Text

Monthly Operating Repts for Oct 1990 for Quad-Cities Nuclear Power Station Units 1 & 2
	ML20058G746
Person / Time
Site:	Quad Cities
Issue date:	10/31/1990
From:	Hamilton L, Robey R; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	RAR-90-77, NUDOCS 9011130386
	Download: ML20058G746 (23)
	v • d • e

.-

Commonwealth Edison ound Cities Nuclear Power Smion

,22710 206 Avenue North

' Cordova, Illinois 61242 9740 Telephone 309'654 2241 T

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RAR-90-77 i

November 1, 1990 i

I U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Wathington, 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, during the month of October. 1990.

' Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION f].

//-1' 'lo R. A. Ro y

.Technica Superintendent 1

'RAR/LFD/vmk Enclosure l

cc: ' A.B. Davis, Regional Administrator T. Taylor, Senior Resident inspector 5,

90111-30386 901031 PDR ADOCK 05000254 R

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i QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT October, 1990 COMMONNEALTH EDISON COMPANY l

AND IONA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR.-30 i

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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 I

V.

Data Tabulations-1

'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.: Contr01 Rod Drive Scram. Timing Data VII.

Refueling Information

'VIII.

Glossary P

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INTRODUCTION o

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 i

t 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 p

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, l

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 18,11973 for Unit One and March 10. 1973 for Unit Two.

This. report was. compiled by Lynne Hamilton and Verna Koselka,-telephone number 309-654-2241, extensions 2185 and 2240 1

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-II.

Sl'MMARY OF OPERATING EXPERIENCE t

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A.-

Unit One i

Unit'One began the month of October operating in Economic Generation Control (EGC). Normal operational activities occurred until October 6.

On October 6, at 2040 hours0.0236 days 0.567 hours 0.00337 weeks 7.7622e-4 months , while attempting to shut off the IB Service Water Pump, it was discovered that the breaker would not trip.

Upon investigation, s

. it was dise' ared that there was smoke coming from bus 14.

In anticipation of' losing tnis bus, power was reduced to 410 MWe over ten minutes.

The Ec breaker wao remotely tripped at 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months , an ascent to full power was l begun. -On October 7 at 0910 hours0.0105 days 0.253 hours 0.0015 weeks 3.46255e-4 months , full-power was achieved. On October 8 L

at:0055 hours, the unit was placed in EGC.

j n For the' remainder of the month, normal operational activities occurred.

The unit operated'near full power or remained in EGC.

Power levels were adjusted according' to the demands of the Chicago Load Dispatcher and routine 7l surveillances-were performed.

B.! Unit Two:

6 r

. Unit Two began the month of October in.the startup mode.

On October 1 at'1013 hours0.0117 days 0.281 hours 0.00167 weeks 3.854465e-4 months , the. reactor became critical.

Ilowever, at 2201 hours0.0255 days 0.611 hours 0.00364 weeks 8.374805e-4 months , the r

1 reactor was manually scrammed due to leakage in-the drywell.

On October 2 atfl820 hours,_the reactor became critical, and on October 3, at 0145

,j hours the generator;was synchronir.ed to the grid. -Power levels were

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held constant while contra.' rod drive scram timing was performed. The 1 testing was completed, and on October 4, an ascent to full power was begun,

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land at:0938 hours, full power was achieved.

On October 6,_at 0115 hours0.00133 days 0.0319 hours 1.901455e-4 weeks 4.37575e-5 months .

-power' levels were adjusted and the unit was placed in Economic Generation i

Control. (EGC). Normal e serational activities occurred from October 6 to

.0ctober 13 with the un.: remaining in EGO with minor interruptions to perform' routine surveillances.

~

On.0ctober 14 'at 0226 hours0.00262 days 0.0628 hours 3.736772e-4 weeks 8.5993e-5 months a power reduction'to 504 MWE was taken to i

~m perform Main Steam-Line Isolation Closure Time Quarterly Testing.

20 outboard main-steam line isolation: valve failed to-close. The main steam gline was isolatedt = power levels were-reduced to 200 MWe while repairs Jwere made to-the valve. On-October 15, at 0252 hours0.00292 days 0.07 hours 4.166667e-4 weeks 9.5886e-5 months , repairs were' completed and the valve was successfully'. tested. At 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months , a load increase

+

was"taken'to~500 MWe'while routine'surveillances were performed. At 1050-

- hours.: full power was : achieved.

0n' October,15, at 1210 hours0.014 days 0.336 hours 0.002 weeks 4.60405e-4 months , 20. moisture separator high icvel alarm i

1 Lwas3 received in the control ream and fifteen seconds later, the main turbine

= tripped and reactor. scrammed-from turbine-stop valve closure. Normal unit' shutdown commenced.

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On 0ctober 17, at 1930 hours0.0223 days 0.536 hours 0.00319 weeks 7.34365e-4 months , the reactor was'made critical, and on l

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g; October 18,'at:0439 hours. the generator was synchronized to the grid.

I EAn. ascent.to full power was begun, and.at 1546 hours0.0179 days 0.429 hours 0.00256 weeks 5.88253e-4 months , full power was i

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A oV' achieved.' On October 10, at 2216 hours0.0256 days 0.616 hours 0.00366 weeks 8.43188e-4 months , power ~1evels were adjusted and Ye >

.the unit was placed in EGC..From October 20 thru October 26, normal coperational activities occurred with the unit remaining in EGC or operating

' 1:

near full power while routine surveillances were performed.

a On.0ctober 27. at 0052 hours6.018519e-4 days 0.0144 hours 8.597884e-5 weeks 1.9786e-5 months , the generator was taken off-line, and the

' at unit was: brought to hot standby.to perform Turbine Torsional Testing..

7 However.1 turbine acceleration could not be maintained and at 1510 hours0.0175 days 0.419 hours 0.0025 weeks 5.74555e-4 months , i

the' testing was terminated. At 1559 hours0.018 days 0.433 hours 0.00258 weeks 5.931995e-4 months , a reactor scram was received

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'from Intermediate. Range Monitor 13 and 16 spiking High-High. On October 29.

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tat,0653 hours0.00756 days 0.181 hours 0.00108 weeks 2.484665e-4 months sthe reactor became critical, and at 1424 hours0.0165 days 0.396 hours 0.00235 weeks 5.41832e-4 months , the generator-d^

was synchronized to'the grid. An ascent to full-power was begun and on rl 10ctober;30, at 0550 hours0.00637 days 0.153 hours 9.093915e-4 weeks 2.09275e-4 months , full power was achieved.- Routine surveillances:

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were performed,~and.on-October.31, at 1950 hours0.0226 days 0.542 hours 0.00322 weeks 7.41975e-4 months , the unit was placed c0I lin'EGC.

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j III.- PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE l

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A; Amendments to Facility License or Technical Specifications i

l There were no Amendments to the Facility License or Technical Specifications

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Facil ty or Procedure Changes Requiring NRC Approval l

There.were no Facility or. Procedure changes requiring NRC approval for

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Tests-and Experiments Requiring NRC Approval I.a in

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D.; C,orrective Maintenance of-Safety Reinted Equipment Thelfollowing represents a 'abular summary of:the major safety related l

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' maintenance: performed on Units One and Two during the reporting. period.

'"This summary includes.the following: Work Request Numbers, Licensee Event-

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3 Report! Numbers ; Components, cause of Malfunctions, Resulte~and Effects 4

on. Safe Operation, and-Action Taken to Prevent Repetition.

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TV. M CENSEE EVENT REPORTS q

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_ ; Thef following;1s _a tabtac summary of all licensee event reports for-Quad.

Citiec Units One and it curring during the reporting' period, pursuant.to-

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' Report Number Date

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- V.

DATA TABULATIONS j

The following data tabulations are presented in this report:

A. -Operating Data Report

18.. Average Daily' Unit Power Level m

C.

Unlt Shutdowns and Po'wer Reductions 3

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o- -

i j

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7 MFENDl! C J

0FERATIN5DATAREPORT Docket hc. 50-254 Unit One Oate Nevester 5, 1990 Cosoleted By Lynne Harilten

-Telephone 307-654-2241 5

/

-OPERATIN.5TATUS tML10P0

1. L Re;orting Period 2iq0,,,121190 '

Grcss Heurs in Feport Periods 19 e;;

O

<2.

Eutrently Authorited Pouer l'evel. iMWt): 25jlMn. Depend.' Capacity (MWeNet): 269 Design Electrical:Kating P We4et) IjB9 3f ; PowerJtevel to Which Restricted (ti Ary) (MWe-Net): ((A o,

1 4.,. Reasons For' Reatriction (If any):

~

i '*

,q

,g ?

L; T

@ "i l

THl! NNTH VR TO DATE CUMULATIVE ^

kL m..

s,; < y T j5y'gReacterPeserve;5iutdaen'HoursNgeber cf Hodrs neactor'Was Critical.

745.0 7050.6 131214.6

?

7

'6.

0.0 0.0 3421.9

-m

17. Hears Generator.On Line; 745;0; 7011.9.

'127102.5-6a Unit Reserve Shutden; Hours 0.0

. 0.0 909.2,

o ab;l i

_.9' /6ross thereal Energy Generated dMA) c!783306'0- E16446792.0 '272129153.0:

Q" j W

.10;16tottLElectricalEnergyGenerated(H5) 593395.0 5342994'01 69194553.0 e. A, j!!.iNe_t Electrical Energy 6enerated (MWh);

"$67732.0 5149761.0-82990147.0 g-(

'12. Rentbr:$efdce Futcr '

100.0 96.6-J 60.7 '

EQ 5 13FAeactor/ Availability 1Fa:ter' 100.0 96.6 -

1 82.8 ;

[*M'

-14.'linitlServicefactor?'

100.0' 96.1

.78.1 315[Dnit Avallability Factor.

100.0 -

96.1-78;7:

OC i

i

/,f'?.

lLle. Unit (Cahnity Factert(Using MDC) l99.1 91.6

66. 4 --

7[:F 17.4 Unit;CapacityLFutorl-lUsi$glesign Wel

'96.6 69.5, 64.7-g L1930nifforcedCutageRate

0. 0 '

1.5 5.2 Aty:p~.

m'y.

,J19. $hutdo ni $cheduled Over Next 6 Menths (Type, Date, and Duration'of Enh):

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4 APPENDIX D c
INIIT SHUTDOWNS AND POWER REDUCTICNS DOCKET:NO.
. 50-254-
~ UNIT NAME " Quad Cities Unit One
. COMPLETED BY Lynne Hamilton
- DATE November'7)1990l-S REPORT 790 NTH ~ Octobhr, 1990 TELEPHONE
'309-654-2241-
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REPORT.NO..
CORRECTIVE ACTIONS /COf9ENTS None e
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1 APPENDIX D UNIT SNUTDOMISlAND POWER REDUCTIONS '
' ~
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DOCKET NOL
'50-265
. UNIT NAME Quad Cities Unit'Two'
~
COMPLETED BY-Lynne Hamilton'
'I
~~DATE November-7,~'1990'~~
. REPORT MONTH ~ OctoberJ.1990 '
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90-10 901001 S.
49.'8
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Continuation from September - Troubleshoot
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EHC cystem and Maintenance on other Systems
'90-11 901014'
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Power Reduction for MSIV Testing and Mainteriance 90-12 901015 F
64.5' A
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Reactor Scrammed From Main Turbine Trip -
Moisture Separator High Level Alarm Actuated l
l l
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Unit 1, Hot Scram Timing for test due
~
(2.36) to 127: Valve _ Diaphragm Replacement 5-09-90 177 0.30 0.68 1.45 2.54'
'H-11 Unit 2,' Hot Scram Timing during-Start Up i
(3.29)
Sequence A&B, Cycle 11 6-21-90 88
'O.29-0.66 1.40 2.46 M-11
' Unit-1, Hot Scram Timing for Sequence B-(2.70) _
Cycle 11, 1st Sequence of Cycle
~
8-11-90 1
0.30 0.65' l.38 2.39 P-10 Unit 2, Hot Scram Timing test for (2.39)
Accumulator Replacement 10-3-90 88-0.31 0.68' 1.'42
'2.48 E-10 Unit _2, Sequence B, Cycle 11, Hot Scram (2.88) ist Sequence of Cycle 10-18-90 2
0.~ 31 0.61 1.46 2.55-F-10 Unit 2. Hot Scram Timing After Drive (2.56)
Maintenance 10-19-90 1
0.27
~~0. 5'9 1.24 2.16 P-7 Unit 2, Hot Scram Timing After Drive (2.16)~~
-Maintenance 0027H/0061Z
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7 VII.. REFUELING INFORMATION
!!i The following information about future ~reloais at Quad-Cities Station was requested in a January 26,' 1978,'11 censing memorandum (78-24) from D. E.
- O'Brien to C.. Reed..et al., ti tled "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Information", dated January 18, 1978.
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QTP 300-532 l
Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST l.-
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.
Wilt 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(i) for subeltting proposed Iiconsing action and supp.trting Infoimation:
e
' AUGUST 31. 1990' a
l 6'L
'Important licensing considerations associated with refueling, e.g., new-or different fuel design'or supplier. unreviewed design or performance m alysis methods.:significant. changes'in fuel design, new operating procedures:'
n
~~NONE AT PRESENT TIME.~~
i o
4 7;-
~The number of' fuel assembltes.
a.-
Number of assemblies in core:.
724
-j A ~ b.
iNusber of assemblies'in spent fuel pool:
1s37-8.1 The'present licensed. spent fuel pool' storage' capacity and the size-of-
~~any increase'in licensed storage capacity that has been requested or is 3~~
planned in number of fuel assemblies:
l, a;
-Licensed storage:caracity 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 b6ndles-'have arrived on site and will'be stored in the Unit One new fuel' storage.vr.lt.~~
l 1
APPROVED
< final >
DCT 3 0 f989
. 14/0395t. 2, C).C.O.S.R.
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I QTP 303-532
~'
Revision 2~
QUA0 CITIES REFUELING Octob'tr 1989 INFORMATION REQUEST-m
.. ).
Unit:
02 Reload:
10 Cycle:
11-2.
Scheduled date for next refualing shutdown:
9-7-91 m
'3. '
Scheduled'date for restart following refuelle.g:
12-9-91
.Wl.11-refueling or resumption of operation thereafter require a Technical c
4.-
Specification change or other license amendment:
NOT AS YET DETEMiLNED.
b h
' Scheduled date(s) for submitting proposed licensing action and 2
5.-
supportl.ng' Informa tion:
\\v NOTA 5YETDETEMbHED.
o 6.'
Important 11 censing considerations associated with refueling, e.g., new' p,
or-different. fuel design or supplier, unreviewed design or performance w
analysis methods, significant changes in fuel design, new operating u&
procedures::
1 b
o i:g
'FnNE.'AT.PRESENT TIME.
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4 uIV.
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7.4 cThe: number of-fuel assemblies.
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~~a.1 Number of. assemblies in core~~

-724 s
I n ? g.{a,
t4 Jumber,fLassembiies 1n spent fuel pool::
2011 g
wy u
f "O
' 8.1 The present.llcensed spent fuel pool storage capacity andLthe: size of
$lV any increase in'.llconsed storage capacity that has been requested or is:
e
~~planned.in number of fuelLassemblies:~~
i;
'a.-
Licensed storage capacity for spent fuel:
3897 i.
~
~~b..~~
Planned increase In' licensed storage: "
u M 9. -
.The projected date of'the last refueling that can be discharged to-the spentifuel pool assuming the present licensed capacity:
2008 n..
~~4 r,~~
APPROVED i
i m nai) i4, L14/0395t. OCT 3 01969 0.C.O.S.R.
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VIII. GLOSSARY r
The following abbreviations which may have been used in the Monthly Report,
~~are defined below:~~
y ACAD/ CAM Atmospheric Contai_nment Atmospheric Dilution / Containment
-Atmospheric Monitoring h-ANSI American National Standards Institute Average Power Range Monitor APRH:
Anticipated Transient Without Scram ATHS:
s
~~Boiling Water Reactor.~~
BWR:
g.
CRD Control Rod Drive
- EHC Electro-Hydraulic Control System-Emergency Operations facility EOF-Generating Stations Emergency Plan GSEP.
L.
HEPA High-Efficiency Particulate Filter HPCI-High Pressure Coolant Injection System L
9,
~~HRSS;~~
~~.High Radiation Sampling System~~
~~IPCLRT!~~
Integrated Primary. Containment Leak Rate Test s
y IRH1 Intermediate Range Monitor
,q ISI
-Inservice Inspection
' Licensee Event Report LER LLRT Local Leak Rate Test 1
Low Pressure' Coolant Injection Mode of RHRS W
LPCI.
.LocalfPower Range Monitor JLPRM:
e
-. Maximum-Average Planar Linear Heat Generation Rate.
(
MAPLHGR MCPR Minimum Critical. Power Ratio iMFLCPR Maximum Fraction' Limiting Critical Power Ratio cMPCD
' Maximum Permissible.Concentratica Main Steam-Isolation; Valve
=MSIV.
LNational Institute for Occucational Safety and Health
?NIOSH Q"r
. Primary Containment Isolation PCI:
PCIOMR.
Preconditioning: Interim Operating Management Recommendations Reactor Building Closed Cooling Water System RBCCHL
-RBM Rod Block Monitor' m
RCIC:
Reactor Core Isolatlon Cooling System Residual'lieat Removal: System
-RHRS.
' Reactor Protection System RPS
'RWM Rod Horth Minimizer Standby Gas Treatment System SBGTS m-4 d
'SBLC Standby Liquid Control SDC
~~- Shutdown Cooling = Mode-of RHRS:~~
Scram Discharge Volumet iSDV' 1
E SRM Source Range Moni_ tor' Turbine Building Closed Cooling Water System m
TBCCW-Traversing'Incore Probe TIP' i
TSC Technical Support Center
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ML20058G746

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