ML20031A835
| ML20031A835 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/21/1981 |
| From: | Woolever E DUQUESNE LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR GL-81-07, GL-81-7, NUDOCS 8109280241 | |
| Download: ML20031A835 (26) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION Washington, DC 20555 jp
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ATTENTION:
Mr. Darrel G. Eisenhut, Director
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SUBJECT:
Beaver Valley Power Station - Unit No. 2 1
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Docket No. 50-412 4}# g f
Generic Letter 81-07 Control of Ileavy Loads
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'o Gentlemen:
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This letter provides information in response to Generic Letter 81-07.
In order to submit the reports discussed in my letter of 5/28/81 (2DLC-4059), a study was initiated to analyze the conformance of Beaver Valley Power Station Unit 2 to the criteria of NUREG 0612. The first phase of this study is complete, and the results are attached to this letter.
This is provided in the format required by Generic Letter 81-07 and your letter of 12/22/81.
The results of the remainder of the study will be provided by April 2, 1982.
If you have any further questions on this subject, please contact ou r s ta f f.
DUQUESNE LIGilT COMPANY j
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J. Woolever Vice President cc: Mr. V. Stello, Director Office of Inspection and Enforcement So3o Mr. B. H. Grier, Director I
Region 1 Mr. K. Jabhour, Froject Manager Licensing and Review Washington, D.C. 20555 8109280241 810921
{DRADOCK 05000412 PDR
DUQUESNE LIGHT COMPANY Beaver Valley Power Station, Unit No. 2 l
Control of Heavy Loads - NUREG-0612 2.1.1 Report the results of your review of plant arrangements to identify all overhead handling systems from which a load drop may result in damage to any system required for plant shutdown or decay heat removal (taking no credit for any interlocks, technical specifications, operating procedures, or detailed structural analysis).
RESPONSE
APPLICABLE OVERHEAD LOAD HANDLING SYSTEMS Equipment No.
Identification Location 2CRN-201 Polar Crane Reactor Containment 2MHR-CRN-207 RHR Pump Monorail Reactor Containment 2MHF-CRN-215 Spent Fuel Cask Trolley Fuel and Decont. Bldg.
2MHF-CRN-227 Movable Platform w/ Hoists Fuel Building 2MHB-CRN-250 Cable Vault Area Monorail Cable Vault Area 2MHP-CRN-209A,B CCP Heat Exchangers Monorails Auxiliary Building 2MHP-CRN-210 Pipe Chase Slab Removal Monorail Auxiliary Building 2MHP-CRN-220A,B,C CHS Pump Removal Monorails Auxiliary Building 2MHP-CRN-221A,B CCP Heat Exchangers Monorails Auxiliary Building 2MHP-CRN-223 Auxiliary Building Miscellaneous Auxiliary Building Filter /Demineralizer Monorail 2MHP-CRN-234 CCP Pump Monorail Auxiliary Building 2MHP-CRN-235 Sweep Gas System Monorail Auxiliary Building The Beaver Valley Power Station Unit No. I "Centrol of Heavy Loads" report transmitted on June 23. 1981 from J. J. Carey of Duquesne Light Company to Steven A. Varga of the NRC included a crane located in the intake structure at the Beaver Valley Site. This crane, identified as CR-17, Screenwell Crane, services the intake structure equipment, including the Unit 2 service water system pumps. The Unit I report can be used to locate safety-related piping and equipment in the areas of the Unit 2 service water pumps.
2.1.2 Justify the exclusion of any overhead handling system from the above category by verifying that there is sufficient physical separation from any load-impact point and any safety-related l
components to permit a determination by iuspection that no heavy load drop can result in damage to any system or component required for plant shutdown or decay heat removal.
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REPONSE NONAPPLICABLE OVERHEAD LOAD HANDLING SYSTEMS Mark No.
Identification and Reason 2FNR-CRN-205 Refueling Manipulator Crane - This crans is located ir. side the Reactor Containment Building. The maximum load this crane will lift is a fuel element l
Bravar Valley Pcwar Statien - Unit No. 2 Control of Heavy Loads - NUREG-0612 Page 2 with its handling tool. This, by definition (NUREG-0612), is not classified as a heavy load.
1 2FNR-CRN-212A,B,C Stud Tensioner Hoists - These hoists are located in the containment building and are not used to lift any heavy loads as defined in NUREG-0612.
2FNR-CRN-234A,B Upender Winches - These winches are located in the fuel transfer canal area, and are not used to lift any heavy loads as defined in NUREG-0612.
1 2FdR-CRN-244 CRDM Drive Assembly Monorail - This monorail is located in the containment building in an area where a load drop would not result in damage to any system required for plant shutdown or decay heat removal.
2MNK-CRN-240 Radwaste Bridge Crane - This crane is located i
inside the Condensate Polishing Building which does not contain any safety-related equipment or systems.
2MHK-CRN-241 Demineralizer Filter Monorail - This monorail is inside the Condensate Polishing Building which does not contain any safety-related equipment or sy> <as.
2CRN-35 Stop Log Monorail System - This monorail is in the Alternate Intake Structure where a load drop would not result in damage to any system required for plant shutdown or decay heat removal.
2CRN-232 Cooling Tower Pump House Crane - This crane is in the Cooling Tower Pump House which does not contain any safety-related equipaent or systems.
I 2CRN-208 Solid Waste Handling Crane - This crane is in the Waste Handling Building which does not contain any safety-related equipment or systems.
i 2MHP-CRN-236 Caseous Waste Filter Monorail - This monorail is located in the Auxiliary Building and is not used to lift any " heavy loads" as defined in NUREG-0612.
2CRN-202 Turbine Room Crane - This crane is located in the Turbine Building which does not contain any safety-related equipment or systems.
2MHT-CRN-239A,B Condenser Water Box Cover Removal Hoist - This crane is located in the Turbine Building which does not contain any safety-related equipment or systems.
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Besver Valley Power Station - Unit No. 2 Control of Heavy Loads - NUREG-0612 Page 3 2MHT-CRN-242 CCS Heat Exchanger Removal Hoist - This crane is located in the Turbine Building which does not contain any safety-related equipment oa systems.
2MHP-CRN-211,212, Nuclear Valve Service Monorail - These monorails i
213 are located in the Auxiliary Building and are not l
ased to lift any heavy loads as defined in i
2MHP-CRN-222 Waste Gas Charcoal Bed Tank Monorail - This mono-rail is located in the Auxiliary Building in an area where a load drop would not result in damage to any system required for plant shutdown or decay heat removal.
2MRP-CRN-237 Waste Gas Surge Tank Monorail - This monorail is located in the Auxiliary Building in an area where a load drop would not result in damage to any system required for plant shutdown or decay heat removal.
2MHP-CRN-225 Charcoal Delay Bed, Degasifier Monorail - This monorail is located in the Auxiliary Building in an area where a load drop would not result in damage to any system required for plant shutdown or decay heat removal.
2MHP-CRN-238,A,B Access Slab Monorails - These monorails are located in the Auxiliary Building in an area where a load drop would not result in damage to any system required for plant shutdown or decay heat removal.
2MHZ-CRN-243 Electrical Equipment and Installation Monorail -
This monorail is located in the Service Building in an area where a load drop would not result in damage to any system required for plant shutdown or decay heat removal.
2.1.3 With respect to the design and operation of heavy-load-handling systems in the containment and the spent fuel pool area and those load-handling systems identified in 2.1.1, above, provide your evaluation concerning compliance with the guidelines of NUREG 0612, Section 5.1.1.
The following specific information should be included in your reply:
2.1.3a Drawings or sketches sufficient to clearly identify the location of safe load paths, spent fuel, and safety-related equipment.
RESPONSE
The attached figures 1 through 5 identify the location of safe load paths, spent fuel, and safe shutdown equipment in several Beaver Valley Unit 2 buildings. Figures 1A and IB are plan views of elevations 767'-10" and 738'-10" of the Containment Building showing safe shutdown equipment and
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Braver Valley Power Station - Unit No. 2 Control of Heavy Loads - NUREG-0612 Page 4 piping located on that elevation and one floor below that elevation. The figures may be used in conjunction with written procedures to define safe load paths for heavy loads not covered in this report. As a general procedure, any lifts performed by the polar crane are not moved over the reactor vessel unless absolutely necessary.
Figures 2A through H describe the safe load paths for all heavy loads that have been determined for inside the containment structure. Figures 2A through D show the safe load path for all heavy load lifts performed during refueling. Figure 2A shows the load paths for the installation of all the operating floor removable slabs, including the temporary removal and replacement of the platform grating and manipulator crane rail. Figure 2B shows the safe load paths for the movement of the CRDM horizontal and and the laydown of the CRDM missile shield and support vertical ductwe 5 structure. Fit
'.C shows the safe load paths and laydown areas for various heavy loat, including the Reactor Head Stand Cover, Stud Carriers, Reactor Head, and Upper and Lower Internals. Also shown on this figure is the movement of the Reactor Head Lift Rig Spreader Assembly during the refueling operation. The assembly is first movea from its permanent storage location during normal operation (in the northeast quadrant of the containment building near che equipment hatch) to temporary placement on top of the CRDM missile shield. After all of the removable plugs have been placed in position (Figure 2A), the Spreader Assembly is moved to a temporary location near steam generator 21A to permit removal of the CRDM missile shield and equipment from the reactor vessel. Finally, the Spreader Assembly is moved back to the reactor vessel and attached to the Head Lifting Rig to allow for removal of the reactor head. Figure 2D shows the safe load paths for the movement of the Reactor Cavity Water Seal from its storage position in the fuel transfer canal area, to the temporary laydown 4
area by steam generator cubicle 21C, to its final position at the reactor.
Also shown in this figure is the movement of the Internals Lifting Rig to a temporary storage position out of the refueling cavity to allow the manipulator crane to complete the refueling process. Figures 2E through G show the location of various other heavy loads which could be lifted by tLe polar crane. Figure 2E depicts the path to be used for the removal of the reactor coolant pumps. Figure 2F shows the safe load paths for the removal of the CRDM Ventilation Fans, the RHS heat exchangers, and the RHS ;; amps.
Figure 2G shows the location of various heavy loads at elevation 738'-10" to be lifted by the polar crane. Figure 2H shows the safe load path that has been determined for the RHS pump removal monorail located above the RHS pumps at elevation 732' in the containment building.
Figures 3, 4, and 5, are plan views of the Fuel and Decontamination Building, Auxiliary Building, and the Cable Vault Area. The figures show the location of safety-related equipment and piping and the safe load paths used when handling heavy loads within these structures.
2.1.3b A discussion of measures taken to ensure that load-handling oper-atian remain within safe load paths, including procedures, if any, I
for deviation from these paths.
RESPONSE
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Beaver Velley Power Station - Unit No. 2 Control of Heavy Loads - NUREG-0612 Page 5 Administrative procedurec will include the general guidelines and evaluation requirements of NUREG-0612. Load handling operational procedures will be written as necessary to ensure compliance with NUREG-0612 The safe load paths shown in this report will be used as the load handling paths. Any deviation from these operational procedures will require an approved procedural change.
2.1.3c A tabulation of heavy loads to be handled by each crane which includes the load identification, load weight, its designated lifting device, and verification that the handling of such load is governed by a written procedure containing, as a minimum, the information identified in NUREG-0612, Section 5.1.1(2).
RESPONSE
The attached Table 1 provides a list of heavy loads that will be carried by each crane along with any designated lifting devices. Table 3.1-1 of NUREG 0612 was used as a guideline in preparing Table 1.
Procedures for the lifting of heavy loads will incorporate the guidance of NUREG-0612.
2.1.3d Verification that lifting devices identified in 2.1.2c above, comply with the requirements of ANSI N14.6-1978, or ANSI B30.9-1971 as appropriate. For lifting devices where these standards, as supplemented by NUREG-0612, Section 5.1.1(4) or 5.1.1(5), are not met, describe any proposed alternatives and demonstrate their equivalency in terms of load-handling reli-ability.
RESPONSE
The two lifting devices listed in Table 1, Reactor Head Lifting Device and the Internals Lifting Rig Assembly, were both designed prior to the publishing of the,above standards. However, they were designed to the applicable American Institute of Steel Construction (AISC) specifications.
The specifications require that the lifting devices be capable of lifting two times the weight of their designated loads without exceeding the yield strength of the material in the devices.
In addition, the devices were preoperationally tested to 125 percent of the maximum load which they will be required to withstand during normal use.
2.1.3e Verification that ANSI B30.2-1976, Chapter 2-2, has been invoked with respect to crarie inspection, testing, and maintenance. Where any exception is taken to this standard, sufficient information should be provided to demonstrate the equivalency of proposed alternatives.
RESPONSE
Crane inspection, testing, and maintenance procedures will comply with ANSI B30.2-1976, Chapter 2-2.
Should any deviations from this standard be required, they will be equivalent to the requirements of ANSI B30.2-1976.
2Property "ANSI code" (as page type) with input value "ANSI B30.2-1976.</br></br>2" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..1.3f Verification that crane design complies with the guidelines of CMAA Specification 70 and Chapter 2-1 of ANSI B30.2-1976, including the demonstration of equivalency of actual design
Beaver Valley Power Station - Unit No. 2 Control of Heavy Loads - NUREG-0612 Page 6 requirements for instances where specific compliance with these j
standards is not provided.
RESPONSE
Cranes 2MEF-CRN-215 (Spent Fuel Cask Trolley) and 2MHF-CRN-227 (Motor Driven Platform With Hoists For Fuel Building) have been designed to comply with the guidelines of both ANSI B30.2-1976 and CMAA 70.
Crane 2CRN-201 (Polar Crane) was designed to comply with ANSI B30.2-1967, and CMAA 70.
The ANSI B30.2-1976 standard is a revision of the same standard issued in 1967. The specifications and design of the polar crane were reviewed for compliance with the 1976 ANSI standard and was found to conform with th entire standard except for the following point:
ANSI B30.2-1976 requires that trolley bumpers have energy absorbing capacity to stop the trolley when traveling with power off in either direct. ion at a speed of at least 50 percent of rated load speed. The Unit 2 Polar Crane was designed with trolley bumpers to stop the trolley from a speed of 40 percent of rated load speed. This design difference is judged not to have a significant effect on the handling of heavy loads by the polar crane.
2.1.3g Exceptions, if any, taken to ANSI B30.2-1976 with respect to operator training, qualification, and conduct.
RESPONSE
Operator training, qualification, and conduct will be in compliance with the requirements of ANSI B30.2-1976.
TABLE 1 Crane Capacity Load Weight Lifting Mark No.
(Tons) lleavy Load Identification (Tons)
Device 2CRN-201 Bridge-396 Reactor Vessel IIcad & Attachments 130*
Vessel llead Trolley No. 1-167/15 Lifting Device Trolley No. 2-167 Reactor Vessel Internals (Upper) 40*
Internals Lifting Rig Assembly Reactor Vessel Internals (Lower) 130*
Internals Lifting Rig Assembly Reactor Cavity Water Seal 8
Reactor Coolant Pump-Hotor 66 Reactor IIcad Lif ting Rig 3.5 Spreader Assembly Reactor Containment Operating 7.5 Floor Plugs (IIcaviest)
CRDM Missile Shield (3 Sections) 34 (Total Weight)
Ventilation Fans 1.0 Ventilation Supply Ducting (To CRDM)
.9 Stud Carriers (Full) 3.6 Removable Rail & Beam 1.15 Removable Platform North & South 3.0 7
TABLE 1 Crane Capacity Load Weight Lifting Mark No.
(Tons)
IIcavy Load Identification (Tons)
Device Internals Lifting Rig Assembly 10.5 Reactor IIcad Storage Stand Cover 2.5 4'
Residual lleat Removal IIeat 9.4 Exchanger Residual IIeat Removal Pump 3.9 i
Regenerative lleat Exchanger 3.5 Polar Cranes - Botton Block &
5.4 llook i
i 2MilR-CRN-207 5
Residual lleat Removal Pump 3.9 s
2MIIF-CRN-215 125 Spent Fuel Shipping Cask 21.5 2HIIF-CRN-227 10/10 New Fuel Shipping Container 3.0 j
(Upended only)
Failed Fuel Assembly Storage Can 1.5 t
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Removable Slabs 2.3 i
Rod Drive Motor Generators 3.8 i
i 2HilP-CRN-209A, 10/10 Component Cooling Water lleat 17.5 B
Exchangers (Two Monorails Together) i 4
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TABLE 1 Crane Capacity Load Weight Lifting Mark No.
(Tons)
IIcavy Loc 3 Identification
_ (Tons)
Device 2MilP-CRN-210 5
Removable Slabs 4.5 Nonregenerative IIcat Exchanger 4.25 2MllP-CRN-220A, 5/5/5 Charging Pumps-Pump 3.75 B,C Charging Pumps-Motor 1.95 2MllP-CRN-221A, 10/10 Component Cooling Wate-lleat 17.5 B
Exchangers (Two Monorails Together) 2MllP-CRN-223 10 Removable Slabs 9.75 Cesium Removal Ion Exchangers
.95 Mixed Bed Demineralizers
.95 Deborating Demineralizers 1.4 2MllP-CRN-234 2
Component Cooling Water Pumps 1.0 Component Cooling W'ater Motor 1.7 2MIIP-CRN-235 3
Removable Slabs 2.8 Weights to which elements were designed.
Based on Unit I data, the weights are expected to be lower.
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LEGEND 9
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No.
EQUIPMENT No.
DESCRIPT ION NOTES gir I
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REACTOR S
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^{
U'(
No.
EQUIPMENT No.
DESCRIPTION NOTES "32 1
2MHP-CRN-234 CCP PUMP MONORAlt g
2 2CCPW P21 A,B,C CCP PUMPS H,5 3
2MHP-CRN 221A,8 kP$k3 EXCHANGERS y
4 2 MHP-CRN-235 SWEEP GAS SYSTEM MONORAll 5
REMOVABLE SL ABS (21)
H 6
REMOVABLE EQUIP PLUCS (tO) 7 2MHP-CRN-203 AuxlLIARY BUILDING MISC.
FLT/DEMIN. MONORAIL
![!k h fII.h f
8 2MHP-CRN-220A,B,C CHS PUMP REMOVAL MONORAILS s S N5kphyrhMWM%,y 9
2CHS 4 P21 A,0,C CHARGING PUMPS H.S PIPlNG 4 4YWxl u )[/% # 1W:M GASEWS WASM NER 10 2 MHP-CRN-236 BELOW
\\
- O :
" " " ^ ' '
'W PIPING It PIPE CHASE 12 VENT CHASE
.x(@XM &M ' "x.
13 CABLE ARE A j
14 ELEVATOR M
12
.y.)
5 S
h5
&5 4.NPIP ING h
k!
.h
~
a &*
igg cs o 1= G.
wA LEGEND M773If M
SAFE LOAD PATH 2 ANN nviaT J
ym.
A h
- W# # "~
' SAFETY REL ATED PIPING AND EQUIPMENT a#
eu ;g N
{-M:
a.
H HEAVY LOAD
$$$${
{g/4 7) vaswvx 4
ii>
S SAFE SHUTDOWN EQUIPMENT N
h 4
PIPING S
- 2 7hl, BELOwy$
MMM-$O2d C C C:
h st w
- unexvr g
>3 Q
,xn m >vi FIGURE 4B CONTROL OF HEAVY LOADS, 6,,
W mlllllll g g j" q
AUXILIARY BUILDING EL.735-g i
i u..
BEAVER VALLEY POWER STATION-UNIT 2 V
PL AN EL. 735'-6"
a'r LEGEND
..t d'y No EQUIPMENT No.
DESCRIPT ION NOTES 1
2MHP -C RN - 209 A,8 CCW HEAT EXCHANGER MONORAILS h
2 ELECTRICAL ARE A 3
2CCP - E21 A,B,C CCW HEAT EXCHANGERS H,S 4
E L E VATOR S
2 MPH-CRN-238A,B ACCESS SL AB MONORAILS VALVE SE RVICE 6
2MHP-CR N-211 k
[t
..s... :):q
. /.... x:.
DI?$Ol'XQXMYNX -D 7
2 MIP - CRN - 212 ONO A NhO Mh h:
8 2MHP-CRN-213 y
All N#hY <NNNNNU dNI 9
PIPE CHASE blb
- ~ ~ '
C g
IO VENT CHASE r
2CHS - F LT 21 BORIC ACID FILTER S
12 2BRS-IOE 21 A,B
$[jN N
RS N N'D ND:6.NDNN $
['
13 2CHS-DEMN 21 A,8 MIXED BED DEMINERAL12ERS H
14 2CHS-DEMN 23 A,8 DEBORATING DEMINERAllIERS H
WAT R INJECilON T j' 13 15 2CHS-FLT 24 A. B g
R 7
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. c3
- -i5
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h LD LEGEND g
f
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g SAFE LOAD PATH C
L A
3
+
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g- ]
. ~
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_b 4
tJ l-cF[
l-e t-4 FIGURE 4C tJ r
k,, [3 t] - l l CONTROL OF HEAVY LOADS r.
illnimil!!!!
AUXILI ARY BUILDING EL.710'-6"
". I II EEEI. ;f
& 7 I 8'- 6" o
BEAVER VALLEY POWER STATION-UNIT 2 PL AN EL.710'-6"'G 718'-6"
t LEGEND I
No EQUIPMENT No DESCRIPTION NOTES S'?
I 2MHB-CRN-2SO CABLE VAULT AREA MONORAIL a *.
2 REMOVABLE SLABS H
l 3
MCC 17 MOTOR CONTROL CENTER 4
MCC 17 MGTOR CONTROL CENTER S
2 MSS M HYVIOIA,B,C N SyEAM ISOLATION TRIP g
6 SSPC-2R9 IBD SOLID STATE POWER CAB 7
PNL-2 ROD LOG LOGIC CAB B
PNL-2 ROD-0CH OC HOLD SUPPY 9
2RDS-MG 21,2.,
g RIVE MOTOR GENER ATOR g
10 DUCT OPENING 0
11 RE AC-2T - SWGR SWITCH GEAR I
W5FDRIVE POWER SUPPLY 12 PND-2RD CONT 6
c..2,7 g
>g g
n Nb he-a t l
@g ip 2
o e
o 5
cea F
- Y f SAFETY RELATED PIPING AND EQUIPMENT PLAN EL. 755'-6" FIGURE 5 CONTROL OF HEAVY LOADS 4
C ABLE VAULT AREA BEAVER VALLEY POWER STATION-UNIT 2 4
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