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Revision as of 04:21, 23 February 2020
| ML18139B819 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 03/31/1982 |
| From: | BECHTEL GROUP, INC. |
| To: | |
| Shared Package | |
| ML18139B818 | List: |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, TASK-A-36, TASK-OR NUDOCS 8203260148 | |
| Download: ML18139B819 (61) | |
Text
{{#Wiki_filter:NINE MONTH RESPONSE TO THE NRC LETTER DATED DECEMBER 22, 1980 ON THE CONTROL OF HEAVY LOADS FOR VEPCO NORTH ANNA UNITS 1 and 2 DOCKET NOS. 50-338 and 50-339 MARCH, 1982 BECHTEL ASSOCIATES PROFESSIONAL CORPORATION (Virginia) GAITHERSBURG, }1ARYLAND 14569-001 ' --8203260148 ---820322 - -. . ----~"'\ PDR ADOCK 05000280 P PDR
TABLE OF CONTENTS Section Title Page I Introduction 1 II Definition of Heavy Loads 1 III Specific Requirements For Overhead Handling Systems Operating in the Vicinity of Fuel Storage Pools 1 IV Specific Requirements For Overhead Handling Systems Operating in the Containment 5 V Specific Requirements For Overhead Handling Systems Operating in Plant Areas Containing Equipment Required for Reactor Shutdown, Core Decay Heat Removal, or Spent Fuel Pool Cooling 8 VI Analysis of Plant Structures 14 VII Summary 17 VIII References 17 APPENDICES A. TARLES TABLE 1 - LOAD/IMPACT AREA DATA B. SAFE LOAD PATH SKETCHES
I. Introduction This report addresses the nine-month response to the December 22, 1980 NRC letter: Control of Heavy Loads. This is the second portion of the North Anna Power Station heavy loads evaluation. The first portion, concerning the general requirements for heavy load handling systems was submitted to the NRC on December 22, 1981. This report provides the information on the specific requirements for heavy load handling systems corresponding to Sections 2.2, 2.3 and 2.4 of the NRC letter. II. Definition of Heavy Loads A heavy load is defined in NUREG 0612 as any load whose weight is greater than the combined weight of a single spent fuel assembly
- and its handling tool. The heavy load was incorrectly defined as 2,500 pounds in the six-month response to the December 22, 1980 NRC letter. The correct combined weight of a single spent fuel assembly and its associated handling tool is 2,000 pounds for North Anna Units 1 and 2. This correction does not alter any of the results in the six-month report.
III. Specific Requirements for Overhead Handling Systems Operating in the Vicinity of Fuel Storage Pools Section 2.2-1 requests the name, type, capacity, and equipment designator of any cranes physically capable (i.e., ignoring interlocks, movable mechanical stops, or operating procedures) of carrying loads which, if dropped, could land or fall into the spent fuel pool. 1
The following heavy ,load handling equipment is physically capable (i.e., ignoring interlocks, movable mechanical stops, or operating procedures) of carrying loads which, if dropped, could land or fall into the spent fuel pool. Equipment Name Capacity Designator (Tons) Fuel Bldg. Movable Platform with Hoists 4 l-MH-FH-13 Section 2.2-2 requests information to justify the exclusion of any cranes in this area from the above category by verifying that they are incapable of carrying heavy loads or are permanently prevented from movement of the hook centerline closer than 15 feet to the pool boundary, or by providing a suitable analysis demonstrating that for any failure mode, no heavy load can fall into the fuel-storage pool. The fuel building trolley (l-MH-CR-15) which is used for moving spent fuel casks does not move over stored fuel, and therefore, is not included in 2.2-1 above. The hook centerline is capable of movement to 5 feet 4 inches from the edge of the fuel pool. The west wall of the fuel pool separates the spent fuel cask storage area from the fuel pool. Only during the movement of spent fuel casks into and out of the fuel building are the casks raised above the top of the fuel pool wall. The centerline of the cask during this movement can be no closer than 1 foot 10 inches from the outside edge of the pool wall. To guard against the possibility of the cask falling from the trolley, the trolley is equipped with eddy current brakes, dual load holding brakes and "dead man" controls. In addition, as analyzed by the FSAR, the lift height is limited to one foot, 2
The new fuel bridge crane (l-MH-CR-20) does not operate within 15 feet of the spent fuel pit, and therefore, is not included in 2.2-1 above. The fuel elevator hoist (l-MH-FH-2) is not included in 2.2-1 above since this device does not handle "heavy loads". Section 2.2-3 requests information for cranes listed in 2.2-1, above, which have been evaluated as having sufficient design features to make the likelihood of a load drop extremely small for all loads to be carried and the basis for this evaluation (i.e., complete compliance with NUREG 0612, Section 5.1.6 or partial compliance supplemented by suitable alternative or additional design features). The heavy load handling equipment identified in 2.2-1 does not meet the single failure proof criteria as outlined in NUREG 0612, Section 5.1.6. No credit is taken for partial compliance. Section 2.2-4-a requests which alternatives (e.g., 2, 3, or 4) from those identified in NUREG 0612, Section 5.1.2, have been selected for the cranes identified in 2.2-1 above. No alternative was selected for the heavy load handling equipment identified in 2.2-1. The fuel building movable platform will not handle "heavy loads" over the spent fuel pool. Section 2.2-4-b requests a discussion of the crane motion% limitations imposed by electrical interlocks or mechanical stops and the circumstances, if any, under which these protective devices may be by-passed or removed. The movable platform with hoists that is identified in 2.2-1 above is a wheel-mounted motor driven platform with two overhead electric hoists. The movable platform spans the spent fuel pit and is 3
designed to be maneuvered over the spent fuel pool, the fuel transfer canals, and the new fuel handling and storage area as required during fuel handling operations. The spent fuel storage pit and the movable platform with hoists are shared by both Unit 1 and Unit 2. The movement of the movable platform is not restricted by electrical interlocks or mechanical stops, however, the hoists that are used to lift spent fuel have a limited maximum lift height so that the maximum required depth of water shielding is maintained. The Technical Specifications prohibit the movement of loads in excess of 2,500 pounds from travel over irradiated fuel assemblies in the spent fuel pit. Plant procedures will be revised to prohibit the handling of loads in excess of 2,000 pounds over spent fuel. Section 2.2-4-c requ~st~ a discussion of any administrative or physical controls that are provided to ensure the validity of crane operational limitations with respect to the time of the storage of certain quantities of* spent fuel at specific post-irradiation decay times. No reliance is placed on operational limitations with respect to time of fuel storage for the heavy load handling equipment considered in 2.2-1 above. Section 2.2-4-d requests a discussion of any administrative or physical controls that are provided to ensure the validity of the physical location of specific fuel modules at certain post-irradiation decay times. No reliance is placed on the physical location of specific fuel modules at certain post-irradiation decay times for the heavy load handling equipment considered in 2.2-1 above. 4
Section 2.2-4-e requests information to justify any exceptions taken to Criteria I through III of NUREG 0612, Section 5.1. No heavy loads can be dropped into the spent fuel pool as discussed in this section. No load drop event associated with bringing a heavy load within 15 feet of the spent fuel pool results in the tumbling of the load into the pool or violation of the fuel pool's integrity. Therefore, no postulated load handling event has radiological consequences. IV. Specific Requirements of Overhead Handling Systems Operating in the Containment Section 2.3-1 requests the name, type, capacity, and equipment designator of any cranes physically capable (i.e, taking no credit for any interlocks or operating procedures) of carrying heavy loads over the reactor vessel. The following crane is physically capable (i.e., ignoring interlocks, movable mechanical stops, or operating procedures) of carrying heavy loads over the reactor vessel: Equipment Name Capacity Designator Polar Crane 2-140 Ton Trolleys and l-MH-CR-1 (Unit 1) 1-50 Ton Auxiliary Hoist 2-MH-CR-l (Unit 2) Section 2.3-2 requests information to justify the exclusion of any cranes in this area from the above category by verifying that they are incapable of carrying heavy loads, or are permanently prevented from the movement of any load* either directly over the reactor vessel or to such a location where in the event of any load-handling-system failure, the load may land in or on the reactor vessel. 5
The manipulator crane (l-MH-CR-5) and the containment dome monorails are not included in 2.3-1 above, since these devices do not handle "heavy loads". The containment annulus hoist (1-MH-CR-19), recirculation spray pump hoists (1-MH-CR-39 A and B), and RHR pump monorails do not handle loads over the reactor vessel, and therefore, are not included in 2.3-1 above. Section 2.3-3 requests information for cranes listed in 2.3-1, above, which have been evaluated as having sufficient design features to make the likelihood of a load drop extremely small for all loads to be carried and the basis for this evaluation (i.e.,* complete compliance with NUREG 0612, Section 5.1.6, or partial compliance supplemented by suitable alternative or additional design features). The crane identified in 2.3-1 does not meet the single failure proof criteria as outlined in NUREG 0612, Section 5.1.6. No credit is taken for partial compliance. Section 2.3-4-a requests a discussion of the crane motion limitations imposed b.Y electrical interlocks or mechanical stops and the circumstances, if any, under which these protective devices can be removed or bypassed. The crane identified in 2.3-1 is of the polar configuration and is supported on the circular crane wall in the containment. The crane has two main hooks. One of the two main hook trolleys also has an auxiliary hook. The polar crane has access to the entire area within the crane wall. The auxiliary hook has access to the ~rea inside and outside the crane wall. The movement of the polar crane is not restricted by electrical interlocks or mechanical stops. 6
Section 2.3-4-b requests a discussion of any administrative controls that are provided to ensure the validity of site-specific considerations (e.g., refueling*sequencing). The operation of the crane is administratively controlled by VEPCO Administrative procedure M.D. ADM-9.1, "Control of Heavy Loads in Reactor Containment - 291 Level" to prevent handling loads over the reactor vessel when there is fuel in the vessel unless the load lift is specifically required for reactor disassembly, reassembly, or vessel inspection. Administrative Procedure M.D. ADM-9.1 defines safe load paths and requires that deviation requests be submitted "prior to use" for those loads which are handled during maintenance operations that require deviation from routine safe load paths. These deviation requests identify the equipment to be handled and include the load weight, the reason for the deviation, and a sketch of the requested load path. Any load lifts that are not covered by a deviation request are controlled by administrative procedure M. D. AD1'1-9 ..1 previously mentioned. A discussion of other site-specific considerations for the containment polar crane is presented in the response to Section 2.4-2-b(3). Section 2.3-4-c requests information justifying any exceptions taken to Criteria I through III of NUREG 0612, Section 5.1 and Appendix A, or analyses demonstrating compliance with these guidelines. Analyses of reactor vessel head drop per Appendix A, Section 2, taking into account subsections (2)a, (2)b, (3), (4), and (5) will be performed by Westinghouse. Reactor vessel head drop analyses outside the envelope of the reactor vessel are presented in Section V of this report. Drops outside the reactor vessel envelope have no radiological consequences and therefore, do not involve criteria I, II or III of Section 5.1, NUREG-0612. 7
V. Specific Requirements for Overhead Handling Systems Operating in Plant Areas Containing Equipment Required for Reactor Shutdown, Core Decay Heat Removal, or Spent Fuel Pool Cooling Section 2.4-1 requests information for cranes identified in the response to Section 2.1-1, which have been evaluated as having sufficient design features to make the likelihood of a load drop extremely small for all loads to be carried and the basis for this evaluation (i.e., complete compliance with NUREG 0612, Section 5.1.6, or partial compliance supplemented by suitable alternative or additional design features). None of the cranes identified in the response to Section 2.1-1 meet the single failure proof criteria as outlined in NUREG 0612, Section 5.1.6. (These cranes are listed in Tables 1 and 2, in Appendix A of the six-month response to the December 22, 1980 NRC letter, "Control of Heavy Loads", that has been previously submitted.) No credit is taken for partial compliance. Section 2.4-2-a requests that a comprehensive hazard evaluation be provided for the cranes identified in the response to Section 2.1-1, including a presentation of all.heavy loads and potential impact areas where damage might occur to safety-related equipment. The following is a list of the cranes from which a load drop may result in damage to a system required for plant shutdown or decay heat removal, taking no credit for any interlocks, technical specifications, operating procedures or detailed structural analysis. 8
Equipment Name Capacity (tons) Designator Containment 2-140 Ton Trolleys and 1-MH-CR-1 (Unit 1) Polar Cranes 1-50 Ton Auxiliary Hoist 2-MH-CR-1 (Unit 2) Containment 5 1-MH-CR-19 (Unit 1) Annulus Hoists 2-MH-CR-19 (Unit 2) RHR Pump 3 Monorails Auxiliary Building 12 1-MH-CR-8A & B Material Handling System Monorails Auxiliary Building 12 1-MH-CR-9B Material Handling System Monorail New Fuel 5 1-MH-CR-20 Bridge Crane
/
Fuel Building 4 1-MH-FH-13 Movable Platform Table 1 in Appendix A provides information on heavy loads and potential impact areas where a load drop from the above overhead load handling systems could result in damage to equipment required for safe shutdown or decay heat removal. Section 2.4-2-b requests which of the load and impact area combinations can be eliminated because of separation and redundancy of safety-related equipment, mechanical stops and/or electrical interlocks, or other site-specific considerations.
\t The hazard elimination categories utilized in Table 1 of Appendix A are identified as follows:
A. Crane travel for this area/load combination prohibited by electrical interlocks or mechanical stops. 9
B. System redundancy and separation precludes loss of capability of system to perform its safety-related function following this load drop in this area. C. Site-specific considerations (e.g., administrative procedures) eliminate the need to consider load/equipment combination. D. Analysis demonstrates that crane failure and load drop will not damage safety-related equipment. E. Likelihood of handling system failure for this load is extremely small (i.e. Section 5.1.6 NUREG 0612 satisfied). F. Analyses to demonstrate that Criteria I, II and III of NUREG 0612 are satisfied will be done by Westinghouse. Section 2.4-2-b(l) requests a discussion of the basis for determining that load drops will not affect continued system operation (i.e., the 'ability of the system to perform its safety-related function) for the load/target combinations eliminated because of_ separation and redundancy of safety-related equipment. Loads carried by the Polar Crane during refueling which originate in the reactor pressure boundary area can be eliminated from further consideration based on separation and redundancy. The hazard being considered is a drop in this area that causes a break in the Reactor Pressure Boundary, and damaging or disabling the Reactor Coolant System. This event will not have unacceptable consequences since the Safety Injection System will be functional to provide cooling to the core. These loads will not be lifted unless one train of the Safety Injection System is operational. In this manner, the Safety Injection System provides redundancy for the Reactor Coolant System, one train of which could be disabled by drops from the Polar Crane. 10
The RHR Pump Monorail Hoist has been eliminated from further consideration based on separation and redundancy of the equipment that could be damaged by a heavy load drop. The hazard being considered is that one RHR train is unavailable due to maintenance and that as part of those maintenance activities, the monorail fails, causing damage and disabling the remaining RHR train. Although this is unlikely, the event will not have unacceptable consequences since the Safety Injection System will be functional to provide cooling to the core. These loads will not be lifted unless one train of the Safety Injection System is operational. Section 2.4-2-b(2) requests details showing the areas where crane travel will be prohibited by mechanical stops or electrical interlocks; and a discussion concerning the procedures that are to be used for authorizing the bypassing of interlocks or removable stops, for verifying that interlocks are functional prior to crane use, and for verifying that interlocks are restored to operability _after operations which require bypassing have been completed. Mechanical stops or electrical interlocks to limit crane travel in areas containing equipment required for reactor shutdown, or core decay heat removal are not needed. Section 2.4-2-b(J) requests a discussion of any administrative procedures or physical constraints invoked to ensure the continued validity of load/target combinations that are eliminated on the basis of other site-specific considerations (e.g., maintenance sequencing). The following discussion provides information concerning the load/target combinations that are eliminated on the basis of site-specific considerations. Additional procedures and changes to existing procedures will be prepared as necessary to reflect the load paths and lift height limitations that are imposed. 11
Containment Polar Crane (l-MH-CR-1) Administration procedures will require that the safe load path and lift height limitations for the CRD Missile Shield are observed. The lift height limitations and physical geometry of the reactor cavity prevents a load drop on the reactor vessel. Plant procedures will require that the reactor vessel head be lifted vertically until it is above the operating floor. Any impact with the fueling cavity wall due to a load swing is not considered credible. Containment Annulus Hoist (l-MH-CR-19) The containment annulus hoist will be prohibited from carrying heavy loads over the main steam and feedwater piping, therefore, this piping will not be subject to damage resulting from a load drop. Auxiliary Building Material Handling System Monorails (l-MH-CR-8A and Band l-MH-CR-9B) Administrative procedures will require that the designated safe load paths and lift height limitations be observed in areas containing equipment required for reactor shutdown or decay heat removal in order to ensure that potential damage that could result from a load drop is prevented. Fuel Building Movable Platform with Hoists (l-MH-FH-13) Administrative procedures will require that the top of the fuel cavity gates be secured to the top of the fuel pool wall by chains during movement of the gates to ensure that the gates, if dropped, will be prevented from tumbling into the fuel pool and damaging the spent fuel racks. 12
Section 2.4-2-c requests information for the handling systems not eliminated by the analysis of 2.4-2-b above which have been evaluated as having sufficient design features to make the likelihood of a load drop extremely small and the basis for this evaluation (i.e., complete compliance with NUREG 0612, Section 5.1.6, or partial compliance supplemented by suitable alternative or additional design features). None of the handling systems identified in 2.1-1 and not eliminated in 2.4-2-b meet the single failure proof criteria. No credit is taken for partial compliance. Section 2.4-2-d requests information to demonstrate that damage would not preclude operation of sufficient equipment to allow the system to perform its safety function following a load drop (NUREG 0612, Section 5.1, Criterion IV) for interactions not eliminated in 2.4-2-b or 2.4-2-c above. The following heavy load/impact area combinations can be eliminated by analysis showing that damage would not preclude operation of sufficient equipment to allow the system to perform its safety function following a load drop:
- a. Drops on the reactor coolant pump without the motor in place.
- b. Drops on the reactor vessel piping
- c. Drop of the reactor vessel head to the containment operating floor These events will not have unacceptable consequences since the Safety Injection System will be functional to provide cooling to the core. These loads will not be lifted unless one train of the Safety Injection System is operational. In this manner, the Safety Injection System provides redundancy for the Re'actor Coolant System, one train of which could be disabled by drops from the Polar Crane. As the drop is not postulated to occur until at least 100 hours after reactor shutdown (NUREG 0612), the Safety Injection 13
System will provide adequate cooling since it has capacity to remove decay heat from a LOCA occurring at power. Section 2.4-2-d(l) requests an indication of whether or not, for the specific load being investigated, the overhead crane-handling system is designed and constructed such that the hoisting system will retain its load in the event of seismic accelerations equivalent to those of a safe shutdown earthquake (SSE). The containment polar crane is designed and constructed such that the hoisting system will retain its load in the event of seismic accelerations equivalent to a design basis earthquake. Section 2.4-2-d(2) requests the basis for any exceptions taken to the guidelines of NUREG 0612, Appendix A. No exceptions were taken to the guidelines of NUREG 0612, Appendix A. Section 2.4-2-d(3) requests the information requested in Attachment 4. Table 1 in Appendix A provides information for heavy loads handled by the containmeP-t polar crane. The e~aluation described in 2.4-2-d, above, assumed that any drop would rupture the Reactor Coolant System. As the results of the evaluation are satisfactory, no mitigation credits were assumed. VI. Analysis of Plant Structures This part of the report provides information concerning the analysis of plant structures for heavy load drops corresponding to Attachment (4) of the NRC letter. Section la. requests the weights of the heavy loads. Appendix A of this report gives the weights of the heavy loads considered. 14
Section lb. requests the impact area of the loads. The actual areas of the specific items, identified as heavy loads, were used in the analysis. If specific items could not be identified, then the area was based on that computed for a solid cube of steel for a given load magnitude. Section le. requests the drop heights. Specific drop heights were not used in the analysis. However, for a given load and a given structural system an allowable lift height was computed. The safe load path sketches have been revised to indicate the allowable lift heights. Section ld. requests the drop locations. The drop was assumed to occur at the center of the structural system under consideration. Section le. requests the assumptions regarding credit taken in the analysis for the action of impact limiters. The analysis took no credit for impact limiters. Section lf. requests the thickness of walls or floor slabs impacted. The analysis used the actual slab thickness or the minimum slab thickness to be impacted for a given heavy load drop. Section lg. requests the assumptions regarding drag forces caused by the environment. The analysis neglected all drag forces. Section lh. requests the load combinations considered. The analysis assumed that the heavy load drop occurred concurre\t:tly with the original design dead and service live loads. Section li. requests the material properties of steel and concrete. The analysis used the same material properties that were used for the original design. Section 2. requests the method of analysis used to demonstrate that sufficient load carrying capability exists within the wall(s) or 15
floor slab(s), the identification of any computer codes employed, and a description of their capabilities. The method of analysis employed is described in Bechtel Power Corporation's Topical Report Design of Structures for Missile Impact" BC-TOP-9A, Revision 2, September 1974. The analysis considered two types of impact effects: local effects (damage that occurs in the immediate vicinity of the impact area) such as perforation and spalling; and structural response using an elasto-plastic energy balance approach with an allowable ductility ratio of ten. The theory used for evaluating depth of penetration and spalling was developed by the National Defense Research Committee (NDRC). Computer codes and test data were not employed in the analysis. Section 3. requests an evaluation comparing the results of this analysis with Criteria III and IV of NUREG 0612, Section 5.1. Where safe shutdown equipment has a ceiling or wall separating it from an overhead handling system, an evaluation to demonstrate that postulated load drops do not penetrate the ceiling or cause secondary missiles that could prevent a safe-shutdown system from performing its safety function is to be_provided. Criteria III and IV of NUREG 0612, Section 5.1 are discussed in Sections III, IV, and V of this report. The analysis determined the maximum allowable lift heights. The allowable lift heights were determined based on the smaller of the two heights computed from the structural response part of the analysis and from the local effects part. To minimize the possibility of forming secondary missiles, lift heights were limited (based on the NDRC's minimum slab scabbing thickness) to a value that would prevent spalling. 16
VII. Summary This report documents the final phase of VEPCO's heavy loads evaluation for North Anna Units 1 and 2, with the exception of the analyses for drops on the reactor vessel, which will be performed by Westinghouse. The safe load path sketches presented in the six-month response have been revised to indicate allowable lift heights and restricted areas over the steam generators. A complete set of the revised safe load path sketches are presented in Appendix B. The results of Virginia Electric and Power Company's review of NUREG 0612 finds that no equipment modifications are required to meet the NUREG 0612 requirements. VIII. References
- 1. NUREG 0612 - "Control of Heavy Loads at Nuclear Power Plants"
- 2. NRC Generic Letter - "Control of Heavy Loads" dated December 22, 1980
- 3. Enclosure 2 of Generic Letter - "Staff' Position - Interim Actions for Control of Heavy Loads"
- 4. Enclosure 3 of Generic Letter - "Request for Additional Information on Control of Heavy Loads"
- 5. VEPCO letter to Mr.Eisenhut of NRC dated December 22, 1981 "Control of Heavy Loads" 17
APPENDIX A TABLES
LOAD/IMPACT AREA DATA CRANE CONTAINMENT POLAR CRANE (l-MH-CR-1) LOCATION UNIT 1 REACTOR BLDG., EL. 343' RAIL HEIGHT LOAD HAZARD LOADS WEIGHT. EQUIPMENT IMPACTED BY A LOAD DROP LOCATION ELIMINATION (LBS) CATEGORY Lifting Rig for Reactor 12,000 Reactor Vessel Containment F Vessel Head Reactor Pressure Boundary (See Sketch 114) B Reactor Vessel Head with 266,500 Reactor Vessel Containment F Lifting Rig Reactor Pressure Boundary (See Sketch l/4) C Lifting Rig for Reactor 14,500 Reactor Vessel Containment F Vessel Internals Reactor Pressure Boundary (See Sketch 114) B Reactor Vessel Upper 107,000 Reactor Vessel Containment F Internals with Lifting Rig Reactor Pressure Boundary (See Sketch 114) B Reactor Vessel Lower 263,000 Reactor Vessel Containment F Internals with Lifting Rig Reactor Pressure Boundary (See Sketch 114) B CRD Missile Shield 66,500 Reactor Vessel Containment C Reactor Pressure Boundary (See Sketch 114) B Reactor Vessel Seal Ring 15,000 Reactor Pressure Boundary Containment B (See Sketch 115) Reactor Coolant Pump Motor 70,900 Reactor Coolant Pump Containment B Reactor Coolant Piping (See Sketch 115) B Reactor Coolant Pump Stand 7,100 Reactor Coolant Pump Containment B Reactor Coolant Piping (See Sketch 115) B
TABLE 1 Page 2 of 13 CRANE CONTAINMENT POLAR CRANE (l-MH-CR-1) - Continued LOCATION UNIT 1 REACTOR BLDG., EL. 343' RAIL HEIGHT LOAD HAZARD LOADS WEIGHT EQUIPMENT IMPACTED BY A LOAD DROP LOCATION ELIMINATION (LBS) CATEGORY Containment Laydown Floor 2,000 to Reactor Pressure Boundary Containment B Concrete Hatches 40,000 (See Sketch 116) Reactor Vessel Inspection 10,000 Reactor Pressure Boundary Containment B Tool (See Sketch 117) Reactor Containment 5,600 Reactor Pressure Boundary Containment B Recirculation Fan (See Sketch 1/8)
TA:BLE 1 Page 3 of 13 CRANE CONTAINMENT ANNULUS HOIST (1-MH-CR-19) LOCATION UNIT 1 REACTOR BLDG., EL. 324' RAIL HEIGHT LOAD HAZARD LOADS WEIGHT EQUIPMENT IMPACTED BY A LOAD DROP LOCATION ELIMINATION (LBS) CATEGORY Various loads 2,000 to Main steam and feedwater piping Containment c. (Containment Maintenance) 10,000 (See Sketch /18)
TABLE 1 Page 4 of 13 CRANE RHR PUMP MONORAILS LOCATION UNIT 1 REACTOR BLDG., EL. 235' FLOOR LEVEL LOAD HAZARD LOADS WEIGHT EQUIPMENT IMPACTED BY A LOAD DROP LOCATION ELIMINATION (LBS) CATEGORY RHR Pump Motors 6,000 RHR (Residual Heat Removal) Pumps Containment B RHR Exchangers (See Sketch 118) B RHR Piping B i I l_
TABLE 1 Page 5 of 13 CRANE AUXILIARY BLDG. MATERIAL HANDLING SYSTEM MONORAIL (1-MH-CR-8A & B) LOCATION AUXILIARY BLDG., EL. 259' FLOOR LEVEL LOAD HAZARD LOADS WEIGHT EQUIPMENT IMPACTED BY A LOAD DROP LOCATION ELIMINATION (LBS) CATEGORY Filter Casks 8,000 Radioactive Pipe Tunnel (Located below Auxiliary Bldg. D floor along Column Row K between Columns (See Sketch Ill) 10 1/2 and 7 5/8) Various Loads 2,000 to HVAC Ductwork (Located 5 ft. north of Auxiliary Bldg. C 8,000 Column Row J between Columns 10 and 8) (See Sketch 111) Various Loads 2,000 to Vertical Cable Trays (Located 5 ft. north Auxiliary Bldg. C 8,000 of Column Row J, 2 ft. east of Column Row (See Sketch Ill) 9 5/8, and 8 ft east of Column Row 9) Various Loads 2,000 to Electrical Conduit (located south of Auxiliary Bldg. C 8,000 shipping hatch at Column Row 8) (See Sketch {fl) Various Loads 2,000 to Electrical Conduit (Located on south face Auxiliary Bldg. C 8,000 of wall 4 ft. north of Column Row H (See Sketch Ill) between Columns 10 1/2 and 10) Various Loads 2,000 to Effluent Filters (Located below floor at Auxiliary Bldg. D 8,000 Column J-8) (See Sketch Ill) Various Loads 2,000 to Electrical Conduit (Located on east face Auxiliary Bldg. C 8,000 of wall at Column Row H, 4 ft. east of (See Sketch Ill) Column Row 10 1/2.
TABLE 1 Page 6 of 13 CRANE AUXILIARY BLDG. MATERIAL HANDLING SYSTEM MONORAIL (l-MH-CR-8A & B) - Continued LOCATION AUXILIARY BLDG., EL. 259' FLOOR LEVEL LOAD HAZARD LOADS WEIGHT EQUIPMENT IMPACTED BY A LOAD DROP LOCATION ELIMINATION (LBS) CATEGORY Various Loads 2,000 to Electrical Conduit (Located along Column Auxiliary Bldg. C 8,000 Row 7 5/8 between Columns Hand K) (See Sketch Ill) Various Loads 2,000 to Piping and Valves (Located 16 ft. east of Auxiliary Bldg. C 8,000 column Row 9 and 2 ft. south of Column (See Sketch Ill) Row H) Various Loads 2,000 to Hydro Test Pump (Located 2 ft. west of Auxiliary Bldg. C 8,000 Column 7 5/8 and 5 ft. south of Column L) (See Sketch Ill) Various Loads 2,000 to Electrical Conduit (Located North of Auxiliary Bldg. C 8,000 Column Row J between Columns 8 and 10) (See Sketch Ill) Various Loads 2,000 to Electrical Conduit and Piping (Located at Auxiliary Bldg. C 8,000 Column Row 10 1/2, south of Column Row K) (See Sketch Ill) Various Loads 2,000 to Pipe and Pipe Support (Located south of Auxiliary Bldg. C 8,000 Column Row H between Columns 9 5/8 and 9) (See Sketch Ill)
TABLE 1 Page 7 of 13 CRANE AUXILIARY BLDG. MATERIAL HANDLING SYSTEM MONORAIL (1-MH-CR-9B) LOCATION AUXILIARY BLDG., EL. 274' FLOOR LEVEL LOAD HAZARD LOADS WEIGHT EQUIPMENT IMPACTED BY A LOAD DROP LOCATION ELIMINATION (LBS) CATEGORY Various Loads 2,000 to HVAC Ductwork (Located at Column Auxiliary Bldg. C 8,000 Row 8 1/8, between Columns J and K) (See Sketch //2) Various Loads 2,000 to Process Vent Blower and Piping (Located Auxiliary Bldg. C 8,000 3 ft. north of Column Kand 8 ft. east of (See Sketch 112) Column 7 5/8) Various Loads 2,000 to Steam Generator Blow Down Panels (Located Auxiliary Bldg. C 8,000 on south face of wall 4 ft. north of (See Sketch //2) Column L, west of Column 9) Various Loads 2,000 to Meter Panel (Located at Column Row 9 5/8, Auxiliary Bldg. C 8,000 2 ft. north of Column L (See Sketch //2) Various Loads 2,000 to Seal Water Heat Exchangers and Non-Regen. Auxiliary Bldg. C 8,000 Heat Exchangers (Located at Column Row L (See Sketch 112) between Columns 9 5/8 and 8 5/8)
TABLE 1 Page 8 of 13 CRANE NEW FUEL BRIDGE CRANE (l-MH-CR-20) LOCATION FUEL BLDG., EL. 288' RAIL HEIGHT LOAD HAZARD LOADS WEIGHT EQUIPMENT IMPACTED BY A LOAD DROP LOCATION ELIMINATION (LBS) CATEGORY Various Loads 2,000 to Motor Control Centers (Located below Fuel Bldg. D 10,000 floor north of Column Row Q between (See Sketch /13) Columns 7 7/8 and 6 7/8) Various Loads 2,000 to Electric Cable Trays (Located below floor Fuel Bldg. D 10,000 north of Column Row Q between Columns (See Sketch #3) 7 7/8 and 6 7/8) Various Loads 2,000 to Waste Gas Diaphragm Compressors, Surge Fuel Bldg. D 10,000 Tank, and Associated Piping and (See Sketch 113) Instrumentation (Located below floor north of Column Row Q between Col~mns 7 7/8 and 6 7/8
TABLE 1 Page 9 of 13 CRANE FUEL BLDG. MOVABLE PLATFORM WITH HOISTS (1-MH-FH-13) LOCATION FUEL BLDG., EL. 292' RAIL HEIGHT LOAD HAZARD LOADS WEIGHT EQUIPMENT IMPACTED BY A LOAD DROP LOCATION ELIMINATION (LBS) CATEGORY Spent Fuel Cavity Gates 3,700 Spent Fuel S~orage Racks Fuel Bldg. C (See Sketch //3) NOTE: The spent fuel cavity gates will be secured to prevent them from tipping onto the spent fuel.
TABLE 1 Page 10 of 13 CRANE CONTAINMENT POLAR CRANE (2-MH-CR-1) LOCATION UNIT 2 REACTOR BLDG. EL. 343' RAIL HEIGHT LOAD HAZARD LOADS WEIGHT EQUIPMENT IMPACTED BY A LOAD DROP LOCATION ELIMINATION (LBS) CATEGORY Lifting Rig for Reactor 12,000 Reactor Vessel Containment F Vessel Head Reactor Pressure Boundary (See Sketch 119) B Reactor Vessel Head 266,500 Reactor Vessel Containment F with Lifting Rig Reactor Pressure*Boundary (See Sketch 119) C Lifting Rig for Reactor 14,500 Reactor Vessel Containment F Vessel Internals Reactor Pressure Boundary (See Sketch /19) B Reactor Vessel Upper 107,000 Reactor Vessel Containment F Internals with Lifting Rig Reactor Pressure Boundary (See Sketch 119) B Reactor Vessel Lower 263,000 Reactor Vessel Containment F Internals with Lifting Rig Reactor Pressure Boundary (See Sketch 119) B CRD Missile Shield 66,500 Reactor Vessel Containment C Reactor Pressure Boundary (See Sketch 119) B Reactor Vessel Seal Ring 15,000 Reactor Pressure Boundary Containment (See Sketch /110) B Reactor Coolant Pump Motor 70,900 Reactor Coolant Pump Containment B Reactor Coolant Piping (See Sketch /110) B Reactor Coolant Pump Stand 7,100 Reactor Coolant Pump Containment B Reactor Coolant Piping (See Sketch /110) B
TABLE 1 Page 11 of 13 CRANE CONTAINMENT POLAR CRANE (2-MH-CR-l) - Continued LOCATION UNIT 2 REACTOR BLDG. EL. 343 1 RAIL HEIGHT LOAD HAZARD LOADS WEIGHT EQUIPMENT IMPACTED BY A LOAD DROP LOCATION ELIMINATION (LBS) CATEGORY Containment Laydown Floor 2,000 to Reactor Pressure Boundary Containment B Concrete Hatches 40,000 (See Sketch #11) Reactor Vessel Inspection 10,000 Reactor Pressure Boundary Containment B Tool (See Sketch #12) Reactor Containment 5,600 Reactor Pressure Boundary Containment B Recirculation Fan (See Sketch #13)
TABLE 1 Page 12 of 13 CRANE CONTAINMENT ANNULUS HOIST (2-MH-CR-19 LOCATION UNIT 2 REACTOR BLDG. EL. 324' RAIL HEIGHT LOAD HAZARD LOADS WEIGHT EQUIPMENT IMPACTED BY A LOAD DROP LOCATION ELIMINATION (LBS) CATEGORY Various Loads 2,000 to Main Steam and Feedwater Piping Containment C (Containment 10,000 (See Sketch #13) Maintenance)
TABLE 1 Page 13 of 13 CRANE RHR PUMP MONORAILS LOCATION UNIT 2 REACTOR BLDG., EL 235' FLOOR LEVEL LOAD HAZARD LOADS WEIGHT EQUIPMENT IMPACTED BY A LOAD DROP LOCATION ELIMINATION (LBS) CATEGORY RHR Pump Motors 6,000 RHR (Residual Heat Removal) Pumps Containment B RHR Exchangers (See Sketch #13) B RHR Piping B
APPENDIX B SAFE LOAD PATH SKETCHES
Sketch No. 1 Auxiliary Building Units No. 1 & 2, Plan El. 259 1 -6 11 Sketch No. 2 Auxiliary Building Units No. 1 & 2, Plan El. 274'-0" Sketch No. 3 Fuel Building Units No. 1 & 2, Plan El. 291 '-10" Sketch No. 4 Reactor Containment Unit No. 1, Plan El. 291 '-10", Reactor Vessel Head, Upper Internals, Rigs and Missile Shield Sketch No. 5 Reactor Containment Unit No. 1, Plan El. 291 '-10", Reactor Vessel Seal Ring and Reactor Coolant Pump Motors Sketch No. 6 Reactor Containment Unit No. 1, Plan El. 291 '-10", Removable Floor Plugs, Hatches and Grating Sketch No. 7 Reactor Containment Unit No. 1, Plan El. 291 '-10", Reactor Vessel Inspection Tool Sketch No. 8 Reactor Containment Unit No. 1, Plans El. 291'-lO"and El. 235'-10" Containment Recirc. Fans and Miscellaneous Equipment Sketch No. 9 Reactor Containment Unit No. 2, Plan El. 291'-10", Reactor Vessel Head, Upper Internals, Rigs and Missile Shield Sketch No. 10 Reactor Containment Unit No. 2, Plan El. 291 '-10", Reactor Vessel Seal Ring and Reactor Coolant Pump Motor Sketch No. 11 Reactor Containment Unit No. 2, Plan El. 291 '-10", Removable Floor Plugs, Hatches and Grating Sketch No. 12 Reactor Containment Unit No. 2, Plan El. 291 '-10", Reactor Vessel Inspection Tool Sketch No. 13 Reactor Containment Unit No. 2, Plans El. 29l.'-10" and El. 235 ' - 7" Containment Recirc. Fans & ,t Miscellaneous Equipment
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NORTH ANNA POWER STATION
\
CONTROL OF HEAVY LOADS NUREG0612
---------- fOAD--------- -
/,.-1/1,,)(IMUM Pl!f"IM1'5.'61eLe LLFT HelGiHT oveH ei... '2"11'-10*
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... --*** -- .. ---*-*** *-----*------- REACTOR CONTAINMENT UNIT N0.2 ITEM We1G-HT LOA.t7 He1c.-HT PLAN EL. 291'-10" C.Ot-ickElt:. HATC.H '40,000 Lt)5. w,'-10 11 0 1 COJJC~f::1E:' H.A.TC.H 2,o'oo Lei5. 1:,5'.o*
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,\ eo~~TAINYEt.JT fl.eCIP.C..
~f-KAY COOLl:A H.ATCttes (4)
<j:_ PERSONNEL HATCH I
LEGEND*.
\
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(R) REMOVABLE C CONTAINMENT POLAP. CRAN!: (l!<) SAFETY RELATED EQUIP. l'\AIL./~*MH*Cl'l-1) NOTES: IJ ICH CTIUN TUOL (IJ\*/llfll UY 'NHEN HA'lCHES A~E' P\etvtov~o. V1E*.,TIIIC.\KIU'.* l') -
- A\.T~P,NAle .,_i.AjH"j HA.vr-:- r~ ~1:-
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1*
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HIii( 1*1\Mf1 -, U,ot*Al\*l~/\llU\.. *
'l Hli*P*ll', ---
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\ ~ PERSONNEL HATCH
\
\, LEGEND',
~ RESTRICTED AREA
[]]]I] GRAflNG (HJ HATCH(REMOVABLE) (RJ REMOVABLE CONTAINMENT POLAP. CMNE' (JI') SAFETY RELATED EQUIP. P, AIL./?* MH*ll-\-1) NOTES: I WKl=N HA1CHcS A ... c P.e!MOVLTO, ALTeF\NAte PAT~";:) HA.VE TO ~e COtJ6:ll1Det-lt.eo CONTAINMl:NT A>H,IUl.U':;) HOl~T MONO?.AIL. {'2-MfH.~-1*\) VEPCO S.~f~ w:.o PATI 1S NORTH ANNA POWER STATION M}\i~t r,:,,y~11t-.111~1c1 IT CONTROL OF HEAVY LOADS NUREG*061? MAXIMUM Pl:Ptt.,116Sl6Le LIFT Hf;:J((HT H11f!. .. ~_llJ1(L)!~~!_L'i_
.. _____...., REACTOR CONTAINMENT UNIT N0.2 ljCM ~OAO Wi;l(sHT LIFT HEICrMT PLANS EL 291*10° I',. fL.23(,' .. 7"
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- 14569 SKETCH No. I:,: C MONO'\A.IL::,
FILE NUMBER:
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_J _J +I-0:: 0 P1Pe SUPPORT
~O CC* HSS*"IIG. : LEGEND:
"5E:E t-.lOTe NO, I t RESTRICTED AREA
--+---+-+ --+-+D j_ GRATING CH) HATCH (REMOVABLE)
CR) REMOVABLE __ ... ____ CW) SAFE LOAD PATHS WALL PANELCREMOVABLE) NOTES: I. iHe P.eSTFI.ICTION AP? l.lES TO VE-I-I, TICAL LOAO L..li:'T'5 At,JD ~ORiZONiA'L. LOAl)S. THAT ARe ~OT ADl:QUATE:L.Y \a.E-STRAl",IE
' .. TO PRE:VeNT A Hl=AV'( L-OAD PROP t i.--+--AU><ILIAP!Y ~LJILCl'-.1~
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MQIJOFliAIL.( 1-MH-CR-eA+ s)
~! BECHTEL AS SOCIA TES PROFESSIONAL CORPORATION(\/.. )
~i i it _j YJ' GAITHERSBURG, MARYLAND JOI 101 10 1j 9 VEPCO NORTH ANN A POWER STATION SEAL wr** '"'* flLT**slJ L **AL WTR. FILTE~_J PLAN EL. 259'-6" CONTROL OF HEAVY LOADS NUREG-0612 AUXILIARY BUILDING UNITS PLAN EL.259 -6 1 11 N0.1&2 FILE NUMBER:
,,t I I
---+
AUXILIAR'( lc!>UILDlij~ i-~-1------©
~ - - ~ " 1 0 , _ , _ __ I ___ ~--~ '---~-~ ___
* ~~AAIC{ITMi . JJ___ l__n0
~ I ~1 ~ C8J - - .J- -'---@ LEGEND:
~ RESTRICTED AREA i I I lfiffltl GRATING I
(H) HATCH (REMOVABLE) 0+--- I 1
-i~e~'~"
MONOPiAIL. T ' (R) REMOVABLE
\ ( 1-1,jH*CA*;o)
NOTES:
©+---
1
,-------1::J
- 1) THE RESTRICTED AREA APPLIES TO LOAD LIFTS OVER SAFETY RELATED CONDUITS.
©t*- ------,I MAXIMUM pe?.Ml~~lflL-l! L-IFT HelGrHT OViP, ei.. '2.74'-o*
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<f Ill PLAN ~o ICALI: NONE oc a:
;~ FILE NUMBER:
NoV,IJ
~ I cpI FWl:L ELEVATOR HOIST
. *. I SPEI-JT FUEL '510PiA~E ~-~----r-_!.l.l-'-'--,---J\
I POOL.. SPe.~T FUE (G) aooaa aaaa LEGEND: CA':>K ARl=A o a a a ~ aoo DO ODD I \.
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!Y,(i'n"m! CHECKERED PLATE
* ~OL.L.*UP OOO?i (G) GATE (REMOVABLE)
'(R) REMOVABLE
~
t-- ul l 7 FUEL PIT FU!R. 8UIL.Ol~Gr 0 oc st u COOL.~RS NOTES:
"TP.01.L.e'( ( SPIS~T FUl!I. ~I FUE:L.. BUIL.D_1"1C:( MOVAe>L.E: l*FC*E*OIA ~B J J: I. 'SAFE: LOAD PATI-IS FO~ THE FUEL. eiLltl.01~
CASK CP.A!lle) CRAIII~ Ill~ PLA,FOR M W 1TH H01ST5 CRANE: MOVABLE PLATFO?iM TV/1-101-e,Ts, 1-MH*FH*lo,
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RAILS FOFII. l*MH*FH*I~ A~E AN'(AFll=AS OU'TSID& OF T"4E: I* MM
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('See ~t;iTE: No. I) IDENTIFIE::D ?.eSTi;,t,\CTED APt!SA~. (MAXIMUM L.lfi H!l<:tMT "1E:W fUcL. 8Pi1DCJE FOR ':.Pl!NT pue1.. CASI( CP.AIIIE! ~AIL..S OVl!A EiL.,':i.11 1~10": IZ 11 ) FOF!i l*MH*C~-20 Et_ ROAD GAITHERSBURG, MARYLAND PLAN VEPCO NORTH ANNA POWER STATION CONTROL OF HEAVY LOADS NUREG-0612 FUEL BUILDING UNITS NO.I AND2 PLAN EL. 291 '- 10" ,l IY 1111/. DAIi 11-17-81 ICALt: NONE 14569 C
'l**
FILE NUM13ER:
CONTAlNIYji:t-JT RECIRC
'5PRA'i' COOL.eA HATC.I-IES /4)
LEGEND: RESTRICTED AREA
- GRATING CH) HATCH (REMOVABLE)
CR) REMOVABLE CO~TAINME!IIIT CiO SAFETY RELATED EQUIP. POL.AA C~ANe RAIL-(\* MH *CF\* l) _J___.-t--1::--::::::"\ NOTES: I. WHE:-t-1 HATCHES ARE: P,EMOVEP, A~TERNA1E PATH~ HAV5 TO ee COIIJSI OER~C. C~NTAINME:NT ANNULU'5 1-!0lST MOloJO""AIL-(1* MH* CR-1q)
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B ,.* l'l5Ul!:P FOP. 'I-MON1H FUPOP. C() ,,1* - A ,,i> ISSUED FOP.<.* MONTH f'IEPOR1 .t/ ri.i>*-=4-~J..'.+-I ND. DAU RIVIIIOkl BECHTEL ASSOCIATES PROFESSIONAL CORPORATION (v~)
,---'----_.;_- llJ SAFI:: LOAO PATl-1'5 GAITHERSBURG, MARYLAND JOI t VEPCO MAXIMUM lil!!M PEP\Ml1US18L.~ l.lFT He14HTOVl!P. 1!:L., '2~1L10*
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- l!L.,1c..'*10" PLAN DAU I\ .. U*61 RIV.
ICAL(: wowa 14569 SKETCH C
*FILE NUMBER:
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lI CONTAIN"-1ENT RECIRC I SPRA"'f ,001..ER I HATCl-lES {4_)
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i
- I LEGEND:
~ RESJRICTED AREA.
*i ITiID GRATING '1 I
-(H) HATCH(REMOVARIE)
CONiA!NMENT POLAR CRANe FIAIL.(l*M~-C~-1)'* i-.--r-'c:;; CR) (-t) NOTES: REMOV/\BLE SAFETY RELATED EQUIP.
'I. WHF.-N HA1(HE'o ARE. P..EMOVED 1 Al.TERNA1E P,A.TH';; HAVE' TO BE-
. C'0"-151DERl!:P.
CG?NTAINMl=N T ANNULU'3 HOl'oT MO>-JOP.AI\... (l*M14-CR-l'll PATHS VESSEL SEAL VEPCO 1,4AXIMUI.A PE:PIMl'oSIBI.E! LIFT Hele.HT OYaR l!l..,'2"11°*10' COOLANT . PUMP NORTH ANNA POWER STATION ITEM LbAD W&ICHff Lll"'T HEIG,HT R,V, '5E!AL. P'olt,J~ \~,000 LEI!!, ,4*. ,~ ONTROLOFH::AVY LOADS NUREG-0612 REACTOR CONTAINMENT UNIT NO 1 Pl~AC'fG>PI ""'7L ... NT LOO, Me/CrHT TO i,e EOUIPMENl~ . PLAN EL. 291'-10" p.JMP' MOlOI'\ 6~TAMO 78,00G> D!li&/lilAJlleD LATeP, HATCH . "'-- FIEACTOP. COOL ANT
*I
- PUMP HAfC.H (l'l'P. 3)
PLAN , tAJI 11*11**1
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........ , .L. .E_N_u_M
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C'C'NTAl"-lt\lENT AECII-IC Sf-'t":A'f '-o.::*Lf:H HA l L Hr*<.:, ( 4) I LEGEND: I
,;~ RESTRICTED AREA
[IIIEJ GRATING (H) HATCH(REMOVAHI I') ( R) REM< WABlS CO"'JTAINMENT ( ,t) SAFETY RELATED EQUIP. POLAR CF'.ANE P.All.. /1-MH*CFH) NOTES: WHr., N ~,A TC..,Lc *~::, A~E 1-',EMOV ED,
..:.1-TEHNAlL f-'ATH':-> HAVl= IC e-E*
C-0"-.ISIDEHEP. Ci:?NTAI NME-N r ANNUl.U'5 HOIST MOf,.JORAIL-(1* MH*CR-1'1) SAFE LOAD PATHS VEPCO t:.~*::,::rT 7::*,;,'~'~~- I REMOV/\1:U Fl1)Uf~ l*'LUGS /\Nli ll/\T01ES M'~~M~..~Pe~~,ss, B ,o* c11/\TINl; NORTH ANNA POWER STATION CONCRETE: HA'lCH 40,0oo Lt3'o. c.'-10"
~------------~~*------~-----------ii CONTROL or: I-IL AVY l.OAD'.) ~~UhFl:i-0612 t cotJcP.E-,e HA-TCH
---*' -*--*~-**--*----**-*-**-*-
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FILE NUMBER:
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- FcODWATE~ A~E*
--,-----,-___ ,ON TAIN 1'1 ENT rl EC IRC
':, ~-'1*,:A'! c.C-'~'1..1= rl HA1(..Hf=.<::, {4)
LEGEND: RESTRICTED AREA DJJ.E] GRATING {H) HATCH (RFMOV/\1 ii I ) (R) REl'v1c Wl\81 .r* CO!s!"TAINMENT Ct) SAFETY RELATED EQUIP. POLAR CF'.ANE
~AIL./1,MH*CFH)
- NOTES:
v,hF*N 1-,,\1(*d::*S AK[: l-l.Elv10VED, ALTERNAlE- PATH'c, 1-iAVL: TC 1.-',E-CONSIDEKED. C.?1-JTAINl'vfE:.N f ANNULU':> H01'6T
~lOt-JOl-',AIL.
(I-MH-CR-19\
. Rf TOUL AC~~: ~:,?;he~:,'.~~Em'] VEPCO NORTH ANNA POWER STATION
-------*-- -*****-----*--* ---*--- ~----------------~-----* ..-
CONTROi_ OF HI. AVY I ()AD'., NUh'f <. ;-061? REACTOR CONTAINM[NT Ut\JIT NO 1
*-t;:MENT PL AN EL. 291'-10" KE-ACTOR CO..?L A ~J T HATCH t , ~, d PUMP HA] L H ( l 'I P. 3) [)HAU . ____ ,. __ / I~~ l/.1~:./._~..i~~;\' h. (f I' .. lj~, H _ ."
- .:~:~::* -:-1456~_~;*~;~H. NC?:_?.J ~
PLAN FILE NUMBER:
MAXIMUM PE?,tv\lSSIBLE:: LIFT HE:l~Hf 'i
- t::;_*-c~;~-:[~;j~~~-~'.: ~=*_ __:!:_~ ------~------;
_H_.~_l~HT_ -0~::A::u 111 I l I* 1411_
~
- Rec I ~c. FA'-! <5,(,00 L.e,tl, ell -S '291'- 10' 1.\ISCE:l.L.AI-Je!OU~ ~.ooo Le,s, IE,'-c..' R,1-1.F',.
tONTAINf'..1ENT ;..;.ECIRC MOI.JOP>AIL...'5
'---------- -**-----**-- - ~ - - - - - - ------ *cil-'KA"( '-0..:..iL..c.K HA1'... HE'::, (4)
CONTAINMENT ANNULUS 1101ST MCJNOH./\IL (I* MH *CR- I')) ---* ----- ---*- LEGEND:
~ RESTRICTED AREA CIIIEJ GRATING (H) HATCH(RF:MOVA!\I I)
( R) 1s?Uv1r. lVf\Hl.1-co .... TAINMENT ( -t) SAFETY RELATED EQUIP. POLAR CF'.ANE
?.AIL.(i,MH*Cf'o*I) _L--r-,c_
NOTES: whi': N HA"[CH[s':.:, Ai;..E: r'>E:MOVEl::i, AL.TEkNAH:: 1-'ATH'c, HAVI= lC' t',E-COt-...1'::,10E::Ht:-D. 1-RH*P*IA u,) 1-RH*P*IB --. (~) .
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- 6. '!~;::l~S:":*~F(j .. G... _<.-- ~*c:~:1: H1.*e'. y.1 ~~:'.i::,,11'1 -th\ .
1111 UAII MI\IIHUl'if\ ! ., 1111 * ~.,.,,, 11,1. "' 1UI Ut
~ BECHTEL ASSOCIATES PROFESSIONAL CORPORATION (~~J SAFE L 0/\D 1-'/\ T IIS ~I GAllHEHSBUHO, MARYLAND >4',,.(\
-------1 REACTOI{ cm-nM-JMEflT VEPCO REClf-lC. F/'..l'IS wm MONORAILS NORTH ANNA POWER STATION 1------------------------
CONTROL Of--:- HI.AVY I OAD'.) MlfW<.',*061;> Rl::ACTOR CClNTAlt'-JM[ NT UNIT NU.1 EQUIPMENT PLANS EL.Z 1,i10" & EL. 235' 10"
~E-ACT.?R COOLAfJl I-RH*E.*18 ---* __ ./
HATCH 77~~,,--- PUMP HAf<.H(lYP. =,) ~ . ; u, ..
,, C-'t:.Q l C-*) PLAN .... . - I DE"T/,C I IED PL Atl EL: 235' -10
- - * * *.- - - **-**-*** ---**--*****~:;.:.. -.-:.-=-::.-::-;*-:..-:. ~,'~;/..~~:* *1 14 5 ~~~--~-~~!CH N~: ~~~
FILE NUMBFR.
L - f
\J I
CONTAIN lv11=NT RE:Ci~G. SPP.A'f COOL.f:P,
~ PERSONNEL HATCH HATGHE:5 (4)
LEGEND*.
-- ~ RESTRICTED AREA lTIIJI] GRATING (H) HATCH (REMOVABLE)
(R) REMOVABLE CONTAINMENT ( ..,) SAFETY RELATED EQUIP. POLAPI CMNe
~ AIL.{2*MH*CF'I-I) _L-.\---n ~'""""'
NOTES: I. WHEN HAiCIH~S AP\e P\eMOV EiD, A1.Te?iNA1'~ PAil-l~ HA.Ve TO BE: CO N '::I I O e Pl I! c:,. COt-JTAINMEt-JT . ANNUL.LI'=> HOl5T MONORAIi.. ('2-MH*CP.-19) BECHTEL ASSOCIATES PROFESSIONAL CORPORATION (\/o.l JOI GAITHERSBURG, MARYLAND SAFE LOAD PATHS (a) REACTOR VESSEL HEAD &RIG VEPCO (b)UPPER INTERNALS & RIG (c)MISSILE SHIELD ~ORTH ANNA POWER STATION (d)LIFTING RIG MA)(IMUM Pe!F'IM1'5'SIBLE: LIFT Hi:'IC:,.Hi OVEI". e!L.~~ 1 -IO" 1 CONTROL OF HEAVY LOADS NUREG-0612 LOAO we,~HT L.IFT Hl:ICrHT REACTOR CONTAINMENT UNIT N0.2 IT!:M
. PLAN EL. 291'-10" FI.V. LIFTlt,.14' P,IQ- 12,000 LP.,~. '!I'*~" DAAWIII P..V. HE'AO e L1Fl1N4 RIG! -ar._<.., i:.oo L.e.s.
iie,c.1-ir. ro ae oenRMl~l!D LA,1ilt PLAN RIV ... '::,'*9' A6o\le PRbS. DATI 1\,12,11 Ml661L..e 51-111:\,.D <-'1, ":>00 LBS, P,OOF* eL. ::!IC..'*10 1 ICAU:Now* 14569 SKETCH No. 9 C FILE NUMBER: NH)ll
~~~------.... ...--.--...-
** -...p~-~. ,.-"-" ,r ' .... : . . . . .
C
,.-J.
I SEAL RING (ALTEP\NATe ~TOF\Ac.,e i.. LOCATIOIJ IS OP>J TOP op . f. ,.Hf Ml'B~ILe 'SHlf!LD*Arp?.O)(
- aevAr1ot..1 9-20 1-s*.
MAXIMUM l.ll"T He'leli-HT . AIIOl/e 1,M,filLi! .; GH 1fLD - :Z '- c;." )--.L---r'---~,c_--
/j CONTAIIJl.;1eNT PIECI ... C:.,
9PP\A'( COOLl!P\
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Cf_ PERSQNNEL HATCH
'i I. LEGEND*.
film RESTRICTED AREA [Il1IlJ GRATING I (H) HATCH(REMOVABLE) CR) REMO\lABLE CONTAINMENT ~ ("*) SAFETY RELATED EQUIP. I POLAP. CMNE i.
~1 ".
PiAIL..{2*1.lK*CPl-1)--
- NOTES: iI
{ I WHEN HAiCl-1ES AP.E- P-E!MOVli-D,
',, ALTeP\NATll' PJ,jH5 HAVE: TO BE-CC,N<E,IOt!P,eD CONTAINMENT .*!
ANNULU~ HOl::,T MONOP.All... ('2-MI-I-CP.-19) SAFE LOAD. PATHS (a) ~FtfCTOR V SS L '.:i VEPCO Cb) REACTOR COOLANT PUMP MOTORS NORTH ANNA POWER STATION CONTROL OF HEAVY LOADS NUREG*0612 REACTOR CONTAINMENT UNIT N0.2 lreM LOAD WE!IG,HT 1.IPT Hl!l<\HT PLAN EL. 291'-10 R.V. '5eAL '2.IIJ~ 1<:,,000 Les. -4'-," .1
- l'laAcroPI COOi.A. IJT H!!1G*H TO el! I . llfV PUMP MOTOP'\
- t!TA>JO Ta,000 Les. C)llJ6~Ml'l!P L4i!ri PLAN 11 11 14 56 9 SKETCH No.10 C FILE NUMBER:
r'
./-l"1Alt--J STE:AM tj, FE:E:DWAT!:P. AREA
-~*-*
c.o,~TA1Nt-.1etJT PiEc1Pic. SPRA'( COOLE:P, H.t.TCHES (4)
~ PERSONNEL HATCH LEGEND*.
~ RESTRICTED AREA DilIO GRAflNG (H) HATCH(REMOVABLE)
( R) REMOVABLE CONTAINMENT POLAP, CMNE
~ AIL../2* MH* CF\-1)
('*' SAFETY RELATED EQUIP. NOTES: -, -- ::t WHEN HA1CHE5 ARE P-eMOVED, ALT~P.NAjE- PATl-1'.:l HAVE TO ~E CONS1DE~ED CONTAINMENT ANNULU'::, HOl~T MONOP.AIL.. (2 -MH-GP.-19)
-----------J l
OAIHURSBURO, MARYLAND SAFE LONl h'\T I IS
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HU.11)V/\EL E F Lu.JR ~tuc*.:, ;; VEPCO
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- . . - * . -* ***-****. ____ ,, *--*- - * * * . * - -** - - - - - .. l . - - - - - - - - - - * * * - * - * - - - - .. - REACTOR CONTAINMENT UNIT N0.2 r
- ITEM_ . _LOAD WE:IC,-HT LOAO Hf:!rC..HT PLAN EL. 291'-10 ,.
. I, co1--1ce1.E-,e. _H~4TCH 40,000 __ Leis._ a.'-10 11 IIMAft'lill I HIIO I / . ) 1/lll _,~u.6~.H!tl'1L t l 11'1 "' 1* R 1'
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14569 SKETC H No. I I IC ; FILE NUMBER:
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_J .it'. 0 CONTAINME:NT F',E:-CIP.C.. SPKAy C.00 LE:R HATcHes (4) - -"
~
Cl_ PERSONNEL HATCH I I
\
LEGEND*.
\
~ RESTRICTED AREA DiillJ GRAflNG (H) HATCH (REMOVABLE)
( R) REMOVABLE CONTAINMENT ( '*) SAFETY RELATED EQUIP. POLAP. C?.ANE
~AIL..(1*MH*Cr'I-I) '-~
NOTES:
!rlSF;ECTION TOOL (O\*/fldJ IJY WHEN HAiCHE:5 APiE- P\eMOVG'D 1
'v1L,TlflCJ IOLJ'.~E) - - - - - - - - ALTeP,NA,e µA'fH";:, HAVf::- ro t\E CON"::ilOE'f'-i~D CONTAINMENT ANNULU'::> HOl::>T MONORAIL (2-MH*l..Fil-19)
/
/
--------------:~~
S/H. LO,"\D 1-'ATI JS - F-<E:ACTUH VES::.EL IW-H:l.Tll) I TOUl. VE-PCO
--------------- NORTH ANNA POWER STATION CONTROL OF HEAVY LOADS NUREG-0612 t,\A>(IMUM P_ef'\MISS_I_BLle __ LI_F"T_HE:IC.-HTfOVE:}\E:L. "2~1 -10P_
1 REACTOR CONTAINMENT UNIT N0.2 ITEM LOAD Wt::IC,IHT LlfT HEIC.HT F'LAN EL. 291'-10"
. -*. 11
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11 11
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- I
. ***----- *----------*-** ------*---- ------------------- ----- IIAII 11 ; j "'1 J I
;,:;, -~~,~;- 1 14569 SKETCH No. I:': C FILE NUMBER
Riff{ \'I IMP l./\'1 I ,1.Ail'J /,HE/\
*.--MONORAILS c.*l(H*P-lr',
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;'.-I/H*P-11\ (i,)
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I II DETACHED PLAN FL. 235*7 CON1AINMEcNT f\E:GIF\C. SPPiA'( C00L.6P, HATCHE5 ( 4 ) - - - - - (L PERSONNEL HATCH
\
\
\
, LEGEND*.
~ RESTRICTED AREA DIIIO GRAflNG (H) HATCH(REMOVABLE)
( R) REMOVABLE CONTAINMENT POLAP. CMNe (*) SAFETY RELATED EQUIP. Pi Al L..{2* lv!H* CF'!- I) NOTES: WHEN KA1CHES A.,_E Plf!MOVITD1 AL.TeRNATI:? PAil-l"::> HAVE TO eiE CONS10l!r'-,l:-D CONTAINMENT ANNUL.LI~ HOl'ST MONO PiAIL. ("2 -MH*GR-1"1) _ t~l -~~~~~!ot !{I ~*.,~~r.f:J _~,?~ l!*~U-.i, i-.c,t.i,.,, ,,o '**~**** ~~~,.~1J\~J([.\I t
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~------**** ************* ...... ****---------------,..,
RHR ~JUr-JUf</\ILS CONTROL OF HEAVY LOADS NUF~EG-0612 MAXIMUM P!:P.MIS5 IBLE: l..lFT HfrlC:fHT
-----------***-,------ ... ---***. ***--****-****-***------- REACTOR CONTAINMENT UNIT N0.2 I fl _I - II PLANS EL291*10 F... r-*L.23~:i-* 7 lit=AC. TO Pi c TM T. oval") e1-.
?,CoOO LBS. 1 Piec1Rc. FAI-) '2"11 -10 1
.. -*- . --*--*-- ---------1---- PLAN
~15CE:LLAI-J eous r,,,000 LBS. IS'-c::."
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