ML20038A662
| ML20038A662 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 10/30/1981 |
| From: | GILBERT/COMMONWEALTH, INC. (FORMERLY GILBERT ASSOCIAT |
| To: | |
| Shared Package | |
| ML20038A658 | List: |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR 2364, NUDOCS 8111160127 | |
| Download: ML20038A662 (101) | |
Text
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VIRGIL C. SUMMER NUCLEAR STATION UNIT 1
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O GAI REPORT 2364 CONTROL OF HEAVY LOADS AT VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 October 30, 1981 O
PPEPARED BY GILBERT ASSOCIATES, INC.
READING, PENNSYLVANIA O
Gibert /Commonwea@
TABLE OF CONTENTS Section Title Page
1.0 INTRODUCTION
1-1 2.0
SUMMARY
2-1 3.0 IDENTIFICATION OF OVEREEAD HANDLING DEVICES 3-1 4.0 CODES AND STANDARD COMPLIANCE 4-1 i
4.1 Crane Design 4-1 4.2 Lifting Devices 4-1 4.3 Inspection, Testing, and Maintenance 4-1 4.4 Crane Operator Training 4-4 5.0 PROCEDURES 5 -1 APPENDIX A STRUCTURAL ANALYSIS OF DROPPED HEAVY LOADS APPENDIX B WESTINGHOUSE ANALYSIS OF THE REACTOR BUILDING LIST OF TABLES Table 1-1 OVERHEAD HANDLING DEVICES, VIRGIL C. SUMMER 1-4 NUCLEAR STATION Table 3-1 HEAVY LOADS VS. IMPACT AREA 3-38 LIST OF FIGURES No.
Title 1
Site Plan 2
Plan at Elevations 374'-0", 388'-0", and 400'-0" 3
Plan at Elevation 412'-0" 4
Plan at Elevation 436'-0" 5
Plan at Elevation 463'-0" l
6 Plan at Elevations 485'-0", 482'-0", and 552'-0" 7
General Section A-A - Looking West 8
Service Water Pump House 9
Turbine Building - Plan at Elevation 412'-0" 10 Turbine Building - Plan at Elevation 436'-0" 11 Turbine Building - Plan at Elevation 463'-0" O
Qtet / Common *wth i
1.0 INTRODUCTION
This report responds to a request by the Nuclear Regulatory Commission (NRC) to all Licensees of Operating Plants, Applicants for Operating Licenses, and Holders of Construction Permits to review their controls for the handling of heavy loads to determine the extent to which their facilities satisfy the recommendations as reported in NUREG-0612 " Control of Heavy Loads at Nuclear Power Plants."
l The procedures to implement the recommendations of NUREG-0612 were outlined in enclosures that accompanied a letter dated December 22, 1980, by Darrell G. Eisenhut.
This letter requires a report, with information submitted at a six-month and a nine-month interval.
The six-month submittal responded to the identification of the extent of potentially hazardous load-handling operations at a site and the extent of conformance to appropriate load-handling guidance. The nine-month submittal responds to the requirement of demonstrating that adequate measures have been taken to ensure that the likelihood of a load drop which might cause damage to either fuel or components necessary for safe shutdown or decay heat removal is extremely small; cr that the estimated consequences of such a load drop will not exceed the limits set by the evaluation criteria of NUREG-0612.
The review that is addressed in this report follows the guidelines as set forth in Darrell G. Eisenhut's December 22, 1980 letter,, and Section 5 of NUREG-0612. The guidelines that are outlined in these references, and followed in this report, require the evaluation of overhead handling systems that handle heavy loads.
A heavy load is defined as a load heavier than a spent fuel assembly and its associated handling tool.
At the Virgil C. Summer Nuclear O
G&t/Cownonweae 1-1
Station, this is defined as a load greater than 2500 pounds.
The guidelines for this report are:
a.
Identify all overhead handling devices from which a load drop could cause damage to fuel or components necessary for safe shutdown or decay heat removal.
b.
Justify the exclusion of any overhead handling device that handles heavy loads by verifying that it is a single-failure p roof handling system or that there is sufficient physical separation from the point of impact and any component necessary for safe shutdown, decay heat removal, or spent fuel storage and fuel in the reactor vessel.
c.
Demonstrate, by analysis, that any overhead handling device not excluded in item b. adheres to Criteria I, II, III, and IV as outlined in Section 5.1 of NUREG-0612.
O d.
Define safe load paths and procedures for the handling of heavy loads to minimize the possibility of the impact of a heavy load dropped onto spent fuel storage racks, spent fuel in the reactor vessel, safe shutdown equipment, or decay heat removal equipment.
Verify degree to which overhead lifting devices comply with e.
either ANSI B30.9-1971, Slings, or ANSI N14.6-1978, Standard for Special Lifting Devices for Shipping Containers Weighing l
10,000 Pounds or More for Nuclear Material.
l l
f.
Verify cranes are designed according to CMAA Specification 70 and ANSI B30.2-1976, Overhead and Gantry Cranes, Chapter 2-1.
g.
Verify cranes are inspected, tested, and maintained in accordance with ANSI D30.2-1976, Overhead and Gantry Cranes, Chapter 2-2.
G.; tert /Commo. weeith a
1-2 1
h.
Review crane operators' training, qualifications, and conduct in reference to ANSI B30.2-1976, Overhead and Gantry Cranes, Chapter 2-3.
s Table 1-1 lists the general information for each overhead handling device at the Virgil C. Summer Nuclear Station.
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lleavy 1.oails llanilleil I.o ail Figure Crane I.D.
Crane Tylie anil I.ilting Device Weight No.
l.ocation XCit-1 Itcactor Cavity Spent anil New Fuel 2500 llis 5,6,67 463' el.
tlanignalator Crane Assemlily anil llanilling Iteactor Tool flui bli ng Sunt Fuel Assemlity 2500 lies 5&7 463' el. Fuel XCit-2 Spent fuel Pit l
& XCit-16 lir iilge Crane anil llanilling Tool lla nill i ng lini lili ng i
p XCit-3,
Fuel llanilling a)
New Fuel Shipping 6600 llis 5&7 463' el. Fuel i
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XCIt-45, &
Iloi lilini, Crane Container anil llanill i ng i
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Spent Fuel (later) s Shipping Cask anil Venilo r-Su pp l i cil J
Lilting Device c)
Fuel Transfer 4500 llis Canal Gates anil 2 Part Sling Cable
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I r raili a t eil (later)
Specimen Shi> ping 1
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O TAllt.E l-1 (Con t ' al) lleavy 1.oatts llamileil 1.oail Figure Crane 1.D.
Crane Type anal I.ilting Device Wj ght No.
l.oca t i on XCR-18 10-ten Electric Power Plant E<guipment f.e s s than 4
436' el.
Cable lloist ami max. capacity Auxiliary Trolley (2 & 3) llu i lili ng XCR-19 7.5-ton Elect ric Power Plant E<inipment 1.e s s than 6
485' el.
Cable lloist anal max. capacity Auxiliary Troiley (2,3,4, llu i lili ng
& 5)
XCR-20A &
5-ton llamt Chain a)
RilR Pumps 4400 lbs 2
374' el.
XCR-20B lloist amt Trolley Iv)
RilR Pump flotor 3200 lbs Auxiliary g
3 tha i lit i ng
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XCR-21A 5-ton tlanual Chain a)
Ril Spray Pumps 5400 lbs 2
374' el.
& XCR-21B llo i s t an41 Trolley b)
Rii Spray Pump 5880 lbs Auxi1iary s
tio t o rs llu i lili ng XCR-54A, 5-ton flanual Si Charging Pumps 2
388' el.
XCR-54!! &
Chain iloist ami a)
Pump 7500 lbs Auxiliary XCR-54C Trolley b)
Hase 6000 lbs Buililing c)
Gear 2l00 lbs it) tiotor 6700 lbs XCR-23A 2-ton flanua 1 a)
Ril Spray Sump 3000 1hs 3
412' e1.
& XCR-23B Chain iloist a nal isolation Valve Auxiliary Trolley Protective Itu i lili ng Chamber Tops b)
S1 Recirculation 3000 lbs Sumps isolation Valves Protective Chamber Tops
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TAllLE l-1 (Cont'd)
L lleavy Loads llandled Load Figure Crane 1.D.
Crane Type and Litting Device Wj ght No.
Location XCR-24 8-ton lland Chain Hain Steam Stop Valves Less than 11 463' el.
l Iloist and Trolley max, capacity Turbine lluilding XCR-25A, 10-ton lland Main Condenser 26,500 lbs 9
412' el.
i XCR-2511, lloist and Trolley Water Boxes (2 Cranes Turbine XCR-25C, &
per Water Box) finilding XCR-25D
)
XCR-26 4-ton lland Chain Feedwater Booster 9
412' el.
Turbine lloist and Trolley Pumps a)
Pump 7800 lbs Building p
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Driver 8500 lbs j
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Bedplate 5900 lbs XCR-27 5-ton Electric Power Plant Equipment Less than 4
436' el.
Cable lloist and max. capacity Intermediate Trolley BuiIding i
i XCR-28 2-ton Electric Chemical Storage Less than 1
Water Cable lloist and Containers max. capeity Treatment Trolley Building l
XCR-29A, 2-ton lland-Generator Parts Less than 4
Diesel 4
XCR-29B Operated lloist max. capacity Gene ra t o r and Trolley Building XCR-31 1/2-ton lland Under heavy load N/A 4
436' el.
Chain iloist and limit I n t e rnedia te Trolley Building
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TAllLE l-1 (Cont'd)
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lleavy Loads llandleil Load Figure Crane I.D.
Crane Type and Litting Device Weiglt_
No.
I,ocation 3
XCR-33 2-ton Iland Chains Turbine-Driven 3
412' el.
lloist and Trolley Emergency Intermediate l
Feedwater Pump llu i l d i ng a)
Pump 3000 lbs i
b) llase 2400 lbs j
c)
Driver 3260 lbs 4
i XCR-34 1-ton Electric Under heavy load N/A 4
Reactor l
Cable lloist and limit fluilding i
Trolley Tendon Access e
Gallery Tk m !5 XCR-36 20-ton Electric Radwaste Facility Less than 4
436' cl.
f Cable lloist and E<1uipment max. capacity Drumming Trolley Station i
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XCR-40A, 10-ton lland Chain fla in Steam Less than 4
436' e'..
XCR-408, lloists and I sol at i<,a Va lves max. capacitv I n t e ri..ed i a t e XCR-40C TrolIeys BuiIding i
XCR-42 10-ton Bridge llot flachine Shop Less than 4
Ilot
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Crane Applications max. capeity fla ch i ne Shop XCR-43 10-ton Ilridge Service lluilding 1.e s s than 1
Service C rane Applications max. capacity Building l
XCR-46 3-ton Bridge a) Concrete Plugs 1770 lbs 5
463' el.
Crane b) Filters and Negligible Aux i l i a ry Cartridges llu i ld i ng c) Storage Casks 2590 lbs i
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O TABl.E 1-1 (Cont'd) llcavy I.oads liainiled 1.oa d Figure Crane I.D.
Crane Type and 1.ifting Device Weight No.
l.ocation XCR-47 10-ton Bridge llot flachine Shop and I.ess than 4
436' & 447' C rane I.ow I.evel Waste max. capacity el. Drununing Storage Station XCR-48 1-1/2-ton lland Instrument and I.e s s than 9
412' el.
Chain lloist and Service Air max. capacity Turbine Trolley Compressors Building XCR-51 &
10-ton Bridge a)
Service Water I.ess than 8
436' el.
XCR-50 Crane and lloist-Traveling Screen max. capacity Service Water Parts Intake Screen
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b)
Service Water 14,000 and Paunphouse Pump lbs
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Service Water 15,650 g
Pump Motor Ibs
- s XCR-53A, 2-ton Twin llook CRDM Cable Support N/A 5
475' el.
XCR-53B, Extension lloists Structures Reactor XCR-53C Bui1 ding XRW-11 1-ton Jib Crane Under heavy load N/A 4
436' el.
1imit Drumming Station XRW-13 3-ton Jib Crane a) Concrete Plugs 1770 lbs 4
436' el.
b) Spent Filters Negligible D raumuing and Cart ridges Station c) Storage Casks 2590 lbs d) 1.i f ting Beam 1350 lbs Reactor lluilding Equipment N/A 5
463' el.
Equipment Access llatch Reactor llatch Door Building
2.0 SLTiARY O
This report presents the results of the study of areas in the Virgil C. Summer Nuclear Station where an inadverdant drop of a heavy load from an overhead handling device could cause damage to components necessary for the plant's safe shutdown or decay heat removal.
Areas where an inadverdent drop could cause a radioactive release that could result in significant offsite doses were also includem.
The study has shown that the Virgil C. Summer Nuclear Station layout does not present a significant number of potential problems due to the handling of heavy loads with overhead handling devices.
Safe load paths have been identified for each crane or hoist, where physically possible, to minimize the chances of an inadvertent heavy load drop and its consequences. The safe load paths will be permanently marked, where practical. Riggers and operators receive training to fully understand and adhere *.o the safe load path concept.
In addition to the safe load paths, special operating procedures are being prepared for overhead handling devices in the plant and where possible, incorporated into standard component maintenance procedures to define the handling of heavy loads by cranes and hoists.
These procedures are being incorporated into the plant's operator and l
rigger training program.
O Gibert / Commonwealth 2-1 L
3.0 IDENTIFICATION OF 0\\ERHEAD HANDLING DEVICES O
This study documents the review of overhead handling devices at the Virgil C. Summer Nuclear Station that can handle a heavy load, defined as any load heavier than a spent fuel assembly and its handling tool.
The following sections are descriptions of each overhead handling device, crane, and hoist at the Virgil C. Summer Nuclear Station.
Each overhead handling device has been reviewed, and each individual description includes the type of crane or hoist being reviewed, the type of handling device being employed, and the items that the device was designed and designated to handle.
The Virgil C. Summer Nuclear Station was then reviewed, in reference to the overhead handling devices, by a physical inspection of the plant and by studying the up-to-date layout drawings.
The various overhead handling devices are shown on Figures 1 through 11.
The figures indicate each uandling device's proximity to any components necessary for safe shutdown or decay heat removal, and to any area were an inadvertent drop of a heavy load may cause a radioactive release, such as the spent fuel pool or reactor vessel.
The safe shutdown and decay heat removal components considered in this study does not include piping, valves, and electric cable.
A safe load path for every overhead handling device is defined where physically possible to do so.
When a crane or hoist is operated within the confines of its defined safe load path, it would be unlikely that an inadvertent drop of a heavy load would cause damage to any component necessary for the safe shutdown of the plant, decay heat removal, or fall into an area that could cause a radioactive release. The safe load path is then de:ised as an area within the crane's or hoist's range where none of the above components are located.
The only exceptions are those necessary components serviced uniquely by a crane or hoist for maintenance.
The overhead handling device will not be operated until after these components have been Gutet /CommonweaV 3-1
isolated from their system and after their function has been assumed by a redundant component.
In areas where the only separation between a dropped heavy load and an item that needs to be protected is a structural floor, a study has been conducted according to item 2, Section 5.1.5 of NUREG-0612 and Attachment 4 to Enclosure 3 of D.G. Eisenhut's December 22, 1980 letter, in order to demonstrate compliance to Criteria III and IV of Section 5.1 of NUREG-0612.
The results and evaluation of this study are presented in Appendix A.
Safe load paths for some cranes and hoists could not be defined.
In those cases procedures will be drawn up and design mod: fications will be made where necessary to minimize the chances and the consequences of an inadvertent load drop.
Procedures for overhead handling devices are being developed to dictate the operation and use of the device.
It should be recognized that because of the construction i
stage of the Virgil C. Summer Nuclear Station, procedures are not generally available at this time.
O Table 3-1 lists the impact area, the designated heavy loads and weights for each overhead handling device, and the safe shutdown / decay heat removal equipment that could be effected for each overhead device.
Table 3-1 also lists a hazard elimination category, which according to Enclosure 3, Figure 1 of D. G. Eisenhut's December 22, 1980 letter are:
r a.
Crane travel for this area / load combination prohibited by electrical interlocks or mechanical stops, b.
System redundancy and separation precludes loss of capability of system to perform its safety-related function following load drop in this area, c.
Site-specific considerations eliminate the need to consider equipment combination, O
Geert / Common
- eau 3-2
d.
Likelihood of handling system failure for this load is extremely small (i.e., Section 5.1.6 NUREG 0612 satis fied), and e.
Analysis demonstrates that crane failure and load drap will not damage safety-related equipment.
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3.1 Reactor Cavity Manipulator Crane
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Reactor Cavity Manipulator Crane XCR-1 is located on elevation 463' directly above the reactor vessel cavity.
There is no safe load path that can be defined for this crane.
The Reactor Cavity Manipulator Crane is shown on Figures 5, 6, and 7.
The Reactor Cavity Manipulator Crane is supplied by the Stearns and Rogers Corporation for Westinghouse Electric Corporation.
The bridge crane is supplied by Dwight Foote, Inc. and the hoist by P&H Harnischfeger Company.
The hoist and crane have a 2 ton capacity and utilize a handling tool to handle the new and spent fuel assemblies.
The crane is an electric motorized bridge crane, and the hoist is an electric cable hoist.
Both the crane and hoist are operated from a remote station. The crane and hoist are both designed in accordance with CMAA Specification 70 and ANSI B30.2, Chapter 2-1.
(}
The Reactor Cavity Manipulator Crane is designated solely for the handling of fuel assemblies during refueling of the reactor.
Crane operation is governed by Westinghouse Refueling Procedures which are being put into an approved standardized format at this time.
By definition of a heavy load, this overhead handling device does not handlr heavy loads and can be excluded from further study or concern.
O G.uwt /Commonweau 3-4
o 3.2 Spent Fuel Pool Bridge Crane O-The Spent Fuel Pool Bridge Crane is XCR-2.
Attached to it is the Protex Cable Reel XCR-16, which is excluded from further study since its maximum capacity is well under the heavy load criteria. This crane is located on elevation 463' of the Fuel Handling Building between column lines Q.5 to R.5 and 2.5 to 6.5 directly over the Spent Fuel Pool. The crane is shown on Figure 5 and 7.
No safe load path is defined for this crane.
Crane XCR-2 is supplied by Dwight Foote, Inc. through Westinghouse Electric Corporation. The crane's hoist is supplied by the P&H Harnischfeger Company. The crane and hoist are rated for a 2 ton capacity and has a maximum 25 foot lift.1 The hoist is an electric cable hoist on a hand geared trolley with a safety hook that attaches to a fuel handling tool when handling spent fuel assemblies. The crane and hoist are controlled by a hand-held pushbutton station.
The crane and hoist design adheres to CMAA Specification 70 and ANSI B30.2, Chapter 2-1.
The Spent Fuel Pool Crane is designated for the handling of spent fuel assemblies in the Spent Fuel Pool.
Since it operates over the Spent Fuel Pool, there is no safe load path defined for this crane.
The operation of this crane and hoist are governed by the Westinghouse Refueling Procedures which are currently being reviewed and placed into a standard format.
By definition of a heavy load, this overhead handling device does not handle heavy loads and can be excluded from further study or concern.
1.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or less than this
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maximum.
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3.3 Fuel Handling Building Crane Fuel Handling Building Crane XCR-3 has associated with it Fuel Transfer Canal Gate Hoist XCR-49 and the New Fuel Elevator Winch, XCR-45.
The New Fuel Elevator Winch is not considered further since by definition it is not an overhead handling device.
All three items are located in the Fuel Handling Building on elevation 463' between column lines Q.5 to S and 2.5 to 4.91.
The three items are shown on Figures 5 and 7, along with the safe load path which includes the New Fuel Laydown Area, New Fuel Storage Area, the Decontamination Area, and the Cask Loading Pit and surrounding area.
The Fuel Handling Building Crane's safe load path does not include any area within 15 feet of the Spent Fuel Pool.
The Fuel Handling Building Crane is supplied by the Whiting Corporation and the Fuel Transfer Canal Gate Hoist is supplied by the American Chain and Cable Company.
The Fuel Handling Building Crane has a main electric motor cable hoist with a 125 ton capacity, a
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sister hook with eye, and a potential for a 60 foot lift. The auxiliary electric motor cable hoist has a 25 ton capacity, a single hook, and a potential lift of 60 feet 6 inches.
The Fuel Transfer Canal Gate Hoist is physically attached to the bridge of the Fuel Handling Building Crane and is a 3 ton capacity electric cable hoist.
The assembly as a whole is designed in accordance with CMAA Specification 70 and ANSI B30.2, Chapter 2-1.
1.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or less than this maximum.
Gabert /Commonwean.h 3-6 l
The Fuel Handling Building Crane is designated to handle New Fuel Shipping Containers, Spent Fuel Shipping Casks and I; radiated Specimen Shipping Casks with vendor-supplied lifting devices.
The Fuel Handling Building Crane does not carry a heavy load within an area or near any equipment necessary for the plant's safe shutdown or decay heat removal.
Between column lines Q.5 and R.6 (Figure 5) it is possible for the Fuel Handling Building Crane to operate within 15 feet of the Spent Fuel Pool while handling a heavy load.
The Fuel Transfer Canal Gate Hoist is designated to handle the Fuel Transfer Canal Gates with a two-point sling cable.
Procedures are being developed (See Section 4.0) to minimize the risk of a dropped heavy load in the Fuel Handling Building.
Special procedures are also being developed for the Fuel Transfer Canal Gate Hoist since it is necessary to cperate within 15 feet of the Spent Fuel Pool.
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3.4 Reactor Building Polar Crane i
l' Reactor Building Polar Crane XCR-4 is located in the Reactor Building at elevation 552' The Reactor Building Polar Crane and safe load paths are shown on Figures 5, 6, and 7.
The Reactor Building Polar Crane is supplied by the Whiting Cerporation and has a main electric motor cable hoist rated at 360 ton with a sister hook with eye.
The auxiliary electric motor cable hoist has a 25 ton capacity with a single hook.
The hoists, bridge, and trolleys all have separate Whiting Telemotive radio control with redundant pushbutton station.
The Reactor Building Polar Crane is designed in accordance with CMAA Specification 70 and ANSI B30.2, Chapter 2-1.
The Reactor Building Polar Crane is designed to handle the loads listed in Tables 1-1 and 3-1.
As shown in Figure 5, safe load paths are identified where the Reactor Building Polar Crane can be operated
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without danger of damage to vital components due to an inadvertent load drop.
The vital components in the Reactor Building are the:
a.
Reactor Vessel, XRE-1-RC.
b.
Steam Generator, XSG-2A,B-RC.
c.
Pressurizer, XTK-24-RC.
d.
Reactor Building Cooling Units, XAA-1A,B-AH and XAA-2A,B-AH.
Reactor Building Cooling Unit Fans, XEN-64A,B-AH and e.
XFN-65A,B-AH.
f.
Reactor Building Cooling Unit Cooling Coil, XCE-8A,B-AH and XCE-8A,B-AH.
The Reactor Building cooling unit assemblies are necessary for the plant's safe shutdown.
However, the Reactor Building Polar Crane only operates during cold shutdown and would not jeopardize the cooling unit assemblies when their operation is necessary. A
()
Westinghouse study has shown that effects of a dropped heavy load Gdbert / Common *ue 3-8
would not result in damage to the reactor vessel, reactor pressure
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vessel, and reactor coolant system piping pressure boundary, crre cooling capability, or integrity of the fuel cladding such as to exceed Criteria I through IV of Section 5.1.1 of NUREG 0612. The procedures used by Westinghouse in this analysis are presented in Appendix B.
Westinghouse suggestions from Appendix B will be incorporated into the plant operating procedures being developed.
O I
i I
Geert / Common *eso 3-9
3.5 Turbine Building Crane Turbine Building Crane XCR-17 is located on elevation 463' of the Turbine Building.
The crane is shown on Figures 7 and 11 along with its safe load path.
The safe load path encompasses the entire 463' elevation of the Turbine Building between column lines 1 and 12, and A and F, as well as those areas on elevation 436' open to hatches from the 463' elevation as shown in Figure 10.
The Turbine Building Crane is supplied by P&H Harnischfeger Corporation, and is a 220 ton, five motor everhead traveling crane with a 30 ton, 6 inch auxiliary hoist. The main hoist has a 95 foot lift and the auxiliary hoist a 111 foot lift.1 The crane is operated through an operator's cab or pendant control and has a festoon conductor on the trolley. The crane's main hoist employs a sister hook and the auxiliary hoist employs a fish hook rated as stated above. The crane and associated hoists are designed in accordance with CMAA Specification 70 for Class A indoor service and ANSI B30.2, Chapter 2-1.
The Turbine Building Crane is designed to service the General Electric Turbine Generator and Associated Power Plant Equipment.
Since there is no equipment in the Turbine Building required for safe shutdown or decay heat removal, this crane can be excluded from further study or concerns.
l l
l 1.
The lift as given is the maximum from the eye of the hook to the top of the beam; t-actual lift as installed may be equal or less than this maximum.
O l
Geibed /Commonwea@
3-10
3.6 10-Ton Electric Cable Hoist and Motor Operated Trolley The 10-ton electric cable hoist and motor operated trolley XCR-18 is located on elevation 436' of the Auxiliary Building between column lines 9.5 and L.
The hoist is shown on Figure 4 and its safe load path is the equipment batch and surrounding area through elevations 436 ', 412 ', 397 ', 388 ', and 374 ' of the Aaxili a ry Building.
The safe load path is shown of Figures 2, 3,
.nd 4.
hoist XCR-18 is supplied by the American Chain and Cable Company and is a 10-ton capacity electric cable hoist with a motor driven trolley.
The hoist has a 90 foot lift and is controlled with a single speed hand held controller.1 The hoist's lifting device is a forged steel shank hook. The hoist and trolley are designed in accordance with CMAA Specification 70 for Class A and C indoor s e rvice, and ANSI B30.2, Chapter 2-1 to the extent to which they apply.
O The 10-ton electric cable hoist is designated to lift power plant equipment through the equipment hatch from elevations 372' to 436' of the Auxiliary Building.
Inside tne safeload path and in the nearby surrounding area there is no equipment necessary for safe shutdown or decay heat removal.
Therefore, the hoist is excluded from further atudy and concerns.
i i
l i
1.
The lift as given is the maximum from the eye of the hook to the top of l
the beam; the actual lift as installed may be equal or less than this i
maximum.
1 O
(
GJbert / Commonwealth 3-11 L
3.7 7.5-Ton Electric Cable Hoist with Motor Operated Trolley The 7.5-ton electric cable hoist and motor operated trolley XCR-19 is located on elevation 485' of the Auxiliary Building between columns P and 6.6.
The hoist is shown on Figure 6, and its safe load path is the equipment hatch through elevations 388', 397', 412', 436', 463',
and 485' of the Auxiliary Building as shown on Figures 2, 3, 4, 5, and 6.
2 Hoist XCR-19 is supplied by the American Chain and Cable Company and is a 7.5-ton capacity electric cable hoist with a motor driven trolley. The hoist has 126 foot lift and is controlled by a hand-held controller.
The hoist's lifting device is a forged steel shank hook.
The hoist and trolley are designed in accordance with CMAA Specification 70 for Class A and C indoor service, and ANSI B30.2, Chapter 2-1 to the extent to which they apply.
The 7.5-ton electric cable hoist is designated to lift general power plant equipment through the equipment hatch from elevations 388' to 485' of the Auxiliary Building.
Inside the safeload path and in the nearby surrounding area there is no equipment necessary for safe shutdown or decay heat remeval.
The hoist is excluded from further study or concerns.
1.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or less than this maximum.
O L
m m _.o 3-12
3.8 5-Ton Hand Chain Hoist and Plain Trollev
~
C)
The 5-ton chain hoists and trolleys XCR-20A and XCR-20B are located in Auxiliary Building on elevation 374' between the column lines K and 8.8 above the Residual Heat Removal Pumps. The hoists are shown on Figure 2 along with their safe load paths.
Hoists XCR-20A and XCR-20B are supplied by the American Chain and Cable Company and are 5-ton capacity hand operated chain hoists with a plain trolley. The hoists have 20 foot lifts and forged steel shank hooks.1 The hoists and trolleys are designed in accordance with CMAA Specification 70 for Class A and C indoor service, and ANS1 B30.2, Chapter 2-1 to the extent to which they apply.
The 5 ton hand chain hoists and plain trolleys XCR-20A and XCR-20B are designated to service the RHR pumps and motors, XPP-31A and XPP-31B, respectively.
The RHR pumps necessary for the removal of decay heat are located within the safe load paths of hoists and trolleys XCR-20A and XCR-20B. While a heavy load drop from the hoists could cause damage to the RHR pumps the only time this would cccur is when the pump in question would have maintenance being performed on it.
During maintenance periods on an RHR pump, the pump would be isolated from its systems and replaced by a redundant unit.
On this basis it can be excluded from further study or concern.
t i
l 1.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or less than this maximum.
l G.ibert / Commonwealth 3-13 l
L
3.9 5-Ton Manual Chain Hoist with Geared Trolley The 5-ton manual chain hoists and geared trolleys XCR-21A and XCR-21B are located in the Auxiliary Building on elevation 374' near column lines K and 8.8 above the Reactor Building Spray Pumps. The hoists and trolleys are shown on Figure 2 along with their safe load paths.
Hoists XCR-21A and XCR-21B are supplied by the American Chain and Cable Company r.nd are 5-ton capacity hand-operated chain hoists on geared trolleys.
The hoists have a 20 foot lift with forged steel shank hooks.
The hoists and trolleys are designed in accordance with CMAA Specification 70 for Class A and C indoor service and ANSI B30.2, Chapter 2-2 to the extent to which they apply.
Hoists XCR-21A and XCR-21B are designated to service the Reactor Building Spray Pumps XPP-38A and XPP-38B and associated motors MPP-38A and MPP-38B.
Within the safe load paths of hoists XCR-21A and XCR-21B there are no components necessary for safe shutdown or
(}
decay heat removal, so these hoists are excluded from further study.
1 I'.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or less than this maximum.
O GJbert(Common ea:tn 3-14
3.10 5-Ton Manual Chain Hoist with Geared Trolley O
i The 5-ton manual chain hoists with geared trolleys XCR-54A, XCR-54B, and XCR-54C are located in the Auxiliary Building on elevation 388' at the column lines M to Q and 7.7 above the Safety Injection Charging Pumps. The hoists and trolleys are shown on Figure 2 along with their safe load paths.
Hoists XCR-54A, XCR-54B, and XCR-54C are supplied by the American Chain and Cable Company, and are 5-ton capacity, closehead room, hand operated chain hoists on geared trolleys. The hoists have an 8 foot lift with a forged steel shank hook.I The hoists and trolleys are designed in accordance with CMAA Epecification 70 for Class A and C indoor service and ANSI B30.2, Chapter 2-1 to the extent to which they are applied.
Hoists XCR-54A, XCR-54B, and XCR-54C are designated to service Safety Injection Charging Pumps XPP-43A, XPP-43B, and XPP-43C.
Inside and near the safe load paths, the Safety Injection Charging Pumps are the only components necessary for the safe shutdown of the plant.
The only time a heavyload drop could cause damage to the pumps is when the pumps are being serviced.
While they are being serviced, the pumps are isolated from their systems and are replaced by a redundant unit. On this basis hoists XCR-54A, XCR-54B, and XCR-54C are excluded from any further study or concerns.
i 1.
The lift.is given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or less than this maximum.
O i
G.itert /#mmonwut:n 3-15 i
i - - - - - - -..
,_,_m..
()
3.11 2-Ton Manual Chain Hoist with Plain Trolley The 2-ton manual chain hoists with plain trolleys XCR-23A and XCR-23B are located in the Auxiliary Building on elevation 412' at column lines J to N and 7.7.
The hoists and trolleys are shown on Figure 3 along with its safe load paths.
Hoists XCR-23A and XCR-23B are supplied by the American Chain and Cable Company, and are 2-ton capacity hand operated chain hoists on plain trolleys.
The hoists have a 26 foot lift and a forged steel shank hook.I The hoists and trolleys are designed in accordance with CMAA Specification 70 for Class A and C indoor service and ANSI B30.2, Chapter 2-2 to the extent to which they are applicable.
Heists XCR-23A and XCR-23B are designated to service the Reactor Building Spray Protective Sump Isolation Valve Chambers XSM-4A and XSM-4B, and the Safety Injection Recirculation Sump Isolation Valve
()
Protection Chambers XSM-5A and XSM-5B.
Since the sump isolation valves and associated piping do not normally contain radioactive materiel, a dropped heavy load on the isolation valve and chamber while servicing an adjacent chamber will not result in a radioactive release.
The only time the sump isolation valves and associated piping would contain radioactive fluid would be under post-accident condition, where service to the valves would not be possible, or allowed by procedures, and the hoist would not be allowed to operate.
Near hoist XCR-23B is a Motor Control Center XMC-1DAZY and an Air Handling Unit for Motor Control Center XAH-32-VL, both of which are necessary for the safe shutdown of the plant. Neither the Motor Control Center nor the Air Handling Unit for the Motor Control Center lie within the safe load path of XCR-23B, and normal operating procedures and separation distance would preclude any damage from a dropped load to either item.
O 1.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or less than this maximum.
CWbert / Common
- eau 3-16
3.12 8-Ton Manual Hand Chain Hoist with Geared Trolley l
The 8-ton manual chain hoist with geared trolley XCR-24 is located in the Turbine Building on elevation 463' at column lines F and 4 to 5.
The hoist and trolley are shown on Figure 11 along with their safe 1
load paths.
1 Hoist XCR-24 is supplied by the American Chain and Cable Company, and is an 8 ton capacity hand operated chain hoist with a geared trolley.
The hoist has a 20 foot lift and a forged steel shank hook.I The l
hoist and trolley are designed in accordance with CMAA l
Specificacion 70 for Class A and C indoor service and ANSI B30.2, i
Chapter 2-1 to the extent to which they are applicable.
Hoist XCR-24 is designated to service the Main Steam Stop Valves XVG-2809 A to D.
Since the Turbine Building contains no equipment necessary for the plant's safe shutdown or decay heat removal, this hoist can be excluded from further study or concern.
I 1.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or less than this maximum.
O 3-17
i 3.13 10-Ton Manual Chain Hoist with Geared Troiley
(}
i The four 10-ton manual chain hoists and geared trolleys XCR-25A, XCR-25B, XCR-25C, and XCR-25D are located on elevation 412' of the Turbine Building between column lines B to B.9 and 5 to 8.
The hoists and trolleys are shown on Figure 9 along with their safe load paths.
Hoists XCR-25A thru XCR-25D are manufactured by the American Chain and Cable Compan/ and are 10 ton capacity hand operated chain hoists on geared trolleys.
The hoists have 15 foot lif ts and forged steel shank hooks.
The hoists and trolleys are designed in accordance with CMAA Specification 70 for Class A and C indoor and outdoor service and ANSI B30.2, Chapter 2-1 to the extent to which they i
apply.
Hoists XCR-25A thru XCR-25D are designated to service the four Main Condenser Water Boxes.
Two hoists service one water box at a time.
(}
Since the Turbine Building contains no equipment necessary fbr the plant's safe shutdown or decay heat removal, these hoists can be excluded from further study or concern.
l i
i i
l l
l i
1.
The lift as given is the maximum from the eye of the hook to the top of the be_am: th.e. actual lift as installed may be equal or less than this
()
maximum.
Gee't /Commonweae 3-18
_ _ _ _ _. _ - - -,. = - -
3.14 4-Ton Manual Chain He'.,t with Plain Trolley The 4-ton manual chain hoist with a plain trolley XCR-26 is located in the Turbine Building on elevation 412' between column lines F to G.1 and I to 3 above the Feedwater Booster Pumps. The hoist and trolley is shown on Figure 9 along with its safe load path.
Hoist XCR-26 is manufactured by the American Chain and Cable Company, and is a 4-ton capacity, hand operated, chain hoist on a plain trolley. The hoists have a 15 foot lift and a forged steel shank hook.1 The hoist and trolley is designed in accordance with CMAA Specification 70 for Class A and C indoor service and ANSI B30.2, Chapter 2-1 to the extent to which they apply.
Hoist XCR-26 is designated to service the Feedwater Booster Pumps XPP-28A through XPP-28D.
Since the Turbine Building contains no equipment necessary for the plant's safe shutdown or decay heat removal, this hoist can be excluded from further study or concern.
l l
l l
1.
The lift as given is the maximum irom the eye of the hook to the top of
~
l the beam; the actual lift as installed may be equal or less than this maximum.
O 3-19
3.15 5-Ton Electric Hoist with Motor Operated Trolley The 5-ton electric hoist and motor operated trolley XCR-27 is located in the Intermediate Building on elevation 436' between column lines G.4 to H.4 and 7.5 to 8.3.
The hoist and trolley are shown on Figure 4 along with its safe load path.
Hoist XCR-27 is manufactured by the American Chain and Cable Company, and is a 5-ton capacity, electric cable hoist on a motorized trolley, with a hand held electric controller. The hoist has a 49 foot lift 1
and a forged steel shank hoist.
The hoists and trolleys are designed in accordance with CMAA Specification 70 for Class A and C indoor service and ANSI B30.2, Chapter 2-1 to the extent to which they are applicable.
I Hoist XCR-27 is designated to handle power plant equipment through the equipment hatch from elevations 412' and 436' in the Intermediate Building. Nowhere within or near the safe load path are there components neces.sary for safe plant shutdown or decay heat removal.
Therefore, this hoist can be excluded from further study or concern.
l l
1.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or less than this maximum.
l Gdtet /Comwap 3-20
()
3.16 2-Ton Electric Cable Hoist with Motorized Trolley The 2-ton electric cable hoist and motorized trolley XCR-28 is located on elevation 463' of the Water Treatment Building between column lines D to D.6 and 10.6.
The hoist and trolley are shown on Figure 1 along with its safe load path.
Hoist XCR-28 is supplied by the American Chain and Cable Company, and is a 2-ton capacity, electric cable hoist on a motorized trolley with a hand-held electric controller. The hoist has a 43 foot lift and forged steel shank hook.I The hoists and trolleys are designed has a in accordance with CMAA Specification 70 for Class A and C indoor and outdoor service and ANSI B30.2, Chapter 2-1 to the extent to which they are applicable.
Hoist XCR-28 is designated to handle containers from the Water Treatment Building's Chemical Storage area.
Inside and near the
()
hoist's safe load path there are no components necessary for safe shutdown or for decay heat removal.
On this basis the hoist is excluded from further study or concern.
I c
l l
t 1.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or less than this maximum.
GJbert /Commonwes:th 3-21
3.17 2-Ton Hand Operated Hoist with Geared Trolley
()
The 2-ton hand operated hoists and geared trolleys XCR-29A and XCR-29B are located in the Diesel Generator Building on elevation 436' between the column lines G.4 to J.1 and column line number 1 above the Diesel Generators. The hoists and trolle; are shown on Figure 4 along with their safe load paths.
Hoists XCR-29A and XCR-29B are supplied by the American Chain and Cable Company, and are 2-ton capacity, single beam, underhung, hand operated hoists with geared trolleys. The hoists have a 24 foot lift dild** forged S teVl' shank hooks.1-~The hoists and trolleys are designed in accordance with CMAA Specification 70 for Class A and C indoor service and ANSI B30.2, Chapter 2-1 to the extent to which they are applicable.
Hoists XCR-29A and XCR-29B are designated to service the two standby
()
emergency diesel generators, XEG-1A-DG and XEG-1B-DG, respectively.
Within the area of each crane's safe load path the diesel generator, the fuel oil day tank, the air receiver, and on elevation 427', the fuel oil transfer pump are necessary for the safe shutdown of the plant.
The only time the four safe shutdown components are in l
jeopardy from a heavy load drop from hoists XCR-29A and XCR-29B, is when a hoist is servicing a diesel generator and associated equipment for maintenance purposes. When one diesel generator train is down l
for maintenance, the other is completely isolated from it and is capable of operating independently.
On the basis presented above and because the two diesel generator trains are completely redundant, hoists XCR-29A and XCR-29B are excluded from further study or i
Concern.
l 1.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal ar less than this O
maximum.
G.lbert / Common *eae 3-22
1 3.18 1/2-Ton Hand Chain Hoist and Trolley The 1/2-ton hand operated chain hoist and plain trolley XCR-31, manufactured by the American Chain and Cable Company, has a maximum rated capacity less than that defined for a heavy load in this study.
On this basis the hoist is not included in this study except for reference and completeness.
It is located on elevation 436' of the Intermediate Building near column lines H.4 and 2 to 3, and can be found on Figure 4.
O O
Geert/ Common ea:th 3-23
3.19 2-Ton Hand Chain Hoist With Trolley
()
The 2-ton hand operated chain hoist and trolley XCR-33 is located on elevation 412' of the Intermediate Building between column lines G.3 to H.4 and 2 to 3, above the Emergency Feedwater Pump and Turbine Drives.
The hoist is shown on Figure 3 along with its safe load path.
Hoist XCR-33 is supplied by the American Chain and Cable Company, and is a 2-ton ccpacity, hand operated, chain hoist with a plain trolley.
lift and a forged steel shank hook.I The The hoist has a 10 foot hoist and trolley are designed in accordance with CMAA Specification 70 for Class A and C indoor service and ANSI B30.2, Chapter 2-1 to the extent to which they apply.
Hoist XCR-33 is designated to service the Turbine Driven Emergency Feedwater Pump XPP-8-EF.
Within the hoist's safe load path the pump (v) and its turbine driver are necessary for the plant's safe shutdown.
The only time the pump and driver are in jeopardy of a heavy load drop is when the emergency feedwater pump has already been isolated for maintenance.
On the basis given above and since the Turbine Driven Emergency Feedwater Pump is redundant with the Motor Driven Emergency Feedwater Pump, the hoist can be excluded from further study or concern.
l 1.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or less than this O
maximum.
1 i
Geert /Commonwesa 3-24
()
3.20 1-Ton Electric Cable Hoist and Trolley The 1-ton electric cable hoist and plain push type trolley XCR-34, supplied by the American Chain and Cable Company, has a maximum rated capacity less than that defined for a heavy load in this study.
On this basis the hoist is not included in this study except for reference and completeness.
It is located at elevation 436' of the Reactor Building over the Tendon Access Gallery, and can be found on Figure 4.
()
l C:)
G.itet /Commeae 3-25 i'. - - - - - - - - - --
3.21 20-Ton Electric Cable Hoist with Motorized Trolley
()
The 20-ton electric 2nle hoist and motorized trolley XCR-36 is located in the Drumming Station on elevation 436' between column lines P to R and 6.6 to 8.8.
The hoist and trolley are shown on Figure 4 along with its safe load path.
Hoist XCR-36 is supplied by the American Chain and Cable Company, and is a 20-ton capacity, electric cable hoist with an electric motorized trolley.
The hoist has a 25-foot lift and a forged steel shank hook.I The hoist and trolley are designed in accordance with CMAA Specification 70 for Class A and C indoor service and ANSI B30.2, Chapter 2-1 to the extent to which they are applicable.
Hoist XCR-36 is designated to handle low and high level radiation shipping casks.
On elevation 463' and within the hoists safeload path there are no components necessary for the plant's safe shutdown
()
Below hoist XCR-36, however, on elevation 412' are the Spent Fuel Pool Cooling Pumps, XPP-32A and XPP-32B.
These pumps are classified as Safety Class 2b.
A study of the effects of dropping a Radwaste Cask shipping on the floor of elevation 436' of the Drumming Station above the Spent Fuel Cooling Pumps (Appendix A) indicates that the floor structure would withstand the drop impact with no resulting damage to the Spent Fuel Cooling Pumps.
The Radwaste Cask contains radioactive material.
The potential effluent releases from a dropped shipping cask would result in insignificant offsite dosage due to the allowable limits on radioactive material contained in a shipping cask and its form as required by the appropriate Federal Regulations for the Transportation of Hazardous Material, 49 CFR 170 through 189 and 10 CFR 71.
1.
The lift as given is the maximum from the eye of the hook to the top of
()
the beam; the actual lift as installed may be equal or less than this maximum.
Gdbert /Commortweau 3-26
3.22 10-Ton Hand Chain Hoists with Geared Trolley 3
The 10-ton hand chain hoists and geared trolleys XCR-40A, XCR-40B, and XCR-40C are located on elevation 436' of the Intermediate Building between column lines H.4 to J.1 and 2 to 8 above the Main Steam Isolation Valves.
The hoists and valves are shown on Figure 4 along with their safe load paths.
Hoists XCR-40A, XCR-40B, and XCR-40C are supplied by the American Chain and Cable Company, and are 10-ton capacity, manually operated chain hoists.
The hoists have a 20-foot lift and a forged steel shank hook.I The hoists and trolleys are designed in accordance with CMAA Specification 70 for Class A and Class C indoor service and ANSI B30.2, Chapter 2-1 to the extent to which they are applicable.
Hoists and trolleys XCR-40A, XCR-40B, and XCR-40C, along with a transfer rail, are designated for servicing the Main Steam Isolation Valves, XVM-2801 A through C.
Directly below the hoists and trolleys on elevation 412' of the Intermediate Building are located the Component Cooling Heat Exchanger, XHE-2B-CC, the Component Cooling Pumps, XPP-1A through C, and the Motor Driven Feedwater Pumps, XPP-21A and XPP-21B.
A study of the effects of dropping a Main Steam Isolation Valve on the floor of elevation 436' of the Intermediate Building above the indicated equipment (Appendix A) has indicated that the floor structure would withstand the drop impact with no resulting damage to the safe shutdown / decay heat removal equipment below.
The study was very conservative considering that the hoists were not designed to lift the complete valve at one time, as the study assumed.
1.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or tess than this
()
maximum.
Gabrt /Commca* eau 3-27 l
I 3.23 10-Ton Bridge Crane and Electric Cable Hoists O-The 10-ton bridge crane and electric cable hoist XCR-42 is located in s
the Hot Machine Shop on an elevation 436' between column lines R.2 to S and 11.6 to 7.8.
The crane is shown on Figure 4 along with its safe load path which encompasses the entire 436' elevation of the Hot Machine Shop.
Crane XCR-42 is supplied by the American Chain and Cable Company, and both the crane and hoist have a capacity of 10 tons. The crane is an underhung, single beam, motor driven, center drive crane.
The crane has a 24-foot lift and a forged steel shank main and safety hook.
There are pushbutton contrals for both the crane and hoist for the full length travel of tne bridge.
The crane and hoist are designed in accordance with CMAA Specification 70 for Class A and C indoor service, and ANSI B30.2, Chapter 2-1.
crane and hoist XCR-42 are designated to handle loads in the Hot Machine Shop. The safe load path is defined as the Hot Machine Shop which contains no components necessary for the safe shutdown of the plant or decay heat removal, and on this basis can be excluded from any further study or concern.
6 1.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or less than this maximum.
O Gitet /Ccmmonwealth 3-28
i
()
3.24 10-Ton Bridge Crane and Electric Cable Hoist The 10-ton bridge crane and electric cable hoist XCR-43 is located in the Service Building and shown on Figure 1 along with its safe load path which essentially encompasses the Service Building Machine Shop.
Crane XCR-43 is supplied by the Ameri:an Chain and Cable Company, and both the crane and hoist have a 10-ton capacity. The crane is a top running, double beam, motor driven, center drive crane.
The crane has an 18-foot 11-inch lift and a forged steel shank main and safety hook.I There are pushbutton controls for the crane and hoist for the full length travel of the bridge.
The crane and hoist are designed in accordance with CMAA Specification 70 for Class A and C indoor service, and ANSI B30.2, Chapter 2-1.
Crane and hoist XCR-43 are designed for General Service Building application in the Service Building Machine Shop.
Since the Service
()
Building contains no equipment necessary for either the plant's safe snutdown or decay heat removal, the crane can be excluded from any further study or consideration.
I i
1.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or less than this maximum.
O Gibert /Commoewea!th 3-29
3.25 3-Ton Bridge Crane with Electric Cable Hoist The 3-ton bridge crane and electric cable hoist XCR-46 is located on elevation 463' of the Auxiliary Building between column lines P to Q and 8.8 to 11.5.
The crane, associated monorail, and safe load path are shown on Figure 5.
The safe load path encompasses the area of the Chemical Volume Control System's Concrete Filter Plugs, the area under the associated monorail, and the Filter Hatch to Drumming Station.
Crane, hoist, and monorail XCR-46 are supplied by the American Chain and Cable Company.
The crane and hoist are each 3-ton capacity.
The crane is an underhung, single beam, motor driven, center driven type crane, and the hoist is an electric cable hoist. Along with the crane is an associated monorail that can interlock with the crane so that the hoist can transfer filter plugs to the Filter Hatch.
The crane and hoist are controlled remotely to remove the operator from the potentially radioactive filter plugs. The crane is designed in accordance with CMAA Specification 70 for Class A and C indoor service, and ANSI B30.2, Chapter 2-1.
Crane XCR-46 is designated to remove the concrete plugs and spent filter cartridges, which are below the heavy load weight limit, from their housing and transport the spent filter and cask to the Filter Hatch.
In case of an inadvertent drop of a radioactive filter, the possible effluent release would result in insignificant offsite doses due to the small amount of radioactive material contained in thr.
filters, and its low level radioactive nature.
I O
Gatert /Commonweau 3-30
3.26 10-Ton Bridge Crane and Electric Cable Hoist O
The 10-ton bridge crane and electric cable hoist XCR-47 is located in the Drumming Station at elevation 447' between column lines P to R and 8.8 to 9.5.
The crane and hoist are shown on Figure 4 along with its safe load path which encompases the low level waste storage area.
Crane XCR-47 is supplied by the American Chain and Cable Company.
The crane and hoist are both rated for a 10-ton capacity and the unit has a 14 foot lift.1 The crane is a underhung, single beam, motor driven, center drive crane, and the hoist is an electric cable type with a forged steel shank hook.
The crane and hoist are controlled remotely with a control panel to remove the operator from close proximity of the low level waste storage area while operating the The crane is designed in accordance with CMAA Specification crane.
70 for Class A and C indoor service, and ANSI B30.2, Chapter 2-1.
Crane XCR-47 is used to handle shielded and unshielded low level radioactive waste storage containers in the storage area.
The potential effluent release from a dropped cask would result in insignificant offsite doses due to the low level nature of the material and the amount of allowable radioactive material in each cask.
1.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or less than this
- maximum,
(:)
i Gaoert/Commonweae 3-31
3.27 1-1/2 Ton Hand Chain Hoist and Plain Trolley O
The 1-1/2 ton hand chain hoist and plain trolley XCR-48 is located on elevation 412' of the Turbine Building between column lines B.8 to D and 12 above the Instrument and Service Air Compressors. The hoist is shown on Figure 9 along with the safe load path.
Hoist XCR-48 is suppliei by the American Chain and Cable Company, and is a 1-1/2 ton capacity, manually operated, chain hoist on a plain trolley.
The boist has a 17 foot lift and a forged steel shank hook.
The hoist and trolley are designed in accordance with CMAA Specification 70 for Class A and C indoor service, and ANSI 30.2, Chapter :.-1 to the extent to which they apply.
Hoist and trolley XCR-48 service the Instrument and Service Air Compressor, XAC-3A and XAC-3B, which are not necessa*.y for safe shut down or decay heat removal.
On this basis XCR-48 can be excluded from further study or concern.
i l
i 1.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or less than this maximum.
O i
9te11Cammenetattn 3-32 l
()
3.28 10-Ton Bridge Crane and Electric Cable Hoists The 10-ton bridge crane XCR-51, and electric cable hoist, XCR-50, are located on elevation 436' of the Service Water Intake Screen and Pump House directly above and behind the Service Water Pumps.
The crane and hoist are shown on Figure 8.
The safe load path, also shown on Figure 8, includes the complete service area behind the pumps and under the monorails over each Service Water Pump.
Crane XCR-51 and hoist XCR-50 are supplied by the American Chain and Cable Company.
The crane and hoist are both rated for a 10-ton capacity, and have a 57 foot litt.
The crane is an underhung, single beam, hand operated crane, and the hoist is an electric cable hoist with a pushbutton control station and a lifting beam.
Associated with the crane and hoists are three monorails, one over each Service Water Pump, that can interlock with the crane. The hoist and crane are designed in accordance with CMAA Specification 70
()
Class A and C indoor service, and ANSI B30.2, Chapter 2-1.
Crane XCR-51 and hoist XCR-50 are designated to service the Service Water Pumps, XPP-39A through C, and the Traveling Screens, XRS-2A through C.
Within the safe load path, the Service Water Pumps are necessary for the safe shutdown of the plant.
The only time the hoist are in operation is when an associated pump and crane ara I
I screen are being serviced.
When the pump and screen are being serviced they are isolated from the Service Water System, and at the l
time are no longer necessary for the plant's safe shutdown. The three Service Water Pumps have a 2 out of 3 redundancy.
Due to spa e limitations it is physically impossible for the hoist to travel over an operating Service Water Pump and Traveling Screen while carrying a designated heavy load.
l i
I
()
1.
The lift as given is the maximum from the eye of the hook to the top of the beam; the actual lift as installed may be equal or less than this maximum.
1 i
Geet /CommocwuO 3-33
()
3.29 2-Ton Twin Hook Extension Hoist The 2-ton twin hook extension hoists XCR-53A, XCR-53B, and XCR-53C are located in the Reactor Building at elevation 475' on the Loop B Steam Generator Wall. The safe load path is the area covered by the CRDM Cable Support Structures and the space directly above it.
The three hoists and the safe load path are shown on Figure 5.
Hoists XCR-53A, XCR-53B, and XCR-53C are supplied by P&H Harnischfeger Company.
Each hoist has twin hooks rated at 2-ton.
The hoists are equipped with a handwheel for manual operation, and are capable of an 18 foot lift.
The hoists are designed in accordance to ANSI B30.2, Chapter 2-1 to the extent to which it is applicable.
The three hoists are used to lift the CRDM Cable Support Structures during refueling or maintenance outages. Since the hoists are only
()
used during cold shutdown, the hoists can be excluded from any further study or concern.
O Gert /Comew*eac 3-34 L
()
3.30 1-Ton Jib Crane - Rad Waste Package As part of the Rad Waste Package there is a one-ton capacity j ib crane, XRW-11.
Since this crane's rated maximum capacity is under the heavy load limit of this study it is not censidered further, and is included herein only for reference and completeness.
The one-ton jib crane is located in the Drumming Station at elevation 436' at column lines Q and 7.7.
The load path of this excluded item is shown on Figure 4.
O I
l l
O Gibert /Commonweso 3-35 i
l
()
3.31 3-Ton Jib Crane - Rad Waste Package As part of the Rad Waste Package in the same area as hoist XCR-36 is a 3-ton jib crane, XRW-13.
The crane is at elevation 436' of the Drumming Station between column lines Q and 7.8 to 8.7.
The jib crane and its safe load path are shown on Figure 4.
Jib crane XRW-13 has a 3-ton capacity with an electric cable hoist supplied by the American Chain and Cable Company.
The hoist utilizes a 3-ton load beam as a handling device.
The hoist is controlled by a pushbutton pendant station.
Crane XRW-13 is designed in accordance with CMAA Specification 70 and ANSI B30.2, Chapter 2-1.
Jib crane XRW-13 is designated to handle the spent Chemical Volume and Control System (CVCS) filters and their storage casks that were lowered through the filter hatch from elevation 463' by hoist XCR-48 and places them in temporary storage.
The potential effluent release
()
due to an inadvertent drop of a spent filter and storage cask would result in insignificant offsite doses due to the small amount of radioactive material contained in the iilter and its low level nature.
O 3-36
3.32 Reactor Building Equipment."ccess Hatch Crane The Reactor Building Equipment Hatch has a permanent crane arm attached to it at elevation 463' of the Reactor Building.
This crane arm is used to swing the equipment access hatch door out of the hatch opening along a guide track when necessary.
By definition of this report, this crane can be excluded from further study since it is not an overhead handling device.
The load path of this excluded item is shown on Figure 5.
O O
GibertICommonweau 3-37
O O
O TAllt.E 3-1 IIEAVY I.0AI)S VS IrlPACT AREA Overheail I,i f ting Device: Reactor Cavity Manipulator Crane, XCR-1 Impact Area: Elevation 463' above Reactor Vessel Cavity anit Refueling Canal, Reactor fluililing Figures: 5, 6, anil 7 Designateil lleavy Sa fe Shutilowt/ Decay Elevation of Ilazaril Elimination Section Reference Loail anel Weight llea t Removal E<1uipment
_ Esp!jgtment Categoyy (Remarks)
Spent anel New Fuel Reactor Cavity 663' c
See Section 3.1 Assembly anil llanilling Tool 2500 lbs.
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Overhead 1.ifting Device. Spent Fuel Pit liridge Crane, XCR-2 jmpact Area: Elevation 463', column lines Q.5 to h.5 and 2.5 to 2.6, Fuel liandling fluilding Figures: 5 and 7 Designated lleavy Sa fe Shut down/llecay Elevation of llazard Elimination Section Heterence 1.oad and Weiglit Ileat Hemova l E<piipment Ertuipment Category (Remarks) i
(
Spent Fuel Assemlily Spent Fuel Rod 412' and 463' c
See Section 3.2 and llandling Tool 2500 lbs.
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O TAlli.E 3-1 (Continucil) 1 Overhea<l 1.i f ting lievice: 10-Ton Electric Catile lloist anal Motor Oper.itet! Trolley, XCR-18 Impact Area: Elevation 436', column lines 9.5 an<l L, tliru Equipment flatcli 374' to 436', Auxiliary lhailding i
Figures: 2, 3, anil 4 Designateil lleavy Sa fe Sliutilown/ Decay Elevation of
!!azard Elimination Section Refenence
__E<pf pment _
Category (Remarks) i I.oail an<l Wei gli lleat Removal Egijpment Power Plant E<guipment None N/A c
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Overliead I.iiting Device: 5-Ton llanil Cliain iloi st and Plain Trolley, XCR-20A anil XCR-20ll i
impact Area: Elevation 374', column lines K and 8.8, Auxiliary lluililing Figure: 2 i
Designated lleavy Safe Sliutdown/ Decay Elevation of llazard Elimination Section Reference l
I.oad and Weig L
!!ca t_ Removal Emi_ipment Eggpment Category (Remarks) i 1.
HilR Pumps 4400 ll>s HilR Pump and tiotor 374' b
See Section 3.8 2.
HilR Pump Motor 3200 lies HilR Pitmp and flotor 374" h
See Section 3.8 yi
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O TA!!I.E 3-1 (Continue <l)
Overhea<l I.i f t ing Devi ce. 5-Ton flanual Chain iloist with Gea reil Trolley, XCit-21 A ain! XCit-2111 Impact Area: Elevation 374', column lines K anal 8.8, Auxiliary lluililing Ngure: 2 Designate <l IIcavy Sa fe Shutilown/ Decay Elevation of llazard Elimination Section Iteterence I.oad anil Weight _
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_Eeluipment Category
( Etema rks )
1.
1111 Spray pump 5400 lbs.
Itll Spray Pump and tiotor 374' b
See Section 3.9 2.
ItB Spray pump tiotor Itll Spray Pump and tiotor 374' b
See Section 3.9 5880 lbs.
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1 Overheat! Lifting Device: 5-Ton ?!anual Chain iloist with Geareil Trolley, XCit-54 A,11, & C
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lleat itemova l Eips_ipment Equipment Category (Hemarks) j 1.
SI Charging Pump SI Charging Pump 388' b
See Section 3.10 I
7500 lbs.
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SI Charging Pump SI Charging Pump 388' b
See Section 3.10 Base 6000 lbs.
Assembly e
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SI Charging Pinnp Gear SI Charging Pump 388' b
< 2500 lbs y5 2100 lbs.
Assembly See Section 3.10 oP
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TAllLE 3-1 (Continuing)
Overhead Li f ting Device: 8-Ton flanual lland Chain iloist with Geared Trolley, XCit-24 Impact Area: Elevation 463', column lines F and 4 to 5, Turbine 15uilding l
F,i gu re : 11 Designated IIcavy Safe Shutdown / Decay Elevation of llazard Elimination Section Reference Load and Weight IIcal Hemoval Equipment Equipment Category (Hemarks) flain Steam Stop VaIves None N/A c
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o TAllLE 3-1 (Continue <t)
Overheatl Lifting Device 10-Ton flanual Ch'in lloist wit h Geareil Trolley, XCR-25A,11, C, anil D
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_limlpment Category (Remarks) i j
Load and Weight lleat Hemoval Equipment i
l 1.
Concrete Plugs None N/A c
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1770 lbs 5 2500 l lis.
l 2.
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O TAllI.E 3-1 (Continueil)
Overticail Lifting Device 1 1/2-Ton llanil Chain lloist anil Plain Trolley, XCit-48 Impact Area: Elevation 412', Column 1.ines 11.8 to D anil 12, Turbine Buileling Figure: 9 Designateil lleavy Safe Shutilown/ Decay Elevation c,f flazaril Elimination Section Iteference 1.oail anil Weigli lleat itemova t Equipment Equipment Category (itema r ks) l Instrument anil Air Compressor None N/A e
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O TABI.E 3-1 (Con t i nue<l)
Overbeaal Lifting Device 10-Ton llriilge Crane arul Electric cable lloists, XCit-51 anil XCit-50 i
i Impact Area: Elevation 436', Service Water Intake Screen anti Pump lionse l'i gu rty: 8 l
Designateil lleavy Sa f e Sinitilown/ Decay Elevation of flazaril Elimination Section iteference l
l.oail ani! Weight lleat Remova l E<piipment Equipment Category (Remarks) 1.
Service Water Service Water Traveling 436' b
See Section 3.28 Traveling Screen Parts Screen anil Pump Assembly j
$ 10 Ton 2.
Service Water Pump Service Water Traveling 436' b
See Section 3.28 14,000 lbs.
Screen anil Pump Assembly e
J 3.
Service Water Pump Service Water Traveling 436' b
See Section 3.28 i
YD Motor 15,650 lbs.
Screen an<l Pump Assembly
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i TAllLE 3-1 (Centinne<l) der %+t 'isting Device. Reactor Btiililing Equi [> ment Access liat ch Cr.nie Impart Area: Elevation 413, React <.r Iluiliting EiS'ilq: 5 Designateil lleavy Sa fe Sliutilown/ Decay Elevation on llazard Elimination Section Reference
_F il pment Category (Remarks)
Loa <l anil Weight.
lleat Removal E<1311pment 3 i None N/A N/A c
See Section 3.32 e
Ye?
o 1
E l
t e
i l
l 4.0 CODE AND STANDARD COMPLIANCE 4.1 Crane Design As stated in NUREG-0612, Section 5.1.1 and Enclosure 3 of D. G. Eisenhut's December 22, 1980 letter, it should be verified that crane design complies with the guidelines of CMAA Specification 70 and Chapter 2-1 of ANSI B30.2.
As already stated in the individual overhead handling device descriptions, each device design was required by the original Purchasing Specification to adhere to the guidelines of the above standards, and each eupplier adhered to the standards qt oted above to the extent to which they were applicable.
4.2 Lifting Devices Lifting devices do not comply with either the requirements of ANSI N14.6-1978, " Standard for Special Lif ting Devices for Shipping
()
Containers Weighing 10,000 Pounds or More Nuclear Material," or ANSI B30.9-1971, " Slings".
Alternate methods for demonstration of equivalency are provided %y a detailed inspection and testing program.
Maintenance procedures are being developed to perform frequent and periodic inspectio2, which include visual and non-destructive examination of critical surfaces.
Periodic load test will be performed as necessary to verify structural adequacy of the special lifting devices.
All rigging and lifting devices are controlled and maintenanced using the plants computerized preventative maintenance program (CIIAMPS).
Existing inspection and maintenance procedures are outlined in the Virgil C. Summer's Nuclear Station Operations Mechanical Maintenance Procedure MMP-165.8, "Use and Control of Rigging Equipment".
4.3 Inspection, Testing, and Maintenance Cranes and rigging equipment are maintained, tested, and inspected to
()
the requirements of ANSI B30.2, Chapter 2-1.
The crane and rigging G itet / Commonwealth 4-1
=
I equipment are scheduled for the specific maintenance tasks by the plant's computerized history and maintenance program (CHAMPS).
4.4 Crane Operator Training Nuclear Operations at the Virgil C. Summer Nuclear Station conducts an extensive training progcam for its crane operators and riggers which meets or exceeds all the requirements of Chapter 2-3 of ANSI B30.2.
The Nuclear Operations Maintenance group at the plant conducts a program for the crane operators and riggers entitled
" Basic Operator and Rigger Training Program" which c wers the following topics:
a)
OPERATIONAL SAFETY PRACTICES AND PREVENTATIVE INSPECTION AhT MAINTENANCE b)
WRIGHT WIRE ROPE ELECTRIC HOIST c)
ANSI B30.16 - 1973, "0VERHEAD HOIST" d)
SPECIFICATIONS FOR ELECTRIC OVERHEAD TRAVELING CRANES C.M.A.A.
- 70 e)
WHITING OVERHEAD CRANE - P&H OVERHEAD CRANE f)
MMP 165.3, " TURBINE BUILDING CRANE INSPECTION AND MAINTENANCE PROCEDURE" g)
MMP 165.7, " MAINTENANCE OF THE REACTOR BUILDING POLAR AND FUEL HASTLING BUILDING CRANES" h)
NUREG-0554, " SINGLE-FAILURE-PROOF CRANES FOR NUCLEAR POWER PLANTS" i)
ANSI B30.2.0-1976, "0VERHEAD AND GASTRY CRAhTS" j)
OSHA 1910.179, "0VERHEAD AND GANTRY CRANES" k)
INSTRUCTION MANUAL MANIPULATOR CRANE 1)
SPENT FUEL BRIDGE CRAN):
m)
ANSI B30.9-1971, " SLINGS" n)
MMP 165.8, "USE AND CONTROL OF RIGGING EQUIPMENT" o)
ANSI B30.10-1975, " HOOKS" p)
INSTRUCTION OF CRAhTS:
O 1)
Wright Electric Hoist 3/20 Tons Gibert / Comme *eae 4-2
()
2)
P&H-Turbine Building 220/30 Tons 3)
Polar Cranc-Reactor Building 360/25 Tons 4)
Manipulator Crane-Reactor Building 5)
Whiting Overhead Crane-Fuel Handling Building 125/25 Tons 6)
Spend Fuel Bridge Crane-Fuel Handling Building The crane operator and rigger training programs include in-class written examinations and in-plant exa.ainations for practical application. After a crane operator or rigger becomes qualified by the training program, an annual physical examination and a biannual retraining and requalification of the crane operators and riggers are required.
O O
~~-
4-3
l 5.0 PROCEDURES
{}
Since the Virgil C. Summer Nuclear Station is still in the construction stage, most procedures for handling heavy loads with overhead handling devices are still under development.
Currently, maintenance procedures are being developed to encompass overhead handling systems with respect to the safe load paths.
Where safe load paths can not be established, special lifting procedures are being developed, and where possible special lifting instructions are incorporated into specific component maintenance procedures. Any l
deviation from established safe load paths will be enforced by established procedures.
Procedures have been transmitted from Westinghouse Electri.c Corporation to Scuth Carolina Electric and Gas Company for the handling of new and spent fuel, refueling, and for the operation of i
refueling equipment.
These procedures are being reviewed and placed
(}
into a standard format prior to issuance and use.
The individual overhead handling device descriptions in Section 3.0 indicate where procedures are being developed to minimize the possibility of an inadvertant heavy load drop.
O Gdtert/ Common eap 5-1
A
.m A
a m
A I
O 1
I i
1 APPENDIX A O
STRUCTURAL ANALYSIS OF DROPPED HEAVY LOADS O
G.lbert / Core ?nweWth
. ~.
APPENDIX A O
STRUCTURAL ANALYSIS OF DROPPED HEAVY LOADS TABLE OF CONTENTS Section Title Page A.1 INTRODUCTION A-1 A.1.1 INITIAL CONDITIONS A-1 A.1.1.1 Case A: Intermediate Building A-1 A.1.1.2 Case B: Drumming Station / Truck Bay A-2 A.2 A9c"MPTIONS/ IDEALIZATIONS A-3 A.2.1 MATERIAL PROPERTIES A-3 A.2.1.1 Loading Conditions A-3 A.2.1.2 Local Effects A-4
()
A.2.1.3 Energy Absorption Mechanism A-4 A.3 BEHAVIOR OF REINFORCED SLABS UNDER IMPACT A-4 A.4 EVALUATION OF SLAB CAPACITY A-5 A.5
SUMMARY
/ CONCLUSIONS A-5 A.6 REFERENCES A-6 TABLE A-1 The Energy Capcity of Target Slabs A-7 TABLE A-2 Kinetic Energy Due to Dropped Loads A-8 O
G,1bert /huta A-i
APPENDIX A O
STRUCTURAL ANALYSIS OF DROPPED HEAVY LOADS A.1 INTRODUCTION An evaluation of the hypothetical heavy-load drop accidents has been made to demonstrate compliance with Criteria III and IV of NUREG 0612, Section 5.1.
Appendix A presents a summary of the results.
Two (2) potential drop areas have been identified requiring structural evaluation to determine if the floor slabs and support systems adequately protect the identified targets.
The floor slabs evaluated are in the Intermediate Building at elevation 436' bounded by Column Lines J1 and H4 between lines 2 and 8 (Figure 4), and in the drumming station and truck bay of the Auxiliary Building at elevation 436' bounded by Column Lines P and R between lines 6.6 and
()
8.8 (Figure 4).
The calculation method adopted uses the energy absorption concept with conservative assumptions.
By comparing the ultimate energy absorption capacity of the slab with the kinetic energy at impact of the falling object, it can be determined whether the dropped object can be prevented from striking the designated target.
A.1.1 INITIAL CONDITIONS A.1.1.1 Case A:
Intermediate Building Target:
The safe-shutdown equipment to be protected in this area are Component Cooling Heat Exchanger XHE-23-CC, Component Cooling Pumps XPP-1A, B, and C-CC, and Motor Driven Feedwater Pumps XPP-21A and B.
All of these are located at elevation 412'.
G.2ert / Common =ese A-1
Load:
The postulated dropping object is a main steam isolation valve weighing 27,250 lbs. with a dropping height of 20 feet.
The approximat,e overall dimensions of the valve ate: 14 feet in length and 4 feet in diameter.
The dropping valve may strike the target slab in any location or orientation.
However, it has been determined that the valve hitting vertically on the center of panel between beam supports would be the worst case.
Slab:
All the floor slabs in this area are supported by steel beams and have similar panel arrangements, thickness, and reinforcement.
A typical slab is 2 feet thick with #9 at 12" top and bottom steels in N-S direction and with #10 at 12" top steels and #9 at 12" bottom steels in E-W direction.
For simplicity, it was idealized as an isotropic slab with #9 at 12" top and bottom steels. The insitu steel decking was ignorea.
A.1.1.2 Case B:
Drumming Station / Truck Bay Target:
Spent Fuel Cooling Pump XPP-32B at elevation 412' is the single safe-shutdown equipment in this area.
Load:
The postulated dropping object is the radwaste cask with an empty weight of 25,250 lbs. and maximum filled weight of 40,000 lbs.
The cask's overall dimensions are 5'-7-5/8" in height and 4'-9-5/8" in diameter.
The maximum dropping height is 10 feet, measured from the bottom of the cask to the top of floor slabs.
The most critical dropping orientation is when the long axis of cask makes an approximate 45 degree angle with the vertical and strikes at the center of the slab panel.
O Gibet /Commonweap A-2
Slab:
The slab over the target is 3 feet thick, supported and
()
monolithic with concrete walls and with reinforcement:
- 10 at 6" of top and bottom steels in E-W direction and #1n at 12" top and bottom steels in N-S direction.
A.2 ASSUMPTIONS / IDEALIZATIONS A.2.1 MATERIAL PROPERTIES For Concrete:
f' = Compressive Strength
= 3,000 psi c = Ultimate Compressive Strain
= 0.003 For Reinforcing Steel:
F = Yield Stress y
= 60,000 psi
()
F = Ultimate Tensile Strength
= 90,000 psi E = Young's Modulus s
6
= 29 x 10 psi c = Ultimate Tensile Strain s
= 0.13 A.2.1.1 Loading Conditions The impact load is distributed over a small area of the contact surface between the dropping object and target slab.
For simplicity, it is conservatively assumed that the impact load acts as a concentrated impulsive force.
O GtertICommnweau --
A-3
A.2.1.2 Local Effects O
Local effects such as penetration and perforation are not considered to be of concern in view of the large slab thicknesses and low velocities at impact of dropped objects.
A.2.1.3 Energy Absorption Mechanisa The kinetic energy of a dropping object upon impact may be dissipated in several of the following ways:
Energy absorption by tLe targe. slabs resulting from the elastic r
a.
response of the structure to the impact.
b.
Energy absorption by the dropping object due to plastic deformation during collision.
Energy absorption by the target slabs due to plastic deformation c.
()
and local crushing.
The manner of absorption of the total kinetic energy of the dropping object will depend on the sharpness, mass, and velocity of the dropping object, and also the material properties of both the dropping object and target slabs.
It is conservative in the present analysis to assume that all of the energy absorption capacity will be due to the plastic deformation of the impacted floor slab.
l A.3 BEHAVIOR OF REINFORCED CONCRETE SLABS UNDER IMPACT References 1 and 2 describe the plastic collapse mechanisms of reinforced concrete slabs with different boundary conditions and j
subjected to different loading cases.
In the case of a incentrated impact force, a collapse mechanism correcponding to a :ene, whose axis is normal to the slab and passes through the point of lead application, may form.
For isotropic slabs (same reinforcement in both directions), the collapse area will be Gibert /Commonwea@
A-4 i
limited by a circular yield line.
For orthotropic slabs (different
()
reinforcement in orthogonal directions), the collapse area will be limited by an elliptic yield line.
The slabs in the Intermediate Building (Case A) are, therefore, likely to experience a circular failure mode while slabs in Drumming Station / Tiuck Bay (Case B) experience an elliptic failure mode.
For both Case A and Case B, it is found that the concrete will reach its ultimate compressive strain before the tensile steel breaks.
When the concrete is completely crushed, the slab loses its moment resistance. However, it can sustain further impact through the membrane effect of reinforcing steel until the steel strain also reaches the ultimate licit.
For Case A, the existing steel deck underneath the slabs wi prevent the scabbing of concrete from underneath the slab; however, its resistance to impact has been neglected.
A.4 EVALUATION OF SLAB CAPACITY O
To evaluate the total capacity of the target slab, two (2) contributions need to be evaluated:
the capacity due to betiding along yield lines U nd the capacity due to membrane effect U,.
b Results are summarized in Table A-1.
The kinetic energy of the dropping object and the external work done by the dead load and service load are given in Table A-2.
Comparison of Table A-1 and Table A-2 shows that for both Case A and Case B, the energy capacity of the target slab is larger than the applied kinetic energy due to drop of corresponding loads.
A.5
SUMMARY
/ CONCLUSIONS It is concluded that the 24 inch slabs in the Intermediate Building and the 36 inch slabs in Drumming 9tation/ Truck Bay of the Auxiliary O
Gatert /Commonweaita A-5
_ ~
Building are capable of withstanding the impact from a dropped
()
heavy-load.
The factor of safety is 1.21 for Case A and 5.6 for Case B.
The results are considered to be conservative for the following reasons:
1.
It is assumed that all of the kinetic energy will be converted into the plastic strain energy of the target slab.
2.
Permissible increases of 25% for compressive strength of concrete and 10% for yield stress of reinforcing steel for dynamic loading are not utilized.
3.
The energy absorption capacity of girder supports and insitu steel deck in Case A is neglected.
It should be noted that the foregoing investigation did not consider
()
any effects that localized distortion at impact may have on the supports of services hung directly from the underside of the elevation 436' slab.
For Case A, scabbing of the underside of the slab can be discounted because of the presence of insitu steel decking; however, for Case B some scabbing is a possibility that has not been evaluated in this study.
A.6 REFERENCES 1.
- Wood, R.H.,
" Plastic and Elastic Design of Slabs and Plates",
The Ronald Press Company, New York, 1961.
2.
Save, M.A. and Massonnet, C.E.,
" Plastic Analysis and Design of Plates, Shells and Disks",
American Elsevier Publishing Company, Inc., New York, 1972.
O A-6
TABLE A-1 O
THE ENERGY CAPACITY OF TARGET SLABS Case A Case B Drumming Station /
Truck Bay Location Intermediate Building (Auxiliary Building)
Thickness 2'-0" 3'-0" Reinforcement Each Way, Each Face
(#10 at 6" E-W)
(#9 at 12")
(#10 at 12" N-S)
Insitu Steel Deck Yes No Secondary Beam Support Yes No O
r 11ere " ae circ =1 r ettintic U
~ "'
~"
b 4
U 1382.40 k-in.
5760.00 k-in.
m U
=Ub+U 8057.58 k-in.
29957.02 k-iu.
p m
O Gibert /Ccmmnweao A-7
TABLE A-2 KINETIC ENERGY DUE TO DROPPED LOADS Case A Case B Drumming Station /
Truck Bay Location Intermediate Butiding (Auxiliary Building)
Dropped Load Main Steam Isolation Radwaste Cask Valve Wei
..t 27,250 lbs.
40,000 lbs.
o Dropping Height 20 ft.
10 ft.
Kinetic Energy V 6540 k-in.
4800 k-in.
k O
Work Due to D.W. of 9.5 k-in.
49.1 k-in.
Slab V d Estimated Work Due 95 k-in.
491 k-in.
to Service Load and Live Load V = V.
+ V
+V 6645 k-in.
5340 k-in.
t K
d S
i O
G.iwt/ Common eao A-8
O APPEhTIX B WESTINGHOUSE ANALYSIS OF THE REACTOR BUILDING I
I O
Galtert /Ccmeta@
APPEhTIX B O
kISTINGHOUSE ANALYSIS OF THE REACTOR BUILDING TABLE OF CONTENTS Section Title Page B.1 INTRODUCTION B-1 B.2 PROCEDURE B-1 B.3 RESULTS B-1 B.4 REFERINCES B-4 O
O Geert /Commoneta@
[
B-i j
APPENDIX B O
WESTINGlf0USE ANALYSIS OF THE REACTOR BUILDING s
B.1 INTRODUCTION The following sections are the procedures and results of Westinghouse's analysis of eavy load drops from the Reactor Building Polar Crane in the Reactor Building, as transmitted in Reference 6.
B.2 PROCEDURE The heavy loads under consideration are those given in Table 1-1, handled by the Reactor Building Polar Crane.
The loads will be compared, where applicable, to the loads given in the head drop analysis of Reference 4.
In this analysis, a dropped integrated head package weighing 423,841 lbs. was shown to cause no consequential
()
damage to the structural integrity of the vessel nozzles, core cooling capability, or integrity of the fuel cladding.
Each of the loads in Table 1-1 will be evaluated as a separate postulated drop accident against the total integrated head assembly drop accident postulated in Reference 4.
B.3 RESULTS For each of the items handled by Reactor Building Polar Crane XCR-4, the following results were obtained:
1.
CRDM Missle Shields (54,000 lbs.) - If dropped on a closed vessel, it would cause damage to CRDM's and reactor vessel head.
However, loads on the reactor vessel, reactor vessel nozzles, and fuel assemblies would be less than those caused by the reactor head drop discussed in Reference 4.
O Qbert /Commonwe*th B-1 l
i
\\
~,
2.
Reactor Vessel Head Assembly (268,000 lbs.) - Westinghouse has
()
performed a $1ropped head analysis, provided in Reference 4, that assures the consequences of dropping the reactor vessel head assembly at all critical points along its travel path to the vessel head storage stand.
This analysis shows that the buckling load on affected fuel assemblies would not exceed design limits and that there would not be any damage to the structural integrity of the reactor vessel, reactor vessel nozzles, or reactor coolant loop piping.
Therefore, since the total head assembly weight for the V.C. Summer Nuclear Station is less than in Reference 4 and since the travel path to the storage stand is essentially the same, it can be concluded that the core cooling capability and fuel cladding integrity will be maintained.
3.
Reactor Vessel Head Lifting Rig (21,000 lbs.) - This item would not cause unacceptable loads on the reactor vessel or nozzles.
()
'.owever, it should not be carried over the open vessel after the upper internals have been removed and prior to removal of the fuel assemblies.
4.
Upper Internals and Internals Lifting Rig (92,000 lbs.) - The loads produced by dropping the upper internals are less than those discussed in Reference 4 because the weight is less.
5.
Lower Internals and Internals Lifting Rig (268,000 lbs.) - The core must be completely removed prior to removal of lower internals, therefore fuel damage is not a problem.
The loads on the reactor vessel nozzles would be smaller than those in Reference 4.
O G. tert /Commonwes@
B-2
6.
Internals Lifting Rig (19,000 lbs.) - This item would not cause
(}
unacceptable loads on the reactor vessel or nozzle.
However, it should not be carried over the open vessel after the upper internals have been removed and prior to removal of the fuel assemblies.
7.
ISI Tool and Westinghouse-Supplied Lifting Device (20,000 lbs.) - This item would not cause unacceptable loads on the reactor vessel or nozzle.
However, it should not be carried over the open vessel after the upper internals have been removed and prior to removal of the fuel assemblies.
8.
RCP Internals (48,000 lbs.), RCP Casing and Lifting Beam (52,000 lbs.) and RCP Motor (77,140 lbs.) - Loads on the reactor vessel nozzles and the reactor vessel would be less than those discussed in Reference 4.
Damage to the upper head assembly would be significant and if the head assembly and the upper internals were not in place, possible fuel cladding failure and
()
release of radioactive materials would take place.
Therefore, the RCP assembly parts should not be carried over the reactor vessel cavity without the reactor vessel shield in place.
9.
RV Studs, Nuts, and Washer Stand (8500 lbs.) - This item
.uld not cause unacceptable loads on the reactor vessel or nozzles.
However, it should not be carried over the open vessel after the l
upper internals have been removed and prior to removal of the fuel assemblies.
10.
Equipment Bridge (4000 lbs.) - This item would not cause unacceptable loads on the reactor vessel or nozzles. However, it should not be carried over the open vessel after the upper l
internals have been removed and prior to removal of the fuel assemblies.
Ov Gdbert /Commonweafth B-3
- ~ _ _.
l 1
l l
It can therefore be concluded that for the above postulated drop I\\_-)
accidents there will be no consequential damage to the structural integrity of the vessel nozzles, no loss of core cooling capability, or loss of fuel cladding integrity.
B.4 REFERENCES 1.
GAI Letter CGGW-1647, dated August 6, 1981.
2.
NUREG-0612, ' Control of Heavy Loads at Nuclear Power Plants",
July, 1980.
3.
NRC Letter by D. G. Eisenhut of December 22, 1980 and attachments.
4.
WCAP-9289, " Integrated Vessel Head Package for One-Lift Operation", March, 1978.
_jh 5.
GAI Report No. 2289, " Control of Heavy Loads at Nuclear Power Plants - Virgil C. Summer Nuclear Station Unit 1",
June 22, 1981.
6.
Westinghouse Letter CGWG-2440 and attachment.
f%
r_/
c.w. a-.a B-4
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