ML20072S735
| ML20072S735 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/31/1991 |
| From: | Losekshort C COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20072S732 | List: |
| References | |
| NUDOCS 9104170011 | |
| Download: ML20072S735 (20) | |
Text
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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT FEBRUARY 1991 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 nrcreprt 9104170011 910402 PDR ADOCK 05000254 R
E TABLE OF CONTENTS I.
Introduction II.
Summary of Operating Experience A.
Unit One B.
Unit Two III.
Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A.
Amendments to Facility License or Technical Specifications B.
Facility or Procedure Changes Requiring NRC Approval C.
Tests and Experiments Requiring NRC Approval D.
Corrective Maintenance of Safety Related Equipment IV.
Licensee Event Reports V.
Data Tabulations A.
Operating Data Report B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions VI.
Unique Reporting Requirements A.
Main Steam Relief Valve Operations B.
Control Rod Drive Scram Timing Data VII.
Refueling Information VIII.
Glossary nrcreprt i
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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.
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 Cynthia A.
Losek-Short and Debra Kelley, telephone number 309-654-2241, extensions 2938 and 2240, nrcreprt
II.
SUMMARY
OF OPERATING EXPERIENCE A.
Unit One Unit One began the month of March with the centinuation of the refuel outage.
Preliminary testing of the Unit continued throughout the month.
B.
Unit Two Unit Two began the month of March operating in Economic Generation Control (EGC).
Normal operational activitieo were performed for the month of March.
The unit remained in EGC for the month with the only interruption being on March 24th.
Unit power was dropped to 200 MWE for entry into the Drywell to check for water leaks.
nrcroprt
s III.
PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.
AND SAFETY RELATED MAINTENANCE A.
Amendments to Pacility License or Technical Specifications Technical Specification Amendments No. 129 was issued on February 21, 1991 to Facility Operating License DPR-29 for Quad-Clites Nuclear Pcwor Station.
This amendment revises the Technical Specification to reflect the modification to the Turbine Control Valves, Fast Acting Solenoids.
Technical Specification Amendment No. 130 and 124 were issued on March 8 to Facility Operating License DPR-29 and DPR-30, respectively, for Quad Cities Nuclear Power Station.
These amendments delete operational demonstrations of ECCS systems when one system is found to be degraded or inoperable for HPCI, RCIC and ADS.
B.
Facility or Procedure Chances Reauirina NRC Annroval There were no Facility or Procedure changes requiring NRC approval for the reporting period.
C.-
Tests and Experiments Reavirina NRC ADDroval There were no Tests or Experiments requiring NRC approval for the reporting period.
D.
Corrective Maintenance of Safety Related Ecuinment The following represents a tabular summary of the major safety related maintenance peformed on Units One and Two during the reporting period.
This summary includes the following:
Work Request Numbers, Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.
nrcreprt
l JW M UNIT 1 MAINTENANCE
SUMMARY
WORK REQUEST SYSTEM EID DESCRIPTION.
WORK PERFORMED Q89916 0020 Raychem splice in As Found: EQ-913 and EQ-914 pulling box gasket, Junction Box EQ-823.
EQ-918 eight screws and washers need replacement.
As Left: EQ-913 and EQ-914 pulling box had new gaskets installed and EQ-918 had eight new screws and washers installed for cover, EQ-823 removed damaged raychem and cleaned conductors, removed insulation and made splice connection and put new raychem on and heat shrunk.
Q78942 0261 DP pressure switch lock As Found: Found the hold down or locking screw for switch stripped and not holding correctly during Q1P 100-10.
As Left: Modified scale plate to fit 288A, and scribed 0-50 and 100%
reading marks on new case. Calibrated pointer to within 2% of full scale and calibrated switch to open at 8 PSID decreasing. Performed appropriate steps of Q1P 100-10 successfully.
Q91016 0300 lustrument Block As Left:
Recoved old valve and replaced with Needle Valve.
valve.
Q90836 0901 During RHR Logic Test, As Found: Relay was found to be bad during RHR time delay relay 10A-K13A Logic Testing. As Left: Replaced relay and didn't function properly.
time delay device. Performed dedication test plant for CR120K timing unit copy in package.
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UNIT 1 MAINTENANCE
SUMMARY
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WORK REQUEST SYSTEM EID DESCRIPTION WORK PERFORMED Q89407 1705
' Reactor Bldg. Vent As Left: Performed steps for station traveler Bypass Switch QAP-1500-S28 to satisfy that B loop bypass switches were in the correct positions for trip units, they were.
Q90612 2201 The wire terminal 6/18 on As Found: There was bare wire showing. As Left:
rack 2201-6 has insulation Taped up the wire and sealed the insulation.
cut exposing wires please repair.
Q88347 2301 Local operating station fails As Found: Valve would not stroke locally and to open or close 2301-10.
switch contacts would not make up when button was pushed. As Left: Problen is in the rubber pad which needs to be replaced or extended. Pushbuttons were removed and gasket material SI #615789 was installed behind 3 switches so they would actuate easier.
Q89862 2400 IB Drywell Rad Monitor As Found: SL;nal connector removed from plugs, A.V. cable pulled out of connector. As Left:
H.V. connectors appears to be working 0.K.
Q87945 2400 IB Drywell Rad Monitor As Found: Measured proper voltage for (+) and
(-) volts, (+) and (-) 15 volts but measured OV for HV supply. As Left: Removed IB monitor SER #072 and installed SER #71 calibraticn or adjustment for SER #71 was done in the IM shop.
1
UNIT 1 MAINTENANCE
SUMMARY
WORK REQUEST SYSTEM EID DESCRIPTION WORK PERFORMED Q89963 3903 Diesel Generator Cooling As Found:
Inboard bear leaks oil and found Water Pump thread lubricant to be minimal. As Left: Disassembled oilers and piping cleaned parts and reinstalled parts using thread lubricate PST Liquid Teflon.
Oilers were adjusted to proper level and locked in place.
Q86649 5501
- 3 Control valve As Found: Valve will not close. As Left: These fast-acting solenoids were replaced with Parker-Hannifin solenoids during QiR11 Refueling Outage.
Q89707 6601 U1 DG Exhaust Gas As Found: Readings in degrees F.
Thermocouple
- 1-90 6-95 11-95 16-95 2-90 7-85 12-95 17-95 3-90 8-95 13-95 18-95 4-90 9-95 14-95 19-95 5-90 10-90 15-95 20-90 Ao Left:
Installed new thermocouple performed testing per WR Traveler, All points were reading approximately between 80-83 degrees F.
Q89908 6706 Bus 14-1 Breaker to DG As Left: Ran tap through jacking nut couldn't find any problems.
Freed up shutters by hand and wiped off the excess grease. Operating then installed breaker and the breaker racked in freely.
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l UNIT 2 MAINTENANCE
SUMMARY
WORK REQUEST SYSTEM EID DESCRIPTION WORK PERFORMED Q90693 0300 Instrument Block As Found: Valve was leaking. As Left: Replace Needle Valve valve with a new valve.
Q76932 1640 Containment Level /
As Left: Replace the chart magazine assembly Pressure Recorder to repair the chart drive gear.
Then calibrated recorder per section 5 of vendor manual.
QS7804 6601 Control Panel As Found: Two 1/4-20X1 bolts were broken off and 4 bolts were missing. As Left: Removed broken off with an extractor and replace all old bolts with new.
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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 Numbgr Date Title of Occurrence 91-004*
2/8/91 SBGT Heater Failure Logic Missing 91-004 3/20/91 10 & 1D RHR Pumps Auto Start 91-008 3/22/91 Reactor Building vent isolation due to lightning strike UNIT 2 There were no licensee event reports for Unit 2 for this reporting period.
- 91-004 report for the month of February has been downgraded, nrcroprt l
V.
DATA TABULATIONS The following data tabulations are presented in this report:
A.
Operating Data Roport B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions nrcreprt
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VI.
UNIOUE REPORTING REOUIREMEffTS The following items are included in this report based on prior commitments to the commission:
A.
Main Steam Relief Valve Operationg There were no Main Steam Relief Valvo Operatins for the reporting period.
B.
Control Rod Drive Scram Timina Data for UnitgL,Qne and Two There was no control Rod Drive scram timing data for Unito One and Two for the reporting period.
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VII.
REFUELING INFORMATIOl{
The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (70-24) 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.
nrcroprt' f.
l l-
QTP 300-532 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST 1.
U11t:
Q1 Reload:
10 II Cycle:
2.
Scheduled date for next refueling shutdown:
11-12-90 3.
Scheduled date for restart following refueling:
4-15-91 4.-
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amen ment Yes, a proposed change to Technical Spect icat on has been made to relax the Minimum Critical Power Ratio (MCPR) safety limit.
This proposal is based on the Unit One Reload 11 Cycle 12 fuel loading, and has received approval.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
August 31, 1990 6.
Important licensing considerations associated with refueling, e.g., new te different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
NONE AT PRESENT TIME.
L The number of fuel assemblies.
a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel,m l:
1681 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is i-planned in number of fuel assemblies:
a.
Licensed storage capacity for spent fuel:
3657 b.
Planned 1%rsa:e in licensed storage:
0
\\
L 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming.the present licensed capacity:
2009 APPROVED i
14/0395t.
O.C.O.S.R.
QTP 300-538 i
Revision 2 l
l QUA0 CITIES REFUELING October 1989 INFORKATION REQUEST 1.
Unit:
Q2 Reload:
10 Cycle:
11 2.
Scheduled date for next refueling shutdown:
9-7-91 3.
Scheduled date for restart following refueling:
12-9-91 4.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:
NOT AS YET DETERMINED.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
NOT AS YET DETERMINED.
6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysts methods, significant changes in fuel design, new operating procedures:
NONE AT PRESENT TIME, 7.
The number of fuel assemblies, a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
2011 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:
a.
Licensed storage capacity for spent fuel:
3897 b.
Planned increase in licensed storage:
0 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capactty: 2009 APPROVED (finai)
OCT 3 01969 14/0395t O.C.O.S.R.
.e-VIII.
GLOSS.ABY The following abbreviations which may have been used in the Monthly. Report, are defined below:
ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring American National Standards Institute ANSI 1 Average Power Range Monitor APRM-Anticipated Transient Without Scram ATWS Boiling Water Reactor BWR Control Rod Drive CRD Electro-Hydraulic Control System EHC o
Emergency Operations-Facility 1
EOF Generating Stations Emergency Plan
-GSEP High-Efficiency Particulate Filter HEPA-High-Pressure Coolant Injection System HPCI High Radiation Sampling System HRSS Integrated Primary Containment Leak Rate Test IPCLRT Intermediate Range Monitor IRM Inservice Inspection ISI Licensee Event Report LER Local Leak Rate Test LLRT Low Pressure Coolant' Injection Mode of RHRs LPCI Local Power Range Monitor LPRM.
Maximum Average Planar-Linear Heat Generation MAPLJIGR
' Rate Minimum Critical Power Ratio MCPR Maximum. Fraction Limiting Critical Power Ratio MFLCPR.
Maximum Permissible Concentration MPC Main Steam Isolation Valve MSIV National-Institute for occupational Safety and-
. NIOSH Health Primary Containment Isolation PCI Preconditioning Interim Operating Management PCIOMR'
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Recommendations Reactor Building Closed Cooling Water System RBCCW
. Rod Block Monitor
- RBM:
Reactor Core Isolation-Cooling System-RCIC:
Residual Heat. Removal System RHRS-Reactor Protection System
. RPS_
Rod Worth Minimizer RWM Standby Gas Treatment System-SBGTS Standby Liquid Control SBLC SDC-
- - - Shutdown Cooling ModeLof RHRS Scram Discharge Volume
- SDV SRM.
. - -- Source: Range Monitor Turbino Building Closed Cooling Water. System TBCCW --
Traversing Incore Probe TIP Technical Support Center TSC-nrcreprt uw* rem
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