ML20127D851
| ML20127D851 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/31/1985 |
| From: | Kronich C, Tamlyn T COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| TKT-85-30, NUDOCS 8506240352 | |
| Download: ML20127D851 (22) | |
Text
-.
e QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT MAY 1985 COMMONWEALTH EDISON COMPANY AND IONA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265-LICENSE NOS. DPR-29 AND DPR-30 lDR 4
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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 V.
Data Tabulations A.
Operating Data Report i
B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions l
VI.
Unique Reporting Requirements A.
Main Steam Relief Valve Operations B.
Control Rod Drive Scram Timing Data VII.
Refueling Information VIII.
Glossary 0027H 0061Z
I.
INTRODUCTION 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 Water Reactors.
The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors.
The Mississippi River is the condenser cooling water source.
The plant is subject to license numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, respectively; pursuant to Docket Numbers 50-254 and 50-265.
The date of initial Reactor criticalities for Units One and Two, respectively were October 18, 1971, and April 26, 1972. Commercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 for Unit Two.
This report was compiled by Becky Brown and Dave Kimler, telephone number 309-654-2241, extensions 127 and 192.
4 0027H 0061Z
II.
SUMMARY
OF OPERATING EXPERIENCE A.
Unit One May 1-6: - Unit One began the month on Economic Generation Control (ECC).
- On May 5, at 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, load was dropped to-700 ::We for weekly Turbine
-tests.
At 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> load began an increase to 750 MWe. At 0235 hours0.00272 days <br />0.0653 hours <br />3.885582e-4 weeks <br />8.94175e-5 months <br /> load reached 751 Ink and the unit was placed on ECC..
May 7-31: On Iby 7, at 1523 hours0.0176 days <br />0.423 hours <br />0.00252 weeks <br />5.795015e-4 months <br />, the Reactor scrammed on a Turbine trip due to high water level. Unit One remained shutdown for a scheduled short maintenance outage. On May 16, at 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br />, the Reactor went critical and was placed on line May 17, at 0445 hours0.00515 days <br />0.124 hours <br />7.357804e-4 weeks <br />1.693225e-4 months <br />.
On May 19, at 2110 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br />, full power was reached after normal load increases.
On May _30, at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />, the Reactor scrammed on MSlV closure due to
- a. faulty main steam line low pressure signal. The unit remained shutdown for the duration of May.
B.
Unit Two May 1-31: Unit Two remains shutdown for the End of Cycle Seven Refueling and Maintenance Outage for the entire month of May.
0027H 0061Z.
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 Liunse or Technical Specifications for the reporting period, f:
B.
Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure changes requiring NRC approval for-the reporting period.
C.
Tests and Experiments Requiring NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period.
D.
Corrective liaintenance of Safety Related Equipnent The following represents a tabular summary of the major Safety Related maintenance performed on Units One and Two during the reporting period. This summary includes the following: Work Request Numbers, LER Numbers, Components, Cause of Italfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.
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UNIT 1
MAINTENANCE SUMMA *,Y CAUSE RESULTS & EFFECTS W.R.
LER OF ON ACTION TAKEN TO NUM8ER NUM8ER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q41938 10 1-2301-9 IIPCI
}Iisalignment of Stroke time was 46 The close. limit switch Injection Valve motor operator's seconds (allowable is was readjusted, and close limit switch.
45 seconds). IIPCI
'the valve was injection valve would successfully stroked have opened on auto-three times, start signal; therefore, IIPCI was available.
4 O
I UNIT 2
MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R.
LER OF
- ON -
ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION
' SAFE OPERATION PREVENT REPETITION Q41831 2-302-22A Scram Valve disc uas Valve leaked Valve disc was removed Discharge Volume originally excessively.
-and reinstalled in North Drain Valve installed correct position.
-incorrectly.
Q41832 2-302-22B Scram
-Valve disc uas Valve leaked Valve disc was removed Discharge Volume originally excessively.
and reinstalled in North Drain Valve installed correct position.
l incorrectly.
l l
Q42078 2-Il05B Standby Instrument set-Settlement caused Relief valve setpoints Liquid Control point drift due to setpoint drift which were adjusted to Relief Valve Sodium Pentaborate caused the valve to proper pressure.
Setpoint precipitating on open prematurely.
the spring acti-vating mechanism.
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 ONE Licensee Event Report Numbers Date Title of Occurrence 85-02 5-9-85 Number 4 TIP Ball Valve Stuck Open 85-03 5-17-85 Standby Cas Treatment Autostart Signal 'A' Failed to Start; 'B' Heater Tripped 85-04 5-23-85
- Loss of Essential Service Bus 85-06 5-30-85 Reactor Scram From Group I Isolation From Rack Vibration 85-07 5-31-85 1A Fuel Pool Radiation lionitor Spiked liigh UNIT TWO 85-11 5-7-85 Loss of Auxiliary Power; Unit One Reactor Scram 85-12 5-20-85 Croup II Isolation 85-13 5-22-85 Loss of Diesel Cencrator to Unit.Two; CSEP Unusual Event 85-14 5-31-85 Scram From Performance of PCI Simulated Auto-matic Closure Initiation Test, Group I 0027H 0061Z L-
'(
c V.
DATA TABULATIONS The following data tabulations are presented in this report:
A.
Operating Data Report i
B.
Average Daily Unit Power Level' i
'C.
Unit Shutdowns and Power Reductions d
i 4
1 1
A 4
6 i
T 4
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OPERATING DATA REPORT DOCKET NO.
50-254 UNIT ONE DATEJune 6 1985 COMPLETED BYCor01 Kronich TELEPHONE 309-654-2241x193 OPERATING STATUS 0000 050185
- 1. Reporting period:2400 053185 Gross hours in reporting period:
744
- 2. Currently authorized power level (MWt): 2511 Mox. Depend capacity (MWe-Net): 769* Design electrical roting (MWe-Net): 789 4
- 3. Power level to which restricted (if any)(MWe-Net): NA 1
4.
Recsons for restriction (if any):
This Month Yr.to Date Cumulative 5.-
Number of hours reactor was critical 508,6 3307,6 91110.0 6.
Reactor reserve shutdown hours 0,0 0.0 3421,9 1
7.
Hours generator on line 484,6 3338,3 80373,6 8.
Unit reserve shutdown hours.
0.0 0,0 909,2 9.
Cross thernal energy generated (MWH) 1129807 7847563 183593953 l
- 10. Gross electricci energy generated (MWH) 374360 2593250 59370709 11, Net electrical energy generated (MWH) 356917 2403791 55439493
- 12. Reactor service factor 68,4 93.5 U0,1
- 13. Reactor ovcilobility factor 60,4 93.5 0 3._ _i 14 Unit service factor 6S i 92.1 77,2 t,
- 15. Unit avollobility factor 65.1 92,1 78,0 J
- 16. Unit copocity factor (Using MDC) 62d 09a 63,0
- 17. Unit conocity factor (Using Des.MWe) 60,0 06.9 61,4 i
- 18. Unit forced outoge rote 32.7 7,2 6.1
- 19. Shutdowns scheduled over next 6 nonths (Type,Date,ond Duration of coch):
- 20. If shutdown at end of report period,estincted date of stortup _ _ 6_ _2_ _8 5_,,, _ _,,,
i 8The PDC ncy be lover then 769 We dsring perisds of high anblent temperatere die to the thernal perfstmonce of the spray canal.
$UN0FFICIAL COMPMY NtmKRS ARE USO IN THIS REPORT
OPERATING DATA REPORT DOCKET NO.
50-265 UNIT
.TWO DATEJ_une 6 1985 COMPLETED BYC_o n1 Kronich TELEPHONE 309-654-2241x193 j
OPERATING STATUS 0000.050185
- 1. Reporting period 2400 053185 Gross hours in reporting period:
744
- 2. Currently authorized power level (MWt): 2511 Mox. Depend capacity (HWe-Net): 769* Design electrical rating (MWe-Net): 789
- 3. Power level to which restricted (if any)(MWe-Net): NA 4.
Reasons for restriction (if any):
This Month Yr.to Date Cunulative
- 5. Number of hours reactor was critical 0.0 1630.0 06536.8 6.
Reactor reserve shutdown hours 0.0 0._0 2985.8 7.
Hours generator on line 0,0 1608,7 83657.0 H.
Unit reserve shutdown hours.
0.0 0.0 702.9
- 9. Gross thernal energy generated (MWH) 0 3722622 175241609
- 1. 0. Gross-electrical energy generated (MWH) 0 1217469 55870000
- 11. Het electrical energy generated (HWH)
-2700 11620!1_
52400051 6
- 12. Reactor service factor 0.0 45.0 76.2
- 13. Reactor avo11ob111ty foctor 0,0 45J 78.8-
- 14. Unit service factor 0.0 44.4 73.7
- 15. Unit avo11obility factor 0.0 44,4 7_4.3
- 16. Unit capacity factor (Using MDC)
,5 41.7 60 ui;..
- 17. Unit copncity factor (Using Des.MWe)
.S 40 2 50.6 18, Unit forced outage rate 0.0 10.6 8.4
- 19. Shutdowns scheduled over next 6 Months (Type, Dote,and Duration of each)i
- 20. If shutdown at end of report period, estimated date o f s t a r t u p _6-4_-y}_ _ _ _ _ _ _
- The PDC nip be lawr thn 769 NWe daring perleds of high anblent tenparatore die 9e the thernal perfstmace of the spray canal.
$UN0FFICIAL COPfMY NUMERS ARE t! SED IN THIS REPORT
APPENDIX B AVERAGE DAILY UNIT POWER LEVEL l
DOCKET NO.
50-254 t
UNIT ONE l
DATEJune 6J985 COMPLETED BYCorol Kronich TELEPHONE 309-654-224ix193 MONTH Mov 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
.(MWe-Net)
(HWe-Net) 1.
738.7 17, 310.0 2.
761.2 18, 589.1 3.
760.7 19, 736.0 4,
750.6 20.
~
789.7 5.
747.7 21, 792.6 6.
752_3 22.
77'i 7 1
7.
476,2 23, 755.7 8.
-12.2 24.
745,3 2
l 9.
-9.9 25.
772.0 l
10.
-7,8 26, 784.0 11.
-7 2 27, 787.8 12.
-6.8 20.
792,4 13.
-7.2 29.
756.0 14.
-7.8 30.
549,3 15.
-8.7 31.
-10.3 16.
-9.4 l
INSTRUCTIONS On 9his fern, list the averegt daily snit power levtl in IWe-Net for ecch day in the reperting nenth.Conpete to the nttrest while negswett.
l These figures will be ssed to plot a graph for toch reporting nenth, Nott thtt when nasinsn dependable Copacity is esed for the net alttfrical rating of the snit there ety be ectosist,s when the daily tetragt ptwar levtl isttids the
[
1981 lint (or the restrittti power level line),In sich costs,the Overage delly snit 96Wtr tutput shtet shtold be festnetti to erplein the opportnt antasly L.
) APPENDIX B AVERAGE DAILY UNIT POWER LEVEL
,f e.
f DOCKET NO.
i o -2 65 r
UNIT TWO DATEJ_tincJ 1985 COMPLETED BYCorel Kronich TELEPHONE 309-654-2241xi93 MONTH Mov 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1.
-3.9 17.
+4.6 2.
-2,4 18.
-5.3
-4.4 3.
-2.8 19.
^
4.
-3.4 20.
-3.8 5
5.
-3.4 21.
-4.0 7 7
'T 6.
-2.7 22.
-3.7 7.
-1,6 23,
-3.6 8.
-2,2 24.
-3.4 9.
-3.0
.25.
-3.7 10.
-2.8 26.
-4,3 11.
-3.3 27.
-4,4 s
12.
-3.8 20.
-4.5 l
d3.
-3.6 29.
-4,5 14
/
-4.0 30.
-4.5 15.
r
_4,9 31,
-4,3 l
r,
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U4o e
INSTRUCTIONS On this fern, list the onrep daily snit power level in Nt-Wet for acch dat in the reporting nanth.Csepite to the nearest while negewett.
These figures will be used to plat a grosh for each repstting ninth. Nate that when naninen dependable copetity is esec for the net electrical reting of the init there may be occasions when the dail; overage power level esteeds the 1892 lire (or the restricted power lent line),In sich cases,the overage dailp init power eetpet sheet sheild be festated to trplun the cp;trent animalp s
}of:
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s
- m P"5 E""1 P'"1 M
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M P"I"5 F""3 M
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ID/5A APPENDIX D
.QTP 300-S13 l
UNIT SilUTDOWNS AND POWER REDUCTIONS Revision 6 l
DOCKET NO. 050-254 Auguat 1982 1
.. UNIT NAftE Quad-Cities Unit 1 C0ffPLETED Hy C. Kronich l
l DATE
. Tune 6, 1985-REPORT HONTil 11AY 1985 TELEPl!ONE 309-654-224i g
N R$
So:
Oc O y$
m x-n d
LICENSEE o
go g
go mo w
DURATION M
EVENT o"
NO.
DATE (Il0URS)
REPORT NO.
CORRECTIVE ACTIONS /COttt!ENTS 85-27 850505 S
0.0 II 5
llA TURBIN Reduced load to 700 MWe for weekly Turbine tests j
85-28 850507 F'
205.45 H
3 Unit 2 -
HA TURBIN Reactor scram on Turbine trip due to l
85-11 high Reactor water' level. Remained shutdown for scheduled short maintenance-outage l
85-29 850530 F
'43.21
. 11 3
85-06 CD VALVEX Reactor scram' on MSIV closure due to faulty main steam line low pressure signal.
l APPROVED AUG 161982 l (final) y c. o 3 g
O - F""I' m P""1 M
M. ElEB EE3 E3 M
M EEl2 M - EL1l3 m
f""1 M
p o
e, ID/SA APPENDIX I)
-QTP'300-S13 UNIT SiluTDOWNS AND POWER REDUCTIONS Revision 6
. DOCKET NO.
050-265 August 1982 UNIT NAME-
-Quad-Citics: Unit 2 COMPLETED BY
.C. Kronich s
A..
ItAY 1985 DATE=
June 6,-1935 REPORT HONTil.
TELEPil0NE 309-654-2241 a:
,' 1 W
so H
~
y g4 C3 Q
- C 84 54
- 84 y
@pM LICENSEE M@
EVENT o"
DURATION w
.g.
NO.
DATE (ll0URS)
REPORT NO.
CORRECTIVE ACTIONS / COMMENTS g
e
'S
'744.0 C '
2 RC FUELXX Unit remains shutdown for End of Cycle 83-20 850317
(
Seven Refueling and !!aintenance Outage 9
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APPROVED AUG1GPJ02
. (final) ydudH
r VI.
UNIQUE REPORTING REQUIRDIElfrS The following items are included in this report based on prior commitments to the commission:
A.
Main Stean Relief Valve Operations There were no Main Steam Relief Valve operations for the reporting period.
B.
Control Rod Drive Scram Timing Data for Units One and Two The basis for reporting this data to the Nuc1 car Regulatory Commission are specified in the surveillance requirements of Technical Specifica-tions. 4.3.C.1 and 4.3.C. 2.
The follouing table is a complete summary of Units One and Two Control Rod Drive Scram Timing for the reporting period. All scram timing was performed with Reactor pressure greater than 800 PSIG.
- s-1
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,)
y; 3
l
s RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD ORIVES, FROM 1-1 TO 12-31-85 AVERAGE TIME IN SECONDS AT %
Max. Time
~~~
INSERTED FROM FULLY WITHDRAWN For 90%
insertion DESCRIPTION NUMBER S
20 50 90 Technical Specification 3.3.Co l&
DATE OF RODS 0.375 0.900 2.00 3.5 7 sec.
- 3. 3.C.2 ( Average Scram insertion Time) 5-17 1
0.31 0.71 1.45 2.50 2.50 Unit 1 L-2 Ilot Scran Yining After Replacement
VII. REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E.
O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Information", dated January 18, 1978.
4
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0061Z-L
L E
QTP 300-S32 I
R3 vision 1 QUAD-CITIES REFUELING ltarch 1978 m
INFORMATION REQUEST o
1.
Unit:
Q1 Reload:
7 Cycle:
8 1-2-86 2.
Scheduled date for next refueling shutdown:
3 Scheduled date for restart following iefueling:
4-2-86 e
4.
Will refueling or resumption of operation thereaf ter require a technical specification change or other IIcense amendment:
NOT AS YET DETERMINED.
5 Scheduled date(s) for submitting proposed licensing action and supporting Information:
DECDIBER 19, 1985; IF LICENSING ACTION REQUIRED.
s 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:
NONE PLANNED AT PRESENT TIME.
7 The number of fuel assemblies.
Number of assemblies in core:
724 a.
b.
Number of assemblies in spent fuel pool:
2340 8.
The present IIcensed 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 storege 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: 2003
~
WPPROVED
. APR 2 01978 Q.C.o.S.R.
~ - -
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nA
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QTP 300-S32 Rsvision 1 m
QUAD-CITIES REFUELING March 1978 6,,
INFORMATION REQUEST
^
~
1.
Unit:
Q2 Reload:
7 Cycle:
8 2.
Scheduled date for next refueling shutdown:
3-16-85 (Actual) 3 Scheduled date for restart following refueling:
6-4-85 4.
Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:
Yes. A routine MAPLHGR amendment has been approved as a preparatory change to allow a 10 CFR 50.59 review.
5 scheduled date(s) for submitting proposed IIcensing action and supporting Information:
Not Applicable.
6.
Important licensing considerations associated with refueling, e.g.,
..a or
- different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel ' design, new operating procedures:
g b
None planned at present time.
T' D.'
1 0-7 The number of fuel assemblies.
a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
176 8.
The present IIcensed 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:
r.
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 j
spent fuel pool assuming the present licensed capacity: 2003 b
XPPROVED APR 2.01978 Q.C.O.S.R.
h i
~
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 BWR Bolling Water Reactor CRD Control Rod Drive EHC Electro-Hydraulic Control System 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 IRM 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 MPC Maximum Permissible Concentration MSIV Main Steam Isolation Valve NIOSH National Institute for Occupational Safety and Health PCI Primary Containment Isolation PCIOMR Preconditioning Interim Operating Management Recommendations RBCCW Reactor Bu11 ding Closed Cooling Water System RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System RHRS Residual Heat Removal System RPS Reactor Protection System RWM Rod Worth Minimizer SBGTS Standby Gas Treatment System SBLC Standby Liquid Control SDC Shutdown Cooling Mode of RHRS SDV.
Scram Discharge Volume SRM Source Range Monitor TBCCW Turbine Building Closed Cooling Water System TIP Traversing Incore Probe TSC Technical Support Center 0027H 0061Z I
Commonwealth Edison ourd Citi;s NuclIir Powtr St: tion 22710 206 Avenue North Corcova, Illinois 61242 Telephone 309/6s4-2241 TKT-85-30 June 3, 1985 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention: Document Control Desk Gentlemen:
Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of May 1985.
Respectfully, COMMONHEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION
/
T. K. Tamlyn Services Superintendent bb Enclosure i
0027H 0061Z w
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