ML20064B317
| ML20064B317 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 09/30/1990 |
| From: | Hamilton L, Robey R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RAR-90-74, NUDOCS 9010160103 | |
| Download: ML20064B317 (19) | |
Text
{{#Wiki_filter:].l, ..: ~~q Commonwealth Edison. l q omd Cites Nuclear Power Station
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- - 22710 206 Avenue North
\ oordova. llhnos 61242 9740 kg . Tekphorie 309$54 2241 l
RAR-90-74 October 2, 1990 l 4 U. S. Nuclear Regulatory Commiss' ion ATTN: Document Control Desk , Washington, D. C. 20555 )
SUBJECT:
Quad Cities Nuclear Station Units 1 and 2 ) Monthly Performance Report NRC Docket Nos. 50-254 and 50-265 Enclosed for your information is the Monthly Performance Report covering ' the operation of Quad-Cities Nuclear Power Station, Units One and Two, i during the month of September, 1990. Respectfully, COMMONNEALTH EDIS0N COMPANY QUAD-CITIES NUCLEAR POWER STATION i
#A.[dy R. A. Robey Technical Superintendent RAR/LFD/jmt Enclosure cc: A.B. Davis, Regional Administrator T. Taylor Senior Resident Inspector bC)30 0027H/0061Z hDR R
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f 6, QUAD-CITIES NUCLEAR. POWER STATION- ! E j F UNITS 1.AND 2 ? MONTHLY. PERFORMANCE, REPORT
~ September, 1990-l COMMONWEALTH EDISON COMPANY i
AND l [' IONA-ILLINOIS GAS & ELECTRIC COMPANY .]
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, l' , , NRC DOCKET NOS.'50-254 AND 50-265 ;
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~ LICENSE NOS OPR-29.AND DPR-30 >
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TABLE OF CONTENTS I. Introduction II. Summary of Operating Experience a A. Unit One ' B. Unit Two III. Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance , A. Amendments to Ft.cility License or Technical Specifications l B. Facility or Procedure C.6.anges Requiring NRC Approval : C. Tests and Experiments Requiring NRC Approval 1
- 0. Corrective Maintenance of Safety Related Equipment t IV. Licensee Event Reports V. Data Tabulations l l 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 I B. Control Rod Drive Scram Timing Data ; i VII. Refueling Information , l- VIII. Glossary , i 0027H/00612
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I s I. INTRODUCTION i Quad-Cities Nuclear Power Station is composed of two Bolling 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 Hater 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 pIrsuant to Docket Numbers 50-254 and 50-265. The date of initial Reictor criticalttles 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. l This report was compiled by Lynne Hamilton and Verna Koselka, telephone number 309-654-2241, extensions 2185 and 2240. I i 1 { L ! i 0027H/0061Z se j
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- 11.
SUMMARY
OF OPERATING EXPERIENCE A. Unit one 'I Unit One began the month of September operating at full power. On ' September 1, at 0124 hours. the unit was placed in Economic Generation l Control (EGC). For the most of the month, the unit operated near full ui
-power or remained in EGC. Power levels were adjusted according to the demands of the Chicago Load Dispatcher and routine surveillances were
.( .
performed. ! On. September 22, a power reduction to 450 MWe was taken to perform Hydrogen !
' Injection Testing. At 1040 hours, the testing was terminated, and the '
unit was taken to full power. ,
'For the remainder of.the month of September, normal operational' activities occurred. . The unit operated near full power or remained in EGC with minor interruptions to perform routine surveillances. Power levels were also. [
adjusted'according to the demands of the Chicago Load Dispatcher. i B. ' Unit Two r Unit Two began the month of September operating at full power. Until , September 28, the unit operated near full power or remained in Economic , Generation Control (EGC). Power levels were adjusted according to the demands of the Chicago Load Dispatcher and routine surveillances were performed. ,l On September812,. at 0453 hours. the-generator'was taken off-line, and the .i unit was brought to hot standby to perform Turbine Torsional Testing. :How-Lever, at'1750 hours, the testing was terminated due to continuous problems with a blown fuse in the EHC cabinet when attempting to reset the turbine.. At 2213 hours, the reactor was manually scrammed-and the unit remained shutdown-for the remainder of the month while maintenance was performed
- on the EHC systemiand other various systems.
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e t 111. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, [ AND SAFETY RELATED MAINTENANCE _l
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t A. Amendments to Facility License or Technical Specifications 1;
. Technical Specification Amendment No. 126 was issued on September 13, 1990 f f-to Facility Operating License DPR-29 and Amendment No. 122 to Facility
.j Operating License DPR-30 for Quad Cities Nuclear Power Station. These 1 amendments... revise'the Technical Specifications to reflect a High Pressure '
y Coolant: Injection (HPCI) area fire protection modification which replaces ! j rpot-type heat: detectors with a linear heat detector. < B. Facility or Procedure Changes Requiring NRC Approval b There were no Facility or Procedure changes requiring NRC approval'for l
-the reporting period.
! C..' Tests and Experiments Requiring NRC Approval I 9 There were no Tests or Experiments requiring NRC approval for the ; reporting period. ' i D. -Corrective Maintenance of Safety Related Equipment li
.There were no work requests on safety-related equipment which were the ;
result of a Licensee Event Report.- The work requests reported are those- 'l
, closed out and put into history for the reporting period, not necessarily j those work requests where work is performed during the reporting period. ,
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4, IV. LICENSEE EVENT REPORTS 4:
.The'following'is a; tabular summary of'all licensee event reports for Quad-D 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-90-19. 08/14/90 Missed Tech Spec-Surv- . eillance on Main < ~
Steam Line Radiation Monitors 90-20 09/20/90 Lack of Continuous Fire-watch on Cable Tunnel Access Hatch 90-21: 08/12/90 .M0-1-1001-50 Failed to Open When Control Switch was Actuated-UNIT 2
, .90-09 09/15/90 HPCI Inoperable - Failure; 3_,'
of. Gland Seal Condenser-Hotwell Pump th l
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- V.:: DATA'TABULATIONSs If q '.,I .
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lA.-Operating-DataReport
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i .,*4.3'* M: . 1 B. Average-DailyLunit Power t.evel > m-19 . . . . _ n'+ ' 7 j ' .
,I C. Unit Shutdowns and. Power Reductions.
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$* Y :APPENDilC-'
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, .0PERATIN6DATAREPORT' Docket No. 50-254 L Unit ' One p' 2 .. :Date' October 5, 1990 CompletedBy 'Lynne Hasilton
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(- M.' -OPERAi!N6 STATUS: . , 7 tm
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- 1. Reporting Period 2400 093090' . . Gross Hours in Feport Period Z29 h
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- 2. t Cur'rently Authorized Power Level (MWt): 21((-Mar. Depend.' Capacity (MWe-Net): ZH. .
m LDesign Electrical Rating;(MWe-Neth ;Zit g
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v> l s'* e 3.--Power Level to Which Restricted (If Any) (MWe-Net) . N_!_g om- - L4. Aeasons'For Rest'riction (If any) - '>
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,, TH15 MONTH- -VRTODATE . CUMULATIVE ,
t ,y Ch h , j _ :NumberfofiHhurs Reactor Was Critt' cal 720.0 6305.B. 1308' 6: g~ 6.fReactor,ReserveShutdownHours- _ 0.02 0.0 344.9 77.LHoursGeneratorDnLine:' 720.0.- .6266.9 126357.5!
"4; g EB..UnitReserveShutdownHours - 0. 0 0.0 ; 909.2 y j
,J , , :9.c Grass Thereal Energy 6enerated (MWn) 1712647.0-146634B6.0 270345847.0 g, , 110. 6ross Electrical Energy.6enerated (MWM - 547833.0 4759601.0 i87611150.0 y< '
Li!.. Net Electrical Energy Generated (MWh F 533297.0 , '4582029.0 B2422415.0:
, , .."cl2.:ReactorServicefactor.- 100.0) ' 96.3 : E90.6 q j; "
- 313.ReactorAvailabilityFactorl 4 100.0- 96.3 iB2.7. j W, W ~ 414'UnitServiceFactor' 100.0 l95;7 E78.0 ' 2 1 il5hunitAvailabilityFactor" 100.0' 95 7 7B.6
(% b , il6.1 Unit Capicity Factor. (Using MDC) '96.3. 91.0 ' 66.2 il
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l17. Unit Capacity Factor (Using Design MWe) ' 93.9- 88 3 64.5 d gll{: > gl,8,: Unit:ForcedOutagekate ' O.0 , ' !.7 5.2=
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4:mm rn o. 720; if Shut Dowa at End of Report Period, Estisated Date of Startup , jh/j[] p$
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fi APPINDl!C, i ME 1 ,' OPERAllN6DATAREPORT,
/ -Docket No d 50-265
. Unit-'Two S2 Date 0ctober 5, 1990
$ CospletedBy. Lynne Hamilton F "
Telephone .309-654-2241.
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- OPERATING STATUS .- . .
$. 2 $ 0 090190 it.,ReportingPeriod 2400 093090' Gross Hours in Report Peried: 720 f? ] ,
- 2. 1 Currently Authorized PowerItevel'(MWt): 2.1(( Max.' Depend. Capacity (Me'-Net): M'
'i Design Electrical Rating (MWe Net): M E 3. Power Level to Which Restricted (If Any):(Me-Net):' N/A.
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-THis. MONTH .YR TO DATE. ; CUMULATIVE:
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.s 25.ENaeberofHoursReactor.WasCritical 670.2 4221.4 :123606.0-m :.6.JReactorReserveShutdown: Hours. 0.0 0.0 2985.8?
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- 7. Hours Generator On Line- 652.9' 4156.3 120254.8 Ef* 8. 0.0 0.0 702.9
%q s9.'f. - Gross Unit Reserve lhereal-Energy 6enerated Shutdoun (MWh)' Hours 1523167.0J -9177585.0. 258574202.0 p
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- 11. Net Electrical Energy Generated (MWh) 497478.0'
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'2968318.0: 82927402.0-2864033.0: 178343682.01 is / ,s' (12.'Reacter;ServiceFactor' 93.~li '64.4 77.1
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Ll3.lReactorAvailabliftyFactori 93.1 64.4; 79.0t @ j h ig(!4 gd ,Ll4MUnitServiceFacterJ 90.7 63.4 75.0, N
^15.Untt'Av'allabilityFactor; . 90.7 ' :63.4 75.4' , Je
[80i 7 < f!6'.UnitCapacityFactor(UsingMDC). 87;3 56.9 563.5 M M k (17. t! nit; Capacity Factor (Using Design MWel '85.1 55.4. 61.9 , ,? [$ ^ y , ' c y LIB. Unit. forced Outage. Rate 0.0 0.0, 7.9 : @!!n J > V.J 1,19.. Shutdowns Scheduled Over Next 6 Months' (Type, Date, and Duration:oi Each): d l
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F , , APPENDl! ! ^,
-AVERA6EDAILYUNiiPOWERLEVEL. 9 s , -
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., h '_ UnitiOne-
,Date October'1,.1990-; ,
- Cospleted By Lynne' Hasiltoni l L Z s Telephone' -309-654-2241: n b -*
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. .i g , DAYAVERA6EDAILYPOWERLEVEL- DAY AVERA6E DAILY POWER LEVEL 'l s
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' 11 746, 17 732
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9 -734- 25~ 746l . > ys ' , 10 761 < ' 26L '7394 .; if1 11. 767 27 1743' t , 12- 764' < ' 28 1753 9
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@plg,hg I0n this fors,1 st11 the average daily' unit pcuer level in MWe-Wet icr each day in the reporting conth.L M g l l4 Cogute. to the nearest.whole negawatt. ] wSfr JEs 1 m i ' .
.* 4 Ghesefigureswillbeusedtoplota'graphforeachreportingconth.'Notethatwhensamlausdependable- 't gg$yR.# /capacityfsusedforthenet=electricalratingoftheunit,theresaybeoccasionswhenthedailya'verage.i i
@hyg % power-level enreds the 100% 'lineL(cr c the restricted pcuer level:line). In such cases, the average daily
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- 4. -AVERA6E DA!LY UNii, POWER LEVEL-y ,
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' Dodet No. 50-265)
W N Unit Two . F 7 L.y Date October 1,-1990 ST Coepleted By Lynne Haellton:
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MONTH' SEPT Q! @ ; < - ; ! L NV . .
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- DAY AVERAGE DAILY POWER LEVEL:
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DAY.AVERA6E.DA!LYPOWERLEVEL , d r
- (MWe-Net) 1
@ , , - l' - 759 17 775 ,
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, 2 '742. 18 777 9.
m ' J3- 605- 19 774 v_-
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p' . 12 f788 . 20 '. 33 J
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, . 13 769. iI gM ,j ' ' . ,
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' APPENDIX D UNIT SNUTDOWNS AND POWER REDUCTIONS -
DOCKET NO. ~50-254 . UNIT'NAME Quad Cities: Unit One COMPLETED BY Lynne Hamilton DATE- October 4, 1990 . REPORT HONTH- September. 1990 TELEPHONE 309-654-2241'" - I
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u s., DURATION .M EVENT $o o O NO. DATE (HOURS) REPORT.NO. CORRECTIVE ACTIONS /COFMENTS 8 90 900922 F 0.0. B 5. Power Reduction Taken to Perform Hydrogen Injection Testing k e
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w._-~ 2- . 9 l; -APPENDIX D + p UNIT SHUTDOWNS f.ND' POWER REDUCTIONS - L - DOCKET NO. 50-265 H . UNIT NAME' Quad Cities Unit Two . COMPLETED BY Lynne Hamilton l . j DATE' October 4, 1990 REPORT MONTH September, . 1990 TELEPHONE 309-654-2241 - l ' '~ at N O -- la O C E* 2
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v NO. DATE REPORT.NO. . CORRECTIVE ACTIONS /COfffENTS (HOURS) g
' 0-9 900903 F 0.0 B 5 Power Reduction Taken to Perform QOS 1300-1 RCIC Monthly and Quarterly Test 90 .. 900928 S 67.1 B 5 ' Reactor to Hot Standby to Perform then Generator / Turbine Torsional Test / Main 2 Turbine Tripped - Reactor Manually Scrammed to Troubleshoot EHC System and Maintenance on other Systems (final)-
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& AG ? Main Steam' Relief Valve Operations- 4i t
' f 'f f iR LRelief valve operations during the reporting period ~are summarized'in the -
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.Date: ~ September.28 1990 i b $
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% Valves Actuated- No. 6 Type of Actuation .
l2-203-3A1 1 Manual M
~2-203-3B .1 Manual' !
-l Manual L2-203-30-~ _,
I2-203-JD; o .l' Manual. . d 2-203-3E- 1-Manual s
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. description-o'lEhents: f Routine surve'illance Semi-annual, Manual _ Operation, j ofLElectromatic Relief. Valves (QOS 201-1),. ,;
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9: ' Tech Spec: Ref. 3.5/4.5.D.1.a'- i
--J B . Control-Rod Drive Scram Timing Data for' Units One and Two i
1 , , , N There .was; no- Control' Rod Drive scram timing data for ' Units One: and' Two g 3 & Lf or.lthelreporting_ period.- V! Lik c
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.. VII. REFUELING INFORMATIONi -
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The foll'owing:information about future: reloads.at Quad-Cities Station was, if -requested in f January 26., 1978, licensing memorandum-(78-24) from D.'E.-
' O'Brien to C. Reed, et al.., titled "Dresden, Quad-Cities, and Zion!
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- . Station--NRC RequestLfor Refueling Information",. dated January 118, 1978 1
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' 'QTP 300-S32 Revision 2, .
QUAD CITIES REFUELING October 1989 INFORMATION REQUEST
- 1. Unit! 01 Reload: 10' Cycle: 11
- 2. Scheduled date for next refueling shutdown: 11-12-90
- 3. Scheduled date for restart following refueling: 1-28-91
- 4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:-
Yes, a proposed change to Technical Specification will be 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. '
- 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 or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: '
S
, 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: 1537
- 8. The_ present 'llcensed spent fuel pool storage capacity and the size of ;
any increase in.llcensed storage capacity that has been requested'or is .j
. planned in number of. fuel assemblies:
.a. ~ Licensed storage capacity for spent fuel: 3657 ?
- b. Planned increase:In licensed storage: 0 9.- The projected date of'the last refueling that can be discharged-to the spent fuel pool assuming the present licensed capacity: '2008
/
*'144 new fuel bundles have arrived on site and will be stored !
in the Unit One new fuel storage vault. ~l APPROVED , l 1
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114/0395't OCT 3 01969 O.C.O.S.R. L;3 . _ ..
l QTP 300-S32 N c " Revision 2. i QUAD CITIES REFUELING October 1989 - INFORMATION REQUEST l
- 1. Unit: 42 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. t
- 5. -Scheduled date(s) for submitting proposed licensing action and supporting information:
l NOT AS YET DETERMINED. l
- 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures. g l
NONE AT PRESENT TIME. . I 1 7.- The number of fuel assemblies. a.- Number of assemblies in core: 724
- b. Number of assemblies in spent fuel pool: 2011 j
- 8. The'present Ilconsed spent fuel pool storage capacity and.the size of any: increase In licensed storage capacity that has been requested or is l l
planned in' number of fuel assemblies:
- a. Licensed storage capacity for spent fuel: 3897 b.. Planned increase in licensed storage: 0 ..
l
- 9. .The projected date of the last refueling that can be discharged to the J spent. fuel pool assuming the present licensed capacity: 2008 !
APPROVED t i (final) 14/0395t OCI 3 01969 O.C.O.S.R. 1 __ _ _g _ _ _ - - _ - - - - - - - - - - - - - - - - - - - ' - - - ^ ^ ^ ~ ^ ' ^ " ^ ^ ^
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VIII. GLOSSARY
.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 ATHS - Anticipated Transient Without Scram ! BHR - Bolling Hater Reactor CRD: - Control Rod Drive EHC- - Electro-Hydraulic Control System a _ 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 IRH - Intermediate Range Monitor ISI - ~ Inservice Inspection LER - Licensee. Event Report
, _LLRT Local Leak Rate Test LPCI- -
Low 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 - Maximum Fraction Limiting Critical Power Ratio HPC - Maximum Permissible Concentration MSIV - Main Steam Isolation Valve NIOSH- - - National Institute for Occupational Safety and Health PCI .
. - Primary. Containment Isolation J PCIOMR: -
Preconditioning Interim Operating. Management Recommendations RBCCH- - Reactor Building Closed Cooling Hater' System
~RBM' = - Rod Block Monitor o RCIC' -- Reactor Core Isolation Cooling System RHRS. -
Residual Heat _ Removal System RPS -- Reactor Protection System RHM -
. Rod Horth Miin mizer SBGTS: -
Standby Gas Treatment System l
- SBLC- - Standby L1 quid Control !
SDC- - Shutdown Cooling Mode of RHRS-vg SDV - Scram Discharge Volume l SRM -
. Source Range Monitor.
.y. =TBCCH: - Turbine Building Closed Cooling Hater System Traversing Incore Probe TIP -
-l TSC -
Technical Support Center l '('. 0027H/00612 W m i ) D' t_}}