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49
DOCKET NO. 50-263 NSPC....MONTICELLO CONTROL OF HEAVY LOADS NRC GENERIC LTR 81,07 Recdd w/1tr 9/30/81.. .8110060191 RECORDS FACILITY BRANCH - NOTICE THE ATTACHED FILES ARE OFFICIAL RECORDS OF THE DIVISION OF DOCUMENT CONTROL. THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE RETURNED TO THE RECORDS FACILITY BRANCH 016. PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE(S) FROM DOCUMENT FOR REPRODUCTION MUST BE REFERRED TO FILE PERSONNEL. QEADLINE RETURN DATE

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Page 1: Forwards partial response to Generic Ltr 81-07 re control ... · GENERIC LETTER 81-07 Item 1 ... The function of this load handling device is to assist in the assembly & ... by this

DOCKET NO. 50-263 NSPC....MONTICELLO

CONTROL OF HEAVY LOADS NRC GENERIC LTR 81,07

Recdd w/1tr 9/30/81.. .8110060191

RECORDS FACILITY BRANCH

- NOTICE THE ATTACHED FILES ARE OFFICIAL RECORDS OF THE DIVISION OF DOCUMENT CONTROL. THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE RETURNED TO THE RECORDS FACILITY BRANCH 016. PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE(S) FROM DOCUMENT FOR REPRODUCTION MUST BE REFERRED TO FILE PERSONNEL.

QEADLINE RETURN DATE

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CONTROL OF HEAVY IDADS

NIC GENERIC LETTER 81-07

NORTHERN STATES POWER COMPANY

MONTICELLO NUCLEAR GENERATING PIANT

SEPTEMBER 30, 1981

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RESPONSE 'IT REQUEST FOR INFORMATION IN SECTION. 2.1

GENERIC LETTER 81-07

Item 1 (NRC Question 2.1.1)

Report the results of your review of plant arrangements to identify all overhead handling system fran 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

A survey of the Mnticello Plant was performed to identify the overhead handling systems that fall in the category referred to in Question 2.1.1. These handling systems are listed below:

Capacity Location Handling System Main/Auxiliary ID No.

Turbine Building Turbine Building Crane 125/5 1 Reactor Buidling Reactor Building Crane 85/5 2

Item 2 (NRC Question 2.1.2)

Justify the exclusion of any overhead handling system from the above category by verifying that there is sufficient physical separation fran any load-impact point and any safety-related component to permit a determination by inspection that no heavy load drop can result in damage to any system or. component required for plant shutdown or decay heat removal.

Response

Table 1 lists the overhead handling systems which have been excluded from further oonsid ration because of capacity or physical separation from any system or com

ponent required for plant shutdown or decay heat removal. In addition the following handling systems have been eliminated fran consideration for the following reasons.

1. Reactor Recirc Pumps Monorail Motor Hoist (Capacity 32,000 lbs) ID E. 6

The function of this load handling device is to assist in the assembly & disassembly of the Reactor Recirculation Pumps during plant shutdown. This device is located in the drywell. The items handled by this handling device would typically consist of the Rx Recirc Pump Drive Motor and the individual parts of the R Recirc Pump as it is disasserbled. The potential impact item of concern is the applicable loop of of the R Recirc System. It is possible, but highly unlikely, that dropping the. Rx Recirc drive motor could rupture the recirc system piping of the loop being repaired. When this device is used to disassemble a Rx.

* Identification number (ID No) used to identify overhead handling systems in attached tables and figures.

1

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Recirc Pump the applicable pump will be isolated. It is phycially impossible to drop this heavy load and disable both Ib Recirc loops. Therefore this load handling device is eliminated because of system redundancy.

2. MSRV Drywell Monorail (Capacity 10,000 lbs) ID Nb. 14

The function of this load handling device is to assist in moving equipment, tools and other omponents from the 935' elevation in the drywell to the 948' elevation when the Rx is in a shutdown condition. Equipment typically handled by this device consists of, Main Steam Safety Relief valves, 1000 lbs, Mtor Operated Valve Components 1000 lbs and tools. In the past it has been used to lift piping and other materials used for modification projects. If a heavy load were dropped it is possible for the heavy load to impact on the A Rx Recirc loop piping and/or the A RHR injection header, the RHR shutdown cooling suction header or the B Rx Recirc loop piping and/or the B RHR loop injection header. It is not physically possible to damage both the A RK Recirc loop & A RHR injection header and the B Rx Recirc loop & B RHR injection header. If the RHR suction header were damaged an alternate shutdown cooling suction would be available through the steam line, safety relief valve and the torus.. Therefore this load handling device is elminated because of system redundancy.

3. Torus Monorail (Capacity 10,000 lbs) ID No. 15

The function of this device is to assist in maintenance activities in the torus. Ioads typically handled by this device would consist of, torus to drywell vacuum breaker valves, tools and other miscellaneous equipnent. In the past this device has been used to handle piping and structural materials used to make modifications in the torus. This load handling device is only used when the reactor is in a cold shutdown condition and if loads

.were handled that were 1000 lbs the torus would typically be drained. No component or system required for plant shutdown or decay heat removal would be affected by a load drop at that time.

4. HPCI Turbine Monorail (Capacity 8,000 lbs) ID No. 17

The function of this load handling device is to assist in the assembly and disassembly of the HPCI turbine. This device would only be used when the HNI system is not required to be operable per plant technical specifications. Any load handled by this load handling device could not impact on the redundant system to the HPCI system. The RCIC system would be available to makeup water to the Px. Therefore this load handling device has been eliminated

,because of system redundancy.

5. Torus Access Hatch Hoist & Lifting Lug (Capacity 4,000 lbs) ID No. 28

The function of this load handling device is to assist in torus maintenance activities. This device is typically used to move tools, equipment and other components into and out of the torus in support of maintenance activities. In addition it may be used in maintenance activities on motor operated valves for other systems that are located in the area above the torus. A typical load would onsist of tools, motor operated valve parts, torus to drywell vacuum breaker valves and other miscellaneous loads within the capacity of the lifting device. It is very unlikely that a load drop from this

2

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device would damage the torus to the point that the water in the torus would be lost. Typically heavy loads would only be handled by this device for torus modification when primary containment is not required and the torus is drained. N other component or system required for plant shutdown or decay heat removal is located in the area of this device.

6. Chlorine Container Monorail and Cylinder Grab (Capacity 4,000 lbs) ID No. 31

The function of this load handling device is to handle cylinders containing liquid chlorine. These containers of liquid chlorine are handled at various intervals depending on the volume used in the plant. It is very unlikely that dropping of one of. these chlorine containers would penetrate the floor of the chlorine storage room or that any spalling of the oncrete ould damage the B RHR-SW loop piping that is located in the area. In the unlikely event that the B RHR-SW loop were disabled the load drop would not damage the redundant A RHR-SW loop. Therefore load handling system has been elminated because of system redundancy.

7. Radwaste and Fuel Pool Shield Blocks Monorail (Capacity 10,000 lbs) ID No. 36

The function of this load handling device is the removal of shield blocks and the assembly and disassembly of the following components: Fuel Pool Filters (2), Radwaste Floor Drain Filter, Radwaste Equipment Drain Filter and the Radwaste Deep Bed Demineralizer. It is very unlikely that dropping one of the shield plugs would cause the load to penetrate the floors (3) separating the shield plugs fran the B Loop RHR & Core Spray systems and render these systems inoperable. In the unlikely event that this were to occur it would not disable the redundant A RHR & Core Spray loops that are located in a separate room. Therefore this load handling device has been eliminated because of system redundancy

8. "A" Turbine Floor Portable A-Frame & Monorail (Capacity 10,000 lbs) ID 1b. 44

The function of this load handling device is to assist in the assembly & disassembly of the turbine generator. This device is normally used to assemble and disassemble the turbine governor, bypass valves and the stop and control valves. No systems required for safe shutdown or decay heat removal are located below this load handling device during normal use.

9. Reactor Building Floor Drain/Equipment Drain Hatch Lifting Device (Capacity 8,000 lbs) ID N. 45

The function of this load handling device is to remove the shield block above the Rx Building Floor Drain & Equipment Drain Tanks. This device is also used for maintenance activities associated with sump pumps located in these drain tanks. This device is also used to move equipnent, tools and other components into and out of the torus area via this tank room. -loads handled by this device ould impact on system components associated with the HECI system, however, the RCIC system would be available to perform as a backup to the HICI system.. Therefore this load handling device has been eliminated from onsideration because of system redundancy.

3

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10. RCIC Pump Rom Acoass Hatch Monorail (Capacity 7,800 1bs)

The function of this load handling device is to remove the shield block above the RCIC system steam driven pump and to assist in the assembly, disassembly and the removal of various system components located in the room. This devicewould not be used to remove the shield plug and disassemble the pump unless the system was not required to be operable per the plant technical specification. If the shield plug were to be dropped and disable the RCIC system it would not disable the alternate method of water makeup to the Rx at rated pressure. The HPCI system can perform this task. Therefore this load handling device has been eliminated because of system redundancy.

11. A RHR Pump Fbom Access Hatch Lifting Lugs (4) (Capacity 7,500 lbs ea.) Id No. 54

The function of these load handling devices is to provide an attachment for portable lifting devices for the removal of the A RHR Room Shield Plug. This load handling device could also be used to assist in the assembly and disassembly of either the A & C RHR Pumps or the A Core Spray Pump which is also located in this room. Maintenance would not be performed on these pumps unless plant technical specifications permitted. In the event of a heavy load drop in this area that would disable the RHR Pumps and/or the Core Spray Pump located in the room, two redundant RHR Pumps and a redundant Core Spray Pump located in a separate roam would not be affected and are capable of performing their functions in the shutdown of the plant and subsequent decay heat removal. Therefore this load handling device is eliminated because of system redundancy.

12. B RHR Pump Rom Access Hatch Lifting Lugs (4) (Capacity 7,500 lbs ea.) ID Ib. 55

The function of these load handling devices is to provide an attachment for portable lifting devices for the removal of the B RHR Room Shield Plugs. This load handling device could also be used to assist in the assembly and disassembly of either the B & D RHR Pumps or the B Core Spray pump which is also located in this room. Maintenance would not be perfornEd on these pumps unless plant technical specifications permitted. In the event of a heavy load drop in this area that would disable the RHR Pumps and/or the Core Spray Pump located in this room, two redundant RHR Pumps and a redundant Core Spray Pump located in a separate room would not be affected and are capable of performing their functions in the shutdown of the plant and subsequent decay heat removal. Therefore this load handling device is eliminated because of system redundancy.

13. B Turbine Building Portable A-Frame & Monorail (Capacity 10,000 lbs) ID No. 61

The function of this load handling device is to assist in the assembly & disassembly of the turbine generator. This devia is normally used to assemble and disassemble the turbine governor, bypass valves and the stop and control valves. No systems or components required for safe shutdown or decay heat removal are located below this devia during normal use.

4

ID No. 53

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14. Drott Mobile Crane (Capacity 6,800 1bs) ID 1o. 62

The function of this load handling device is to assist in moving equipnent that is too heavy or awkward to handle by other methods. This device can only be used in a very limited area of the Reactor Building and in the railroad access area of the turbine building. It would be possible to transport a heavy load over the floor above the A & C RHR pumps and the A Core Spray pump or the B & D RHR and B Core Spray pumps. It is not normally used to assist in the assembly and disassembly of these system components. It would not normally be transporting a heavy load in these areas with the shield blocks removed. If it did transport a heavy load in this area it would be physically impossible to drop the load and disable both loops of these systems. The redundant loop to the disabled system would be available to perform its function in plant shutdown and decay heat removal. Therefore this load handling device has been eliminated because of system redundancy.

Item 3 (NRC Question 2.1.3)

With respect to the design and operation of heavy load handling systems in the reactor building and those load handling systems identified in the response to Question 1 above, provide your evaluation cncerning compliance with the guidelines of NURE 0612, Section 5.1.1. The following specific information should be included in the reply:

Sub Question 2.1.3a

Drawings or sketches sufficient to clearly identify the locations of safe load paths, spent fuel and safe shutdown equipment.

Response

Drawings are attached that show the location of the Reactor Core, the Spent Fuel Pool, Safe Shutdown equipment, and Safe load path.

Sub Question 2.1.3b

A discussion of measures taken to ensure that load handling operations remain within safe load paths, including procedures, if any, for deviations fran these load paths.

Response

Procedures are used to control the handling of loads by the Reactor Building Crane and the Turbine Building Crane. These procedures define the path of movement that are to be followed for each load handled by these cranes. As a part of the interim work for the control of, heavy loads, (enclosure 2 of Nuclear Regulatory Commission letter dated 22 December 1980), these procedures were reviewed and revised, .as necessary, to ensure that the load paths 'defined in the procedure were safe load paths. These procedures permit ontrolled deviations fran the specified safe load path.

5

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Sub Question 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 loads are governed by a written procedure ontaining, as a minimum, the information identified in NUREG 0612, Section 5.1.1(2).

Response

See Table II.

Procedures were prepared and or revised to meet the requirements of NUREG 0612 Section 5.1.1(2) as part of the interim actions for the control of heavy loads, (Nuclear Regulatory Commission letter dated 22 December 1980).

Sub Question 2.1.3d

Verification that the lifting devices identified in the response to Question 2.1.3c 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 reliability.

Response

a. Slings ANSI B30.9-1971

The slings used with the Reactor and Turbine Building Cranes for handling heavy loads omply with the design and inspection requirements of ANSI B30.9-1971. The slings have a minimum factor of safety of five (5) and the rated capacity of the slings used for handling heavy loads shall be taken as those listed in tables 3 through 14 of ANSI B30.9. Inspection of these lifting devices will be performed as required by ANSI B30.9-1971, per annual Hoisting Equipment and Rigging Inspection, Preventative Maintenance procedure.

b. Special Lifting Devices AMI N14.6-1978

The special lifting devices identified in Table II were manufactured as specific tools to be used to handle a specific load. These devices were manufactured prior to the existance of ANSI N14.6-1978. These special lifting devices are not used to handle loads other than the load they were designed to transport. These devices are inspected prior to each use. They have been used to transport the load they were designed to handle many times with no signs of design deficiencies. Inspection of these lifting devices will be performed per ANSI N14.6-1978 sections 5 & 6 Special Lifting Devices for Critical Loads. A procedure will be developed to cover the inspections of special lifting devices that satisfy the requirements of AISI N14.6-1978. Preparation of this procedure will begin without waiting on staff review so that implementation can occur within 2.years of information requested in section 2.4 of enclosure 3 of Nuclear Regulatory Commission letter dated 22 December 1980.

6

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Sub Question 2.1.3e

Verification that ANSI B30.2-1976, Chapter 2-2 has been invoked with respect to crane inspection, testing and maintenance. Where any exception is taken to this standard, sufficient information should be provided to denonstrate the equivalency of proposed alternatives.

Response Procedures for inspection, testing and maintenance of the cranes were reviewed and revised as appropriate as part of the Interim Actions for Control of Heavy Loads, Enclosure 2 of Nuclear Regulatory letter dated 22 December 1980, to comply with the standards of ANBI B30.2-1976, Chapter 2-2. b excepticn to the standards is taken.

Sub Question 2.1.3f

Verification that crane design complies with the quidelines of CMAA Specification 70 and Chapter 2-1 of ANSI B30.2-1976, including the demonstration of equivalency of actual design requirements, for instances where specific compliances with these standards is not provided.

Response

These guideline requirements apply to overhead and gantry type, top running, multiple girder, electric, traveling cranes. The reactor building and turbine building cranes were both manufactured prior to the issuance of these guidelines. The respective code committees have been requested to review the adequacy of the earlier codes. A response is expected by November 1981. The NC Staff will be informed of the results of this review. The reactor building crane has been modified to provide redundant lifting features for Monticello based on Regulatory Guide 1.13. The modification takes into consideration the ANSI B30.2, CMAA Specification 70 requirements and Regulatory Guide 1.104 (subsequently withdrawn). The modifications made were. found acceptable with provisions by the NRC as described in the NRC letter of May 19, 1977.

Sub Question 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 was reviewed as part of the interim actions for the control of heavy loads, Enclosure 2 of Nuclear Regulatory letter dated 22 December 1980. No exception is taken to ANSI B30.2-1976in this respect.

Attachnents:

Table I & II Figures 1-34

7

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. Table I

List of Overhead Load Handling Devias Not Considered Because of Physical Separation or Capacity

Handling Device Capacity-

Rx Building

RX Building

RX Building

RX Building

R.W. Building

R.W. Building

R.W Building

R.W. Building

O.G. Stack

R.W. Building

Turbine Building

Drywell

Refueling Facilities Channel Handling Jib Boom

Refueling Facilities Mtor Drive Jib Crane A

Refueling Facilities Motor Drive Jib Crane B

Channel Handling Overhead Rigging

Radwaste Conveyor Load-Out Monorail

Radwaste Centrifuge Hoist A

Radwaste Centrifuge Hoist B

Radwaste Building Monorail

Off Gas Stack Mnorail

Radwaste Building Sump Monorail

C Turbine Building Portable A Frame Mnorail C

MSIV Area Lifting Iug

* A Heavy Load has been defined (per NUREG 0612) as, any load carried in a given area after a plant becomes operational, that weighs more than the combined weight of a single spent fuel assembly and its associated handling tool for the specific plant in question. At Monticello Nuclear Plant this weight has been conservatively calculated to be 1500 lbs.

1

Location

50 lbs

ID No.

1500 lbs

1500 lbs

50 lbs

3

4

5

7

8

9

12000 lbs

4000 lbs

4000 lbs

6000 lbs

6000 lbs

6000 lbs

1500 lbs

1000 lbs

10

11

12

13

16

18

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Location

Drywell

Steam Chase

Steam Chase

D.G. Building

*D.G. Building

Turbine Building

Turbine Building

R.W. Building

Hot Machine Shop

H2 Storage Building

Intake Structure

Intake Structure

Turbine Building

R.W. Building

Rx Building

Turbine Building

Turbine Building

Turbine Building

Handling Device

MSIV Area Lifting Lug

MSIV Area Mnorail

MSIV Area Monorail

Diesel Generator A Mnorail, A & B Lifting lugs

Diesel Generator B Monorail, A & B Lifting Lugs

Electric Breakers Bridge Hoist Room A

Electric Breakers Bridge Hoist Room B

Radwaste Storage Bridge Crane

Hot Machine Shop Monorail

CO2 & H2 Monorail

Screen House Bridge Crane

Trash Basket Jib Crane

Tube Pulling Pit Monorail & Lifting Tug

Radwaste Capping Station bnorail

WCU Filter Shield Block Mnorail

Condensate Drain Holding Pump A Hatch Monorail

Condensate Drain Holding Pump B Hatch Mnorail

Condensate Drain Holding Pump C Hatch Monorail

2

Capacity

1000 lbs

6000 lbs

6000 lbs

470 lbs

470 lbs

1000 lbs

1000 lbs

20000 lbs

4000 lbs

4000 lbs

10000 lbs

4000 lbs

2000 lbs

1000 lbs

10000 lbs

6400 lbs

6400 lbs

6400 lbs

I.D. No.

19

20

21

22

23

24

25

26

27

29

30

32

33

34

35

37

38

39

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Location

Trbine Building

Turbine Building

R.W. Storage Bldg

Rx Building

Rx Building

R.W. Building

R.W. Building

O.G. Storage Bldg

O.G. Storage Bldg

Rx Building

Rx Building

Rx Building

Rx Building

Turbine Building

Turbine Building

Turbine Building

Handling Device

Condesnate Drain Holding Pump D Hatch Monorail

Condensate Drain Holding Pumrp E Hatch Mbnorail

New Shipping Building Crane

Rx Refueling Platform Handling Device

Reactor Vessel Service Platform

Radwaste Devices Entrance Monorail

Hot Machine Shop Jib Crane and Lifting Lug

Off Gas Storage Building Jib Crane

Off Gas Storage Building Monorails

CRD Rebuild Area Monorail

Drywell Equipment Hatch Monorail & Lifting Device

Low level Contamination Work Area Monorail

Rx Building Closed Cooling Water Heat Exchange Lifting Lugs

R Feedwater Pump A Mbnorail

Rx Feedwater Pump B Monorail

Miscellaneous Lifting Lugs

3

Capacity

6400 lbs

6400 lbs

20000 lbs

1000 lbs

1500 lbs

2000 lbs

2000 lbs

15000 lbs

1000 lbs

1000 lbs

3000 lbs

1000 lbs

6000 lbs

2000 lbs

2000 lbs

6000 lbs

I.D. No.

40

41

42

43

46

47

48

49

50

51

52

56

57

58

59

60

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Table II

Heavy Loads Handled by the Reactor & Turbine Building Crane

Crane

Turbine Bldg

Load Weight

Turbine H.P. Hood Turbine L.P. Hood A Turbine L.P. Hood B L.P. Inner Closing A L.P. Inner Closing B L.P. Rotor A & B

108,420 60,515 60,515

103,280 103,280 226,000

H.P. Rotor

Lifting 'Device

lbs lbs lbs lbs lbs; lbs

82,583 lbs

L.P. Turbine Diaphrams L.P. Turbine Diaphrams Bypass Valves Shield Block Generator Rotor Generator Endbells Exciter Hood Exciter Rotor R.F.P. Motor Condensate Punp Shield Block Condensate Pump Condensate Pmp Motor HIP Heaters HP Heaters Turbine Gen Bearing Diaphrams Palets & Miscellaneous Material

Turbine Rotor Stands

9000-12000 lbs 12000-18000 lbs

2,700 lbs; 281,832 lbs 112,000 lbs 22,000 lbs 35,000 lbs 35,000 lbs 10,800 lbs 18,600 lbs 12,900 lbs 45,100 lbs 46,900 lbs 5,580 lbs 2,000 lbs

22,400 lbs

Slings Slings Slings Slings Slings

Strongback & Slings

Strongback & Slings Slings Slings Slings Slings Slings Slings Slings Slings Slings Slings Slings Slings Slings Slings

Palet Lifting Device Slings

1

Procedure

Yes Yes Yes Yes Yes Yes

Yes

Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes

Yes

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Weight

Rx Building Vessel Service Platform Stud Detentioner Carousel

Fuel Pool Shield Blocks (3) PRV Head

Drywell Head

Fuel Pool Skiirmr Tank Shield Blocks (3) Steam Separator

Steam Dryer

Rx Head Insulation Refueling Canal Shield Spent Fuel Shipping Cask New Fuel Storage Shield Block (3) GE Model 1600 Cask Equip Storage Pool Shield Block (3) Rx Cavity Shield Block (6) Fuel Pool Shield Blocks New Fuel Shipping Container Drywell Radiation Shield RPV Head Piping Fuel Preparaticn Machine RPV Invessel Work Platform

6,000 lbs 20,000 lbs

10,000 lbs 90,000 lbs

80,000 lbs

6,000 lbs

66,000 lbs

44,000 lbs

9,000 30,000 49,464 5,000

25,950 87,000

lbs lbs lbs lbs lbs lbs

100,000 lbs 10,000 lbs 2,000 lbs

30,000 lbs 2,000 lbs

10,000 lbs 100,000 lbs

Lifting Device

Slings RPV Head Strongback Slings

RPV Head Strongback DW Head Strongback

Slings

Procedure

Yes Yes

Yes Yes

Yes

No*

Dryer Separator Yes Strongback & Slings Dryer Separator Yes Strongback & Slings

Slings Yes Slings Yes

Special Device No* Slings tb*

Special Device Yes Slings Yes

Slings Slings Slings Slings Slings Slings Slings

Yes Yes Yes Yes Yes Yes No*

* Procedures will be written.prior to the handling of these heavy loads.

2

Crane Load

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FIGURES

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-4- ..-- -

Designated Safe Load Path for GE Model 1600 Cask Procedure 8111 Rev. 1

FIG.

- - ~---.---.,------

/ ( N

RAF P&oCA

/ /

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r5~ 1-17V 11/\J1

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I

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* JTCI

Dalwta "PO -.O Ita.s

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- ____- - -1~--

Fig. --2 Designated Safe Load Path for the Removal of the Reactor Well Shield Block 5

Procedure No. 9203 Rev.4 --- -N

0OOL N.0

LIFId

L~J

'Woo

1

ZEI

1A~f.~

z~t.

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-4- - -

- -___ - --- -W-I-- -- ---- - ------- - __- -

Fig. - 3 Designated Safe Load Path for theRemoval of the Drywell Head Procedure 9207 Rev. 4

04 ____- ---- 1OO -Tr

Pu oo, so1 ot w 9tt Aug Na' per

grw*

rM e

o

69* *~A,,*b(

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/

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SUIt I9*~I OO. K > XI

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i ~ .1

I

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os~~la .M~ "0 'C~

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Page 34: Forwards partial response to Generic Ltr 81-07 re control ... · GENERIC LETTER 81-07 Item 1 ... The function of this load handling device is to assist in the assembly & ... by this

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