Text

Rev 2 to Control of Heavy Loads at VC Summer Nuclear Station
	ML20101S438
Person / Time
Site:	Summer
Issue date:	01/21/1985
From:	; GILBERT/COMMONWEALTH, INC. (FORMERLY GILBERT ASSOCIAT
To:	;
Shared Package
ML20101S431	List: ML20101S430; ML20101S438;
References
	REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR 2364, 2364-R02, 2364-R2, NUDOCS 8502050391
	Download: ML20101S438 (150)
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{{#Wiki_filter:. v CAI REPORT 2364 i 1 1 CONTROL OF HEAVY LOADS AT VIRGIL'C. SUMMER NUCLEAR STATION Initial Issue - October 30, 1981 Revision 1 - June 25, 1984 l-Revision 2 - January 21, 1985 'l Z .I PREPARED BY. CILBERT/ COMMONWEALTH,-INC. READING, PENNSYLVANIA -8502050391 850125 gDRADOCK05000g

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TABLE OF CONTENTS Section Title Pm

1.0 INTRODUCTION

1-1 2.0

SUMMARY

2-1 '3.0 IDENTIFICATION OF OVERHEAD HANDLINC DEVICES 3-1 4.0 CODES AND STANDARD COMPLIANCE 4-1 4.1 CRANE DESIGN 4-1

4.2-LIFTING DEVICES 4-1 4.2.1 Special Lifting Devices for Reactor Vessel Servicing 4-1 4.2.2 Slinas 4-6 4.3

' INSPECTION, TESTING, AND MAINTENANCE 4-6 4.4 CRANE OPERATOR TRAINING 4-6 5.0 -PROCEDURES 5-1 APPENDIX A STRUCTURAL ANALYSIS OF DROPPED HEAVY LOADS APPENDIX B-WESTINGHOUSE ANALYSIS OF THE REACTOR BUILDING APPENDIXIC ' ANALYSIS OF IMPACT LOADS LIST OF TABLES Table 1-1 OVERHEAD ' HANDLING DEVICES, VIRCIL C. SUMMER 1-4 NUCLRAR STATION Table 3 HEAVY' LOADS VS. IMPACT AREA 3-49 Table 4-1 RESULTS OF IMPACT LOADINC CALCULATIONS 4 DRAWINGS Finure No. Title -1 ~-Site Plan 2 ' Plan and Elevations 374'-0", 38S'-0", and 400'-0" 3 Plan at Elevation 412'-0" 4 Plan at Elevation 436'-0" 5" Plan at Elevation 463'-0"~ f .'6- -Plan at Elevations 485'-0", 482'-0", and 552'-0" 7 Ceneral Section A-A --Looking West 9eanir" i REVISION 1: 6-25-84

DRAWINGS (Cont'd) Finure No. Title 8 Service Water Pump House '9 ' Turbine Building - Plan and Clevation 412'-0" 10 Turbine Building - Plan at Elevation 436'-0" 11 . Turbine Building - Plan at Elevation 463'-0" i 1 .~ j Geertle 11 REVISION 1: 6-25-84

1.0 INTRODUCTION

p This report responds to a request by the United States 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 reconumendations as reported in NUREC-0612, " Control of Heavy Loads at Nuclear Power Plants." The procedures to implement the reconnendations of NUREC-0612 were outlined in enclosures that accompanied a letter dated December 22, 1980, by Darrell C. 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 smalli or that the estimated consequences of such a load drop will not exceed the limits set by the evaluation criteria of NUREC-0612. The review that is addressed in this report follows the guidelines as set forth in Darrell C. Eisenhut's December 22, 1980 letter,, and Section 5 of NUREC-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. n ( Geert/Commanuseu l-1 REVISION 12 6-25-84 b

.j s Summer Nuclear Station, this is defined as a load greater than \\- ) ,) 2500 pounds. The guidelines for this report are: Identify all overhead handling devices from which a load drop a. 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-proof 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 NUREC-0612. [) 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 10,000 Pounds or More for Nuclear Material. P f. . Verify cranes are designed according to CMAA Specification 70 and ANSI B30.2-1976, Overhead and Cantry Cranes, Chapter 2-1. g. Verify cranes are inspected, tested, and maintained in accordance with ANSI B30.2-1976, Overhead and Cantry Cranes, (~']T Chapter 2-2. Q. Geert /*" 1-2 REVISION 1: 6-25-84 L

l .h. Review crane operators' training, qualifications, and conduct in reference to ANSI B30.2-1976, Overhead and Gantry Cranes, Chapter 2-3. -Revision 1 of GAI Report 2364 incorporated changes resulting from l comments made by the NRC through EG&G Idaho, Inc., Report j EGG-HS-6371. This issue was also intended as a general update to the original report which was prepared during the construction of l the Virgil C. Summer Nuclear Station. Revised items included the addition of piping, valves, and conduit into the determination of safe load paths; dynamic analysis of lifting devices; and the addition of several small hoists. A field walkdown of all the hoists at the Virgil C. Summer Nuclear Station was conducted on April 2 through 5, 1984, to determine the locations of the safe shutdown / decay heat removal piping, valves, cable trays and conduit previously excluded from the study. Several items of concern were discovered during the re-evaluation and were 7 investigated for Revision 2 to this report. These items were mainly concerned with safe load paths. Revision 2. incorporates'the changes recommended in Revision 1. The necessary protectivt guards, trolley stops, sud piping support

modifications were designad under Virgil C. Sususer plant modification number MRF 20725 and are scheduled for installation in 1985. The structural floor analyses recommended in Revision 1 were completed, with results provided;in Appendix A.

The' procedural. changes reconssended for electric hoists XCR-19 and XCR-27.have been incorporated into the applicable SCE&G maintenance procedures. 4 Maintenance procedure changes for the special. lifting devices for reactor vessel servicing (reactor vessel head lifting and the vessel. internal life rig) have been developed based on the intent l(C of Westinghouse recommended guidelines in Section 4.2.3 cf this f L -report. + Geert/Commanussah 1-3 REVISION 2: 1-21-85 2

~The above-mentioned changes when complete vill bring the {D' Virgil C. Summer Nuclear Station into compliance with NUREC 0612, to the extent practicable. Table 1-1 lists the general information for each overhead handling . device at the Virgil C. Sunumer Nuclear Station. \\ 4 F 6 L} Geert/Commenuesth 1-3a REVISION 2: 1-21-85 L_ :

n- ,, ~ p ,- \\, ( TABLE l-1 OVERHEAD HANDLING DEVICES, VIRGIL C. SID9 DER NUCLEAR STATION Heavy Loads Handled Load Crane I.D. Crane Type and Liftina Device Weight Finure No. Location XCR-1 Reactor Cavity Spent and New Fuel 2500 lbs 5, 6, & 7 463' el. Manipulator Crane Assembly and Randling Reactor Tool Building ICR-2 Spent Fuel Pit Spent Fuel Assembly 2500 lbs 5&7 463' el. Fuel & XCR-16 Bridge Crane and Handling Tool Handling Building XCR-3, Fuel Handling a) New Fuel Shipping 6600 lbs 5&7 463' el. Fuel f XCR-45, & Building Crane Container and Handling XCR-49 Vendor-Supplied Building 7" ~ 8' Lifting Device s b) Spent Fuel (Note 2) Shipping Cask and Vendor-Supplied Lifting Device c) Fuel Transfer 4500 lbs Canal Cates and 2 Part Sling Cable R d) Irradiated 50,000 lbs. Specimen Shipping est. m Cask and Vendor-g[ Supplied Lifting Device (Note 1) y ~ Notes: Ej* 1. Assumed to be an irradiated fuel assembly. 3 2. This device has not been purchased since Virgil C. Summer Nuclear Station is currently installing capability for onsite storage (i.e., spent fuel racks).

,o p ~y TABLE l-1 (Cont'd) Heavy Loads Handled Load Crane I.D. Crane Type and Lifting Device Weight Figure No. Location ICR-4 Reactor Building a) CRDM Missile-54,000 5, 6, & 7 552' el. Polar Crane Shields 1bs Reactor i b) Reactor Vessel Head 268,000 Building Assembly lbs c) Reactor Vessel Head 21,000 lbs Lifting Rig i d) Upper Internals 92,000 i and Internals 1bs Lifting Rig ] e) Lower Internals 268,000 ~ and Internals 1bs I. { Lifting Rig f) Internals Lifting" 19,000 - ~ 0 Rig Ibs j g) ISI Tool and 20,000 Westinghouse-Ibs i{ Supplied Lifting Device I h) RCP Internals 48,000 } lbs i i) RCP Casing and 52,000 i Lifting Beam Ibs g j) RCP Motor 77,140 ) Ibs g k) RV Studs, Nuts, 8500 lbs i o and Washer Stand [ 1) Equipment Bridge 4000 lbs i ICR-17 Turbine Building Ceneral Electric Less than 7 & 11 (10) 463' el. a crane Turbine Cenerator and max. capacity Turbine y Associated Power Building cn Plant Equipment

This building does not contain any safe shutdown or decay heat removal equipment.

d O O 0 TABLE 1-1 (Cont'd) -Heavy Loads Handled Load Crane I.D. Crane Type and Liftina Device Weiaht Fiaure No. Location ICR-18 '10-ton Electric Power Plant Equipment Less than 4 (2 & 3) 436' el. Cable Hoist and max. capacity ' Auxiliary Trolley Building XCR-19 7.5-ton Electric Power Plant Equipment Less than 6 (2,3,4,65) 485' el. Cable Moist and max. capacity Auxiliary Trolley-Building XCR-20A & 5-ton Hand Chain a) -RHR Pumps 4400 lbs 2 374' el. XCR-208 -Hoist and Trolley b) RHR Pump Motor 3200 lbs Auxiliary Building I 7 XCR-21A 5-ton Manual Chain a) RB Spray Pumps 5400 lbs 2 374' el. & XCR-21B Hoist and Trolley b) RB Spray Pump 5880 lbs Auxiliary Motors Building XCR-54A, 5-ton Manual SI Charging Pumps 2 388' el. XCR-545 & - Chain Hoist and a) Pump 7500 lbs Auxiliary XCR-54C Trolley b) Base 6000 lbs Building c) Cear 2100 lbs d) Motor 6700 lbs g XCR-23A 2-ton Manual a) .RB Spray Sump 3000 lbs 3 412' el. & XCR-23B Chain Hoist and Isolation Valve Auxiliary Trolley Protective Building = -g Chamber Tops b) SI Recirculation 3000 lbs U Sumps. Isolation Valves Protective 4 Chamber Tops Y

O)- .( '.7 /3 i U V TABLE 1-1 (Cont'd) Heavy Loads Handled Load Crane I.D. Crane Type and Liftina Device Weimht Fiaure No. Location XCR-24 8-ton Hand Chain Main Steam Stop Valves Less than 11 463' el. Hoist and Trolley max. capacity Turbine Building XCR-25A,- 10-ton Hand Main Condenser 26,500 lbs 9 412' el. XCR-258, Hoist and Trolley Water Boxes (2 Cranes Turbine XCR-25C, & per Water Box) Building XCR-25D XCR-26 4-ton Hand Chain Feedwater Booster 9 412' el. Hoist and Trolley Pumps Turbine { a) Pump 7800 lbs Building b) Driver 8500 lbs - ~ 4 c) Bedplate 5900 lbs XCR-27 5-ton Electric Power Plant Equipment Less than 4 436' el. Cable Hoist and max. capacity Intermediate Trolley Building XCR-28 2-ton Electric Chemical Storage Less than 1 Water Cable Hoist and Containers max. capcity Treatment Trolley Building 5< XCR-29A, 2-ton Hand-Cenerator Parts Less than 4 Diesel m XCR-29B Operated Hoist max. capacity Generator g and Trolley Building I XCR-31 1/2-ton Hand Under heavy load 4 436' el. Chain Hoist and limit Intermediate [ Trolley Building

This building does not contain any safe shutdown or decay heat removal equipment.

a

D TABLE.1-1 (Cont'd) Heavy. Loads. Handled Load Crane I.D. Crane Type and Liftina Device Heizht Finure No.- Location ICR-33 ton Hand Chains Turbine-Driven 3 412' el. Hoist and. Trolley Emergency Intermedlate Feedwater Pump Building a) Pump 3000 lbs b) Base 2400 lbs c), Driver 3260 lbs XCR-34 1-ton Electric-Under heavy load H/A 4 Reactor Cable Hoist and . limit Building Trolley Tendon Access f Callery XCR-36 20-ton Electric Radweste Facility Less than 4 436' el. Cable Hoist and Equipment max. capacity Drumming Trolley Station ICR-40 5-ton Hand Chain Main Steam 4500 lbs 4 436' et Hoist and Trolley Isolation Valve Intermediate ' Subassemblies' Building XCR-40A, 10-ton Hand Chain Main Steam 4500 lbs 4 436' el. so XCR-408, Hoists and Isolation Valve Intermediate XCR-40C Trolleys Subassemblies Building as o XCR-42 10-ton Bridge Hot Machine Shop Less than 4 Hot [ Crane Applications max. capcity Machine Shop I XCR-43 10-ton Bridge -Service Building Less than 1 Service y ' Crane Applications max. capacity Building - *This building'does not contain any safe shutdown.or decay heat removal equipment.

,x s TABLE 1-1 (Cont'd) Heavy Loads Handled Load Crane I.D. Crane Type and Lifting Device Weight Figure No. Location' XCR-46 3-ton Bridge a) Concrete Plugs 1770 lbs 5 463' el. Crane b) Filters and Negligible Auxiliary Cartridges Building c) Storage Casks 2590 lbs XCR-47 10-ton Bridge Hot Machine Shop and Less than 4 436' & 447' Crane Low Level Waste max. capacity el. Drumming Storage Station ICR-48 1-1/2-ton Hand Instrument and Less than 9 412' el. Chain Hoist and Service Air max. capacity Turbine Trolley Compressors Building E XCR-51 & 10-ton Bridge a) Service Water Less than 8 436' el. XCR-50 Crane and Hoist Traveling Screen max. capacity Service Water Parts Intake Screen b) Service Water 14,000 and Pumphouse Pump lbs c) Service Water 15,650 Pump Motor Ibs XCR-53A, 2-ton Twin Hook CRDM Cable Support N/A 5 475' el. XCR-538, . Extension Hoists Structures Reactor m{ XCR-53C Building sa o XCR-55 1-ton Jib Crane Under heavy load N/A 5 463' el. limit Reactor Building i Ul

This building does not contain any safe shutdown or decay heat removal equipment.

q g r. ~y sj: P TABLE 1-1 (Cont'd) Neavy Loads Naadled Load Crane I.D. Crane Type and Liftian Device Weiaht Fiaure No. Location ICR-56 1-ton Jib Crane Under heavy load N/A 5 463' el.. limit Reactor Building ICE-57 1-ton Jib Crane Under heavy load N/A 5 463' el. limit Reactor Building ICR-58 1-ton Jib Crane Under heavy load N/A 5 463' el. limit Reactor 7 { Building XCR-60 1/2-ton Mand Chain Under heavy. load N/A 5 485' el. Noist and Trolley limit Auxiliary Building ICR-61 1/4-ton Jib Crane Under heavy load N/A 4 457'-0" el. -limit Control Building IEW-11 1-ton Jib Crane Under heavy load N/A 4 436' el. l limit Drunning g Station o:s IEW-13 3-ton. Jib Crane a) Concrete Fluss 1770 lbs 4 436' el. b) Spent Filters Negligible Drunning and Cartridges Station c) Storage casks 2590 lbs e h d) Lifting Beaa 1350 lbs E Reactor Building Equipment N/A 5 463' el. Equipment Access Match Reactor Match Door Building

l 2.0

SUMMARY

(Tv) This report presents the results of the study areas in the Virgil C. Summer Nuclear Station where an inadvertent 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 inadvertent drop could cause a radioactive release that could result in significant offsite doses were also included. 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 are permanently marked, where practical. Riggers and Q operators receive training to fully understand and adhere to the safe load path concept. In addition to the safe load paths, special operating procedures have been 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 holsts. These procedures are incorporated into the plant's operator and rigger training program. v Gert/Ph 2-1 REVISION 2: 1-21-85

y I 4 XCg-238 O Place a trolley stop at a distance 5'-10" from the north end of - the monorail. Xcs-27 1. . Institute administrative procedures to protect the ductwork and piping at elevations 426'-10" and 424'-0". 2. Add protective guards for the cable tray at elevation 420'-0" and the chilled water risers at elevation 436'-0". 3. Investigate the ability of the floor at the south edge of the hatchway to resist the penetration of a 5 con load. Eft!-il { Investigate the ability of the floor directly beneath the hoist to resist the penetration of a 3 ton load. IEd.1 Investigate the ability of the floor directly beneath the hoist to resist the penetration of a 10 ton load. Liftina Devices Incorporate the recommendations listed in Section 4.2 into the applicable maintenance procedures. t s 0 0 -,\\/ GesM10ammemment 2-2 REVISION 11 6-25-84 a (

_r 7 3.0 IDgNTIFICATION OF OVgRHEAD HANDLINC DEVICES +Qp 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. gach 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 I'tems that the device was designed and designated to handle. The Virgli 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 handling 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 rolesee, such_as the spent fuel pool or reactor vessel. The safe shutdown and decay heat removal components considered in this study 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 defined as an area within the crane's or hoist's range where none of the above components are located.. The only esceptions are those necessary components serviced uniquely by a crane or hoist for {G.l v' ensnicamemann 3-1 REVISION 1: 6-25-84 m-

r 4 .O-maintenance. The overhead handling device will not be operated until'after these components have been 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 NUREC-0612 and Attachment 4 to Enclosure 3 of D. C. Eisenhut's December 22, 1980 letter, in order to demonstrate compliance to Criteria III and IV of Section 5.1 of NUREC-0612. The results and evaluation of this study are presented in - Appendix A. Safe load paths for'some cranes and holsts could not be defined. In those cases procedures have been generated and design modifications have been made where necessary to minimise the chances and the consequences of an inadvertent load drop. Procedures for overhead handling devices have been developed to dictate the operation and use of the device. / Table 3-1 Lists-the impact area, the designated heavy loads and weights for each overhead handling device, and the safe shutdown / decay heat removat equipment that could be effected for each overhead device. Table 3-1 also lists a hasard elimination category, which according to Enclosure 3, Figure 1 of D. C. Eisenhut's December. 22, 1980 letter aret 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 elletnate the need to consider equipment combination, h V soeces===== 3-2 REVISION 18 6-2$-84 4

c: d. Likelihood of handling system failure for this load is extremely small (i.e., Section 5.1.6 NUREC 0612 satisfied), and e. Analysis demonstrates that crane failure and load drop will not damage safety-related equipment. In addition to the hasard elimination categories listed in D. G. Eisenhut's letter, the following categories are included: f. Load is less than the minimum required by NUREG-0612. 3 Administrative procedures will be instituted to govern this hasard. h. Protective devices are installed. ( O L) Gest /Commensese 3-3 REVISION 2: 1-21-85

_g'"s 3.1 Reactor Cavity Manipulator Crane (XCR-1) Reactor Cavity Manipulator Crane XCR-1 is located on elevacion 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 hois't. 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 s.,_ handling of fuel assemblies during refueling of the reactor. Crane operation is governed by Westinghouse Refueling Procedures. By definition of a heavy load, this overhead handling de/ ice does not handle heavy loads and can be excluded from further study or concern. 4: edet/Comunseem 3-4 REVISION 1: 6-25-84

} . (A - 3.2 Spent Fuel Pool Bridae Crane (XCR-2 and XCR-16) u) 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 1 cad 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 Figures 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 HarnisciifegerCompany. 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 ' O 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. r r 1. l. The lift as given is the maximum from the eye of the hook to the top of the beami the actual lift as installed may be equal or less than this maximum. w, Gest /Cannenessa 3-5 REVISION 1 6-25-84 i ..._._..-......,.m..._.-_......,_~,

rc - ~ 3; 3.3 Fuel Handlina Buildina Crane (XCR-3. XCR-45. XCR-49) =. ! \\ Fuel Handling Building Crane XCR-3 has associated with it the Fuel Transfer Canal Cate, 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 LPool. The Fuel' Handling Building Crane is supplied by the Whiting Corporation and the Fuel Transfer Canal Cate Holst is supplied by ~ ' g(, the American Chain and Cable Company. The Fuel Handling Building -Crane has a main electric motor cable hoist with a 125 ton j -v capacity, a sister hook with eye, and a potential for a 60 foot . lift. The auxiliary electric motor cable hoist has a 25 con capacity, a single hook, and a potential lift of 60 feet 6 inches.1 -The-Fuel Transfer Canal Cate Holst 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. i lt 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. .. A - S-Best/Commensemh 3-6 REVISION 1: 6-25-84 't

. = -. d':d TheFuctHdndlir.gBuildingCraneisdesignatedtohandleNewFuel /~N Shipping Containers, Spent Fuel Shipping Casks and Irradiated ~- Specimen Shipping' Casks with vendor-supplied lifting devices. The . ( Fuel Handling Building Crane does not carry a heavy load within an i~ a.,- 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 Cate Hoist is designated to handle the Fuel Transfer Canal Cates with a two point sling cable. Procedures have been developed (See Section 4.0) to minimize the risk of a dropped heavy' load in the Fuel Handling Building. . 2# { Special procedures have been developed for the Fuel Transfer Canal Cate Hoist since it is necessary to operate within 15 feet of the Spent Fuel Pool. Refer to CMP 100.012, " Crane Operations - Fuel Handling Building." ,;l'"~ - y V ~ ,.,y 4- 'l' r vu . s

l. -

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~ t' j'*3 3,4 Reactor Buildina Polar Crane (XCR-4) -O~ Reactor Building Polar Crane XCR-4 is located in the Reactor -Building at elevation 552'. The Reactor Building Polar Crane is shown on Figures 5, 6, and 7. The Reactor Building Polar Crane is supplied by the Whiting Corporation 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 . f'T ( ) operated 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, XSC-2A,B-RC. -c. Pressurizer, XTK-24-RC. 'd. ' Reactor Building Cooling Units, XAA-1A,B-AH and KAA-2A,B-AH.

e..

Reactor Building Cooling Unit Fans, XFN-64A,B-AH and 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

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("N . Westinghouse study has shown that effects of a dropped heavy load would not result in damage to the reactor vessel, reactor pressure x . vessel, and reactor coolant system piping pressure boundary, core cooling capability, or integrity of the fuel cladding such as to exceed Criteria I through IV of Section 5.1 of NUREC 0612. The . procedures used by Westinghouse in this analysis are presented in Appendix B. 6 r -f c ks I t t l-i 2 l IL l ..7 j; A ~ amart/commenssee i I 3-9 REVISION 1: 6-25-84 (.- s =gg

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r s ~3.5 Turbine Building Crane (XCR-17) { \\ '\\ / 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 overhead 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 77 accordance with CMAA Specification 70 for Class A indoor service -i \\m / 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. P 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. ,\\ .\\ v Geert/r " 3-10 REVISION 1: 6-25-84 . ~,,

m t cr'41 3.6 10-Ton Electric Cable Hoist and Motor Operated Trolley (XCR-18) U The-10-ton electric cable hoist and motor operated trolley XCR-18 is located on elevatio'n 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 hatch and surrounding area through elevations 436',~412', 397', 388', and 374' of the Auxiliary Building. The safe load path is shown on Figures 2, 3, and 4. LThis monorail and hoist system is designed in accordance with HMI 100, Standard Specifications for Electric Wire Rope Hoists. 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.l The hoist's lifting device is a forged steel shank hook. The 10-ton electric cable hoist'is designated to lift power plant y(_s) . equipment through-the equipment hatch'from elevations 372' to 436'- 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' removal. Therefore, the hoist is-excluded from further study and concerns. y 1 - 1. The lift as.given is.the maximum.from the eye of the hook to the top of othe beam; the actual lift as installed may be equal or~less than this ~

maximum.

' g. Geert/r- '3 REVISION 1: 6-25-84

r~ s j-3.7 7.5-Ton Electric Cable Hoist with Motor Operated Trolley (XCR-19) \\ 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 through 5. This monorail and hoist system is designed in accordance with HMI 100, Standard Specifications for Electric Wire Rope Hoists. 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 s trolley. The hoist-has 126 foot lift and is controlled by a hand-held controller.1 The hoist's lifting device is a forged steel shank hook. The 7.5-ton electric cable hoist is designated to lift general a power _ plant equipment.through the equipment hatch from .\\. elevations 388' to 485' of the Auxiliary Building. Several safety related cable trays and pipelines are located near the hatchway . opening at various elevations. The following items were considered as possible hazards: three cable trays located near the north side of the hatchway at elevations 471'-11", 476'-2", and 476'-6"; a.16" service water line running near the southeast corner of the hatchway at elevation 451'-6"; and a cable tray E located: near the southeast corner of the hatchway at elevation 428'-3". None of the affected items are within the load path of the hoist and would not be affected by a direct drop. L r 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. ll [) y L, Geert/r-3-12 REVISION 2: 1-21 " h

E f'~s The three cable trays located at elevations 471'-11", 476'-2", and \\s-476'-6" were considered to be in the most vulnerable position. The trays run diagonally near the northwest corner of the hatch opening, then turn and run along the north side of the hatch. The trays could be struck if an odd size load such as a steel beam were being handled and the operator inadvertently moved the trolley in the wrong direction. This hazard was eliminated through administrative procedures requiring the use of taglines on odd-sized loads. Guards placed on the cable trays were deemed inappropriate since a guard could cause an obstruction of the - hatchway opening, creating a potentially greater hazard. The service water piping located at elevation 451'-6" was determined-not to be a potential hazard due to an uncontrolled movement of the hoist. Calculations were performed to analyze the effect of a t'pical load defined as a large steel beam striking y - the pipe. The basis and results for the calculation are discussed lN~-l in Appendix C, " Analysis of Impact Loads." ,/g The cable tray located at elevation 428'-3" is considered to be a sufficient distance'from the edge of the hatchway to be eliminated as a hazard. The closest distance between the edge of the hatch and the cable tray is approximately four (4) feet. Ccasidering the 32 fpm trolley speed and load sway, the trolley would need to be inadvertently engaged for approximately six (6) seconds before the load would make contact with the cable tray. This is ~ considered to be a. sufficient amount of time for the operator to take corrective action. V Geert/Conunoneesth 3-13 REVISION 2: 1-21-85

-.= ~C'E '5-Ton Hand Chain Hoist and Plain Trolley (XCR-20A/B) p 3.8 ~~s 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. This monorail and hoist system is designed in accordance with HMI 200, Standard Specifications for Hand Operated Chain Hoi ~sts. Hoists XCR-20A and XCR-208 are supplied by the American Chain and -Cable Company and are 5-ton capacity hand operated chain hoists 3 with a plain trolley. The hoists have 20 foot lifts and forged steel shank hooks.1 c The 5 ton hand chain hoists and plain trolleys XCR-20A and XCR-20B are des'ignated 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 7 (,,g ; trolleys XCR-20A and XCR-208. While'a heavy load drop from the hoists could cause damage to the RHR pumps the only time this-would occur 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. -Each pump is isolated in its own concrete cubicle;: therefore, an inadvertent drop by either hoist would not affect the redundant pump. On this basis it can be. excluded from further study or concern.- s 4 1.- .The lift as given is the maximum from the eye of the hook to the top of J "~ the beam;;the actual lift as installed may be equal or less than this maximum. Geente" 3-14 REVISION 1: 6-25-84

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- 3.9 ~ 5-Ton Manual Chain Hoist with Ceared Trolley (XCR-21A/B) \\ 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. This monorail and hoist system is designed L in accordance'with HMI 200, Standard Specifications for Hand Operated. Chain Hoists. Hoists:XCR-21A and XCR-21B are "'pplied by the American Chain and Cable Company and are 5-ton capacity hand-operated chain hoists on geared trolleys. Th5 hoists have a 20 foot lift with forged steel shank' hooks.1 gg Hoists'XCR-21A and XCR-218 are designated to service the Reactor Building Spray Pumps XPP-38A and XPP-38B and associated motors MPP-38A and HPP-388. XCR-21A and 218 are physically. separated by J a concrete wall; therefore, an inadvertent drop by either hoist would not affect the redundant, reactor building spray pump train.

There are no' components necessary for safe shutdown or decay heat removal within the safe load paths of hoists XCR-21A and-XCR-21B, so these hoists are excluded from further' study.

.e t i. t-i.~. r C 1 ~ [ el.- The. lift as given is the maximum from the eye of the hook to the top of i 'the beam; the actual lift as, installed may be equal or l'ess than this l V..N ~ maximum. 'b Geert/P" s 3 REVISION 1: 6-25-84 ..-,at .+...... _,.,.. _ .-_,..--.m._,......-.._.-._.. i -4

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3.10 5-Ton Manual Chain Hoist with Ceared Trolley (XCR-54A/B/C)' I The 5-ton manual chain hoists with geared trolleys XCR-54A, XCR-548,'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. This monorail and - hoist system is designed in accordance with HMI 200, Standard Specifications for Hand Operated Chain Hoists. 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.1 Hoists XCR-54A, XCR-548, 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 ^thelplant. 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. Each charging / safety injection and hoist is,enclo' sed in a separate concrete cubicle. On this basis ' hoists XCR-54A, XCR-54B,-and XCR-54C are excluded from any further l ~ study or concerns. , M: 1 s y 1. The lift as given is the maximum from the eye of the hook to the top of

the beam;1the actual lift' as -installed may be-equal or less than this E.-

maximum.

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3.11 2-Ton Manual Chain Hoist with Plain Trolley (XCR-23A/B) \\,l .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. This monorail and hoist system is designed in accordance with HMI 200, Standard Specifications for Hand Operated Chain Hoists. 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.1 Hoists XCR-23A and XCR-23B are designated to service the Reactor Building Spray Protective Sump Isolation Valve Chambers XSM-4A and XSM-48, and the Safety Injection Recirculation Sump Isolation Valve Protection Chambers XSM-5A and XSM-58. Since the sump isolation valves and associated piping do not normally contain radioactive material, 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 the north end of the monorail for hoist XCR-23B is a Motor Control Center XMC-lDAZY 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 -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. \\ ) w/ GentIcemmenesso 3-17 REVISION 1: 6-25-84

ljr~. Control Center. lie-within the normal load path of XCR-23B, and normal operating procedures and separation distance would preclude any damage from a dropped load to either item. A design has been implemented which would add a trolley stop on the monorail 5'-10" from the north end of the monorail to limit trolley movement. Installation is scheduled for 1985.

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2 m es. A/ Geert /r-3-18 REVISION-2: 1-21-85

-= l/"~'N ' 3.12 8-Ton Manual Hand Chain Hoist with Ceared Trolley (XCR-24) 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.' Elis hoist and trolley are shown on Figure 11 along with their~ safe' load paths. This monorail and hoist system is designed in accordance with HMI 200, Standard Specifications for Hand Operated Chain Hoists. 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.1 Hoist XCR-24 is designated to service the turbine stop valves XVG-2809 A to D. Since the Turbine Building contains no equipe.ent i-necessary for the plant's safe shutdown or decay heat removal, this hoist can be excluded from further study or concern. 4 I L c-1.- The lift as given is the maximum from the eye of the hook to the top of-j -N .the beam; the actual lif t as installed may be equal or less than this i M ) . max mum. \\m,/ I Geert/Commennesp 3-19 REVISION 1: 6-25-84 -n r m. b. ._~.,i_,_..,-...,..,m ....,__,......m._-__._,______,,_.,... ..__._._,.__,.m.._,-

/* 3.13 10-Ton Manual Chain Hoist with Ceared Trolley (XCR-25A/B/C/D) 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. These hoists are shown on Figure 9. This monorail and hoist system is designed in accordance with HMI 200, Standard Specifications for Hand Operated Chain Hoists. Hoists XCR-25A thru XCR-25D are manufactured by the American Chain and Cable Company and are 10 ton capacity hand operated chain hoists on geared trolleys. The hoists have 15 foot lifts and forged steel shank hooks.1 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 for the plant's safe shutdown or decay heat removal, these hoists () 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' h the beam; the actual lift as installed may be equal or less than this maximum. Geert/f-3-20 REVISION 1:- 6-25-84 e rw - m

f~~} _ 3.14 4-Ton Manual Chain Hoist with Plain Trolley (XCR-26) V 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 1 to 3 above the Feedwater Booster Pumps. These hoists are shown in Figure 9. This monorail and hoist system is designed in accordance with HMI 200, Standard Specifications for Hand Operated Chain Hoists. 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 Hoist XCR-26 is designated to service the Feedwater Booster Pumps XPP-28A through XPP-28D. This hoist can he excluded from further study or concern since the Turbine Building contains no equipment necessary for the plant's safe shutdown or decay heat removal. \\ 'l. 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 z( m maximum. mp 3-21 REVISION 1: 6-25-84 }

y D 3.15 5-Ton Electric Hoist with Motor Operated Trolley (XCR-27) The 5-ton electric hoist and motor operated trolley XCR-27 is located in the Intermediate uilding on elevation 436' between column lines C.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. This monorail and hoist system is designed in accordance with HMI 100, Standard Specifications for Electric Wire Rope Hoists. 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 and a forged steel shank hoist.1 Hoist XCR-27-is designated to handle power plant equipment through the eo'uipment hatch from elevations 412' and 436' in the Intermediate Building. No safe shutdown equipment is located (' 'directly in the path of the hoist. However, several items of V safety related equipment are located near.the path of this hoist and could be considered potential hazards if an odd size load such as a steel beam is considered. These include a cable tray near the south side of the hatchway at elevation 420'-0", two 6" chilled water piping risers near the laydown area at elevation 436'-0", a horizontal run of 16" diameter battery room exhaust duct near the east side of the hatch at elevation 426'-10", and two 2" horizontal chilled water pipe runs at elevation 424'-0" near the east side of the hatchway. A protective guard has be'en designed to alleviate the hazard associated with the cable tray 'near the south side of the hatchway at elevation 420'-0". e I 1.- .The lift as given is the maximum from the eye of the hook to the top _of , h 'the beam; the actual lift as installed may be equal or less than this %I maximum. Geert /r -- -- a* .3-22 REVISION 2: 1-21-85 t-

d _( An impact analysis was performed on the two chilled water piping 4 - -risers at elevation 436'-0". It was determined that a guard was not necessary to protect these lines; however, three pipe supports were determined to require reinforcement. The design has been completed for the modification of the pipe supports and is scheduled for implementation in 1985. Details of the impact analysis are provided in Appendix C. The calculated load sway associated with this hoist does not affect either the duct or the horizontal chilled water pipe runs. .Each of these lines run parallel to the monorail, with the closest point being 6'-6-1/2" from the monorail centerline. The maximum calculated sway at this elevation is 6-1/2" from vertical. A hazard does exist due to uncontrolled load rotation. The concrete ,~~ ~ wall along.the. west side of the hatchway will stop the major portion of a load rotation; however, it may not stop all secondary effects. Administrative procedures have been prepared to include E the use of tag lines or that a heavy tarpaulin or net be dropped along the east side of the hatchway ::o limit any load rotation in l the area of these lines. ~ A load drop analysis was performed to investigate the ability of the floor at the south edge of the hatchway to resist the penetration of a 5-ton load. It was determined that the floor would withstand this impact without severe loss of structural integrity.which could jeopardize safe shutdown or decay heat removal components. ' Refer to Appendix A for a detailed y description of the impact analysis. Geert/r-23 REVISION-2: 1-21-85 L__

-f 3.16 2-Ton Electric Cable Hoist with Motorized Trolley (XCR-28) 'x 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 is shown on Figure l' This monorail and hoist system is designed in accordance with ~ HMI 100, Standard Specificatione for Electric Wire Rope Hoists. 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 has a forged steel shank hook.1 Hoist XCR-28 is designated to handle containers from the Water Treatment Building's Chemical Storage area. There are no components necessary for safe shutdown or for decay heat removal in the Water Treatment Building. The hoist is excluded from further study or concern on this basis. V. 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 z.. maximum.. Geertle" 3-24 REVISION 1: 6-25-84 --m-4e m v a4+--.gny yq .-9-gwg.~,q ,wy

p l 3.17 2-Ton Hand Operated Hoist with Ceared Trolley (XCR-29A/B) fj .\\J 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 C.4 to J.1 and column line number 1 above the Diesel Generators. The hoists and trolleys are shown on Figure 4 along with their safe load paths. This monorail i and hoist system is designed in accordance with HMI 200, Standard Specifications for Hand Operated Chain Hoists. l Hoists XCR-29A and XCR-298 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 and forged steel shank hooks.1 Hoists XCR-29A and XCR-29B are designated to service the two standby emergency diesel generators, XEC-1A-DC and XEC-1B-DG, respectively. 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 and are within each crane's load path. The only time the four safe shutdown components are in 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 for maintenance, the other is completely isolated from it and is capable of operating independently. Each diesel generator is isolated in a separate concrete cubicle. On the basis presented above and because the two diesel generator trains are completely redundant, hoists XCR-29A and XCR-298 are excluded from further study or concern. .l. The lift as given is the maximum from the eye of the hook to the top of n the beam; the actual lift as installed may be equal or less than this jv) maximum. Geert /P----- - ** 3-25 REVISION 1: 6-25-84

- r'~'v 3.18 1/2-Ton Hand Chain Hoist and Trolley (XCR-31) ~ t 1 -- V 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 thr: Intermediate Building near column lines H.4 and 2 to 3, and is shown on Figure 4. This monorail and hoist system is designed in accordance with HMI 200, Standard Specifications for Hand Operated Chain Hoists. 'O -d e p; '%Y.. Gdhert/Comumenmenth 3-26 REVISION-1: 6-25-84

7 m ( ) 3.19 2-Ton Hand' Chain Hoist With Trolley (XCR-33) ' %_./ 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. This monorail and hoist system is designed in accordance with HMI 200, Standard Specifications for Hand Operated Chain Hoists. Hoist XCR-33 is supplied by the American Chain and Cable Company, and is a 2-ton capacity, hand operated, chain hoist with a plain trolley. The hoist has a 10 foot lift and a forged steel shank hook.1 Hoist XCR-33 is designated to service the Turbine Driven Emergency Feedwater Pump XPP-8-EF. The pump and its turbine driver are .. /N within the hoist's safe load path and are necessary for the I e 3s/ 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 two Motor Driven Emergency Feedwater Pumps which are physically separated from the turbine driven Emergency Feedwater Pump and are not serviced by XCR-33, the hoist 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 7T-the beam; the actual lift as installed may be equal or less than this .Q maximum. Geert/P-3-27 REVISION 1: 6-25-84

7-(~'s 3.20 1-Ton Electric Cable Hoist and Trolley (XCR-34) b~/ 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 Callery, and can be found on Figure 4. This monorail and hoist system is designed in accordance with HMI 100, Standard Specifications for Electric Wire Rope Hoists. !~ f f\\ 2D 4 i :: d Geert/Commennede 3-28 REVISION 1 6-25-84 .ma

L i I i 20-Ton Electric Cable Hoist with Motorized Trolley (XCR-36) 3.21 ^ ( -y. \\ V i "The 20-ton electric cable hoist and motorized trolley XCR-36 is located in the Drumming Station on elevation 436' between column l . 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. This monorail and hoist system is designed in accordance with HMI 100, Standard 4 Specifications for Electric Wire Rope Hoists. i i 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.1 Holst XCR-36 is designated to handle low and high level radiation j shipping casks. There are no components necessary for the plant's I safe shutdown or decay heat removal on elevation 463' and within the hoists safeload path. Below hoist XCR-36, however, on ]7"i elevation 412' are the Spent Fuel Pool Cooling Pumps, XPP-32A and N_ / XPP-328. These pumps are classified as Safety Class 2b. A study i of the effects of dropping a Radwaste Cask on the floor of elevation 436' of the Drumming Station above the Spent Fuel 1 Cooling Pumps (Appendix A) indicates that the floor structure j 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 Radwaste 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 lif t as installed may be equal or less than this maximum. O v Bert/Cammensath 3-29 REVISION 1: 6-25-84 m

f q 3.22 10-Ton Hand Chain Hoists with Ceared Trolley (XCR-40A/B/C) b The 10-ton hand chain hoists and geared trolleys XCR-40A, XCR-408, and XCR-40C are located on elevation 436' of the Intermediate Building between column lines U.4 to J.1 and 2 to 8 above tne Main Steam Isolation Valves. The hoists and valves are shown on Figure 4 along with their safe load paths. This monorail and hoist system is designed in accordance with HMI 200, Standard Specifications for Hand Operated Chain Hoists. 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 an approximate 15-foot lift and a forged steel shank hook.1 Hoists and trolleys XCR-40A, XCR-408, and XCR-40C, along with a transfer rail, are designated for servicing the Main Steam p Isolation Valves, XVM-2801 A through C. The Component Cooling b Heat Exchanger, XHE-28-CC, the Component Cooling Pumps, XPP-1A through C, and the Motor Driven Feedwater Pumps, XPP-21A and XPP-218 are located directly below the hoists and trolleys on elevation 412' of the Intermediate Building. 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 would not normally be utilized to lift and move the heaviest part (i.e., the valve body) 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 less than this rr.4ximum. pV Geert/r - 3-30 REVISION 2: 1-21-85 .y.

p- ~4 - Two vertical nuclear safety-related service water risers are 'Ns,/c located approximately three (3) feet from the end of the XCR-40B monorail. -Calculations were performed that show the maximum amount of load sway for these hoists will not exceed three (3) inches from the vertical. This calculation is based on data from the' hoist manufacturer, a chain overhaul of 120 ft/ min., and the hoist hitting the monorail stops. Therefore, rh.e service water risers would not be affected. This information, combined with the fact that the hoists do not handle odd sized loads or operate unless the plant is in cold shutdown, is sufficient to eliminate service water risers as potential hazards. -O V b \\ Geert/Cammenw W 3-31 REVISION 2: 1-21-85 i-

p- .p 3.23 10-Ton Bridae Crane and Electric Cable Hoists (XCR-42) The 10-ton bridge crane and electric cable hoist XCR-42 is located in the Hot Machine Shop at elevation 436' between column lines R.2 to S and 11.6 to 7.8. The hoist is shown on Figure 4. 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.1 There are pushbutton controls fo.- both the c. 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 C indoor service, and ANSI B30.2, Chapter 2-1. l 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. s 7 1 T 1. The lift as given is the maximum from the eye of the hook to the top of the beams the actual ~ lift as installed may be equal or less than this maximum. O .\\j Gews/Coussenessah '3-32 REVISION 1: 6-25-84

h y('^$ - 3.24 10-Ton Bridae Crane and Electric Cable Hoist (XCR-43) fiv/ .The 10-ton bridge crane and electric cable hoist XCR-43 is located in the Service Building and essentially encompasses the Service Building Machine Shop. The crane is shown on Figure 1. Crane XCR-43 is supplied by the American Chain and Coble 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 stee.1 shank main and safety hook.1 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 C indoor service, and ANSI B30.2, Chapter 2-1. Crane and hoist XCR-43 are designed for Ceneral Service Building application in the Service Building Machine Shop. The crane can be excluded from any further study or consideration since the Service Building contains no equipment necessary for either safe 3 j J.; shutdown or. decay heat removal. ?.' 1 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 ~ j. maximum. i o .[h I-( x- /. Gdtert/r-3-33 REVISION 1:.6-25-84 ew y-,---,-,w. g.- 9 yw. ,w.-,-, -,r w .w-- a,-- ,.we-.g e we + * -"'--*fe w-e-r--* +-

r. l ~3.25 3-Ton Bridae' Crane with Electric Cable Hoist (XCR-46) .f-d~ 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 i capacity. The crane is an underhung, single beam, motor driven, 1 -f center driven type crane, and the hoist is an electric cable w 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 C indoor service, and ANSI B30.2, u

Chapter'2-1.

J Crane XCR-46 is designated to remove the concrete plugs and spent filter cartridges from their housing and transport the spent filter and' cask to the Filter Hatch. The concrete plugs and spent filter cartridges are below the heavy load weight limit. If an w . inadvertent drop of a radioactive filter occurs, the possible effluent release would result in insignificant offsite doses due to the small. amount of radioactive material contained in the U filters, and its 'ow level radioactive nature. l 30 ,s The only safety'related. equipment in the vicinity of-the hoist is a cable tray which runs parallel to the monorcil. - The tray itself is located away from the path of the hoist; however, the tray

3 f;.

supports are located 30-1/2" from the monorail. The tray is GestIP - 3-34 REVISION 1: 6-25-84 t

. Q {MiQ- .4 3 ceiling-supported and the bottom of the support is 3'-10" below . k /. j. ithe bottom of the monorail. i The shipping casks have a 20" square base and are carried from the ,1 . cask centerline. A calculation was performed to determine the s ,.3. maximum amount of load sway for XCR-46. The calculation assumed ':~4Li" hat the load was -fully extended, the trolley was travelling at ~ t ,ifull' speed, and the hoist came to a sudden stop. This results in n e, 4 a load sway _of 9 inches in the direction of trolley travel at the . floor 12'-9" below the monorail. Since-the load would have to ' sway perpendicular to the direction of travel to strike the-supports,.a circular load, swing was assumed. This places the most outward' corner of the cask'a distance of 23" from the centerline i A of the monorail at floor elevation. The bottom of the tray supports are 8'-11" above the floor and well out of the-sway path. .h ^ ~ Severaliitems of safety related equipment are located on the + i ~ t' ifloors below XCR-46. These are listed in Table 3-1.- A structural y( 7 l LV ' analysis of the-floor directly.below XCR-46 has been performed to .l. determine the structural integrity of the floor in case of a 3 ton . load' drop. It was determined-that.the floor slab would withstand ~ the impact load'vithout severe loss of structural integrity which' x O'ft: 1could jeopardize safe shutdown or decay heat removal components. T Referlt'o Appendix A for a. detailed description of the impact .' analysis.

3' u

e r q gg ffg[ s '[ %23 g O

,j,l j'

I c jb A NWll - 3-35' REVISION-2: 1-21-85 k t ' ' ' ^ ^ y -,.a. .._.,,....;a.n- ,~ _..:. n... -,, _. _. ,.--.,_.._,_..,.n.._,.

IE ~ 3.26 10-Ton Bridae Crane and Electric Cable Hoist (XCR-47) The 10-ton bridge crane and electric cable hoist, XCR-47, are 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 an 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 crane. The crane is designed in accordance with CMAA Specification-70.for Class C indoor service, and ANSI jy .B30.2, Chapter 2-1. M). , 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, i.

s No safe shutdown or decay heat' removal equipment is located'in the }g immediate vicinity of XCR-47; however, several safety related pipelines are' located on the floors below.- These lines are in no 1.;.The lift as given is the maxinna from the eye of the hook to the top of the beam; the actual lif t as ' installed may be equal or less than this maximum. Geert/f" 3-36 REVISION 1: 6-25-84

. (W.- . danger from a heavy load drop. A study Conducted for this r .(f vicinity of the Intermediate Building (presented in Appendix'A) showed that dropping a 10-ton load on the floor of the Intermediate Building at elevation 436'-0" would not result in severe loss of structural integrity of the floor. On this basis, XCR-47 can be eliminated from further study or Concerns. O u / i q Geert/Commenuesth 3-37. REVISION 2: 1-21-85

s " s[ 3.27 1-1/2 Ton Hand Chain Hoist and Plain Trolley (XCR-48) ~ \\s, The 1-1/2 ton hand chain hoist with 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. This monorail and hoist system is designed in accordance with HMI 200, Standard Specifications for Hand Operated Chain Hoists. Hoist XCR-48 is supplied by the American Chain and Cable Company, and is a 1-1/2 ton capacity, manually operated, chain hoist on a plain trolley. The hoist has a 17 foot lift and a forged steel shank hook.1 Holst'and trolley XCR-48 service the Instrument and Service Air Compressor, XAC-3A and XAC-38, which are not necessary for safe shut down or decay heat removal. On this basis XCR-48 can be excluded from further study or concern. ,,s [ x. 7 -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. fSv)- 1 Geert/r-3-38 REVISION 1: 6-25-84

m 3.28 10-Ton Bridge Crane and Electric Cable Hoists (XCR-50, XCR-51) .v 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 lift.1 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. Three monorails are associated with the crane and 1.1ists, 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 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. The Service Water Pumps are necessary for the safe shutdown of the plant. Each pump is contained within its own concrete cubicle. The only time the crane and hoist are in operation is when an associated pump and screen are being serviced. When the pump and screen are being serviced they are isolated from the Service Water System, and at the time are not required for the plant's safe shutdown. The three Service Water l-Pumps have a 2 out of 3 redundancy. Due to space limitations and physical separation by concrete walls, it is physically impossible l l .1. The-lift as given is the maximum from the eye of the hook to the top of f the beam; the actual lift as installed may be equal or less than this -( j maxtmum. v Geert/Commanuseith 3-39 REVISION 2: 1-21-85 L

c. of-g- _for the hoist to travel over an operating Service Water Pump and k -) Traveling Screen while carrying a designated heavy load. s Several service water discharge lines are located on the elevations below the floor of XCR-51. A structural analysis of the floor directly below XCR-51 was performed to determine the structural integrity of the case of a 10 ton load drop. It was determined that the floor slab will withstand the impact load without severe loss of structural integrity which would jeopardize the service water piping. Refer to Appendix A for a detailed description of the impact analysis. .,O t 4 %../ LJ m p.-. 3-40 REVISION 2: 1-21-85 3.

~ s'-'V 3.29 2-Ton Twin Hook Extension Hoist (XCR-53A/B/C) (V) 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-538, 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-three hoists are used to lift the hinged CRDM Cable Support Structures through a defined arc path during refueling or maintenance outages. Since the hoists are only used during cold ~ hutdown, the hoists can be excluded from any further study or s l] - concern. p). ( \\_ /. mjem 3-41 REVISION 1: 6-25-84

r. 3.30 1-Ton Jib Crane - Rad Waste Package (XRW-11) I( ]/ v A one-ton capacity jib crane, XRW-ll, is furnished as part of the ~ Rad Waste Package. Since this crane's rated maximum capacity is under the heavy load limit of this study it is not considered further, and is included herein only for reference and .i 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 v 4 0 3 p') Gdbet/f-3-42 REVISION 1: 6-25-84

(._ ['). .3.31 3-Ton Jib Crane - Rad Waste Package (XRW-13, XCR-46) -Q) A 3-ton jib crane, XRW-13, is furnished as part of the Rad Waste Package in the same area as hoist XCR-36. 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 (w_,) XCR-46 and places them in temporary storage. The potential I I 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 filter .and its low level nature. 1 i, \\ I s/ l ,,,,r______ l 3-43 REVISION.1: 6-25-84 1

3.32 Reactor Building Equipment Access Hatch Crane v 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. a 1 'I v-Geert/r-3-44 REVISION 1: 6-25-84

~g -3.33 5-Ton Hand Chain Hoist (XCR-40) -LI. XCR-40 is a 5-ton hand chain hoist with a geared trolley located at elevation 436'-0" of the Intermediate Building between column lines H.4 to H.7 and 5.9 to 7.5. The hoist is shown on Figure 4, along with its safe load path. The hoist and trolley is designated for servicing Main Steam Isolation Valve XVM-2801A. This monorail and hoist system is designed in.accordance with HMI 200, Standard Specifications for Hand Operated Chain Hoists. Component Cooling Water Pump XPP-1B-CC, several chilled water pipes, and several essential duct runs are located directly below floor elevation 436' in the load path of XCR-40. A study of the effects of dropping a Main Steam Isolation Valve on the floor at 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 A safe shutdown / decay heat removal equipment below. The study was very conservative considering that the hoist was assumed to. lift the valve body (i.e., the heaviest part). See electric hoist XCR-40. A Id onesIc-an 3-45 REVISION 2: 1-21-85

E~ 1 L( 3.34 One-Ton Jib Cranes and Electric Chain Hoists (XCR-55, XCR-56, KCR-57, and XCR-58) XCR-55, ICR-56, XCR-57, and XCR-58 are one-ton jib cranes located .within the Reactor Building. These cranes are shown on Figure 5. -XCR-55 is located at elevation 463'-0" near Steam Loop A. XCR-56 is located at elevation 463'-0" near Steam Loop B. XCR-57 is located at elevation 463'-0" near Steam Loop C. XCR-58 is located at elevation 463'-0" near Steam Loop B. Each jib crane is provided with a one-ton electric chain hoist and motorized trolley. 13ut hoists are intended to handle miscellaneous loads during maintenance outages. These cranes are being excluded frem further study on the basis that they only handle loads lighter than the 2500 lb minimum required by NUREG-0612. A k_ I' 1 l' I '(s_/ Geertic-3-46 REVISION 1 6-25-84 ~

r- [ 3.35 1/2-Ton Hoist (XCR-60) 'w/ XCR-60 is a 1/2-ton manual chain hoist located at elevation 485'-0" in the Auxiliary Building near Boric Acid Tank A. The hoist is shown on Figure 5. This crane.is being excluded from further study since the hoist's rated capacity is less than the 2500 lb minimum. The hoist has been included herein for reference and completeness. .7 i .( t ,v Gdhertle" 3-47 REVISION 1 6-25-84

F. A' 3.36 1/4-Ton Jib Crane With Electric Hoist (XCR-61) XCR-61 is a 1/4-ton jib crane located at elevation 457'-0" of the Control Building. The jib crane is fitted with a 1/4-ton electric hoist designated for lifting various control equipment. The rated capacity of the hoist is less than the heavy load established for this report; therefore, it can be excluded from further study. - O ij G ' U Geert/Camunessah 3-48 REVISION 1 6-25-84

( I ( ( sx. s s TABLE 3-1 HEAVY LOADS VS. IMPACT AREA HAZARD ELIMINATION CATEGORIES (as defined for each overhead lifting device) Crane travel for this area / load combination prohibited by electrical interlocks or mechanical stops. a. b. System redundancy and separation precludes loss of capability of system to perform its safety related function following load drop in this area. Site-specific considerations eliminate the need to consider equipment combination. c. d. The likelihood of handling system failures for this load is extremely small. { Analysis demonstrates that crane failure and load drop will not damage safety related equipment. e. f. Load handled is less than the minimum required by NUREC-0612. g. Administrative procedures govern this hazard, h. Protective devices designed and scheduled for installation. 55 m O= U T2 b i

m /\\ -TABLE 3-1 (Continued) Overhead Lifting Device: Reactor Cavity Manipulator Crane, ICR-1 Impact Area: Elevation 463' above Reactor Vessel Cavity and Refueling Canal, Reactor Building Figures: 5, 6, and 7 Designated Heavy Safe. Shutdown / Decay Elevation of Hazard Elimination ~ Section' Reference Load and Weight Heat Removal Equipment Equipment Category (Remarks) Spent and New Fuel Reactor Cavity 463' c,f See Section 3.1 Assembly and Handling Tool 2500 lbs. , f a N

5 5

e i U

O O O-TABLE 3-1 (Continued) Overhead Liftina Device: Spent Fuel Pit Bridge Crane, ICR-2 Impact Area:' Elevation 463', column lines Q.5 to R.5 and 2.5 to 2.6, Fuel Handling Building Figures: 5.and 7 Designated Heavy Safe Shutdown / Decay Elevation of . Hazard Elimination Section Reference Load and Weight Heat Removal Equipment Equipment Category (Remarks) Spent Fuel Assembly Spent Fuel Rod 412' and 463' c,f-See Section 3.2 and Handling Tool 2500 lbs. vi =

5

= 0.= U T 0: b

rT O O 101 TABLE 3-1 (Continued) Overhead Liftina Device: Fuel Handling Building Crane, ICR-3; Fuel Transfer Canal Gate Hoist,;XCR-49 Impact Area: Elevation 463', column lines Q.5 to_S'and 2.5 to 4.91, Fuel Handling Building Figures: 5 and-7 Designated Heavy Sa fe - Shutdown / Decay Elevation of Hazard Elimination-Section Reference Load and Weight Heat Removal Equipment Equipment Category (Remarks) XCR-3: 1. New Fuel Shipping ~ ' Spent' Fuel Pool 412' to 463' d See Section 3.3 Container and Vendor

Supplied Lifting Device 6600 lbs.

I d. 2. Spent Fuel Shipping Spent Fuel Pool 412' to 463' d See Section 3.3 Cask and Vendor-Supplied Lifting Device (Note 2) 3. Irradiated Specimen Spent Fuel Pool 412' to 463' d See Section 3.3 Shipping, Cask and-Vendor-Supplied Lifting Device (50,000 lbs. est.') g (Note 1) m XCR-49 o2 Canal Gates and Spent Fuel Pool 412' to 463' d See Section 3.3 Two Part Sling Cable 4500 lbs. w E 7 Notes: 1. . Assumed to. be an irradiated fuel assembly. 2. This device has not been purchased since the Virgil C. Sumuner Nuclear Station ic currently installing the capability for onsite storage (i.e., spent fuel racks).

' TABLE 3-1 (Continued)'. Overhead Lifting Device: Reactor Building Polar Crane, ICR-4' Isoect Area: Elevation 552', Reactor Building Figures: 5, 6, and 7. Designated Heavy. ' Safe Shutdown / Decay

Elevation of Hazard Elimination Section Reference Load and Weight' Heat Removal Equipment Equipment Category (Remarks) 1.

CRDN Missle Shield

1. Reactor Vessel,.

408' to e Section 3.4 and- ~ ~ 54,000 lbs. Reactor Vessel 437' 3/4" Appendix B Hozzles, and Associated Piping 2. Reactor Vessel Head

2. Steam Generators 430' 4-3/4" to c,e Section 3.4 and

& 1l l Assembly 268,000 lbs - 514' Appendix B w 3. Reactor Vessel Head

3. Pressurizer 430' 9" to-c,e Section 3.4 and Lifting Rig 21,000 lbs 488" 6" Appendix B 4.

Upper Internals and

4. Reactor Building 514' c

Section 3.4 Internals Lifting Rig . Cooling Units,. 92,000 lbs Associated Fans, and Cooling Coils 5. Lower Internals and E . Internals Lifting Rig -268,000 lbs 6. ISI Tool and Westinghouse-Supplied Lifting Device 20,000 lbs

r1 -3 ( TABLE 3-1 (Continued) -Overhead Lifting Device: Reactor Building Polar Crane, XCR-4 ' Impact Area: Elevation 552',' Reactor Building Finures: 5, 6, and:7. Designated Heavy Safe Shutdown / Decay

Elevation of-Hazard Elimination.

Section Reference Load and Weizht Heat' Removal Equipment Equipment Category (Remarks) 7.. RCP Internals 48,000 lbs 8. RCP Casing and Lifting Beam 52,000 lbs f 9. RCP Motor 77,140 lbs u ~ v.

10..RV Studs, Muts, and Washer Stand 8500 lbs 11.

Equipment Bridge 4000 lbs

All loads and safe. shutdown / decay heat. removal equipment combinations were considered for each of the eleven (11) heavy: loads listed above.

5! 2 5 e = i $t

f ~ L l 4 TABLE 3-1 (Continued)' 1 Overhead Liftina Device: Turbine Building Crane, ICE-17 ' Elevation 463', column lines A to F and 1 to 12, and 436' elevation open to Equipment Hatches Impact Area: from 463', Turbine Building t Designated Heavy. Safe Shutdown / Decay Elevation of Hazard Elimination Section Reference l Load and Weight Heat Removal Equipment Equipment Category (Remarks) Ceneral Electric Turbine None N/A c See Section 3.5 Cenerator and Associated Power Plant Equipment i < 220 ton 4 } i i t" 4 4 l i t i i ~ i I I = E! i { 5 a ~ O ) U l 2 } 0: l I t

_ f-s, g .(, ) G/ TABLE 3-1 (Continued) Overhead Liftina Device: 10-Ton Electric Cable Moist and Motor Operated Trolley, XCR-18 Impact Area: Elevation 436', column _ lines 9.5 and L, through Equipment Hatch 374' to 436', Auxiliary Building - South Finures:.:2, 3, and 4 Designated Heavy Safe Shutdown / Decay Elevation of_ Hazard Elimination Section Reference Load and Weizht Heat Removal Equipment Equipment Category (Remarks) Power Plant Equipment Mone N/A c See Section 3.6 ~ < 10 ton vI E = 'I O

c: n TABLE 3-1 (Coatinued) overhead Liftina Device: 7.5-Ton Electric cable Moist and Motor Operated Trolley, ICR-19 Impact Areat Elevation 485', column lines P and 6.6, through. Equipment Hatch elevation 388' through 485', Auxiliary Building - Horth .Fiaures: 2 through 6 Designated Heavy Safe Shutdown / Decay Elevation of Hazard Elimination Section Reference Load and Height Heat Removal Equipment Eeuipment Catemory (Remarks) Power Plant Equipment cable Tray 476'-6" g See Section 3.7 < 7.5 tons cable Tray 471'-11" g Cable Tray 428'-3" e 16" Service Water Pipe 451'-6" e vI Nl3 = C lit 5 i 0: h

gs n s l U J U l T4BLE 3-1 (Continued) overhead Liftina Device: 5-Ton Hand Chain Hoist and Plain Trolley, ICR-20A and XCR-208 l Impact Area: Elevation 374', column lines K and 8.8, Auxiliary Building - South Finure: 2 Designated Heavy Safe Shutdown / Decay Elevation of Hazard Elimination Section Reference Load and Weight Heat Removal Equipment Equipment Category (Remarks) 1. .RHR Pumps 4400 lbs RHR Pump and Motor 374' b See Section 3.8 [ 2. RHR Pump Motor 3200 lbs RHR Pump and Motor 374' b See Section 3.8 l Yf = l M li m O= U T 0:

r-q ,r n f-f' ~ b TABLE 3-1 (Continued) Overhead Liftina Device: 5-Ton Manual Chain Hoist with Geared Trolley, ICR-21A and ICR-215 Impact Area: Elevation 374', column lines E and 8.8, Auxiliary Building -' South Finure: 2 Designated Heavy Safe Shutdown / Decay Elevation of Hazard Elimination Section Reference Load and Weizht Beat Removal Eeuipment Equipment Catemory (Remarks) 1. RB Spray Pump 5400 lbs. RB Spray Pump and Motor 374' b See Section 3.9 2. RB Spray Pump Motor RB Spray Pump and Motor 374' b See Section 3.9 5880 lbs. vi

S E

l __J

(G J TABLE 3-1 (Coatinued) Overhead Liftina Device: 5-Ton Manual Chain Holst'with Geared Trolley, ICR-54 A, B, & C Impact Area: Elevation 388', column lines M to Q and 7.7, Auxiliary Building - Horth Finure: 2 Designated Heavy Safe Shutdown / Decay Elevation of Hazard Elimination Section Reference Load and Weimht Heat Removal Equipment Equipment Category (Remarks) 1. SI Charging Pump SI Charging Pump 388' b See Section 3.10 7500 lbs. Assembly 2. SI Charging Pump SI Charging Pump 388' b See Section 3.10 Base -6000 lbs. Assembly f 3. SI Charging Pump Gear SI. Charging Pump 388' b < 2500 lbs wE-2100 lbs. . Assembly See Section 3.10 o. 4. SI charging Pump Motor SI Charging Pump 388' b See Section 3.10 6700 lbs. Assembly 2 2 E I B. i i f

~-

.R x:- y, ' n ('w,} _(w).. - O)- (

~

n .4 TABLE-3-l'(Continued) Overhead Liftina Device:.2-Ton Manual Chain Hoist with Plain Trolley, XCR-23A and XCR-238 Impact Area: Elevation 412', column lines J to M and 7.7, Auxiliary Building Figure: 3 Designated Heavy Safe Shutdown / Decay Elevation of. Hazard Elimination Section Reference Load and Weight Heat Removal' Equipment Equipment Category (Remarks) RB Spray and

1. Motor Control Center 412' a,c See Section 3.11 SI Recirculation Sump Isolation Chamber

2. Air Handling Unit for 412' a,c See Section 3.11 Tops 3000 lbs.

Motor Control Center vI O w

5 2o2 U

T 3 l .i

.y .L n ".?" ?. 'S' ) ' (% - \\ - (~]. , 2.-e y .~ Q) ' TABLE 3-1 (Continued) Overhead Lifting Devices 8-Ton Manual Hand Chain Hoist with Ceared Trolley,.XCR ' Impact Area: Elevation 463',-column lines F and 4 to-5, Turbine Building-Designated Heavy Safe Shutd wn/ Decay Elevation of-Hazard Elimination Section Reference Load and Weight Heat Removal Equipment Equipment Category (Remarks) Main Steam Stop Valves .None N/A c See Section 3.12 Parts < 8 ton-vi ~

J u

h 5 = 0 2: U 'T 0:

. 3-; g, 7 );.., y. u ~~ + 1l,,},,. g - .p T Q' s Q s .c n -. y.- s TABLE 3-{(Continued): .; Overhead Liftina Device: 10-TonManualChainHoistwitii-GearfdjTrolley,XCR-25A,B,C,andD - ~ 's . Impact Areat Elevation:412', column lines B-to B.9 and 5'to'8, Turbine Building Designated Heavy l-Safe Shutdown / Decay Elevation of'. Hazard Elimination Section Reference Load and Weight Heat Removal Equipment Equipment Category (Remarks) v'Y IMain' Condenser Water None N/A c See Section 3.13 Box. 2 hoist service one water box 6iT yI e~ M

C H

C/3 MO E U '8 PJ Ut l' . 00 o

I ;. .,~.,,;- i I A] .r TJulI2 '3-1 (Continued) Overhead Liftina Device:14-Ton Manual' Chain Hoist with Plain Trolley,-XCR-26 Impact'Areat Elevation 412',. column lines F.to C.1 and 1 to 3,' Turbine Building ' Designated Heavy ' Safe Shutdown / Decay; Elevation of Hazard Elimination Section Reference -Load.and Weight-Heat Removal Equipment-Equipment Category (Remarks) -1. Feedwater Booster-Pump None. N/A c See Section 3.14 7800 1bs. 2. Feedwater' Booster Pump None N/A c See Section 3.14 Driver 8500 lbs. 3.- Feedwater Boster Pump None N/A c See Section 3.14 Bedplate 5900 lbs. .~ S* 5 OE N 'TK

O O O TABLE 3-1-(Continued) 0"erhead Liftina Device: 5-Ton Electric Hoist with Motor Operated Trolley, XCR Impact' Area: Elevation 436',' column lines G.4 to'H.4 and 7.5 to 8.3, 412' elevation open to Equipment Hatch, Intermediate Building - West 'Pigure: '4 Designated Heavy Safe Shutdown / Decay Elevation of Hazard Elimination Section Reference Load and Weight Heat Removal Equismient Equipment Category (Remarks) Power Plant Equipment-Cable Tray 420'-0" h See Section 3.15 -< 5 Ton-6" Chilled Water-Risers 436'-0" e 16" Dia BS Duct 426'-10" e 2" Horizontal Chilled 424'-0" e { Water Pipe m& v.

i 5

e-e T

. R': ~ r). N. j: LTABLE 3-1 (Continued) Overhead Liftina Device: 2-Ton Electric Cable Hoist with Motorized Trolley, XCR-28 Impact Areat Elevation 463',' column lines D to D.6 and 10.6, Water Treatment Building. Designated Heavy. Safe Shutdown / Decay Elevation of. Hazard Elimination Section Reference i Load and Weight Heat Removal Equipment Equipment Category (Remarks) d Chemical Storage Containers None N/A c See Section 3.16 < 2 ton l: 2 i a i j i 1 3 Mo 2: 4 2 e 8 i l D 3 f 1 i

I

N..

h \\ s--].. ~ TABLE 3-1 (Continued) Overhead'Liftina Device 2-Ton Hand. Operated Hoist with Ceared Trolley,-XCR-29A and XCR-29B ~ Impact Areat Elevation 436',. column: lines C.4'.to J.1.and 1,' Diesel'Cenerator Building . Figure:. <4 ~ Designated Heavy Safe Shutdown / Decay-Elevation of Hazard Elimination Section Reference Load and' Weight Heat Removal Equipment-Equipment Category (Remarks)- Diesel Generator Parts '1. Diesel Generator' 436' b See Section 3.17 -< 2 Ton

2. Fuel Oil Day-Tank 436' b

See Section 3.17

3. Air Receiver 436' b

See Section 3.17 y

4. Fuel Oil Transfer Pump 427' b

See Section 3.1'7 N 5 e .e 0 l I

-~- ( i-TABLE 3-1 (Continued) Overhead Liftina Device: 1/2-Ton Hand Chain Hoist.and Trolley, XCR-31 ~ Impact Area:' Elevation 436', column lines H.4 and 2 to 3, Intermediate Building.- East ~ Figure: '4-l ' Designated Heavy Safe Shutdown / Decay Elevation of Hazard Elimination Section' Reference Load and Weight Heat Removal-Equipment Equipment Category (Remarks) 4 None N/A N/A' N/A-See Section 3.18 I i a I y. i. 15 3 53 I 4 i .N o-2; !i .C i e,. l. 00 i. i i

~' -1 h. ~w y.

s

k,) - (f \\h. N TABLE 3-1 (Continued). Overhead Lifting Devices.2-Ton Hand Chain Hoist with Tro11ey,.XCR-33; Impact Areat Elevation 412', column lines G.3 to H.4 and 2 to 3,, Intermediate Building - East Figure: 3 Safe Sh'tdown/ Decay Elevation of Hazard Elimination Section Reference Designated HeavyL u Load and Weight ' Heat Removal Equipment Equipment Category (Remarks) 1. Turbine-Driven Emergency ~Feedwater Turbine-Driven Emergency 412' b See Section 3.19 3000 lbs. Feedwater Pump Assembly 2. Turbine-Driven Emergency Fe'dwater Turbine-Driven Emergency 412' b See Section 3.19 e $, f. 2400 lbs. Pump Base Plate Feedwater Pump Assembly aa e 3. Turbine-Driven Emergency Feedwater Turbine-Driven Emergency. 412' b See Section 3.19 Pump Driver 3260.lbs. Feedwater Pump Assembly 5!

5 5

e

a. '

. TABLE 3-1;(Continued) Overhead Liftina Device: 'l-Ton Electric Cable. Hoist'and Trolley,1XCR-34 ^ Impact' Area: Ele'vation 436',. Tendon Access Callery, Reactor Building. Figure: 4 Designated' Heavy' Safe Shutdown / Decay-Elevation of Hazard' Elimination Section Reference Load and Weight Heat-Removal Equipment Equipment Category (Remarks) None N/A N/A N/A See Section 3.20 yi

5 5

e i h

t. 7' j k O m) TABLE 3-1 (Continu'ed)~ Overhead Lifting Device: 20-Ton Electric Cable Hoist'with Motorized Troll'ey,'XCR-36 Impact Area:-Elevation ~436', column lines P to R and 6.6 to 8.8, Auxiliary Building - North (Drumming Station) Figure: 4-4 . Designated Heavy Safe Shutdown / Decay Elevation of-Hazard Elimination Section' Reference Load and Weight Heat Removal Equipment Equirment Category (Remarks) Radwaste Facility Equipment Spent Fuel Pit Cooling 412' e See Section 3.21 < 20 Ton Pumps vI m C; 5= 'N ia

y' s + Lif y 'v'- .%/ 1 . TABLE 3-1 (Continued) ' Overhead-Liftina Device: '10-Ton' Hand Chain. Hoists'and.Ceared Trolley, XCR-40A, B, and C Impact Area: Elevation 436',fcolumn. lines H.4 toLJ.1 and-Z to 8, Intermediate Building Figures: 3 and 4 Designated Heavy- . Safe Shutdown / Decay Elevation of Hazard Elimination Section Reference ' Load and Weight Heat Removal Equipment Equipment Category (Remarks) Main Steam Isolation

1. Component Cooling

.412' e See Section 3.22 Valve Parts < 4500 lbs Heat Exchanger

2. Component Cooling 412' e.

See Section 3.22 Pumps . i{

3. Motor Driven Feedwater 412' e

See Section 3.22 Pumps 5=- U T 0: l $[ 1' L

7- -- 21 >N,

(A-{..

N ,I f_ TABLE 3-1.(Continued) Overhead Liftina' Device: 10-Ton Bridge Crane.and Electric Cable Hoists,,XCR-42 Impact' Areat Elevation 436', column' lines R.2 to S and 7.8 to 11.6, Hot Machine Shop-Designated Heavy Safe Shutdown / Decay: Elevation of Hazard Elimination Section Reference Load and Weight-Heat Removal Equipment Equipment Category (Remarks) Hot. Machine Shop Application None N/A c See Section 3.23 <,.10 Ton yi E T3

~ 6- ..s% )I TABLE 3-1 (Continued) Overhead Liftina Devicesf 10-Ton Bridge Crane and Electric Cable Hoist, XCR-43. Impact Area:. Service Building Machine Shop-Designated Heavy ~ ' Safe Shutdown / Decay Elevation of Hazard Elimination Section Reference - Load and Weight . Heat Removal Equipment Equipment Category (Remarks) . Service Building Application None. N/A c See Section 3.24 5,10-Ton vi x-g. 5 O Z U O l

_3 .t + y.. .p j' ) TABLE 3-1-(Continued)' l Overhead Lif tina Device: 3-Ton. Bridge ~ Crane and' Electric Cable Holst, XCR-46 Impact Areat Elevation 463', column' lines P to Q and 8.8 to 11.5, through equipment hatch to Drumming Station Elevation.436', Auxiliary Building - North i Figures:- 4 and 5-Designated Heavy Safe Shutdown / Decay Elevation _of Hazard Elimination Section Reference j_ Load and Weight Heat Removal Equipment' Equipment Category (Remarks) 1.- Concrete Plugs See Section 3.25 1770 lbs < 2500 lbs. i i 2. Filters and Cartridges' See Section 3.25 ? negligible < 2500 lbs. l f ~ w4-- 3. Storage Casks 2590 lbs. c,e See Section 3.25 2" CS Line 449'-0" e 2" CS Line 448'-3-3/4" e 2" CS Line 447'-9" e 2" CS Line 437'-6" e 8105-CS 437'-6" e HCV-186-CS (valve) 447'-9" e i 3 2" CS Line 427'-0" e 2" CS Line 428'-8" e Cable Tray 431'-11" e m Cable Tray 430'-4" e Cable Tray 430'-4" e N j O f. i i D: N 4 l-1 l l

z.y yy o- \\ (!.- '(,h

j ',

TABLE 3-1 (continued)I . Overhead Liftina Device: 10-Ton Bridge Crane and-Electric-Cable Holst,.XCR-47 -Impact Areat Elevation 447', column lines P to R and 8.8 to 9.5,' Drumming Station Figure:. 4 Designated Heavy' Safe Shutdown / Decay. Elevation of Hazard Elimination Section Reference Load and Weight Heat Removal Equipment Equipment Category (Remarks) Shielded and Unshielded Rad. 2" CS Line -427'-0" e See Section 3.26 Waste Containers < 10 Ton 2" CS Line 428'-0" e ~ 2" CS'Line 428'-8" e Cable Tray-431'-5" e Cable Tray 430'-4" e Cable Tray-430'-4" e E S = 0= N T 0:

=: .m 7-g q' S. ,kj ) ) TABLE 3-1 (Continued): -Overhead Liftina D'vice: 1 1/2-Ton Hand Chain ' Hoist and Plain Trolley, XCR ' e Impact Area: Elevation 412',. Column Lines B.8 to D and.12, Turbine Building Designated Heavy-Safe Shutdown / Decay Elevation of' Hazard Elimination Section Reference Load and Weight -Heat Removal Equipment Equipment Category (Remarks) Instrument and Air Compressor 'None' ,N/A c See Section 3.27 Assembly Parts ' < l-1/2 Ton-1 ? vi }- N t I i 2 n O 2C U T U 1 4

TABLE.3-1 (Continued) i Overhead Liftina Device: 10-Ton Bridge Crane and Electric Cable Hoists, XCR-51 and XCR-50 Impact Area: Elevation'436', Service Water Intake Screen and Pump House Figure: 8 I Designated Heavy Safe. Shutdown / Decay Elevation of Hazard Elimination Section Reference Load and Weight Heat Removal Equipment Equipment Category (Remarks) 1. Service Water Service Water Traveling .436' b, e See Section 3.28 l Traveling Screen Parts Screen, Pump Assembly, i ~< 10 Ton and Associated Piping t t .2. Service Water Pump Service Water Traveling 436' b, e See Section 3.28 l { 14,000 lbs. Screen, Pump Assembly, w 4 and Associated Piping i

=

l 3. Service. Water. Pump Service Water Traveling 436' b, e. See Section 3.28 Motor 16,600 lbs. Screen, Pump Assembly, j and Associated Piping j-l i M 5 m re i O q 2; ? N 1 w g. 4 m 4 3-i i

i e -/ 7 L '[ 3 \\ v /. V s TABLE 3-l'(Continued) Overhead Lifting Device: 2-Ton Twin Hook Extension Hoist, XCR-53A, B, and C'. Impact Area: Elevation 475', Reactor' Building'. Figure: 5 Designated Heavy Safe Shutdown / Decay Elevation of Hazard Elimination 'Section Reference Load and Weight Heat Removal Equipment Equipment Category (Remarks) CRDN Cable Support None N/A c See Section 3.29 Structure vI 5 5 O 2: U Tu

1 1 O O O ' TABLE 3-1;(Continued) Overhead'Liftina Device: 1-Ton Jib Crane, XRW-ll Impact Area: Elevation 436', column lines Q and 7.7, Auxiliary Building - North (Drumming Station) Figure:. 4' Designated Heavy Safe _ Shutdown / Decay Elevation of ' Hazard Elimination Section Re'ference Load and Weight Heat Removal Equipment Equipment Category (Remarks) None N/A N/A f See Section 3.30 vI = =

5 O

2: w e 0:

7-, ~ (r s-<.- _ -[q - t 2 TABLE 3-1 (Continued) Overhead Liftina Device: 3-Ton Jib Crane,.XRW-13. Impact Area:. Elevation 436', column lines Q and 7.8 to 8.7, Drumming Station Figure 4: Designated Heavy ' Safe Shutdown / Decay Elevation of Hazard Elimination Section Reference Load and Weight Heat Removal Equipment-Equipment Category (Remarks) 1. ~ Concrete Plugs 1770 lbs.. None N/A c,e See.Section 3.31' < 2500 lbs. 2. Spent Filters and None N/A c,e See Section 3.31 Cartridges Negligible < 2500 lbs. { 3. Storage Casks 2590 lbs. None N/A c,e See Section 3.31 4. Storage Casks and Lifting 'None N/A c,e See Section 3.31 Beam 3940 lbs. E M e .e u

ec 2 .~d n 3 er) 3 .( es fk n er o Ra i m t ne c oR e i( S tc e e e S S no i tany i rmo i g l e c Et a dC raza H ena ) r f d C o e t u h nn n c oe A i t i m / t a t p N n H ai o vu C s eq ( s l E e E 1 c . b c 3 A t E t n L n e B e ym A m ap T p ci i eu u g D q q n /E E i n A d wl / g l oa N n i d v i u t o d B um l h e i r SR u o B t et c f a r a ae o e SH t R ca 'e R '3 1 4 ec n i o v i e t D av g e y n l vt i E ah t eg f Hi i a e L e 5 dW r e d A td a an e t e na h c r g r a u id e e p g sa n G v m i eo o O I F DL N I-I E" OE U i" $ y.N

. (em. ~R ' s f [Q ) )~ \\J 3. TABLE 3-1 (Continued) Overhead Lifting Device:L5-ton Hand Chain Hoist and Geared. Trolley, XCR-40 Impact Area: Elevation 436',-column lines H4.to H7 and 5.9 to 7.5, Intermediate Building. - Figure: :4-Designated Heavy' Heat Removal Equipment Equipment Category (Remarks) Safe Shutdown / Decay Elevation of Hazard Elimination Sectice Reference Load and Weight Main-Steam Isolation. l.. Component Cooling 412' e See Section 3.33 Valve Pieces Heat Exchanger

2. Component Cooling 412' e

Pumps

3. Motor Driven-412' e

ws 's Feedwater Pumps w 5 E i D: 1

7 ,-- s. /x, \\ 4 . N,) ' '\\ v - J 1 TABLE 3-1.(Continued) . Overhead Lifting Device: One-Ton. Jib; Crane-and. Electric Chain Hoist, XCR-55 Impact Area: Elevation 463' Reactor Building Designated Heavy; Safe Shutdown / Decay Elevation-of Hazard Elimination Section Reference Load and Weight Heat Removal Equipment Equipment Category (Remarks) N/A N/A N/A f See Section 3.34 1 6 yi OD O L tra 5 OZ U T U $t

e , ) c 4 3 n e / r) 3 es fk n er o R a i m t ne c oR e i( S tc e e e S S no i tany i r mo i g l e f Et a dC 6 r 5 a z R a C H X ) t f d s o e i t u o nn n H oe A i i m / t n t p N e n i ai o a vu C h eq ( C lE E 'l c i 3 r t t E c n L e e B l ym A E ap T ci d eu n Dq a g /E n n A e i wl / n d oa N a l d v r i t o C u um B h e b SR i r J o e 't t f a n c ae o a SH T e R en O '3 64 sec n i o v i e t D av g e y. n l vt i E ah t eg f Hi i a e L e dW r e' d A td a an e t na h c g r a id j e p sa A v m eo / "r, O I DL N I~ y.k a 8= 5 T?? n \\ a 4 4 i' i! l 4

f. y m..

]

s 4 .,m, (. D', - b'-_ Aj TABLE 3-1 (Continued) Overhead Lifting Device: One-Ton' Jib Crane and Electric Chain Holst,.XCR Impact Areat Elevation ~463' Reactor Building ~ . Designated Heavy Safe' Shutdown / Decay Elevation of-Hazard Elimination Section Reference. Load and Weight Heat Removal Equipment ' Equipment Category (Remarks) N/A ' N/A N/A f- 'See Section 3.34 y I - =

5

= l o = U T i u l

.,/~'\\, ' s ~ ' TABLE 3-1 (Continued) Overhead Liftina ' Devices One'-Ton Jib Crane and' Electric Chain Hoist, XCR-58 Impact' Area: Elevation 463' Reactor Building Designated Heavy -Safe Shutdown / Decay Elevation of Hazard Elimination Section Reference Load and Weight Heat Removal Equipment Equipment Category (Remarks) N/A N/A_ N/A f See Section 3.34 I y e 3 5 e I = l u h t

r/ e n c 6 n 3 er) 3 es fk n er o Ra i m t ne c oR e i( S tc e e e . S S no i tany i r mo ig l e f Et a dC raza H' ) f d o e t u nn n oe A i i m / t t p N n ai o 0 vu C 6 eq ( lE R E 1 C ( X 3 t E t n L s e B i ym A o ap T H ci g eu n. n D q i i /E a d n A h l wl / C i oa N u d v l 'B t o a um u y h e n r SR a a M i et l f a n i ae o x SH T u A 2 / '5 1 84 ec n i o v i e t D av g e y n l vt i E ah t eg f Hi i a e L e dW r e d A td a an e t na h c g r a id ~ e p sa A v m eo / O I DL N {- itb i Y 55e :

r- .,., y .,-m ,rs ~y 'O ', s.. TABLE 3-1 (Continued) Overhead Lifting Device: 1/4-Ton Jib Crane and Electric Chain Hoist, XCR-61 Impact Area:-Elevation 457'-0" Control Building Designated Heavy Safe Shutdown / Decay Elevation of Hazard Elimination Section Reference Load and Weight . Heat Removal Equipment Equipment Category (Remarks) N/A N/A N/A f See Section 3.35 Y f = E .m O ~* i i il j a a k 4 = k

r f i l 9 I l 10 8 7 i 1 c3 j \\' _,/ A B C c'E$"TfNG N fala STRUCTURE b sg./7 )'\\ FH o j o a/ N d O + oitSEL OL q;, F rR B"" SM AB ~ g L-I DG 'N ; / o '/\\ "'s? oil"ci EllYd f4c wg <g conoEus m CB TB A# l8 me v gga /Q ~ h n y 'w P L A 96 9 ( -j 3,. q,, i 1 1 1 L. k 1 ii I

if h l l l l 5 4 3 2 1 t \\ A l. SulL0 LNG DEstGhail0NS AB =:' C.B =G D G OIESEL GENERATOR B SulLDING F H

=="" IB = = " " R

e REACTOR BUILDING SWPH

="" TB =- 2. WALL DE$1 GNAT 10N$ l l CONilNUQUS FRou I FLOOR TO CELLING Also Availabic On o NOT CailMucus FRa g FLOOR TO CEILING

3. f )
I l LCAO PATH $

PH (4, SAFE $ HUT 00Tle EQUIP 11ENT r APERTURE CARD .. p l CRA N,, 4. EQPT NO. DESCRIPil0N 250 MACHINE $ HOP CRANE, le TON (ICR-43) 251 SATER TREATWENT SUILDING CHEulCAL STORAGE SulLDING. 2 TON NOIST (ICR-28) L \\ G 1 I SOUTH CAROUNA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION Site Plan Figure 1 gal Dwg. C-021001 loll l-lilil lNIOl6l1l2l lClOl NIT l lHIVlYl lLlOlAlOlSI INIPIPISI j 85 02 0$ 0 3 91 -01 e

l 10 l 9 l l 7 k 8 6 t'N A N ,N-h i k'- " -' I g _ t. B s KEY PLAN fly L g M p" o 10 20 30 40 50 60 _ y i C GRAPHIC SCALE Iki itLEELT PL AN AT EL 400'-O" - s o e e e o e o g . _ c_ g_ (J + rgy. g O ("')- 7 , a.a. _Q h-- h @l--- h-E r' 0#= .? 21 t. W

v

- x-e-s.t .,--g Q _. o 2 ~ -A B = O dd _g O, Y F i _ _ +___ Q/_ . Q-. a n 9l j a f Q-Q \\ G h si 3 14 2 12 PL AN AT EL 374'-O' -e H )

x..

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w. v_. ;..,,., 1.4 p

e

l l l l 2 1 3 y 5 4 EQPT 10 DESCR IPf10N l RMR PVuP A 2 anA PuuP e A 3 RMR/$PRAf PUNP ROOM I COOLING UNIT PLENUM 4 RMR/5PRAf PUNP ROOu 2 COOLING UNlt PLENUu 5 CMARGING/$AFEff INJECTION PUNP A 8 CMARGING/$AFETT INJECil0N Pl;uP S E QUIPM EN T I CHAR $1 ngl $AFETY INJECTION PUNP C ~ H ATCH (ABOVE) CMARGING/$AFEff INJECTION PUuP 200u 1 COOLING UNlf 9 CHARGING /5AFETT INJECTION PUNP 9004 2 COOLING UNIT 10 CHARGING /$AFEff INJECTION PUuP R00u 3 COOLING UNIT C-- 29'- 6" 21'-0" @-28'-3" 18 anA mP 4, 5 m Holst (ICR-204) v' 31' 3" _v g 12 RNR PUuP 8. 5104 M015T (ICA-200) 13 RE ACTOR BUILDING SPRAf PUllP 4, 5 TON MOIST (ICR-2n A) 3 __9.._.__ r-14 RE ACTOR SUILDING $PRAf PuuP S. 5 TON H00$T (ICR-210) I I l 18 CHARGING /SAFETV INJECTION PUur 3. 5 TON M0lli (ICA-540) 17 CHARGING SAFEff INJECil0N PuuP C. 5 TON N01st (ICA-54C) g y 4 o p .s g .h ^ C 0 0 .g 1 F-l

0 /..

l t j 2 -- -FNs E M Also Available on Ng 0 0 o ~ g i nl y Aperture Girvi x y,2 g - G, a m + l , ~ ~ ~. .'v p; q l I l t"-- ~~ "RB.~ TI p, i o a ed.n a y 1 ~ Q APERTURE CARD X Fs . O =:=- O / ch.J -J. -- - Q s .s EQUIPMENT HATCH AB g z. m b btgg!y' y (A80VEj g _ v w.5 _[] c SOUTH CAROLINA ELECTRIC & GAS CO. MRGIK. SUMMER NUGEAR STARON PL AN AT EL. 388'-O" & 397'-0 Plan at Elevations 374'-0", 388'-0", a nd 400'-0" Figure 2 gal Dwg. C-021002 10121-11lll lN}Ol6lIl2l IClOINITI lHIVlYI lLIOlAIDlSl INIPIPISI p 8502050391-O'1

n,,._-,-- 9 l 8 7 6 10 l _ 2.9 6 2 8'-Q"._ __28}3" 31-3" Sg;91 8 l ( REACTOR BUI A i SPENT N FUEL N gj a + e. - j 7, O eygg--N e i -= m i B KEY PLAN O --DE ~ f a ,oe,-+ x-1""M NO D 'N -)- 0 10 20 30 40 50 60 g; GRAPHIC SCALE m IN FEET [? l

3 V

c g ><-< g r-<: S e s - g m .a g

o n,

+ . &.5 9_ lo

=

i s -e p x o o o e:: -yg Argt: i. gs o H E55 O'

e 2

n m.c e t s : t ~ 's 5 s N a w s ~l 1-1 \\

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L p e ry@ 'N', O - w Bo r-,s v._, r = o, = i

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"!!S @;_.

> d 1 4_;p..3 4 h = , e m .3 I_. E y CB o

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gi y 5 4 3 2 1 _ 19*-8" 2 5'- 8" 2 5*- 8" E0P1 PEFUELING WATER 10R A A j 27 MOTOR CONTROL CENTER g. ,h f i 28 UOTOR CONTROL CENTER

n's bi 28 RNR NE At EICMANGER A d

30 RHR MEAT EICHANGER 8 1, CC. b ~ LM-q i 1 M i,_ M 31 SERVICE WATER 9005fER PulsP A

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cs 34 BATTERY B hM; j

- ['j '/ 9 _py j ' 35 8ATTERT CHARGER la 9,' ' 7 ~ I

38 BAffERY CHARGER 10 B

ig j ,I e ~O~~'~ ' ~~ N I EQU1PMENT EQUIPMENT

37 BATTERY CHARGER lillt r; t -

8ATCH sAtcs 38 DISTRIBUTION PANEt A (ABOVE) 2A

38 OISTR18U11GI PANEL 8 h-g PL AN AT EL. 424'-0"

',"',",5'", 5 ', " *",,,, C,,, o t E,, a' = 42 HWAC EQUIPuENT WATER CHILLER S -{ r. 43 NVAC EQUIPu!NT SATER CMILLER C d, ' ,_'r Ara 44 HVAC EQUIPutNT WATER CHILLER PUuP A g ,f 45 HVAC EQUIPuENT WATER CHILLER PUup 3 C 48 MVAC EQUIPMENT SATER CHILLER PuuP C 4T TRANSFER StliCH 48 CouPONENT COOLING HEAT EICHANGER A O 48 CouPONENT COOLING HEAT EXCHANGER S ~ SC COMPONENT COOLING PUuP A g. Q 51 CCuPONENT COOLING PUuP O \\ O 52 co Peara' coa'i a Pu=P c \\ 53 TUR8tNE ORIVEN ENERGENCY FEECWATER PUMP 1 / l' REACTOR BUILDING i 55 Il0 TOR ORIVEN EutRGENCY FEE 09ATER PUuP S D f. 58 FUEL OIL TRANSFER PUur 4 4 57 FUEL Olt TRANSFER PUUP 3 h

l' 58 FUEL Olt TRANSFER PUuP I A N

\\, - b, 4* l ] 58 FUEL OIL TRANSFER PUNP 19 / SO GENERATOR NEUTRAL TRANSFER 801 A + o oo i MERWE 'rataa'oa atu'a>' 'a^a5'ta 'a' ' 82 TUR81NE ORIVEN EllER FOS PURP.2 70N (ICR-33) F

p

--EOUIPMENT 83 M W M N M A.2 m (M) OO 0 e HATCH 84 IECIE RIP VALVE PET QueOER B,2 704 (ION 3) E O (ABoVE) 85 18" 08A DUCI (NAIARD) 88 (2) 2' VU PIPES (MAZAR0) 87 12' I 8' CA8LE TRAT (NAZARD) 't O g 88 14' I 18' OUCI (HAZAR0) 8 I $8 BCC StGR AN Ultli (MA2ARD) I 70 (2) 8' I 8' CABLE TRATS (MAZARD) [ _. .... h. 1 ***',, 'l g, g { ) ? (@ D G e urm m . 19 e ~@

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3 IN FEET

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1 RAILROAD, HATCH (ABOVE) 28 REFUELING BATER STORAGE TAME 119 OlssEL GENERATOR A x

A '\\i '?y 7"E ll - 78 PRESSURIZE R 120 OIESEL GENERATOR B I 77 STEAu GENERATOR A 121 GENERATOR LOCAL CONTROL PANEL A j gag.. -2 5,- 8' 7e STEAu GENERATOR S 122 GENERATOR LOCAL CONTROL PANEL 0 h l l p 18 SIEAu GEhERATOR C 123 AIR RECElVERS, GENERATOR A a 6 ". LV j r* * ~ ~ -i >b 'o 31 PRC3 INSTR CONTROL RACE PROI SET 111 125 FUEL Olt DAV TAME A n 124 AIR RECEIVERS, GENERATOR B e I l ~ T T I 3 '2 5'"5'"**"''"'5" ruf t Oit car iANE e L- - - - 'q / 83 N55 AUIlLIARY RELAY RACE 3 127 EXCliER CONTRCL PANEL A e 1 l to 120V INVERTER 4 N$15 820 EACITER CONTROL PANEL 0 P 05 N553 AUllLIARY RELAT RACR 2 129 OIESEL GENERATOR 4, SUPPLT F AN A g f T 06 $3PS CAllNET TRAIN 8 130 OlESEL GENERATOR A, $UPPLY FAN O lI h "O 87 $5PS it$i PANEL TRAIN 3 131 OlESEL GENERATOR 0. SUPPL 1 FAN A } ll F / g 84 ISPS CAllNET TRAIN A 132 OlESEL GENERATOR 8, SUPPLT FAN 9 1 W Q.6 89 35P5 YE57 PANEL TRAIN A 133 NOT MACH $NOP CRANE 10 TON (ICR-42) E I-8 30 N355 AUIlLIARY RELAY RACE i 134 Lgg Ly(gASTE STOR CAN,10 im (ICR-47) N 91 1201 INVERTER 8, NSS 135 RA0fAsit FACILiff CAN,29191 (ICR-34) { EQUIPMENT 82 PltCs INSTR CONTROL RACE PROI SET I 138 JIB CRAME. 3 TW (IRW-13-90) 53 PRCS INSTR CONTROL RACE PR0f SET ll 13; jlg CRANE, 4 104 (1R9-11-50) f k TENDON GALLERY 94 120V INVERTER 3. N155 130 EQUIPutNT NATCH, $ TON (ICR-27) ACCESS 95 00P lusTRuutNT PANEL, TRAIN e 139 uAIN sfu 15LN Valve A lS TOM (ICR-40) C i , ON l 96 1.E. AUIILI ARY RELAY RACR 140 uAIN Siu 15LN VALVE B.10 f0N (ICR-40A) 97 BOP INSTRUMENT PANEL. TRAIN A 141 uAIN Siu 15LN VALVE C,10 TON (ICR-40C) p 98 (20V SNVERTER 2. N553 142 CNEulCAL STORAGE, fit 104 (ICA-31) 76 ts 120V INVERTER I. N555 143 05L GEN BLOG CRANE A.2 TON (ICR-294) I 100 AUIILIART $AFEGUARO CABINET, TRAIN O 144 0$L GEN GLOG CRANE 3.2 TON (ICR-294) (g B 101 E5F LOAD $EQUENCE PANEL. TRAlm 0 145 EQUIPutNT NafCH,10 TON (ICA-11) 102 E5F LCAO SEQUENCE PANEL. TRAIN A 148 IENOW GALL AC3 N4fCN.8 ISI (ICR-34) I

/

103 AutlLIARY SAFEGUARD CABINET, TRAIN A 14f TRAN5FER 50NCRAIL (ICR-488) / 104 120V 1NVERTER f, N555 148 (2) l' VU PlPE5 (NAZARG) \\ // D 105 NCC - Euc 1082I let (2) 18" St PIPES (NA2ARG) J 108 480V $11TCMGEAR S 150 Alt CRANE (ICR-61) []# I A 107 7200V StifCNGEAR S I I 108 7200V 5tliCNCEAR S g j 109 CONTROL R00ll ETACUAfl0N PANEL A 4 \\ // llo CCNTROL ROOu EVACUAfl0N PANEL B \\ / g 112 REACTOR PR0fECil0m UF/UV PANEL 113 Coup 0NENT COOLING PUur SPEED 5tifCN 4 EQUIPMENT 114 CouPONENT COOLING Pour $ PEE 0 stifCN 0 { HATCH 115 C01F0ENT COOLING Puur $ PEED 5tlTCM C r Ill CouPONENT COOLING TRANSFER SfliCN -/ lif CouPOWENT COOLING $ PEED 11 CLC UNii A Also Ava,lable On i iis C=PONENT CC0 ting snE0 59 Ctt UNii. 2 Aperture Card 's 144 Ph M {U U wa m i J TI / ,4, b-N- _. %e- - APERTURE ,i .e.. e, JS00@ / ff[i { l CARD ,,4 WO::ORAll ~ [ I 1 l ~ c-3 L d 22 .. 7 ~ l &A l %,4-w ol Nr 11 g 1 1

M, 7E;,i,ns6 gai " h ca7r d [!f SOUTH CAROLINA ELECTRIC & GAS CO.

m ? i VIRGIL C. SUMMER NUCLEAR STATION f@h @@Q@@@! R& M@. V "'*" "* Eleva t. ion 5%s"' PL AN AT EL. 436'-O" g A4% PLAN AT EL. 45f-0" Figure 4 P o G Al Dwg. C-021 004 l0l41-lllll lNIOl6lll2l lClOINITl (HlVlYl ILl0lAl0lSI INlPIPlSl l l8 5 0 2 0 5 0 3 91 -

10 l 9 l 8 l 7 l 6 ('b b 1 N 1- ^ b FH --u e +c e es e A_ g 2 aw 2e sc e b' l m b ] B KEY PLAN

9 w

H aI t g x ea w <- ~,,,, ( M v "'. g' 0 10 20 30 40 50 60 e l .f GRAPHIC SCALE ~ J -q i C IN FEET I'x S 9ffc"f*' ~ 20, 8 ,,o s 7 i ja g . g "~ 0 7M / y p i o ~ , n b TQ Qi. wm Qg A B Q, < s ..o K O J> '4I .r. i ,a e l a a 1 Du, D s'. 2(- v 2 7:< 0

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P y-5 l 4 l 3 l 2 l i E: @^* @ ,C,, ^' l E 0C'IPI'0" t

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<gM QUIPMENT W = 78 PRESSURllER D*.h' ^ ' ^ EL i TO ' 8t AN S FE R as J M 78 STEAu GENERATOR C ix ~ ANAL 158 80RIC ACID TANR A y 152 80RIC ACIO TANR 8 M 153 480V 5eliCNGEAR + 9 NT _ h [8 3. 154 uCC IuC10827 g ?O ts 155 uCC Iuct0821 + f ?' EL Pli e pj ] 158 Nil CONSOLES 1. II. Ill, AND IV b ist utlN CONTROL 80ARD B T~ w' 3-d== ' x.+ g 158 NVAC CONTROL 80ARD N4 158 UCC Iucl0423 1 ~ G.1 # 4 ~ h'< Q ISS MCC IUC10A2X r 5 U \\^ CASK t \\ O ' **" 5' c"ar A R L-182 480V ssliCNGEAR (RS. LOADING \\ 183 7200V $31TCNGEAR Pli L EW FUEL 184 7200v 18tiCHGEAR l N STCRAGE ISS REACTOR TRIP seliCNGEAR } 188 OIESEL CINERATOR A, IIHAUST SILENCER i 3 E> "' ' ' '5' ' ""'"> 'a' ' "" a"$ ' ' ' "c' " C tF7 18 SPENT FUEL Pli SRf 0GE CRANE (ICA-002) F b 18 2 M 188 FUEL NANDLING SulLDING CRANE (ICR-003) LOAO PATH O e i>0 riList NAN 0 tina CRANr. 3 Tc N0ist (ICR-4 > 1 ' O-h \\ lit REACTOR SUILDING POLAR CRANE (ICR-004) LCAD PATM [\\' 172 REACTOR CAflii WANIPULATOR CRANE (ICR-001) 113 REACTOR SulLDING EQUIPutNT ACCES$ NATCH NEAD (Blu 3C-4) EQUIPMENT ITA CRou CASLE SUPPCRT PLATFORM A, 2 TON (ICR-53A) /,(- H ATCH 175 CRCu CA8LE SUPPORT PLATFORu A, 2 TON (ICR-538) ( [ 178 CRou CABLE SUPPORT PLATFORu A, 2 TCN (ICR-53C) 0 I 177 NES FUEL ELEVATCR WINCN (ICR-45) > 7j 178 PROTit CA8LE REEL (ICA-18) PART OF ICR-002 f 3 1 178 REL T1uMSFill CJhAL GRTES, 3 T3e N0157 (IM) PART OF ICRalC3 RE Y i 1 e ') 188 Jll CRANE (ICR-55) i ^f [ t 181 Jlt CRAN.(ICA-58) + 8 182 JIS CRANE (ICR-57) l [ 183 JIS CRANE (ICR-88) ? pg ' l w L. - N t E QUI PM E N T 184 (ICA-88) 'd ACCESS 185

MATCH, 8* I 8'. CABLE TRAT (NAZARG) ig, g 4 CABLt TRAT (NAZAR0)

E \\ 12' I 8' CAstt TRAT (NAIARD) 6

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d Figure 5

'.; @ AD C-028-007 gal Dwg. C 021005 10151-11111 INlOl6lIl2l lCICINITl lHIVlYI lLIOlAIDISI INIPlPlSI l l l Ip 8502050391-05

) k l l 10 l 9 l 6 7 8 i N { 3 -%g A !h ti-C v'd zs's s f-f QQ l j B KEY PLAN { 0 If d_ 'i g_. { i. g O 10 20 30 40 50 60 y g GRAPHIC SCALE g IN FEET (A._ a_ \\ / P""I D ac31 M C v J ! /.

== I w? 003 F j. '52

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h l l 1 5 4 3 2 EQPT 10 OESCRIPfl0N 14 PRESSURllER A 77 STEAR GENERATOR A 74 STEAU GENERATOR 8 Q 75 STEAR GENERATOR C N/ 151 80RIC ACID TANK A = 152 BORIC ACIO TANK B 171 RE ACTOR OUI'. DING POLAR CRANE (ICR-004) 20* 172 RE ACTOR CAVlif MANIPULATOR CRANE (ICR-001) y 201 REACTOR 8UILDING COOLING UNIT lA E NENT 7 A5 202 REACTOR eUitoi4G C00 ting UNir 2A g 203 REACTOR BUILDING CCOLING UNIT lt l-% g 20A RtAct0R Bull 0iNG C00 ting uNir 2s l / V6 204 203 19 208 CONTROL R004 NORu1L $UPPLY AIR PLENuu 8 205 CONTROL R00u NORuAL SUPPLY AIR PLENUM A p7[ 207 RELAV R005 $UPPLY PLENUM A g g 208 REur R00m suPPtv PLENun e / g g 209 AUIILI ART 8LDG EQUIPMENT NAfCH,7.5 704 CRANE (NCR-It) f' ha J l 184 (ICR-80) a RB ,rN: c A t__- 4 g N, (' 'N [ l' \\ em q -l N !I % ?>,: h t u J t d J: jf h l M ; S' d 5* Also Available On o d F -f -t.. Aperture Card 7 ax 3sylJ, y a nib ll cf%,r i i s ,%w,.

g g

cm, y ~ "? g ~ [ ...~, I PLAN AT E L. 5 5 2'- O" TI APERTURE 7. 20, r o u n.,. CARD A5 c-ozi-oor G SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION Plan at Elevations 485'-0",482'-0", and 552*-0" Figure 6 gal Dwg. C 021006 p 10161-11111 INIOl6lIl21 lCIOINlTl lHIVlYI lLIOIAlDjSl lNjPlPlS Il1 85 02 0 5 0 3 91 -O G

} l l 10 l 9 8 l 7 6 /' -( i' A - m B C C.R ANE_ SPAN r a c j i 1 tl lll .j [j - ~ ~. iI TOP 0F RAIL l EL. sof-( j l t TB r e: e e r o o N.. ] l n '.I l %A ur d fh dE l r--1 k/hOk O i {; -* tL.. 3.o-l i ol. .n l /,4y, 4, oo,,,t L, t o o. s 7-t 7 EL. 4 36'-O* i ,. _c -.. m / r o@ $, 49

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i l h l l 4 l 3 1 2 5 EQPT 1 DE$CalPil0N 41 NVAC EQUIPutNT BATER CHILLER A 48 00MPONElli COOLING HEAT EXCHANGER A 49 COMPONENT COOLING HEAT EXCNANGER S A 9 52 CouPONENT COOLING PUMP C 78 PRE 55URI2ER 77 $fE AM GENERATOR A 78 STEAU GENERATOR 8 113 COMPONENT COOLING PUMP SPEE0 $91TCM A 117 COMPONENT COOLING PuuP $ PEED SRITCN COOLING UNii A 118 COMPONENT COOLING PuuP $ PEED 5tiTCN COOLING UNif 9 L d 140 NAIN STE AW 150L4fl0N VALVE 8.10 TON (ICR-400) 185 RE ACTOR TRIP SelTCMGEAR B 188 SPENT FUEL Pli SRIDGE CRANE (ICA-002) 189 FUEL HANDLING BUIL0iNG CRANE (ICR-003) g ] l 171 RE ACTOR BUILDING POLAR CRANE (ICR-004) 112 RE ACTOR CAflTY MANIPULATOR CR ANE (ICR-001) p gp p iff NER FUEL ELEVATOR flNCN (ICR-45) L. 552-(7 202 RE ACTOR SUILDING COOLING UNIT 24 204 RE ACTOR BUIL0 LNG COOLING UNil 2B 1?2 231 CONCEN$st BATER 80I.10 TON N0l$f (ICR-254) 0 2i. tin $rt A. iTOP AND CONTROL iAL,E.. TON N0isi <iCR-24 242 IUROINE SyllolNG CRANE (ICR-li) C lie PROTEI CABLE REEL (ICR-18) PART OF ICR-002 179 FUEL TRANSFEll CJhAL GATES.3106 WIST (IC44) PART OF ICE 003 N 112 l j ~ ~ 7 EL. 94-6 "T 4 D ') l srr y 9 ) gl= Mxg 1is s I g I [-- ) ~ i( d it. sy v i . ;=-- a w ~ l =_- ^ t l l , A-j l u_ E g e ,t. <sse d'(o (ph u = -! 21 1 T W IB u u [ Q .c.,1-e ( V r J Also Available On x x Aperture Card i 3 WEST 'fl a APEWEUld CARD SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION GeneralSection A A-Looking West Figure 7 gal Dwg. C-021007 e p 10171-11111 INIOl6lIl21 lClOlNlIl lHIVlYl ILl0lAlOlSl INIPIPISl 8502050391-07

I } l 10 l 9 l 8 l 6 7 A tr,1 c-a h Os 5 a s n x t"ix j 4 .p d Q lN C. 2 d f' C XE SWPH d_.. t Jr u. =7 ( ..Z ~~ (GylFMENT y f g H ATC H (ASOy[) p' @@D PL AN AT EL 425'-O" m)- A E PLAN A SWPH a / -g g. h G et. es-v l f m r - J f '. ]' EL. 2f-( l t c m 6. g 265 j g =i 6 i f =< i l / et m-e m I..;,qi y[ :: ll .,i : :: : 232 t.., t.., :.. SECTION B-B H II w.r..ptr.rrpurrrg g g l

e h l l l l 5 4 3 2 1 EQPT 10 DESCRIPIION 250 $f flVICE E8TER PUuP A 251 StilVICE SATER PUUP e A N 252 $ERmt.Ar R Puur C 253 AIOV $slTCMGEAR 0 254 7200V $sifCHGIAA 8 255 $Pf ED $ ELECTOR StifCN 258 WCC IuCIE31I 257 $ERVICE 9AfEit PUUP HOUSE $UPPLV F ANS (I AND 9) 25 25 265 25s 4:0V $sliCHEE AR A 259 NCC IuClfAll 260 7200V telTCMGEAR 281 $ PEED $91TCH d 242 TRA81$FER StifCH Q g 283 $ PEED $slTCH 264 uCC IuCIECit ^ 245 SERVICE e4TER PuuP MOU$E TRANSFER R8lt, it 701 #CIST (OSI) 'O 268 $lRVICE BATER PuuP A. le TON N01st (ICR-50) 0 ,4 do -J l 2sr $ERvits strER PUu' O. le imi M015T (ICR-50) l I ~ 288 $EptlCE EATER P IS f 31 MOIST (ICR-50) ^ [ .c 269 EQUIPutui NATCM.

- uCN0AAll IP -/ W

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i Qp i j l 10 l 9 l 8 l 7 6 i N (a, ,l + i x 'x J KEY PLAN g 'li' ly'ry' "" _{ l 0 10 20 30 40 50 G0 GRAPHIC SCALE IN FEET Ej j C - -- --- ?~ ^ ^ p_I.~.@:_@ [] \\[] [] h y ~~ M [ touiputur watcw Ap : ; L g # < -o g, 7m insTRuutNT AND SERyt(t f i 1 ~"1 D AI R couPRtsscas g w, i - - - + _[] LLL <=r- _{. -- o-I C,) -+ \\ y _L g l N y-n. n, E IQ }. O - r; T-GT - i is ,4., ,- ~, ,* h .T J E2 @ { _jt _'i i ' ) Ew-i, ll4 ffB -+- ' . 3 g _._l pj G1-J- _0, i ( o F ~ ~l ll l l f -d1_. r1 (1_ f- -Nf1 f1 7 ta 'a i i'd6 l i, ; i' i i i

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e l l 3 l l y 5 4 2 1 EQPT 1 CEttelPfl0N 228 FEEDSATER 600$ftR PL'eP 4. 4 TON N0lli (ICR-28) 227 FitDeaf! A OOO$fER PUNP 9. 4 TON N0ili (ICit-28) A 228 FEE 004 tit 800$fER PUNP C. 4 TON N01st (ICR-28) 229 FEIOctif t 800$iER PUuP 0, 4 TON N0lsi (ICR-28) 230 FifD9ATit 800$fER PUuP51 THRU 0. 4 TON HOIST (ICD-28) 231 C01 CENSER WAftR 80I. le TON N0lli (ICR-258) 232 CONOENSER 9ATER BOI. le 100 N0lli (ICR-255) 233 CONCENSER DATER 90I. IS TON HOIST (ICR-25C) 234 CONDENSER BAftt 501, it TON N0lli (ICR-250) 230 229 228 227 235 lisimAENT Af8 SERVICE AIR CGME550lt,1112 TGI NOIST (I01-40) A4im l I "13_.- [j'I I g _- _._d g i l )- Mao Available on g V csca w\\ y ~/ m/s-y/a Aperture Carel / / r 1 - r1' r1 r f u b ,L a La i.] L kd . rtro::.it ecostER PtJ M P S I -4;1 m -.=(E-EDe ,7 E "a = B i! [- a a: J at -u. -sNmQ "" ' E 8 _g. 3 + cs _ [- l v__ . _q 3 ~ _E- .E g i [*'- (h. E ( -ELI---- - Ih-n ("3 fr/ A b~ 23L -{l Ih g ~ TI ~ o si c3_. e o 1 g APERTURE ~ E3 GEF i 1 2J CARD f t 4- 'a 0 1~ .__['} _ _-_ [~ A_ _ _1_ _ 'g J --' 2 8'-T 200' 28T _ 2 tT b b b b g A4ms c-028-007 SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION Turbine Building Plan at Elevation 412' 0" Figure 9 gal Dwg. C 021009 i k 10191-1IIIIIN101611121 ICIOINITI lHjVlYl lLIC4A1Dl$l lNlPIPlSI ! l 8502050391 -09 4

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m,.. f(n 4.0 CODE AND STANDARD COMPLIANCE N 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 supplier adhered to the standards quoted above to the extent to which they were applicable. 4.2 LIFTING DEVICES The lifting devices at the Virgil C. Summer Nuclear Station are grouped into two general categories: special lifting devices and L' slings. These lifting devices do not comply with either the requirements of ANSI N14.6-1978, " Standard for Special Lifting -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 by a detailed inspection and testing program. Maintenance procedures have been developed to perform-frequent and periodic inspection, l which include visual and non-destructive examination of critical l surfaces.- Periodic-_ load tests are performed to verify structural-l adequacy of'the special lifting devices. _All rigging and lifting devices are controlled and maintenanced using the plants computerized preventative maintenance program (CHAMPS). Existing inspection and maintenance procedures are outlined in the Virgil C. Summer's Nuclear Station Operations Mechanical Maintenance Procedure 19fP-165.8, "Use and Control of Rigging Equipment". bLL tnentit " 4-1 REVISION 13 6-25-84

4.2.1 'Special Lifting Devices for Reactor Vessel Servicing 1 Several special lifting devices are provided at the -Virgil C. Summner Nuclear Station for servicing reactor vessel components. These devices include the reactor vessel head lift rig, the reactor vessel internals lift rig, the load' cell, and load cell linkage. An evaluation of the acceptability of the reactor vessel head lift rig, reactor vessel internals lift rig, load cell, and load cell l linkage has been performed (see Westinghouse WCAP 10233). The evaluation included a stress report and a critical items list prepared in accordance with ANSI N14.6-1978. The following conclusions resulted from the evaluation:

1..

Design, fabrication, and quality assurance of these special lift devices are generally in agreement with ANSI N14.6. LJ 2. The ANSI N14.6 criteria for stress limits associated with certain stress design factors for tensile and shear stresses are adequately satisfied. 3. The application of the ANSI N14.6 criteria for stress design l factor of 3 and 5 are only for shear and tensile loading conditions. Other loading conditions are~ analyzed to other appropriate criteria. 4. .These.special lift devices are not in strict compliance with l the ANSI N14.6 requirements for acceptance testing, . maintenance, and verification of continuing compliance. I 5. In lieu of the requirement of ANSI N14.6, Section 5.2.1, requiring an initial acceptance load test prior to use equal ,m__ to 150 percent of the maximum load, the 125 percent of v() Geert/P-4-2 REVISION 1 6-25-84

maximum load test that was performed is considered to meet \\g the intent of the load test requirement. 6. The non-destructive testing of the lifting device welds as required by ANSI N14.6 is not performed annually because: a. The items that are welded remain assembled and cannot be misused for any other lift other than their intended

function, b.

All tensile and shear stresses in the welds are within the allowable stress. c. Access to the welds for surface examination is difficult. These rigs are in containment and some contamination is present. p .d. To perform non-destructive tests would require: N). (1) Removal of paint around the area to be examined which is contaminated. (2) Performance of either magnetic particle inspection or liquid penetrant inpsection and (3) Repainting after testing is completed. (4) Cleanup of contaminated items. e. Performing non-destructive tests on these welds every refueling.would increase the critical path refueling ~ time. 7. Dimensional checking as required by ANSI N14.6 is not performed since these lifting rig structures are large (about (p) v m /remmem-mann 4-3 REVISION 2 1-21-85

13 feet diameter by 43 feet high) and the results of dimensional checking would always be questionable. Other checks on critical load path parts, such as pins, are also not included since an examination of these items would require disassembly of the special lift devices. The following recommendations resulting from the evaluation address the areas of ANSI N14.6 which are incompatible with the special lifting devices for reactor vessel servicing and which are considered most important in demonstrating the continued reliability of these devices. 1. The stresses determined in the evaluation, although higher than the ANSI N14.6 allowables, are considered acceptable since: a. The design weight used in the stress calculations is based on the weight of the lower internals. The lower ( internals are only removed when a periodic inservice inspection of the vessel is required (once/10 years). b.- Normal use of the rig is for moving the upper internals which' weigh less than one-half of the lower internals. The design' weight is based on lifting the lower internals. Thus, all the stresses could be reduced by approximately 50 percent and considered well within the ANSI N14.6 criteria for stress design factors. c. Prior to removal of the lower internals, all fuel is removed. Thus, the concern for handling over fuel is non-existent in this p,teticular case. 2. SCE&C maintenance procedures are being revised to include consideration of ANSI N14.6 Sections 5.1.3 through 5.1.8. p These. sections include requirements fort scheduled periodic b tesm/Camunsuch 4-4 REVISION 2: 1-21-85

p(,) testing; special identification and marking; maintenance, repair, testing and use. Westinghouse remarks on addressing these sections _are listed in Attachment A, Appendix B, Items 5, 6, and 7 of WCAP-10233. 3. It has been reconenended that SCE&G maintenance procedures be l revised to include the following in lieu of ANSI N14.6 Section 5.3 which requires, annually, either a 150 percent maximum load test or dimensional, visual and non-destructive testing of major load carrying welds and critical areas. The following is based on the intent of Westinghouse WCAP-10233, with modification to account for inaccessibility of critical welds during full load lifting of reactor vessel components. a. Reactor Vessel Head Lift Rig Prior to use and after reassembly of the spreader ( ) assembly, lifting lug, and upper lifting legs to the upper portion of the lift rig, visually check all welds. Raise the vessel head slightly above its support and hold for 10 minutes. If no problems are apparent, continue to lift, monitoring the load cell readout at all times. b. Reactor Vessel Internals Lift Rig Prior to use, visually inspect the rig components and welds while on the storage stand for signs of cracks or deformation. Check all bolted joints to ensure that ' they are tight and secure. After connection to the upper or lower internals, raise the assembly slightly off its support and hold for 10 minutes. If no problercs are apparent, continue to lift, monitoring the load cell readout at all times. A Geertir-a 4-5 REVISION 2: 1-21-85

n ./ 1 s 4.. A periodic.non-destructive surface examination of critical T welds and/or parts would be performed once every ten years as part of an inservice inspection outage. )4.2.2 Slinas [ m h " Dynamic load calculations were performed on each hoist to /

determine loading characteristics. The calculations were conducted'in accordance CMAA Specification No. 70, 1983 Edition, Paragraph 3.3.2.1.1.1.4.2.

The results of these calculations, are . presented in Table 4-1. The dynamic load associated with each ~" electrified hoist was found to be 15% or less in all cases due to . generally slow hoisting speeds. Dynamic load characteristics for manual hoists have not been established by the applicable code, HMI'200.~ To establish an analysis criteria for these hoists and apply CMAA Specification No. 70 Standard, it was necessary to U determine the maximum instantaneous-lifting speed. The maximum ~ , A 'l', i chain overhaul speed established for these hoists was 90 fpm which j results in extremely'st'ow hoisting speeds and negligible dynamic loading forces.- -It.is felt that this method complies with the ' intent of Guideline 5 oflNUREC-0612.- The lifting devices were ,,- j ' c # excluded from further study on the basis that all hazards to .s / essential shutdown equipment were eliminated,by the methods .previously. discussed in this-report. o e t ( [ t 4.3 INSPECTION, TESTING, AND MAINTENANCE .. Cranes and rigging equipment are maintained, tested, and inspected to the requirements ofl ANSI B30.2, Chapter 2-1. The crane and h-rigging equipment'are scheduled for the specific maintenance tasks by the plant's computerized history and maintenance progran t-(CHAMPS). 93 4 -r - 1 A' w w./ Gert/Commonseeth 1 - 4 REVISION 2: 1-21-85

m TABLE 4-1 -p j.7-Nj RESULTS OF IMPACT LOADINC CALCULATIONS i ACTUAL ALLOWABLE RATED LIFTING IMPACT IMPACT -CRANE CAPACITY SPEED LOAD LOAD TAC NO. (TONS) (FPM) (TONS) (TONS) i> XCR-3;(MAIN HOIST) '125 6 3.75 18.75 XCR-3 (AUX. HOIST) 25 27 3.38 3.75 lXCR-4'(MAIN HOIST) 360 4.2 7.56 54.00 - XCR-4 '( AUX HOIST) 25 27 3.38 3.75 XRW-13 3 22 0.33 0.45 XCR-18 10 20 1.00 1.50 .XCR-19' 7.5 20 0.75 1.13 [. -XCR-20~ 5 0.45 0.01 0.75 -XCR-21' .5 0.45 0.01 0.75 XCR 2 1.67 0.02 0.30 iN XCR 5 22 0.55 0.75 ,ICR 2 20 0.20 0.30 7XCR-29 2 1.67 0.02 0.30 -XCR 2 1.67 0.02 0.30 )XCR-36 20 10 1.00 3.00

XCR-40 10 0.23 0.01 1.50 XCR-42 10 20.7 1.00 3.00

' f}- ~XCR-46 3 22 0.33 0.45 k~j'~ XCR-47 10 11 0.55 1.50 XCR-49 3 30 0.45 0.45 XCR-50 10 20 1.00 1.50 XCR-51 10-0.23 0.01 1.50 XCR-53 2 1.67 0.02 0.30 XCR-54 5 0.45 0.01-0.75 r o 3 m: i 't0 ' O Geert/Commesmosan .4-7 REVISION lt 6-25-84 a

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3-4.4 CRANE OPERATOR) TRAINING 1$Q Nuclear Operations at the Virgil C. Summer Nuclear Station conducts an' extensive training program for overhead crane if ',i operators and riggers regarding heavy load lifts over safe load paths which meet or exceed applicable requirements of the references and standards listed below. The training programs include classroom-training, written examinations, and practical examinations. An annual physical examination and bi-ennial

11 (2 years) refresher training is required to maintain iyy qualifications.

{y1 References / Standards: ANSI B30.2, " Overhead and Cantry Cranes" ANSI B30'.9, " Slings"~ ' ANSI B30.10, " Hooks" ANSI 830.11, " Monorail Systems and Underhung Cranes" fe .c i Nf ANSI B30.16, " Overhead Hoist" OSHA 1910.179, " Overhead and'Cantry Cranes" NUREC 0612,," Control of Heavy Loads at Nuclear Power Plants" Applicable General Maintenance Procedures Applicable Mechanical Maintenance Procedures Applicable Vendor Manuals M y h.,i . ym .!v).i ..q, Gemir" 4-8 REVISION 2: 1-21-85

? b - [) u) ' HMP-500.005, " REACTOR VESSEL HEAT REMOVAL AND INSTALLATION" V' v) MMP-500.006, " REACTOR VESSEL INTERNALS REMOVAL /REINSTALLATIONS" w) . INSTRUCTION OF CRANES: 1) Wright Electric Hoist 3/20 Tons - 2). P&H-Turbine Building 220/30 Tons 3) Polar Crane-Reactor Building 360/25 Tons 4)' Manipulator Crane-Reactor Building . 5) Whiting Overhead Crane-Fuel Handling Building 125/25. Tons 6) Spent Fuel Bridge Crane-Fuel Handling Building The' crane operator and rigger training programs include in-class written examinations and in-plant examinations for practical - application. After a crane operator or rigger becomes qualified by the training program, an annual physical examination and a biennial retraining and requalification of the crane operators and riggera are required. U.V ,u /: l Gimette" 's 1 4-9 REVISION 1: 6-25-84

_m 6 I 5.0 PROCEDURES-s/ s\\ I' Since the Virgil C. Summer Nuclear Station is in commercial operation, most procedures for handling heavy loads with overhead handling devices have been developed. Currently maintenance [ procedures are developed to encompass overhead handling systems I with respect to the safe load paths. Where safe load paths can not be established, special lifting procedures are developed, and where possible special lifting instructions are incorporated into specific component maintenance procedures. Any deviation from 4 established safe load paths is enforced by established procedures. s s Procedures have been transmitted from Westinghouse Electric Corporation to South Carolina Electric and Gas Company for the i -handling of new and spent fuel, refueling, and for the operation of refuelinglequipment. These procedures have been reviewed and placed into a standard format prior to issuance and use. ~ 4 LThe individual ~-overhead handling device descriptions in - Section'3.0 indicate where proce'ures have been developed to d t ' minimize the possibility of an inadvertant heavy load drop. L ll' -t U - t-M- 1 , 5;+ e J C l ~~\\ [ }(j r Gast/Commanussa ' 5-1. REVISION 1: 6-25-84 N ? y we e -=

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y e LA--sA a- --a A emaa -aA e 4-- 2 am k - + - 4 -G1 6 -a4--w-e t a w f APPENDIX A STRUCTURAL' ANALYSIS OF DROPPED HEAVY LOADS i t b I 1 l l l l - l i <Q-g 4 ' N ', e k Gdtert/Comnenuesth W

n APPENDIX A STRUCTURAL ANALYSIS OF DROPPED HEAVY LOADS TABLE OF CONTENTS 'Section-Title M n A.1 INTRODUCTION A-1 A.1.1 INITIAL CONDITIONS A-2 A.1.1.1 XCR-40A/B/C A-2 -A.1.1.2 XRW-13 and XCR-36 A-3 'A.1.1.3 XCR-27 A-3 -A.1;1.4 XCR-46 A-4 P 'A.1.1.5 XCR-51 A-4 J A.2 ASSUMPTIONS / IDEALIZATIONS-A-5. 'A.2.1 MATERIAL PROPERTIES-A-5 .A.2.1.1-Loadina conditions A-6 A.2.1.2 Local Effects A-6 A. 2.1.3 ~ Energy Absorption Mechanism' A-6 A.2.1.4' Yield Line Theory A-7 A.3 BEHAVIOR OF REINFORCED SLABS-UNDER IMPACT A-7 . A.4 - EVALUATION OF SLAB' CAPACITY A-8 A.5,

SUMMARY

/ CONCLUSIONS' A-8 e

-A.6 REFERENCES A, i TABLE A-1 Impact Analyses Data Summary-A-10 ),^ L mr A-i REVISION-2: 1-21-85 .. ~.

r~N, APPENDIX A 'Q ' 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 NUREC 0612, Section 5.1. This appendix presents a summary of the results. Five (5) potential drop areas have been identified requiring structural evaluation to determine if the floor slabs and support systems maintain structural integrity such that safe shutdown and decay heat removal equipment are not jeopardized. The floor slabs evaluated are as follows: /N XCR-40A/B/C h. Intermediate Building at elevation 436' bounded by Column Lines J1 and H4 between lines 2 and 8 (Figure 4). XRW-13 and XCR-36 Druauning Station.and Truck Bay of the Auxiliary Building at elevation 436' bounded by Column Lines P and R between lines 6.6 f and 8.8 (Figure 4). XCR-27 Intermediate Building at elevation 436' between Column lines'C.4 .to H 4 and 7.5 to 8.3. The floor slab at elevation 436' near the south end of the. hatchway:is considered to be the loaded area (Figure 4). ,es;. b&. Gdhert/Commennesith A-1 -REVISION 2: 1-21-85 m.

r~x. XCR-46 \\ '\\ -). Auxiliary Building at elevation 463' between Column lines P to Q and 8.8 to 11.5 (Figure 5). XCR-51 Service Water Pump House at elevation 436' directly above and behind the service water pumps. The floor slab directly below XCR-51 is assumed to be the loaded area (Figure 8). The calculation method adopted uses the energy absorption concept with conservative-assumptions. By comparing the utlimate energy absorption capccity 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 safe shutdown and/or decay heat removal equipment located below. 3.m s_s. A.I.l' INITIAL CONDITIONS A.l.l.1 XCR-40A/B/C Load: The postulated dropping object _is a main steam isolation valve weighing 20,000 lbs. with a center of gravity dropping height of 10'-9". The approximate overall -dimensions of the valve are: 78 inches in length and 32 inches 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. fN i ). %) ~' reerticennesseeth A-2 REVISION 2: 1-21-85

Tx 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 steel in N-S direction and with #10 at 12" top steel and #9 at 12" bottom steel in E-W direction. For simplicity, it was idealized as an isotropic slab with #9 at 12" top and bottom steel. The l insitu steel deckir,g was ignored. A.1.1.2 XRW-13 and XCR-36 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 f. S'-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 slab. The most l .p critical dropping orientation is when the long axis of V cask makes an approximate 45 degree angle with the vertical and strikes at the center of the slab panel. Slab: The slab'is 3 feet thick, supported and monolithic with l concrete walls and with reinforcement: #10 at-6" of top and bottom steel in E-W direction and #10 at 12" top and bottom steel in N-S direction. A.l.l.3 XCR ' Load:' A load drop of 5 tons with a dropping height of 16' above the floor was assumed in the analysis. The crane handles miscellaneous equipment; therefore, no definite configuration can be established. However, it has been determined that the sharp corner of the dropping object hitting vertically at the free edge.would be t'..e worst a .A -case-k )- Geert/Commoneesem A-3 REVISION 2: 1-21-85

k if-i, - ( )' 3,,f7 Slab: All the floor slabs in this area have the same thickness and' reinforcement. The selected square slab has one free edge and is 2 feet thick with #9 at 12" top and bottom steel in N-S and E-W direction. A.1.1.4' XCR-46 Load: The postulated dropping object is a transfer cask with a weight of,3 tons from a height of 11' above elevation 463'. The cask overall dimensions are 38" in height and 20" in diameter. The most critical dropping ~ orientation is the long axis of_the cask at a 450 angle with the vertical striking at the center-of the rectangular slab or centerline of the slab-strip along the long sides. Slab: _ The floor slab at elevation 463' directly below XCR-46 is' considered to be the loaded area. All the floor slabs in this area are 2. feet thick, supported by concrete walls and have similar reinforcement: #9 at -12" of-top'and bottom steel in E-W and N-S direction. A selected rectangular slab and slab. strip beneath the electric cable hoist and bridge crane, respectively, are chosen in the analysis.- A.I.1.5' XCR-51 Load:- The postulated dropping object _is the Service Wat'er Pump Motor _with a weight of 16,600 lbs. The motor's overall ,_n ~ dimensions'are 100.5" in diameter and 94" in height with 6 a shaft 5" in' diameter'and 7" long under the base of the motor.- The maximum dropping height is-mearured from the 4 ' bottom of the shaft to the top.of the slab at () ' elevation 436'. Geert/Commenmesth 'A-4 REVISION 2: 1-21-85 t -s w

l s# \\ (,) It is assumed that the most critical case is when the shaft end strikes the center of the slab first. Therefore, in this case, a drop load of 16,600 lbs, from a height 4'-6" above elevation 436' will be assumed as an impact load acting on the center of the considered slab. Slab: All the floor slabs in this area are 2' thick, supported by concrete walls. For simplicity, this area was idealized as an isotropic slab with #9 at 12" top and bottom steel in each direction. A.2 ASSUMPTIONS / IDEALIZATIONS A.2.1-MATERIAL PROPERTIES 7y '.N For Concrete: fe = Compressive Strength = 3,000 psi ec = Ultimate Compressive Strain = 0.003 L ,For. Reinforcing. Steel: F = Yield Stress y = 60,000 psi F ~= Ultimate Tensile Strength u = 90,000 psi Es = Young's Modulus = 29 x 106 psi ym (} cs = Ultimate Tensile Strain ~ .= 0.13 Geert/Commenmeath A-5 REVISION 2: 1-21-85 n= .-.-.;._-._..__-..-...-._-..__._...~,-...-._._..

4 4 / (,,) 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. A.2.1.2 Local Effects - The intent of this analysis is to ascertain the structural integrity of the floor with respect to jeopardizing safe shutdown and decay heat removal equipment located below. Therefore, local effects such as spalling of the top of the concrete have not been considered. A.2.1.3 Energy Absorption Mechanism jx wl The kinetic energy of a dropping object upon impact may be -l -dissipated in several of the following ways: a. Energy absorption by' the target slabs resulting from'the elastic response of the structure to the impact. 3 b. Energy absorption by'the dropping object due to plastic deformation during collision. Energy absorption by the target slabs due to plastic c. deformation and local crushing. The manner of absorption of-the total kinetic energy of the h dropping object will depend on the sharpnesa,. 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 elastic and plastic deformation-e-Q (items a. and c. above) of the-impacted floor slab.. ~ me-s A-6 REVISION 2: 1-21-85 n.- . _ _ - _. _ _., _. - _.. ~. ~ _ _..

^ i . 2 fq.

A.2.1.4 Yield Line Theory t

o Yield line theory is based on the consideration of flexural collapse mode. A.3-BEHAVIOR OF REINFORCED CONCRETE SLABS UNDER IMPACT i'

References 1 and 2 describe the plastic collapse mechanisms of steinforced concrete slabs with different boundary conditions and

-subjected-t'o different loading cases. i In the case of a concentrated impact force, a collapse mechanism

corresponding to a cone, whose axis is normal to the slab and passes through the point of load application, may form.

For ' isotropic slabs (same reinforcement in both direct' ions), the ~ ' collapse area will be limited by a circul'ar yield line. The slabs under hoists XCR-40A/B/C, XCR-46A and XCR-51 are, therefore, g likely to experience a circular failure mode. For-orthotropic . slabs (different reinforcement in orthogonal directions), the -collapse area will be limited by an elliptic yield line. The r-slabs under XRW-13 and XCR-36 in Drumming Station / Truck Bay experience an elliptic failure mode.

u

'For an isotropic sq~uare slab with one free edge, i.e. XCR-27, yield lines are attracted toward the free edge and form a -h'alf-circular collapse mechanism when the' loaded point is at the. center of-the free edge. p( For all cases it is found that the concrete will reach.ite ultimate compressive strain before-the tensile' steel breaks. When 1

the concrete _is completely crushed, the slab loses its coment

< resistance..However, it.can sustain further impact through the ~ = membrane effect'of reinforcing steel until the steel strain'also p' reaches:the ultimate limit. Geeste-A-7 REVISION 2: 1-21-85' >Q _. 4-

31 ,ew; A.4 EVALUATION OF SLAB CAPACITY \\,- To evaluate the total capacity of the considered slab, the total plastic energy was calculated. The kinetic energy of the dropping object was also determined. The energy capacity of the slab was found to be larger than the applied kinetic energy due to the dropping load in each case. Table A-1 provides an impact analyses data summary. A.5

SUMMARY

/ CONCLUSIONS It is concluded that the concrete slabs under the consideration of heavy-load drop accidents are capable of withstanding the impact.

The results are considered to be on the conservative side for the following reasons: -~ - 'N_,/ ' a. The capacity due to membrane effect is neglected. b. Energy absorption by the plastic deformation of the dropping object is neglected. The energy absorption capacity of insitu steel deck in c. XCR-40A/B/C is neglected. It should be noted that the investigation did not include'the consideration of any secondary dropped objects that might be generated from distortion of the slab at the point of dropped load impact. t

\\

) %s Geert /r-h A-8 REVISION 2: 1-21-85

f-s 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. 3.

Johansen, K.W., " Yield-Line Formulate for Slabs", Cement and Concrete Association.

4. Johansen, K.W., " Yield-Line Theory", Cement and Concrete Association. 5. Nilson,'A.H., " Design of Prestressed Concrete". +

e 1

~s. f q ). Juj - M jr m m A-9 REVISION 2: 1-21-85 E --

,3 /-~\\. ~ ~ TABLE A IMPACT ANALYSES DATA

SUMMARY

XCR-36' XCR-40A/B/C XRW-13 XCR-27 XCR-46 'XCR-51 Location Intermediate Bldg. Auxiliary Bldg. Intermediate Bldg. Auxiliary Bldg. Service Water-Pump House Slab Thickness 2'-0" 3'-0" 2'-0" 2'-0" '2'-0" Reinforcement T 5 8 Each Way

10 at 6" E-W T & B Each Way T & B Each Way T & B Each Way (49 at 12")

(#10 at 12" N-S) (f9 at 12") (#9 at 12") (f9 at 12") Failure Mode Circular Elliptic Half Circular Circular Circular { Dropped Object Main Steam-Radwaste Cask Misc. Equipment Transfer Cask Service Water Isolation Valve Pump Motor o Dropped Load 20,000 Lbs. 40,000 Lbs. 5-Ton 3-Ton 16,600 Lbs. Dropping Height

10'-9" 10' 16' 11' 4'-6" Ratio of Energy Capacity of Slab to Kinetic Energy of gj Dropped Object

>l >l >l >l >l d us Ez

Center of gravity drop height 7%

b

e V APPENDIX B WESTINCHOUSE ANALYSIS OF THE REACTOR BUILDING O e d l .i b', t 5 (. tl' t - ~ I-O p. g

~

L APPENDIX B C,p WESTINCHOUSE 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 REFERENCES B-4 4 (~]\\ Q Gdhert/Commoneene B-i REVISION 1: 6-25-84

c:. .- B.1 INTRODUCTION fs-The following sections are the procedures and results of Westinghouse's analysis of' heavy load drops from the Reactor ~ -Building Polar Crane in the Reactor Building, as transmitted in Reference 6. B.2 PROCEDURE JThe 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 p1 cladding. ?

(

Each of the loads in Table 1-1 will be evaluated as a separate s 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,itwould'causedamage'toCRDM'sandreactor. 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. 2. Reactor Vessel Head Assembly (268,000 lbs.) - Westinghouse has performed a. dropped head analysis, provided in ..y~ - i V Geert/Cammenmese B-1 REVISION 1: 6-25-84 l

r, y-q 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 Virgil 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. However, it should not be carried over the open vessel after the upper internals have been removed and prior o 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 ir. Reference 4. 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 E, the upper internals have been removed and prior to removal of the fuel assemblies. ie I smartIcemmassen B-2 REVISION 1: 6-25-84 V ^~

o pM, 7. 'ISI Tool and Westinghouse-Supplied Liftina Device (20,000 L( 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 Casina and Liftina 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 cla'dding 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 ..:yN

(8s)7

-would not cause unacceptable. loads on the reactor vessel or p ~ nozzles. However,'it should not be carried over the open . vessel after'the upper internals have been removed and prior n to removal of the fuel' assemblies. r ~ 10. Equipment Bridae (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 internals have been removed and prioroto. removal of. the fuel assemblies. '~ -It can therefore be concluded that.for the above postulated drop ~ e on - b accidents'there will'be nu consequential damage _to'the structural. tntegrity of'.the vessel nozzles, no loss of core cooling (Gje ' capability, o-loss'of' fuel cladding integrity. 3 V, i _. 6? fi \\. L i - B-3 REVISION'1: 6-25-84 j. s =

r, B.4 REFERENCES x x.) 1. CAI Letter CCCW-1647, dated August 6, 1981. 2. NUREC-0612,'" Control of Heavy Loads at Nuclear Power Plants", July, 1980. 3. NRC-Letter by D. C. Eisenhut of December 22, 1980 and attachments. 4. WCAP-9289, " Integrated Vessel Head Package for One-Lift ~ Operation", March, 1978. 5. CAI Report No. 2289, " Control of Heavy Loads at Nuclear Power Plants - Virgil C. Summer Nuclear Station Unit 1", June 22, 1981. - 6. Westinghouse Letter CCWC-2440 and attachment. k .g-4 ' ' }(N. Geert/f-B-4 REVISION 1: 6-25-84

p..

f

<\\ APPENDIX C ANALYSIS OF IMPACT LOADS 1-i 4 e u 1 i. I I) ^ J' 1 Gdhert/Casemmesah i: I .. a

r.. _ APPENDIX C g'""j U ANALYSIS OF IMPACT LOADS TABLE OF CONTENTS Section Title Page C.1 INTRODUCTION C-1 C.2 BASIS FOR ANALYSIS C-1 C.3L RESULTS C-3 C.4 REFERENCES C-3 _k I i l' l . /"'i ~ ' ' ' \\,). 1 eentI"" l C-i REVISION 2: 1-21-85 c

./~5 C.1 INTRODUCTION Two impact loa'd analyses were performed for NUREC-0612. The first l evaluation was performed to determine the effects of a large steel beam impacting a section of service water piping. The service water line of interest is located at elevation 451'-6" in the Auxiliary Building near the equipment hatch for XCR-19. The line cannot be struck by a load drop; however, an inadvertent movement of the trolley could cause an odd size load, such as large steel beam, to strike the service water pipe. The second evaluation was performed to study the effects of a sharp cornered object striking at a section of 6" chilled water risers with respect to the pipe puncture and collapse. The two chilled water risers are located between El. 421'-3" and El. 453'-6" in the Intermediate Building nearby the path of hoist . ("s XCR-27. Although the risers are not in the path of the hoist, an inadvertent movement of the trolley could cause an odd size load to strike the risers. C.2 BASIS FOR ANALYSIS The following data were used as the input to the analysis: XCR-19 I-Beam: Size: W 18 x 60 Length: 14 ft Total Weight: 840 lbs Pipe: Size: 16" Wall Thickness: 0.375" Material: SA 106 Gr B ,/~T Support: 11.27 ft span fixed at both ends k camir--- - - sen C-1 REVISION 2: 1-21-85

f A W 18 x 60 I-beam was. chosen for the study since this is the ks largest section that could be expected at the elevation of the pipe. XCR-27 Sharp' cornered object: Wt: 5 tons = 11,200 lbs(6) Vh (Horizontal Speed): 32 FPM d (Projectile Diameter): 0.1 in.(2) Water risers: Size: 6" Wall Thickness: 0.28" Material: SA 106, Gr. B, Su = 60 ksi(3) m-Support Span: 11.25' The evaluation investigated both pipe puncture and pipe collapse. The criteria used for pipe puncture was based on an equation developed by The Stanford Research Institute, as noted below: 2 2, 3r ,0.0452 DV (d o 128 d-Su where,- ? e = Penetration depth ~(in.) d = Effective projectile diameter (in.) F = B/d, except F1100 (e/d) and F18, whichever is lower B = Width of plate between rigid supports (in.) 3 3 = W/d, caliber density (1b/in ) D '

W = Projectile weight (Ib)

Vo = Traveling speed of projectile (Ib) 2 Su = Ultimate strength (1b/in ) v r i-Geert/r-C-2 REVISION 2. 1-21-85 L.

)/"N ..The criteria used for pipe collapse is. based on a ductility analysis of the pipe. The equations and curves used for the analysis were taken from " Introduction to 3tructural Dynamics" by J. M. Briggs, McGraw Hill, 1960, page 72. C.3 -RESULTS XCR-19 The evaluation indicates that the pipe is in no danger due to the impact of the beam. The puncture analysis showed that maximum indentation of the pipe to be 0.016 inches which is much less than the 0.375 inch wall thickness. The ductility analysis determined that the pipe stays well within its elastic limits after the impact; therefore, pipe collapse can be eliminated as a concern. XCR-27 \\~- The evaluation indicates that the 6" chilled water risers are in no danger due to the impact of the sharp cornered object with the weight of 5 tons and the traveling speed of 32 FPM. The calculated penetration depth of the target risers is 0.155 in. which is less than 0.28 in., the wall thickness of 6" pipe. The ductility analysis determined that the target riser is within the elastic limit. Therefore, it is concluded that there is no pipe rupture or collapse occuring during the impact. C.4 REFERENCES 1. CAI Drawing C-314-251, Rev. 5. '2. -ASCE, " Structural Analysis and Design of Nuclear Plant Facilities", 1980, page 346. /y i LJ Geert/Cammeneesth C-3 REVISION 2: 1-21-85

3. ASME Boiler and Pressure Vessel Code Section III, Division 1, j- ! \\,J ~. Appendices,. Table I-1.1. 4.- " Introduction to Structural Dynamics", J. M. Briggs, McGraw Hill, 1960, page 72. 5. " Formulas for Stress and Strain", R. J. Roark and W. C.. Young, 5th Edition, McGraw Hill, 1975, page 576. 6. Design Information Transmittal from F. P. Drazal to J..E. Lisney, 8/6/84. b m y-. C REVISION 2: 1-21-85 u, o l' -}}

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