECTS ON SAFE OPERATION: There was no effect on safe operation as the acoustic monitor for this relief valve was functional and therefore adequate valve position monitoring was available to satisfy Technical Specfication Table 3.2-4.
Also, position light indication for the relief valve position was available.
ACTION TAKEN TO PREVENT REPETITION: The corrective action involved replacing both the window splices on the inside and outside of the drywell penetration on two separate occasions.
The thermocouple was replaced at both times also to be conservative. Due to past failures, action item record (AIR) 4-87-17 has been initiated to improve the relief valve temperation indication system.
WORK REQUEST NO.: Q61026 LER NUMBER: N/A COMPONENT:
System 8800 - Rebuilt solenoid valve FCV-2-8802A.
CAUSE OF MALFUNCTION:
Valve A0 2-8802A did not close due to the failure of its valve operator solenoid due to normal operational wear.
RESULTS & EFFECTS ON SAFE OPERATION: As soon as the failure was identified the operator immediately closed the redundant isolation valve A0 2-8801A to ensure primary containment. Therefore, safety implications were minimal.
ACTION TAKEN TO PREVENT REPETITION:
The valve operator solenoid was rebuilt and the valve subsequently cycled three times successfully.
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WORK REQUEST NO.: Q61144 LER NUMBER:
87-013 COMPONENT:
System 6700 - Cubicles in Bus 23 were cleaned.
CAUSE OF MALFUNCTION: The cause of the damage done to bus 23 was the result of an Equipment Operator accidently racking out the wrong breaker, which was energized.
RESULTS & EFFECTS ON SAFE OPERATION: The safety of the plant and personnel was not affected during thie event.
No one was injured and all Engineered Safety Features acted as designed to bring the reactor to stable conditions.
ACTION TAKEN TO PREVENT REPETITION: The event was discussed with members of the Operating Department.
Training sessions will be held to discuss lessons learned.
A review of 4 KV switching procedures has been conducted and revisions implemented as necessary.
WORK REQUEST NO.:
Q61302 LER NUMBER: 87-013 COMPONENT:
System 6700 - Installed 4KV circuit breaker in bus 24.
CAUSE OF MALFUNCTION: The cause of the damage done to bus 23 was the result of an Equipment Operator accidently racking out the wrong breaker, which was energized.
RESULTS & EFFECTS ON SAFE OPERATION: The safety of the plant and personnel was not affected during this event.
No one was injured and all Engineered Safety Features acted as designed to bring the reactor to stable conditions.
ACTION TAKEN TO PREVENT REPETITION:
The event was discussed with members of the Operating Department.
Training sessions will be held to discuss lessons learned.
A review of 4 KV switching procedures has been conducted and revisions implemented as necessary.
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WORK REQUEST NO.: Q61345 LER NUMBER: 87-013 COMPONENT:
System 6700 - Inspected and reassembled cubicles in Bus 23.
b CAUSE OF MALFUNCTION: The cause of the damage done to bus 23 was the result of an Equipment Operator.accidently racking out the wrong breaker, which was energized.
RESULTS & EFFECTS ON SAFE OPERATION: The safety of the plant and personnel was not affected during this event. No one was injured and all Engineered Safety.
Features acted'as designed to bring the reactor to stable conditions.
ACTION TAKEN'TO PREVENT REPETITION: The event was discussed with members of the Operating Department. Training sessions will be held to discuss lessons learned.
A review of 4 KV switching procedures has been conducted and revisions implemented.
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as necessary.
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t WORK REQUEST NO.: Q61471 P
LER NUMBER: 87-015 i
COMPONENT:
System 1700 - Replaced Off-Gas Timer, 1705-23.
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CAUSE OF MALFUNCTION: The cause of the malfunction of the Off-Gas Timer, 2-1705-23 f
was due to its motor end-of-life, 1
'RESULTS & EFFECTS ON SAFE OPERATION: The Off-Gas Timer is tested every refueling l
outage, it was last tested on 1-9-87 successfully. Since then there has been no unusual radiation levels detected by the. chimney radiation monitors requiring l
actuation of the timer.
i ACTION TAKEN TO PREVENT REPETITION:
The Off-Gas Timer was replaced like-for-like and tested successfully. An Action Item Record (AIR), 4-87-19, was initiated t
to develop a means of indicating motor failure or a design change to prevent this problem from recurring, l
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IV.
LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.1. and 6.6.B.2. of the Technical Specifications.
UNIT 1-Licensee Event Report Number Date Title of Occurrence 88-001 1-14-88 Overexposure of 2 Individuals in 1980 88-002 1-12-88 Missed Functional Surveillance UNIT 2 88-001 1-11-88 U2 Reactor Scram -
Turbine Generator Load
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Rej ection 1
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DATA TABULATIONS The following data tabulations are presented in this report:
A.
Operating Data Report B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions 0027H/00612
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APPENDIX C OPER ATING DATA REPORT 00CKET NO.
50-254 UNIT ONE DATE FEBRUARY 8, 1988 L. DEELSNYDER COMPLETED BY 309-654-2241 l
TELEPHONE OPERATING STATUS 0000 010188 704 2400 013188 GROSS HOURS IN REPORTING PERIOQ:
- 1. REPORTING PERIOO 2511 M Ax. ogeEND. CAPACITY (MWWl:
769
- 2. CURRENTLY AUTHORlIED POWER LEVEL (MWIL.
DESIGN ELECTRICAL MATING (MWeNetit W
- 3. POWSR LEVEL TO WHICH RESTRICTED (IP ANY) (MWeNetit
_ N/A
- 4. REASONS FOR RESTRICTION (IP ANYit THIS MONTH YR TO DATE CUMULATIVE 744.0 109808,3 S. NUMSER OF HOURS REACTOR WAS CRITICAL.............. 74 4. 0 0.0 0.0 3421.9
- 8. REACTOR R ESERVE SHUTDOWN HOURS...................
- 7. HOURS GEN ER ATOR ON LINE......................... 7 3 7.1 737.1 106195.3 0*O O0 909 2
- 8. UNIT RESERVE SHUTDOWN HOURS
- 9. GROSS THERMAL ENERGY GENER ATED (MWHI..............I756464 1756464 225055639 571773 571773 _72995275
- 10. GROSS ELECTRICAL ENERGY GENER ATED (WWHI...........
24A56 24856 679?R145
- 11. NET ELECTRICAL ENERGY GENERATED (WWHI..............
- 12. ' E ACTOR SE RVIC E F ACTOR........................... I O O O I00 0 79 7
- 13. R E ACT O R AV AI LA t! LIT Y F ACTOR....................... I O O O IOO'O 82 2 99.0 99.0 77.0
99*0 99 0 77 7
- 15. UNIT AV AILAtlLITY F ACTOR..........................
4.3 64.0 4.3
- 10. UNIT CAPACITY F ACTOR (U#g MDC) 4.2 4,2 62.5
- 17. UNIT ': UACITY F AC10m (Us.no Demon MWel.................
0*9 09 5'O f t. UNIT F O RCE D OUTAG E RAT E........................
- 19. SFUTDOWNS SCHEDULED OVER NEXT S MONTHS (TYPE, DATE. AND OURATION OF EACHit
- 20. IF SHUT DOWN AT END OF REPORT PERIOD. ESTIM ATED DArg c:' STARTUP:
- 21. UNITS IN TEST STATUS (PRIO9 TO COMMERCt".L OPERAllON):
FORECAST ACHIEVED INITI AL CRITICALITY INITI AL RECTRICITY COMMERC4.L OPSr.ATlON 1.16 9 J
APPENDIX C OPERATING DATA REPORT DOCKET NO.
50-265 UNIT Tk'O DATE FEBRUARY 8, 1988 i
COMPLETE 0 BY L. DEEL9NYDER l
TELEPHONE 309-654-2241 OPER ATING 3TATUS 0000 010188 700 240_0 013188 GRO8s HOURS IN REPORTING PERICO:
- 1. REPORTING PERICO:.
- 2. CURRENTLY AUTHORIZFD POWER LEVEL (WW:
2511 max OEPENO. CAPACITY (MWe Noti:
769 DESIGN ELECTRICAL RATING (MWe Nedi 789 N/A
- 3. POWER LEVEL TO WHICH RESTRICTED (IF ANYI (MWe Ned: __
- 4. REASONS POR RESTRICTION (IP ANYl THIS MONTH YM TO DATE CUMULATIVE 648.0 105105.1_
S. NUdttR OF HOURS REACTOR WAS CRITICAL.............. 64 8. 0
- 0. 0 _
0.0 2985.8
- 8. R EACTOR R ESERVE SHUTOOWN HOURS................... 631.9 631.9 102167.2.
- 7. HOURS GENERATOR ON LINE,...........
0.0 0.0 702.9_
- 8. U NIT R ESE RVE SHUTOOWN HOURS......................
- 9. GROSS THERMAL ENERQY GENERATED (MWHI............. 1424400, 1474400 718794967 4633S7 463357 70021141 l
- 10. GROSS ELECTRICAL ENERGY GENER ATED (MWM)...........
19610 19610 65574635
- 11. NET ELECTRICAL ENERGY GENERATED (MWM)
.I
- y. I 76.9
- 12. E ACTOR SE RVICE F ACTOR..................
87*l 07*I 79 I l
- 13. R E ACTOR AV AI LA tlLITY F ACTOR......................
84.9 84.9 74.6
- 14. UNIT SERVIC E F ACTOR........................
00*9 80 9 75 1 l
- 15. UNIT AV AILABILITY F ACTOR..........................
i 3.4 3.4 69.1 it. UNIT CAPACITY F ACTOR (using MOCl.....................
60,7
- 17. UNIT CAPACITY F ACTOR (Usant Oomen MWel.................
15.2 15,2 8.3
- 18. UNI T F O RC E O OUT AG E RAT E...........,.....
- 18. SHUTOOWNS SCHEDULEO QVER. NF.AT 6 MONTHS (TYPE. DATE. AND OURATION CP EACHl:
i
- 20. IF SHUT DOWN AT END W/ R$ PORT Pr.RIOD. ESTIMATED DATE OF STARTUP;
- 21. UNITS IN TEST STATUS ORIOR TO COMMERCI AL OPERATIONI:
FORECAST ACHIEVED INITI AL CRITICALITY INITI AL E'.ECTRICITY COW 4RClAL OPERATION 1.16 9
APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-254 UNIT ou DATE February 4, 1988 COMPLETED BY L Daalanvaer TELEPHONE 309-654-2241 MOG JANUARY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe-Net) 3 gy 751 718 2
686 gg 783 302 gg 764 3
4 720 g
734 5
21 732 715 3
760 22 76I 794 7
23 793 756 760 3
24 786 771 i
g g
785 10 776 3
11 777 27 741 12 755 g
726 796 3
711 13 786 7II 14 30 1
l 15 767 31 672 16 775 INSTRUCTIONS On this form, hst the average daily unit power level m MWe Net for each day in the reporting month. Compute to the neassst whole megawatt.
These figures will be used to plot a graph for cash reporung month. Nute that when maximum dependable capacity is used for the net etestrical rating ut the unit, there may be owntons when the daily average power level exceeds the 100A line (or the rntncted power lesel hnc). In such cases, the average da@ urut power output sheet should be fwtnoted to explam the apparent anomaly.
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APPENDIX 3 AVERAGE DAILY UNIT POWER LEVEL i
DOCKET NO. 50-265 UNIT Te l
DATE Februarv 4, 1988 COMPLETED BY 1.. nectanvaer TELEPHONE 3n9-654-7241 MONTH JANUARY DAY AVERAGE DAILY MWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe h et)
(MWe Net) 1 751 jy 473 720 698 2
q, 745 788 3
gg 704 4
3 765 5
354 21 746 3
730 22 753 775 y
23 753 747 g
24 716 779 744 g
25 736 717 10 26 343 711 qq p
-8 750 12 g
729 13 29
~ll 14 N
710 15
-12 31 652 16 363 INSTRUCTIONS On this form, list the average daily unit power new! in MWe Net for each day in the reporting month. Compute to the nemicst whole megawatt.
These figures will be used to plot a graph for cash reporung month. Note that when maximum dependable capacityis used for the itet cleetncal rating ut the unit. there may be occasions whers the daily average power levcl exceeds the 100'J hne (or the restricted power level Itnc). In such cases, the average daily urut power output sheet should be footnoted to explaua the apparent anomaly.
1.l H
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ID/SA APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-254 Revision 6 August 1982 UNIT NAME QUAD CITIES UNIT ONE COMPLETvJ) BY L. DEELSNYDER DATE FEBRUARY 3, 1988 REPORT HONTH JANUARY 1988 TELEPHONE 309-654-2241 w
w" 5 @
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LICENSEE m@
g DURATION R
EVENT
$u )
u g
o NO.
DATE (HOURS)
"g REPORT EX),
o CORRECTIVE ACTIONS /COf9 TENTS 88-1 880103 F
6.9 A
9 HA RELAY Main Turbine Tripped Due to EllC Leak on Turbine Front Standard 88-2 880109 0.0 H
9 CB 222222
, Power Reduction to Perform Flow Drop i Test (Surveillance)
APPROVED AUG161982 (final) yCUSN
- ~ - -
)
ID/SA APPENDIX D QTP 300-S13 UNIT SNUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.
50-265 August 1982 UNIT NAME QUAD CITIES UNIT TWO COMPLETED BY L. DEELSNYDER DATE FEBRUARY 3, 1988 REPORT MONTH JANUARY 1988 TEIIPMONE 309-654-2241 Aont M
m x
h@w
$w w
o o
g$
$ gM LICENSEE m
g DURATION M
EVENT
$0 u
g o
NO.
DATE (HOURS)
REPORT NO.
o g
CORRECTIVE M IONS / N 88-1 880105 0.0 11 9
CC VALVEX Power Reduction Due to Drywell Leak 4
Inspection 88-2 880111 F
96.0 A
3 04-2-88-00]
EB GENERA Reactor Scram on Generator / Turbine Load Mismatch - Main Generator Ground APPROVED AUG161982 (final) y g_ g g g
r 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 R0D 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.
t I
h 1
0027H/00612
VII.
REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) frot 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.
0027H/0061Z
QTP 300 532 Revision 1 QUAO CITIES REFUELING March 1978 INFORMATION REQUEST 1.
Unit:
01 Reload 9
Cycle:
in 2.
Scheduled date for next refueling shutdown:
6-24-89 3.
Scheduled date for restart following refueling:
9-17-89 4.
Will refueling or resamption of operation thereaf ter require a technical specification change or other Ilconse amendment:
NOT AS YET DETERMINED.
5.
Scheduled date(s) for submitting proposed IIcensing action and supporting information:
MARCH 24, 1989 6.
Important licensing considerations associated with refueling, e.g., new or
' different fuel design or supplier, unreviewed design or performance analysis methods, signiflcant changes in fuel design, new operating procedures:
NONE AT PRESENT TIME.
7.
The number of fuel assemblies.
a.
Number of assemblies In core:
724 b.
Number of assemblies in spent fuel pool:
1773 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:
Licensed storage capacity for spent fuel:
a.
3657 b.
Planned increase In !! censed storage:
n.
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2008 APPROVED APR 2 01978 Q.C.O.S.R.
.e qTP 300-532 Revision 1 QUAO-CITIES REFUELING March 1978 INFORMATION REQUEST 1.
Unit:
02 Reload:
8 Cycle:
9 2.
Scheduled date for next refueling shutdown:
4-9-88 3.
Schedulsd date for restart following refueling:
6-18-88 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment:
YES. 'fECHNICAL SPECIFICATION CRANGES WILL BE REQUIRED FOR NEW FUEL TYPES (MAPHLCR CUR CHANGE TO MCPR LIMIT AND OPERATION AT INCREASED CORE FLOW / FINAL FEEDWA 5.
Scheduled date(s) for submitting proposed licensing action and supporting in forma tion:
March 4, 1988 6.
Important licensing considerations associated with refyeling, e.g., new or
' different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
FIRST RELOAD OF GENERAL ELECTRIC, GE8E FUEL WITH 4 WATER-RODS AND LHCR LIMIT OF 14.4 KW/FT.
7.
The number of fuel assemblies, a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
1311 S.
' he present licensed spent fuel pool storage capacity and the size of any i
increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:
Licensed storage capacity for spent fuel:
a.
3897 b.
Planned increase in licensed storage:
0 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
2008 APPROVED APR 2 01978 Q.C.O.S.R.
VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report, are definet below:
ACAD/ CAM Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI American National Standards Institute APRM Aver &ge Power Range Monitor ATHS Anticipated Transient Without Scram BWR Solling Water Reactor CRD Control Rod Drive Electro-Hydraulic Control System EHC EOF Emergency Operations facility Generating Stations Emergency Plan GSEP HEPA High-Efficiency Particulate Filter HPCI High Pressure Coolant Injection System High Radiation Sampling System HRSS IPCLRT Integrated Primary Containment Leak Rate Test IRM Intermediate Range Monitor ISI Inservice Inspection LER Licensee Event Report LLRT Local Leak Rate Test LPCI Low Pressure Coolant Injection Mode of RHRS Local Power Range Monitor LPRM MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MFLCPR Maximum Fraction limiting Critical Power Ratio MPC Maximum Permissible Concentration MSIV Main Steam Isolation Valve NIOSH National Institute for Occupational Safety and Health Primary Containment Isolation PCI PCIOMR Preconditioning Interim Operating Management Recommendations RBCCH Reactor Building Closed Cooling Hater System RBM Rod Block Monitor Reactor Core Isolation Cooling System RCIC RHRS Residual Heat Removal System RPS Reactor Protection System RWM Rod Horth Minimizer SBGTS Standby Gas Treatment System SBLC Standby Liquid Control SDC Shutdown Cooling Mode of RHRS SOV Scram Discharge Volume SRM Source Range Monitor TBCCW Turbine Building Closed Cooling Water System TIP Traversing Incore Probe TSC Technical Support Center 0027H/00612
.I O 22710 206 Avelrue North Commonwealth Edison ound Cit!es Nuclear Power Station Cordova, Illinois 61242 Telephone 309/654-2241 RAR-88-01 January 28, 1988 U.S. NRC Office of Nuclear Reactor Regulation Washington, D. C.
20555 Attn:
Document Control Desk Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of January, 1988, Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION 0&
R. A. Robey Services Superintendent yk Enclosure d
0027H/00612