ML20072G446
| ML20072G446 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/22/1983 |
| From: | Swartz E COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR 6773N, NUDOCS 8306280502 | |
| Download: ML20072G446 (26) | |
Text
e Commonwealth Edison O
One First N:tional Plaza. Chic!go, Illinois
('
O Address Reply to: Post Office Box 767 Chicago. Illinois 60690 June 22, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
LaSalle County Station Units 1 and 2 NUREG 0612 Control of Heavy Loads Supplemental Response NRC Docket Nos. 50-373/374 Reference (a):
EG&G Idaho, Inc. Phase I Report for Control of Heavy Loads at LaSalle County Station Published April 1983
Dear Mr. Denton:
Reference (a) was provided to the Commonwealth Edison Company on an informal basis for our review and comment.
This Phase
- 1. Report discusses our compliance with NUREG 0612 Control of Heavy l
Loads at LaSalle County Station.
Reference (a) contains four (4) areas of concern that were subsequently discussed with the NRC Staff and their Consultants during a conference call on June 14, 1983.
As as result of our review,'and'to document our conference call discussions, enclosed is s
the Commonwealth Edison Company response to these four (4) areas of concern.
To the best of my knowledge and belief, the statements contained in the Enclosure are true and correct.
In some respects these statements are'not based on my personal knowledge but upon I
information furnished by other Commonwealth Edison employees.
Such information has been reviewed in accordance with Company practice and I believe it to be reliable.
Please address any questions that you may have concerning this matter to this office.
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B306280502 830622 PDR ADDCK 05000373 P
4 i One (1) signed original and forty (40) copies of this letter with Enclosure are provided for your use.
Very truly yo
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=ca E. Douglas Swartz Nuclear Licensing Administrator Enclosure j
cc:
J. G. Keppler - RIII A. Bournia - LB 2 RIII Inspector - LaSalle 6773N l
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ENCLOSURE COMMONWEALTH EDISON COMPANY
.l LaSalle County Station Units 1 and 2 i
NUREG 0612 Control of Heavy Loads -
Supplemental Response to EG&G Idaho Phase I Report Published April 1983 i
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6773N
r 4 2.2.1.C EG&G Conclusions and Recommendations
" Based on the information provided, EG&G concludes that the applicant has not included all applicable hoists and cranes in their list of handling systems which must comply with the requirements of the general guidelines of NUREG-0612.
EG&G recommends that the applicant supply a better justification for _the exclusion of cranes and hoists from the referenced list, or include the cranes and hoists in plant procedures as being subject to the requirements as NUREG-0612."
LaSalle County Station Response:
The overhead handling systems which are listed on CECO.'s Phase I Table 2.1 have been excluded from Table 1.1 either on the basis of sufficient physical separation from safety related equipment or cases where a crane has been specifically provided over a piece of equipment solely to aid in it's disassembly and reassembly for maintenance purposes when the equipment is out of service, and potential load drops would not affect any other safety related equipment.
Reference (a) indicates that nineteen (19) cranes were not included in CECO.'s Phase I submittal Table 1.1
" Crane /Holst Systems Considered as Potential Sources for Damage of Safety Components" but were included in CECO.'s l
Phase 2 submittal-dated September 22, 1981.
Our review of this EG&G observation indicates that 5 of the 19 cranes / hoists were inadvertantly omitted from the Phase I submittal.
However, our Phase II analyses provided the proper disposition of 'the potential for load drop from these 5 cranes.
The following information provides a discussion of this matter, corrects our Phase I submittal, and provides clarification to-the crane / hoist numbering system of the Phase II submittal to be consistent with Phase I.
Fourteen (14) of the nineteen (19) cranes listed in Reference (a) Table 2.1 on page 5 are included in CECO.s Phase I Table 1.1 under different equipment numbers.
The Phase II submittal utilized equipment numbers as assigned i
by the crane / hoist equipment supplier (R. W. Roberts) whereas the Phase I submittal utilized equipment numbers as assigned by our AE (Sargent & Lundy).
4 i The five (5) crane systems that we have identified as not being originally included in our Phase I submittal Table
-1.1 are now included in the attached revised Table 1.1 and are so indicated by a single asterick "*".
Also attached is a' supplement to Table 3.1 which identifies'the crane system number,_ load path drawing, equipment name, capacity,
. load designation, load-weight, lifting device, and governing station procedure for each of these five (5) additional crane systems.
Additionally, Table 1.1 has been slightly revised to indicate corrected equipment names as necessary and so indicated by a double asterick "**".
The Phase II submittal has been revised to utilize Sargent
& Lundy equipment numbers in lieu of the previously assigned R. W. Robert's numbers and is also attacned.
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TABLE 1.1 CRANE / HOIST SYSTEMS CONSIDERED AS POTENTIAL SOURCES FOR DAMAGE OF SAFETY COMPONENTS EQUIPMENT NO.
EQUIPMENT NAME OHC02G Reactor Building Crane OHC22G New Fuel Vault Jib Crane JB-3 OHC23G Jib Crane No.-5 (fuel inspection)
OHC38G Trolley Hand Hoist TH05 OHC39G Trolley Hand Holst TH05 OHC41G Trolley Hand Holst TH06 OHC95G New Fuel Handling Gantry Crane 1HCB7G Rail Hugger Holst RH28 lHCB8G Trolley Wire Rope Hoist TWR21 2HCB9G Trolley Wire Rope Holst TWR22 1HCElG Jib Crane No. 8
- 1HCJ5G Trolley Wire Rope Hoist TWR23 (JB-6)
- 2HCO2G Electric Wire Rope Holst EWR-5 l
lHC08G Rail Hugger Holst RHO 5 lHC09G Rail Hugger Holst RH06
- 1HC20G Trolley Wire Rope Hoist TWR01
- 2HC20G Trolley Wire Rope Hoist TWRll 1&2HC21G Trolley Wire Rope Hoist TWR02/TWR12 1&2HC22G Trolley Wire Rope Hoist TWR03/TWR13 l
1&2HC23G Trolley Wire Rope Hoist TWR04/TWR14 1&2HC24G Trolley Wire Rope Holst TWR05/TWR15 l
- Equipment was added
- Equipment name was changed.
TABLE 1.1-(Cont'd)
EQUIPMENT NO.
EQUIPMENT NAME 1&2HC27G Trolley Wire Rope Holst TWR06/TWR09 1HC29G Rail Hugger Hoist RH13
- 1&2HC30G
. Trolley Wire Rope Hoist TWR18/TWR19 2HC37G Hand Chain Holst HCH03 1HC46G Trolley Wire Rope Hoist TWR02 (JB-2) 1&2HC66G Rail-Hugger Hoists RH33/RH45
- 1HC67G Double Girder Crane DG-1 With Holst EDM-1
- 2HC68G Double Girder Crane DG-2 With Holst EDM-2
- 1HC70G Trolley Wire Rope Holst TWR16 1HC75G Hand Trolley T33 2HC76G Hand Trolley T34 lHC79G Rail Hugger Holst RH17 i
- lHC80G Rail Hugger Hoists RH41 and RH42 l
(Replaces RH36) i
- 2HC81G Rail Hugger Hoists RH43 and RH44 (Replaces RH37) lHC87G Hand Trolley T40 1HC89G Rail Hugger Holst RH22 2HC90G Rail Hugger Hoist RH23
- Equipment was added
- Equipment name was changed.
6773N
ADDITIONS TO TABLE 3.1 H_EAVY LOAD IDENTIFICATION FOR THE CRANE / HOIST SYSTEMS l-BEAM DWR.
EQUIPMENT EQUIPMENT NAME CAP.
LOAD DESIGNATION WEIGHT DESIGNATED LIFTING
- 0ggG NO.
M-53 NUMBER
[ TONS)
(LBS.)
DEVICE 93 6
IHC30G TROLLEY WIRE R0PE HOIST 2
RHR SERVICE WATER PUMPS 680 AS REQUIRED LMP-GM-9 TWR 18 127 6
2HC30G TROLLEY WIRE R0PE HOIST 10 HPCS COOLING WATER PUMP 2100 AS REQUIRED LMP-GM-9 TWR 19 187 6
2HCO2G ELECTRIC WIRE R0PE HOIST 3
RHR SERVICE WATER PUMPS 680 AS REQUIRED LMP-GM-9 EWR-5 i
JB-6 5
1HCJ5G TROLLEY WIRE R0PE HOIST 2
MISC.
4000 AS REQUIRED LMP-GM-9
. TWR 23 f
128 6
2HC20G TROLLEY WIRE ROPE 20 HPCS PUMP 32700 AS REQUIRED LMP-GM-9 50IST TWRll 4
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2.2 Fuel Storage Pool Vicinity Request 1:
Identify by name, type, capacity, and equipment designator, any cranes physically capable (i.e. Ignoring interlocks, moveable mechanical stops, or operating procedures) of carrying 1 cads over spent fuci in the storage pool or in the reactor vessel.
Response 1:
Following is a listing of the cranes physically capable (i.e.
Ignoring interlocks, moveable mechanical stops, or operating procedures) of carrying loads over spent fuel in the storage pool or in the reactor vessel.
1)
Reactor Building Crane - The Reactor Building Crane is an electric overhead traveling double girder bridge crane equipped with a 125 ton Main hoist and 10 ton Auxilliary hoist. The crane was manufactured by P&H and is designed by P&H Serial No. CN 24500 or CECO Equipment No. OHC02G.
2)
Refuel Platform - The load currying components of the refuel platform consist of the following:
a)
One platform complete with 1200 lb. capacity fuel hoist, hoist trolley, and frame.
b)
One 1000 lb. capacity electrically operated pendant controlled auxiliary hoist mounted to the fuel hoist trolley frame.
c)
One 1000 lb. capacity electrically operated, monorail mounted, motorized trolley, pendant controlled, auxiliary hoist.
l The Refuel Platform is a gantry type crane and there is one Refuel Platform for each unit. Unit 1 Refuel Platform is designated F21E003 and Unit II Refuel Platform is designated F21E004.
3)
JIB #' - Jib Crane #1 is a Bushman Model 480, 1000 lb.
capacity Jib Crane with a boom 16' - 0" In length, and is equipped with motorized rotation nounted on the jib boom is a Yale 1000# capacity wir, rope electric hoist.
The hoist is equipped with a powered trolley. All movements of the Jib and hoist are controlled by a push button pendant station.
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The Jib Crane is designated by CECO Equipment Number 1HC93G and the Yale bolst is designated as hoist TWR06, CECO Equipment Number 1HC27G.
4)
J1B #4 - Jib Crane #4 is identical to Jib Crane #1. The Jib Crane is designated by CECO Equipment Number 2HC93G, and the Yale hoist is designated as hoist TWR09, CECO Equipment Number 2HC27G.
5)
New Fuel Vault Jib Crane (JIB #3) - Jib Crc.ne #3 is a Bushman Model 480, 2000# capacity Jib Crane with a boom 40' 8" in length, and'is equipped with motorized rotation.
Mounted on the Jib Boom is a P&H, 2000# capacity wire rope electric "Hevi-Lift Hoist".
The hoist is equipped with a motorized, geared trolley. All movements of the hoist and Jib are controlled by a six button, pushbutton pendant station.
The Jib Crane is designated by CECO Equipment Number OHC22G and the P&H hoist is designated as hoist TWR08, CECO Equipnent Number OHC37G.
6)
Channel Handling Boom (Jib #5) - Jib Crane #5 is a Bushman Model 480, 200# capacity Jib Crane with a boom 9' 3" in length. The Jib Crane is designated by CECO Equipment Number OHC23G. The Jib will handle a normal load of 80#
and a design load of 200#. Mounted on the Jib Boom is an Aero-Motive Model 9050-J-a spring loaded balancer to aid in the handling of the channels.
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Request 2:
Justify the exclusion of any cranes in this area from the above category by verifying that they are incapable of carrying heavy loads or are permanently prevented from movement of heavy loads over stored fuel or into any location where, following any failure, such load may drop into the Reactor Vessel or Spent Fuel Storage Pool.
Response 2:
1)
Each refuel Platform is equipped with a 1200# capacity Fuel hoist and two 1000# capacity Auxiliary hoists. The rated capacity of each of the hoists is below the designated weight of 1800# for a heavy load. The Auxiliary hoists are equipped with load sensing cells and circuitry which will automatically stop the hoists on an overload signal when a load of 1000# or over is applied to the hoist cable.
The Fuel hoist is equipped with a similar circuit and will automatically stop the hoist motor when a load of 1200# + 50# is applied to the hoist cable.
The Refuel Platforms are therefore excluded from the above category on the basis of being incapable of lifting a heavy load.
2)
Jib Cranes #1 and #4 are 1000# capacity units, and are physically incapable of lif ting a heavy load. These units are therefore excluded from the above category.
3)
Channel Handling Boom (Jib #5) has a 200# capacity and will be used only in the handling of 80# channels. This unit is therefore excluded from the above category on the basis of being incapable of lifting a heavy load.
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Request 3:
Identify any cranes listed in 2.2-1, above, which you have evaluated as having sufficient design features to make the likelihood of a load drop extremely small for all loads to be carried and the basis for this evaluation (i.e., complete compliance with NUREG 0612, Section 5.1.6 or partial compliance supplemented by suitable alternatives or additional design features).
For each crane so evaluated, provide the load-handling system (i.e., crane-load-combination)
Information specified in Attachment 1.
Response 3:
2.2-3 is not applicable to any cranes listed in 2.2-1.
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l Request 4:
For cranes identified in 2.2-1, above, not categorized according to 2.2-3, demonstrate that the criteria of NUREG 0612, Section.
5.1, are satisfied.; Compliance with Criterion IV will be demonstrated'in response to-Section 2.4 of this request. With-
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respect to Criteria 1 through 111, provide a discussion of your evaluation of crane operation in the Reactor Building and your determination of compliance. This response should include the following information for each crane:
Which alternatives (e.g. - A, B, C, or D) from those identified in " Request for Additional Information on Control of Heavy Loads," Section 2.2-4, have been selected.
t Response 4:
1)
Reactor Building Crane - Altern6tives A and C are applicable to the Reactor Building Crane. Also, the response to 2.1-3 demonstrates that the recommended guidelines presented In Section 5.1.1 of NUREG 0612, have been met for the Reactor Building Crane.
The following design specifications, tests, and procedures ensure that the potential for a load drop by the Reactor Building Crane is extremely small.
The Reactor Building Crane is designed to withstand tornado wind velocities of 300 MPG tangential and 60 MPH translational. The design provides that the crane will not be dislodged from the crane rails, the' trolley will remain attached to the bridge, and all components will be prevented from flying off and acting as missiles, when the crane is subjected to tornado conditions. Also, the crane is designated to equalize pressure differentials which may develop in the girders or compartments due to a decrease in atmospheric pressure during a tornado. The structural steel supporting the crane is also designed to withstand the described tornado loadings.
The Reactor Building Crane is also designed to withstand earthquake forces due to horizontal and vertical accelerations resulting from an operating basis earthquake (OBE) or a design basis earthquake (DBE). The crane is designed to be operable following, but not necessarily during, an OBE, and it is also designed to remain intact, but not necessarily operable, during and after an OBE.
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The Reactor Building Crane was' also subjected to several tests during assembly and prior to initial use. All butt welds ore the top and bottom cover plates were radiographed to ensure that the welds meet AWS DI.1 specification.
The books, both the 125 ton capacity main hoist sister hook and 10 ton capacity Auxiliary-hoist book, were proof tested.at twice the rated capacity. Af ter proof testing each hook was subjected to magnetic particle and ultrasonic examination. Also, all lifting tackle and gearing was designed to have a minimum safety factor of 5 Prior to initial use the crane was inspected and load tested at 125% of rated capacity. The heaviest load to be lif ted is the 200,000# reactor head, and this required only 80% of the rated lifting capacity.
Bridge, hoist, and trolley travel is regulated by limit switches.
Specific limit switches are used to control crane movements when handling the spent fuel shipping cask. These limit switches prevent movenent of the shipping cask over the Reactor
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Vessel or the Spent Fuel Pool.
in addition to the above listed design requirements, procedures or lesson plans have been written for the handling of heavy loads, operator training, and regularly scheduled crane inspections.
In addition, all load movements are minimized, and follow the safest and shortest route with the load as close to the floor as practical.
The above listed criteria assures that the potential for a load drop are extremely small for the Reactor Building Crane, and therefore this crane is excluded from the above category.
2)
New Fuel Vault Jib Crane (Jib #3) - Alternative C is applicable to Jib #3 Jib #3, with electric Wire Rope hoist TWR08, has a rated capacity of 2000#. Jib Crane #3 will be used only to transfer new fuel back and forth between the new fuel inspection stand and the new fuel vault. Therefore, Jib Crane #3 will never be used to lif t a load greater than 1800#.
Because Jib Crane #3 has the physical capacity to lift a heavy load, an administra-tive procedure is being written which will limit the Jib Crane rated capacity to 1800#. The rated capacity of -1800# will be marked on the Jib Boom and a sign will be placed on the pedestal of the Jib Crane which will refer the operator to the Administrative Procedure which will refer the operator to the Administrative Procedure which controls the use of the Jib.
Based upon the above listed measures taken to limit the lif ting capacity of Jib Crane #3, this crane is therefore excluded from the above category.
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2.3 Specific requirements for overhead handling systems operating in plant areas containing equipment required for reactor shutdown, decay heat removal, or spent fuel cooling.
Request 1:
Identify any cranes listed in 2.1-1, above, which you have evaluated as having sufficient design features to make the Ilklihood of a load drop extremely small for all loads to be carried and the basis for this evaluation (i.e., complete compliance with NUREG 0612, Section 5.1.6, or partial compliance supplemented by suitable alternative or additional design features).
For each crane so evaluated, provide the load-handling-system (i.e., crane-load-combination) information specified in Attachment 1.
Response 1:
2.3-1 is not applicable to any cranes listed in 2.1-1.
Request 2:
For any cranes identified in 2.1-1 not designated as single-failure-proof in 2.3-1, a comprehensive hazard evaluation should be provided which includes the following'information.
Request 2A:
The presentation is a matrix format of all heavy loads and potential impact areas where damage might occur to safety-related equipment. Heavy loads identification should include designation and weight or cross-reference to information provided in 2.1-3-C.
Impact areas should be identified by construction zones and elevations or by some other method such that the impact area can be located on the plant general arrangement drawings.
Response 2A:
The-information requested above is listed in Table 4.1.
Request 28:
For each interaction identified, indicate which of the load and impact area combinations can be eliminated because of separation and redundancy of safety-related equipment, mechanical stops and/or electrical interlocks, or other site specific l
considerations.
Request 2B-1:
For load / target combinations eliminated because of separation and' redundancy of safety-related equipment discuss the basis for determining that load drops will not affect continued system operation (i.e., the ability of the system to perform its safety-related function).
Response 2B-1:
l A discussion is given below for each of the crane systems l
listed in Table 4.1.
These discussions give the basis for determining that a load drop from the given crane system will not prevent safe reactor shutdown or decay heat removal. These discussions are based on the l
" Safe-Shutdown Analysis" given in the LaSalle County Station Final Safety Analysis Report (LSCS-FSAR H.4 Safe Shutdown Analysis).
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Crane Systems 12 & 18:
System 12 is used to lift heat recovery coils located in the Unit 1 Turbine Exhaust Filter Room.
System 18 is used to lift Unit JCC heat recovery coils. The load paths of the two systems are two floors above control panels located in the Control Room.
if a load drop' from either system occurs, and damage to Control Room panels result, operation of the systems necessary for safe shutdown can be continued and controlled from the remote shutdown panels located in the Auxiliary Electric Equipment Room (AEER).
Crane System 22 & 23:
System 22 is used to service Unit 1 main steam isolation valves located outside of the primary containment, and System 23 is used for the same purpose in Unit J07.
If a load drop occurs from either crane system and a main steam line is damaged, the release of steam can be stopped by closing the appropriate redundant MSIV located inside the primary containment.
Crane System 93, 169, & 187:
Systems 93, 169, & 187 are used to service RHR Service Water Pumps and Fuel Pool Emergency Make-up Pumps.
System 93 is used to lift loads in the vicinity of Unit 1 RHR Service Water Pumps A, B, C, & D and Fuel Pool Emergency Make-Up Pumps A & B.
RHR Service Water Pumps A & B, and Fuel Pool Emergency Make-Up Pump A are located in a room adjacent to, but separated from, another room containing RHR Service Water Pumps C & D and Fuel Pool Emergency Make-Up Pump B.
if a load drop did occur in one of the rooms, damaging any of the pumps, a separate, redundant pump located in the adjacent room would be put into service to perform the system function.
Systems 169 & 187 are.used to service Unit 11 RHR Service Water Pumps
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and fuel Pool Emergency Make-Up Pumps.
System 169 is used to lift loads
- In the vicinity of RHR Service Water Pumps C & D and Fuel Pool Emergency Make-Up Pump B.
System 187 is used to lift loads in the vicinity of RHR Service Water Pumps A & B and Fuel Pool Emergency Make-Up Pump A.
These pumps are located in a room separate from the pumps serviced by System 169 If a load drop occurred in either room, a separate, redundant pump, located in the other room, would be put into service to perform the system function, l
l Crane System 94 & 128:
System 94 is used to service the Unit 1 HPCS Pump and System 128. services the HPCS Pump for Unit 337.
The load paths of these cranes are directly above the HPCS Pumps, if a load drop occurred, and the HPCS' Pumps were inoperable, safe shutdown would be achieved by initiating the RCIC System for depressurization, reactor water make-up,.and initial decay heat removal.
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Crane Systems 95, 96, 97, 129, 130, & 131:
Crane Systems 95, 96, t 97 are used to service Ha!t 1 RHR Pumps B, C, & A, respectively.
Crane Syst' ems 129, 130, & 131 are used to service Unit II RHR Pumps B, C, & A respectively.
The load paths of the cranes are directly above the related RHR Pumps.
If a load drop did occur and one of the RHR Pumps was damaged, the separate, redundant RHR Pump would be put into service to perform the system function.
Crane Systems 98 & 132:
Crane System 98 is used to service the Unit 1 LPCS Pump and System 132 is used to service the Unit II LPCS Pumps.
If a load drop does occur, and the LPCS Pumps become inoperable, the functions of the LPCS System will be completed by the continued use of the HPCS System.
Crane Systems 127 & 168:
System 127 is used for servicing the Unit 1 HPCS Diesel Cooling Water Pump and Strainer.
System 168 is used for the same purpose in Unit II.
If a load drop did occur and these components were damaged, resulting in the loss of the HPCS System, the RCIC System would be initiated to perform the required functions for safe shutdown.
Crane. Systems 179 & 184:
trane Systems 179 and 184 are located directly above the RCIC Turbine Driven Pumps for Units 1 & II.
These cranes will be used only when the RCIC Systems are out-o(-service.
However, if the RCIC Systems were damaged by a load drop, the HPCS Systems would be used to perform the functions necessary for safe shutdown.
Crane Systems 182 & 183:
Crane Systems 182 & 183 will 'b'e used to move the Motor Driven Reacter Feed Pump Motors for Units 1 & II.
If a load drop did occur, damage may result to the main steam lines below the load paths of the cranes.
If a main steam line did break, the flow'of steam could be stopped by closing the appropriate separate & redundant MSIV.
Crane Systems SG1 & SG2:
Systems SGI & SG2 will be lif ting loads directly above Units 1 & II RHR "A" Heat Exchangers.
If a load drop occurs the heat exchangers may be damaged, causing RHR Loop "A" to be inoperable.
If this occurs, RHR Loop "B" will be used to perform the functions s
necessary for the safe shutdown of the reactor.
l Crane Systems DG1 & DG2:
Crane Systems DG1 & DG2 will be used to service l
the Turbine Driven Reactor Feed Pumps for Units 1 & II.
If a load drop did occur, damage to the HPCS Diesel Control Panels, located two floors
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below may result, if, as a result of a load drop, the HPCS System is inoperable the RCIC System will be used to perform the functions required Lfor the safe shutdown of the reactor.
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1 Cfane Systems' 193 & 194: Crane Systems 193 & 194 are used to lift flowmeters installed in the main steam lines for Units 1 & 3][.
If a z
load drop did occur from one of) these systems, a main steam line could be damaged.
If a break in a main steam line occurs, the release of i
i steam could be stopped by closing the appropriate MSIV.
Cranes JB2',#J B6', & J B8 : lJib Cranes 2, 6, & 8 are used to lift various eqvipment through the equipment hatches located above the equipment access way. The items are being lifted above the Unit 1 RCIC Pump, and-damage to the pump may result if a load drop occurs.
if the RCIC System is damaged, the Unit 1 HPCS. System will be used to perform the functions necessary for the s'afe shutdown of the reactor.
Patented-Track Crane Systems PTS 5 & PTS 6:
Crane Systems PTS 5's PTS 6 are used to lif t Turbine Building Exhaust [ans for Units 1 & II.
The load J
paths of these cranes are two floors'above control panels located in the Control Room.
if a load drop from e_ither system occurs, and damage to Control Roon Panels result,coperation of the systems necessary for safe shutdown;can be continued and controlled from the remote shutdown panels
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. located in the Auxiliary Electrie, Equipment Room.,
Patented Track Crane Systems' PTS 10 & PTS 11.
Crane Systems. PTS 10 & PTS 11 are used to service the Motor Driven Reactor Feed Pumps for Units 1 & II.
The load paths of these systems will permit loads to be carried above
. the HPCS Diesel Control Panels / if,-as a result of a lead drop, the HPCS System is inoperable, the RCIC System will be used to perform the functions required,for the safe shutdown of the reactor.
_s Allof:thecraneslistedin(Table 4.1arethereforeexcludedbasedon the sepa ation and reduncanCY of safety-related equipment.
l The remaining sections, 2.3-2-B-2,'2.3-2-B-3, 2.3-2-C, 2.3-2-D-1, 2.3 l D-2, and 2.3-2-D-3,.will not'be discussed.
No reliance is placed on l'
these sections for the. elimination of any cranes carrying heavy loads in the vicinity of safety-related equipment, and therefore no discussion is required.,.
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TABLE 4.1
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CRANE SYSTEM /
TROLLEY'NO.
LOAD DESCRIPTION LOAD WT.
SAFETY RELATED EQUIP.
BLDG, LOCATION ELEVATION bb"
- 12 /1 HC29.G__ __ ___. _IIea_t_.Recov_e_ry. Coils
_2JS#
_ Control Room Panoin
- Any, J12 11 _
8 2 0 '_-- 6"__ _a 18/1Hc79c unat Recoverv Colin 7,1nne Control Room Pannin Aux _
J17-18 820'-6" B
_22/_lllC 70 G__ _ ___ __ Main Steam _Isol-Val _ _e_ _1.6,900#. Main SteattLinen (naetni
.H11 17 716*
7"
__H.,____.
v
__E_ quip _ _H<Ltch_Cov_er_iEHC)._2 4 l_1 6 #. flain._S_ttam__ Lines teactor H11-12 736'-7" B
23/lilC70G Main Steam Isol. Valve 16.900#
Main S_ tram Lines (nactnr H17 1A 71A*
7" n
EllC 24.116#
Main Steam Linen fonctnr H17 1R 736'-7" n
93/lHc30G Fuel Pool Emerg_M/UPumt 1.354#
RHR S.W.
Pumnn A ruol Any P_ T.
4 AA2*
n" n
Aux.
F-L 9
._.RHR SERV. WATER Pumn 4,177#
Pnn1 vmo rn _ M/H pumpe 662'-O" B
a
. aux.
F-L9 667'-O" n
bliC 4 567#
94/lHC20G HPCS He n r1 A pump rinm_
32.700#
HPCS Pump Ranctn
- P_c4h 673' O"
B rHe 4.442#
HPCS Pump leactor F-G 9b 673'-O" B
95/111C21G RiiR Pump Shell 10,400#
RilR Pump B teactor D9 673'-O" B
EliC 4_776#
Rilk Putno B D 9!s 673' O"
n 96/lliC22G RHR Pump Shell 10,400#
RHR Pump C
.teactor B 10 673'-O" B
EHC 4.776 RilR Pump C teactor B 10 673'-O" B
97/1HC23G RIIR pump Shell 10,400#
RiiR Pump A
- teactor F-G 14 673'-O" B
Elic 3.622#
RiiR Pump A
.teactor F-G 14 673'-O" B
98/lilC24G LPCS Pump Motor 10.400#
LPCS Pump Reactor B13-14 673'-O" B
EllC 3,627#
LPCS Pumn senctor B13-14 673'-O' B
I
TABLE 4.1 CRANE SYSTEM /
HAZ.
TROLLEY WO.
LOAD DESCRIPTION LOAD WT.
SAFETY RELATED EQUIP.
BLDG.
LOCATION ELEVATION A
- 12.7/2HC10G
. IIPCS._ Diesel Cooling _W 1 1.nnne HPcs niacal tnnling u_p. Anv LN 21 673'-O" B
HPCS Diesel Cooling W.P.
2,477#
llPCS Diesel Cooling W.P. Aux.
LN 21 673'-O
B EHC 18,400#
HPCS Diesel Cooling W.P.
Aux.
LN 21 673'-O" B
128/2HC20G HPCS Head & Pump Elem.
32,700#
HPCS Pump Reactor F -G15 673'-O" B
EHC 4,442#
IIPCS Pump Reactor F-G 15 673'-O" B
129/2HC21G RHR Pump Shell 10,400#
RilR Pump B Reactor C-D 15 673'-O" B
EHC 4,442#
RHR Pump B Reactor C-D 15 673'-O" B
130/211C22G RHR Pumo Shell 10.400#
RHR Pump C Reactor B-16 673'-O" B
EllC 4.776#
RHR Pumo C leactor B-16 673'-O" B
131/2IIC23G RHR Pump Shell 10.400#
RIIR Pumo A Reactor P-G20%
673'-O" B
EHC 3 622#
RHR Pumn A tenctnr F-G 70k 6738 41" B
132/2HC24G LPCS Pumo Motor 10.400#
LPCS Pumn teactor B 19-20 673'-O" B
EHC 3.627#
LPCS Pumn teactni n 19 70 6738-o" B
168/lllCB8G D/G Coolina Water Pump 2,477#
Diesel Gen. Cooling Wtr. Aux.
L-N 9 662'-O" B
D/G Cnnlinn Water Str.
1 800#
Pumn & Strainer Auv_
T.-N 9
662'-O" B
EHC 1R,433#
Samp An Abnve Auv.
L-N 9 662'-O" B
169/211CB9G RHR Service Water Pump 4.122#
RHR Service Water Pumps Aux.
J-L 21 662'-O" B
El{C 4,567#
C&D and Fuel Pool Emerg.
Aux.
J-L 71 667'_o" M
Pumn B
1
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T
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B B
R B
B n
B B
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6 6
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0 0
7 7
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2 S
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1 1
1 8
8 6
6 6
2 7
7 7
7 7
6 6
6 6
6 3
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8 9
9 2
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1 4
6 5
5 5
^
1 1
7 7
1 1
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1 1
1 2
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t t
t x
r x
x x
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x c
c c
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u u
u u
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a a
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A A
A A A a
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t A
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l n
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t t
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7 0
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S 9
9 B
B B
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1 1
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T_
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P P
P l
1 1l1
1 Z
B_. B_
B B
B B
B B
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n n
n B
B B B
B A
A N
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6 6
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4 4
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4 4
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6 6_
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VE 7
2 7
7 7
7 2
2 3
1 0
0 n
0 88 8
8 L
6 6
8 8
8 8
6 6
7 7
1 1
1 1
6 6
6 6
E 6
6 6
6 6
6 6
6 6
6 7
7 7
7 7
7 7
7 2
3 2
2 N
h %
- 2 1
1 O
2 2
9 9
h s
1 1
1 1
1 4
4 2
7 0
0 4
4 8
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T 2
9 1
1 2
7 7
7 1
1 1
8 6
6 A
1 1
8 8
1 C
C r
1 1
1 1
C C
1 1
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T.
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2 7
L A
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N N
N A
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G G
G N N N
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i r
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r r
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o n
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n o o
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=
t t
t t
t t
t t
DL y v x
x x
x x
x x
x c
c c
c c c c
c B
n n
u u
u u
u u
u u
a n
a a
n a a
a A A A
A A
A A
A A
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(
R R
t t
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l l
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/
n n n
n P
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P P P
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u U
n a
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n n
s i
l l
l Q
n n
n n
m r
r r
r n o o
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i i i
i r
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e e
e r r r
r h
b s
s s
s b
b e
g g g c t
t t
t D
r r
e e
e e
r r
t L
n n
n n n n n
n E
u u
n n
n n
u u
a O
a a
a a n o o
o T
T T
i i
i i
T T
W O
h h
h h C C C
C A
L L
L L
P c
c c c L
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x x
x x l
l l
l E
m m
m m
c L E
E E E e e e
e R
p p a
a a
a p
p i E n s s
s m
m e
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t t t n e e
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u u
t t
t t
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r F a
a a a i
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S S
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A e
e e e D D D
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H H
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C n n n
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C S
C C
a a a
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2 0
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3 0
0 0
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5 D
0 2
0 4
0 4
0 7
2 6
5 8
5 n
0 4 0
4 0
0 2
7 2
1 0
4 3
4 1
0 9 0
9 2
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C b p b
p i
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e e
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o n
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F S
r r
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D C_ C C C t
t b
b C
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n C
- n. C rC r
C C
A I I O
C C x
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R E
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C E C
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/
M T)
G G
G G
G G
G G
G E.
S!
7 8
9 7
2 6
6 7
8 H
0 0
B O
6 6
6 6
Y' B
SY C
C C
C C
C C
C C
E H
H H
H H
H H
H H
EL l
l 1
l 2
l 2
l 2
NL
/
/
/
/
/
/
/
/
/
AO 9
2 3
4 7
l 2
1 2
RR 7
8 8
8 8
G G
G G
CT 1
1 1
1 1
S S
D D
I
. 2.3.1.C EG&G Conclusions and Recommendations "EG&G concludes from the applicant's response that the LaSalle Nuclear Station does comply with the intent of Guideline 1.
However the applicant should clearly define the duties of supervisors / foreman with respect to heavy load-handling, particularly in regard to load paths."
LaSalle County Station Response:
Crane operators at LaSalle County Station will move heavy loads as defined by NUREG-0612 and previous CECO.
submittals under the direction of an appropriate signalman.
LaSalle County Station will revise the General Handling Procedure LMP-GM-9 to describe the job responsibility of the individual directing the heavy load movement.
4 l
l 1
l l
-. -, - ~.
-. -. +.
~-
er
. 2.3.4.C EG&G Conclusions and Recommendations "LaSalle Nuclear Station partially complies with Guideline 4.
In order to satisfactorily comply with the criteria, the applicant should perform the following:
Review, evaluate, and report more adequately on the design and fabrication of the spent-fuel shipping cask lifting yoke with respect to the requirements of ANSI N14.6-1978 and Guideline 4.
Compliance with this guideline should be complete for each lifting device before they are used in a critical situation."
LaSalle County Station Response:
The spent fuel Shipping cask lifting yoke has not been purchased at this time.
When purchased, this device will comply with ANSI-N.14.6-1978 requirements and Guideline 4 of NUREG 0612 as applicable.
l l
l I
i l
l l
.- 2.3.5.C EG&G Conclusions and Recommendations "LaSalle. Nuclear Station substantially complies with Guideline 5 of NUREG-0612.
In order to provide the load-handling reliability required to be consistent with this guideline, the applicant should implement additional precautions for hoist and cranes with hoist speeds greater than 30 fpm, including but not limited to, the following recommendations:
(a) modify hoist controls to reduce the maximum speed to less than 30 fpm; (b) restrict operational use of the hoists so that they)do not handle loads within the scope of NUREG-0612; or (c use specially marked slings which incorporate the dynamic loads imposed by the hoists."
LaSalle County Station Response:
LaSalle County' Station will revise the General Handling Procedure LMP-GM-9 to incorporate a limitation on the selection of slings used on the Reactor Building Auxiliary Hoist.
A factor of "2" will be used for the selection of slings to accommodate the dynamic load of this hoist-For example:
If a 2000 lb load is to be lifted, the sling selection will be based on a 4000 lb load (original load x 2).
i 6773N