ML18139B674
| ML18139B674 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 12/31/1981 |
| From: | BECHTEL GROUP, INC. |
| To: | |
| Shared Package | |
| ML18139B675 | List: |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR NUDOCS 8201110278 | |
| Download: ML18139B674 (74) | |
Text
SIX 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 DECEMBER, 1981 BECHTEL POWER CORPORATION GAITHERSBURG, MARYLAND
Section I.
II.
III.
A:e:eendices A.
Tables Table 1 rable 2 Table 3 Table 4 TABLE OF CONTENTS Introduction
- Response to Section 2.1 Summary References Title
- Plant Overhead Load Handling Systems (North Anna Unit 1)
- Plant Overhead Load Handling Systems (North Anna Unit 2)
- Heavy Loads Handled by Group I Overhead Handling Systems
- Plant Maintenance Procedures B
- Safe Load Paths Sket*ches 1
1 9
9
I.
Introduction This report addresses the six-month response to the December 22, 1980 NRC letter: Control -of Heavy Loads.
II.
Response to Section 2.1 This section provides the information described in Section 2.1, Enclosure 3 to the NRC December 22, 1980 ~etter.
Section 2.1.1 - Identification of Ov.erhead Handling Systems Section 2.1.1 requests a review of plant arrangements to identify all over-head handling systems from which a load drop could result in damage to any systems required for plant shutdown or decay heat removal.
A heavy load as defined in NUREG 0612 is any load whose weight is greater than the combined weight of a single spent fuel assembly and its handling tool.
The combined weight of a single spent fuel assembly and its associ-ated handling tool is approximately 2,500 pounds for North Anna Units No. 1 and 2.
Therefore, a heavy load is'considered greater than 2,500 pounds.
Complete lists of the permanently installed overhead handling systems that are capable of li~ting heavy loads have been prepared for North Anna Units No. 1 and 2.
Each of these systems, except the handling systems that are located in the Decontamination Building, the charging pump area of the Auxiliary Building, and the Unit 2 Reactor Building were visually inspected in the field.
The handling systems that were not accessible for visual inspection in the field were reviewed on the_ drawings.
The overhead handling systems are classified into Groups I and II as follows:
Group I - Heavy load handling systems from which a load drop may result in damage to any system required for plant shutdown or decay 1
(
heat removal.taking no credit for interlocks, technical specifications, operating procedures, detailed structural analysis or system redundancy.
Group II - Heavy load handling systems excluded from Group I based upon a determination by inspection that there is sufficient physical separation between any load-impact point and any system needed for plant shutdown or decay heat removal.*
Tables 1 and 2, in Appendix A, provide this listing and classification.
Section 2.1.2 - Group II Handling Systems Section 2.1.2 requests information to justify the exclusion of overhead load handling systems from Group I.
Reactor Building The recirculation spray pump hoists (1-MH-CR-39A and B) service plant
- equipment that is not required for plant shutdown or decay heat removal.
The load paths are unique to each load handling system and do not cross safety related systems or components.
Auxiliary Building The charging pump monorails (l-MH-CR-7) are unique to each charging pump and are located in separate concrete reinforced-structures.
The associated removable monorail is used for maintaining the charging pumps.
Load paths are designed unique to each charging pump.
No load drop can result in damage to any other system or component required for plant shutdown or decay heat removal.
The jib crane is used to transport materials and equipment in and out of the auxiliary building.
Load paths do not cross safety related systems or components
- 2
The, bridge crane (1-MH-CR-9A) is used to transport materials and equipment in and out of the* auxiliary building and to other areas of the auxiliary building.
The load paths do not cross any system or component required for safe shutdown or decay heat removal.
Fuel Building The fuel building trolley (l-MH-CR-15) is used to transport loaded spent fuel casks from the spent fuel pit to the transporting vehicle outside the fuel building.
The crane rails span the west end of the spent fuel pit in an area where no spent fuel storage racks are installed and pass outside the building.
The load path does not cross any safety related systems or components.
Decontamination Building The decontamination building trolley (1-MH-CR-28), solid waste crane (1-MH-CR-36), and solid fill area crane (l-MH-CR-37) are used to transport materials and equipment into and out of the decontamination building and to other areas of the decontamination building.
Load paths do not cross safety related systems or components.
Turbine Building The steam generator feed pump trolleys (1,2-MH-CR-6) are used for mainten-ance of the steam generator feed pumps.
The load paths do not cross any system or component required for safe shutdown or decay heat removal.
The removable trolley beams for the condenser water box hoists (1-MH-CR-lOA and B) are used during maintenance of *the condenser.
The load paths do not cross any _system or component required for safe shutdown or decay heat removal.
The turbine building overhead cranes (l,2-MH-CR-2) 1 are used for maintenance.
The load paths do not cross any system or component required for safe shutdown or decay heat removal.
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/
- Trolley beams for feedwater heater hoists (l-MH-CR-17A and B) are used during maintenance on the feedwater heaters.
Load paths are designed unique to each feedwater heater.
No load drop can result in damage to any system or component required for plant shutdown or decay heat removal.
Machine Shop The machine shope monorails (1-MH-CR-llA & Band l-MH-CR-38) and the machine shop bridge crane (l-MH-CR-24) are used to transport materials and equipment in the machine shop.
These load handling systems are being moved from the service building to a new structure.
The load paths will not cross any system or component required for safe shutdown or decay heat removal.
Service Building The overhead load handling systems used for maintenance of the diesels and generators are unique to each diesel generator and are located in separate reinforced concrete rooms.
This load handling system is used only when the diesel generator is already out of service.
Intake Structure The load path for the trash basket monorail and hoist (l-MH-CR-26) does not cross any other system or component required for safe shutdown or decay heat removal.
Section 2.1. 3 a - Safe Load Paths Section 2.1.3 a requests drawings or sketches identifying safe load paths.
Load paths have been identified for the Group I overhead handling systems I
taking into account the location of plant equipment needed for plant shutdown or decay heat removal, and conservatively adding the effects of 4
- c*
- possible load swings.
The plant equipment identified during the system walkdown included components, instruments, electrical pan;ls, cable trays, and pipes.
Each item of plant equipment was evaluated to determine if damage from a load drop could prevent achieving and maintain~ng a safe shutdown condition. For the overhead load-handling systems which were inaccessible to the walkdown inspection due to plant.operation or high radiation, design drawings were reviewed to determine if a load drop could potentially damage.. plant equipment required for plant shutdown or decay heat removal.
\\
This identification of safe load paths assumes that the structural integrity of the floors is maintained following the postulated load drops.
The results of the analyses justifying this assumption will be included in the 9-month response to the December 22, 1980 NRC letter.
Sketches showing the load paths are provided in Appendix B.
Section 2.1.3 b - Deviations from Safe Load Paths Section 2.1.3 b requests a description of measures taken to ensure adherence to the specified safe load paths.
Current plant procedures for control of heavy loads inside the reactor containment require that safe load paths be observed, and that any required deviations be approved in advance.
Additfonal procedures and changes to existing procedures will be prepared as necessary to reflect load paths in other areas of the *plant or changes to already existing load paths resulting from this review *.
Section 2.1.3 c - Heavy Loads Section 2.1. 3 c requests that heavy _loads to be handled by each crane be tabulated along with the load weight, designated lifting device and special handling procedure.
5
i.
- Table 3 in Appendix A provides a tabulation of heavy loads periodically handled by Group I cranes and lists the special procedures which follow the guidelines of NUREG 0612, Section 5.1.1 (2) for the handling of these loads.
Section 2.1.3 d - Lifting Devices Section 2.1.3 d requests that lifting devices comply with the requirements of ANSI B30.9-1971 or ANSI Nl4.6-1978 as applicable.
ANSI B30.9 addresses slings.
The maintenance procedure for the Reactor Containment Polar Crane (M.M.ADM-4.0) requires that these slings comply with ANSI B30.9.
Slings used in other areas of the plant are currently being marked as required by this standard.
ANSI Nl4.6 - 1978 addresses lifting devices'used for lifting loads weighing 5 'tons or more.
The lifting devices fo,; the reactor vessel heads, reactor internals, and reactor coolant pump _motors are standard lifting devices supplied by Westinghouse for these specific functions. The results of analyses currently being performed by the vendor for these devices will be provided to the NRC as soon as they become available.
Section 2.1.3 e - Crane Inspection, Testing and Maintenance Section 2.1.3 e requests verification that ANSI B30.2~1976 Chapter 2-2 has been invoked with respect to crane inspection, testing and maintenance.
ANSI B30.2 -
1976Property "ANSI code" (as page type) with input value "ANSI B30.2 -</br></br>1976" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process. has been invoked in the following maintenance procedures for Group I cranes at the North Anna Units 1 and 2 station:
MMP-P-MH-1, MMP-P-MH-3, MMP-P-MH-5, and M.D. ADM-9.1.
For' convenience, the titles of these procedures are provided'in Table 4.
Section 2.1.3 f - Crane Design Section 2.1.3 f requests verification that crane design complies with the guidelines of the Crane Manufacturers Association of America Specif!-
6
I
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- cation 70 - "Specifications for Electric Overhead Traveling Cranes" (CMAA 1>70) and Chapter 2-1 of ANSI B30. 2-1976 '~Overhead and Gantry Cranes."
The reactor containment polar crane and turbine room cranes listed in Table 1 of this report are designed to the Electric Overhead Crane Institute Specification 61 - "Specifications for Electric Overhead Traveling Cranes" (EOCI #61) that was in effect at the time of manufacture of the cranes.
These specifications are the predecessors of CMAA #70 now in effect and are similar.
The primary difference between the EOCI #61 and CMAA #70 specifications are changes in the design of bridge girders.
These changes reflected in the CMAA #70 specification allow the use of higher allowable stresses for the better grade materials available today and also provide new design formulas.
These changes are a result of advancements in the state of the art of girder structural design, allowing the use of lighter, more efficient structures and do not increase the conservatism in the design from the older EOCI 1161 specification.
The North Anna cranes, hoists, and trolleys are designed in accordance with I
the requirements of ANSI B30.2, 1967, which was the applicable edition for design requirements when the cranes were manufactured.
Section 2.1.3 g - Operator Training Section 2.1.3 g requests information on deviations, if any, from the requirements in ANSI B30.2 - 1976 with respect to operator training.
Crane operations are handled by either Maintenance Department or Operations Department personnel.
Current Maintenance Department proce 1dures require that crane operators be trained and qualified according to ANSI B30.2 - 1976.
7Property "ANSI code" (as page type) with input value "ANSI B30.2 - 1976.</br></br>7" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process.
(
- r.-*
Crane operators from the Operations Department are selected by the refueling senior reactor operator/coordinator.
Each crane operator receives the following instructions:
- 1.
He must read, understand and sign the sign off sheet of the master r~fueling procedure, Op 4.1, covering the manipulator crane and the fuel building bridge and trolley crane.
- 2.
Practice walk throughs are conducted on all fuel handling equipment.
A dummy fuel assembly is used to simulate actual fuel.
- 3.
All equipment is tested and is verified to be in calibration prior to use.
- 4.
Procedures are provided for the following cranes:
(a)
(b)
(c)
(d)
Manipulator Crane Fuel Building Bridge and Trolley Crane New Fuel Crane Spent Fuel Crane
- 5.
Safe load paths and restricted areas are outlined in the appropriate procedure.
- 6.
Each operator whom the SRO feels operates the equipment in a safe manner will be certified on the crew training check off sheet indicating what equipment he may operate.
A copy of which will be in his training record.
8 I
I
III.
Summary This report documents the first phase of Virginia Electric and Power Company's review of the controls for the handling of heavy loads at the North Anna Units No. 1 and 2 plant as requested by the NRC generic letter dated December 22, 1980.
The second phase of our review is underway and a report is scheduled to be submitted by March 22, 1982.
This report will provide the specific information requested in Sections 2.2, 2.3 and 2.4 of the NRC generic letter.
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. of Generic Letter - "Request for Additional Information on Control of Heavy Loads"
- 4.
ANSI B30.2-1976 - "Overhead and Gantry Cranes"
- 5.
ANSI B30.9 - 1971 - "Slings"
- 6.
ANSI N14.6 - 1978 - "Standard for Special Lifting Devices for Shipping Containers Weighing 10,000 pounds (4500 kg) or More for Nuclear Materials."
- 7.
Crane Manufacturers Association of America (CMAA) Specification 70 -
"Specifications for Electric Overhead Traveling Cranes"
- 8.
Electric Overhead Crane Institute (EOCI) Specification 61 -
"Specifications for Electric Overhead Traveling Cranes."
9
- .. /
- NAME A.l - Containment Polar Crane (l-MH-CR-1)
TABLE 1 - PLANT OVERHEAD LOAD HANDLING SYSTEMS NORTH ANNA UNIT 1 LOCATION Reactor Bldg., El.* 343' Rail Height A.2 - Manipulator Crane (l-MH-CR-5) Reactor Bldg., El. 291' Floor Level A.3 Containment Annulus Hoist (l-MH-CR-19)
A.4 - Recirc. Spray Pump Hoists (l-MH-CR-39 A'& B)
A.5 - Containment Dome Monorail A.6 - Containment Dome Monorail A.7 - RHR Pump Monorails B.l - Charging Pump Monorails (Total of 6)(1-MH-CR-7)
B.2 Removable Section of Monorail w/Chainfall B.3 - Auxiliary Bldg. Material Handling System Monorail (l-MH-CR-8 A & B)
B.4 - Bridge Crane (1-MH-CR-9A)
B.5 - Auxiiiary Bldg ** Material Handling System Monorail (l-MH-CR-9B)
B.6 - Drumming Area Monorail (1-MH-CR-30)
Reactor Bldg., El. 324' Rail Height Reactor Bldg., El. 239 1 Rail Height Reactor Bldg., El. 396' Rail Height Reactor Bldg., El. 380' Rail Height Reactor Bldg., El. 235' Floor Level Auxiliary Bldg., El. 244' Floor Level Auxiliary Bldg., El. 244' Floor Level Auxiliary Bldg., El. 259 1 Floor Level Auxiliary Bldg., El. 274' Floor Level Auxiliary Bldg., El. 274' Floor Level Auxiliary Bldg., El. 274' Floor Level RATED CAPACITY (TONS)
GROUP 2 - 140 Ton Trolleys and I
1 - 50 Ton Auxiliary Hoist Note Ill 5
2 Note Ill Note Ill 3
12 12 12 12 12 Note Ill N.A.
I II N.A.
N.A.
I II II I
II I
N.A.
TABLE 1 - Page 2 of 4 NAME LOCATION B. 7 - Jib Crane Auxiliary Bldg., El. 291' Floor Level C.1 - Fuel Bldg. Trolley Fuel Bldg., El. 325' Rail He_ight (1-MH-CR-15)
C.2 - New Fuel Bridge Crane Fuel Bldg., El. 288' Rail Height (1-MH-CR-20)
C.3 - Fuel Elevator Hoist Fuel Bldg., El. 249' Floor Level (l-MH-FH-2)
C.4 - Fuel Bldg. Movable Fuel Bldg., El. 292' Rail Height Platform With Hoists (1-MH-FH-13)
D.1 - Decon Bldg. Trolley Decontamination Bldg., El. 267' Floor Level (1-MH-CR-28)
D. 2 - Solid Waste.. _Crane Decontamination Bldg., El. 271' Floor Level (1-MH-CR-36)
D.3 - Solid Fill Area Crane Decontamination Bldg., El. 271' Floor Level (1-MH-CR-37)
E.1 - Turbine Bldg. Overhead Crane Turbine Bldg., El. 343' Rail Height (l-MH-CR-2)
E.2 - Steam Generator Feed Pump Trolley (l-MH-CR-6)
Turbine Bldg., El. 254' Floor Level E.3 - Removable Trolley Beams for Turbine Bldg., El. 272' Rail Height Condenser Water Box Hoists (Total of 6)(1-MH-CR-10 A & B)
RATED CAPACITY (TONS) 3 125 Ton Main Hook 10 Ton Aux. Hook 5
Note Ill 4
10 25 10 206 15 5
GROUP II II I
N.A.
I II II II II -
II II
TABLE 1 - Page 3 of 4 NAME LOCATION E.4 - Trolley Beams for Feedwater Heater Hoists (Total of 8)
Turbine Bldg., El. 291 1 Rail Height (1-MH-CR-17A & B)
F.l - Machine Shop Monorails Machine Shop (1-MH-CR-llA & B)
F.2 - Machine Shop Bridge Crane Machine Shop (1-MH-CR-24)
F.3 - Machine Shop Monorail Machine Shop (1-MH-CR-38)
G.1 - Erner. Diesel Gen. Monorails Service Bldg., El. 271 1 Floor Level (Total of 4)(1 Ea. Generator)
RATED CAPACITY (TONS) 20 2
. 7.5 2
2 H.l - Basket Lift Monorail (1-MH-CR-29)
Service Wtr. Pumphouse, El. 327 1 Floor Level Note Ill I.l - Trash Basket Monorail
& Hoist (1-MH-CR-26)
Intake Structure, El. 282' Rail Height 6
GROUP II II II II II N.A.
II
TABLE 1 - Page 4 of 4 Group I -
Heavy load handling systems from which a load droP, may result in damage to any system required for plant shutdown or decay heat removal taking no credit for interlocks, technical specifications, operating procedures, detailed structural analysis or system redundancy.
Group II - Heavy load handling system~ ~xcluded from Group I based upon a determination by inspection that there is sufficent physical separation between any load impact point and any system needed for plant shutdown or decay heat removal.
Note 1 -
Maximum loads administratively controlled to no more than 2500 pounds.
TABLE 2 - PLANT OVERHEAD LOAD HANDLING SYSTEMS NORTH ANNA UNIT 2 NAME A.l - Containment Polar Crane (2-MH-CR-1)
A.2 - Manipulator Crane (2-MH-CR-5)
A.3 - Containment Annulus Hoist (2-MH-CR-19)
A.4 - Recirc. Spray Pump Hoists (2-MH-CR-39 A & B).
A.5 - Containment Dome Monorail A.6 - Containment Dome Monorail A.7 - RHR Pump Monorails B.1 - Turbine Bldg~ Overhead Crane
. (2-MH-CR-2)
B.2 - Steam Generator Feed Pump Trolley (2-~IB-CR-6)
B.3 - Removable Trolley Beams for Condenser Water Box Hoist (Total of 6)(2-MH-CR-10 A & B)
B.4 - Trolley Beams for Feedwater Heater Hoist (Total of 8)
(2-MH-CR-17 A & B)
LOCATION Reactor Bldg., El. 343' Rail Height Reactor Bldg., El. 291' Floor Level Reactor Bldg., El.. 324' Rail Height Reactor Bldg., El. 239' Rail Height Reactor Bldg., El. 396' Rail Height
. Reactor Bldg., El. 380' Rail Height Reactor Bldg., El *. 235' Floor Level Turbine Bldg., El. 343' Rail Height Turbine Bldg., El. 254' Floor Level Turbine Bldg., El. 272' Rail Height Turbine Bldg., El. 291' Rail Height RATED CAPACITY (TONS)
GROUP 2-140 Ton Trolleys and I
1-50 Ton Auxiliary Hoist Note Ill N.A.
5 I
2 II Note 111 N.A.
Note Ill N.A.
- 3 I
206 II 15 II 5
II 20 II
TABLE 2 - Page 2 of 2 Group I -
Heavy load handling systems from which a load drop may result in damage to any system required for plant shutdown or decay heat removal taking no credit for interlocks, technical specifications, operating procedures, detailed structural analysis or system redundancy.
Group II - Heavy load handling systems excluded from Group I based upon a determination by inspection that there is sufficent physical separation between any load impact point and ~ny system needed for plant shutdown or decay heat removal.
Note 1 -
Maximum loads administratively controlled to no more than 2500 pounds.
TABLE 3 HEAVY LOADS HANDLED BY GROUP I OVERHEAD HANDLING SYSTEMS Containment Polar Cranes (l-MH-CR-1 AND 2-MH-CR-l)
LOAD Reactor Vessel(RV)
Lifting Rig RV head RV Internals Lifting Rig RV Upper Internals RV Lower Internals CRD'Missile Shield RV Seal Ring Reactor Coolant Pump Motor Containment Laydown Floor Concrete Hatches RV Inspection tool Reactor Containment Recirc. Fan LOAD WEIGHT (LBS) 12,000 254,500 14,500 107,000 263,000 66-,500 15,000 78,000
. 2,000 to 40,000 10,000 5,600 VEPCO PROCEDURES M.D. ADM-9.1 MMP-C-RC-15 M.D. ADM-9.1 MMP-C-RC-15 M.D. ADM-9.1 MMP-C-RC-14 MMP-C-RC-17 M.D. ADM-9.1
. MMP-C-RC-14 M.D. ADM-9.1 MMP-C-RC-17 M.D. ADM-9.1 MMP-C-RC-6 MoD, ADM-9.1 MMP-C-RC-7 M.D. ADM-9.1 M.D. ADM-9.1 M.D. ADM-9.1 M.D. ADM-9.1 MMP-C-RC-29,
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- TABLE 3 - Page 2 of 2 Containment Annulus Hoists (1-MH-CR-19 and 2-MH-CR-19)
Various loads up to rated capacity could be lifted by this crane.
appropriate procedures for handling these loads will be developed.
RHR Pump Monorails The limiting loads to be lifted by these monorails are the RHR pump motors with a weight of 3 tons.
Appropriate procedures for handling these loads will be developed.
Auxiliary Building Material Handling System Monorails (l-MH-CR-8A & Band l-MH-CR-9B)
The limiting loads to be lifted by these monorails are filter casks with a weight of 4 tons.
Appropriate procedures for handling these loads.will be developed.
New Fuel Bridge Crane (1-MH-CR-20)
Various loads up to rated capacity could be lifted by these cranes.
Appropriate procedures for handling these loads will be developed.
Fuel Building Movable Platform (1-MH-FH-13)
LOAD Spent Fuel Cavity Gate LOAD WEIGHT (lbs 3700 VEPCO PROCEDURE l-OP-4.1
TABLE 4 Plant Maintenance Procedures M.D. ADM-2.0 - "Training" M.D. ADM-9.1 - "Control of Heavy Loads in Reactor Containment - 291.Level" M.M. ADM-4.0 - "Polar Crane Operating Instructions" M.M. ADM-9.0 - "Material Handling Program" MMP-C-RC "Disassembly, Inspection, and/or Repair and Reassembly of a Reactor Coolant Pump" MMP-C-RC "Removal, Storage and Reinstallation of the CRD Missile Shield and Ventilation Ducts" MMP-C-RC "Installation and Removal of the Reactor Cavity Seal Ring" MMP-C-RC "Removal and Reinstallation of the Reactor Vessel Upper Internals" MMP-C-RC "Removal and Installation of the Reactor Vessel Closure Head" MMP-C-RC "Removal and Installation of the Reactor Vessel Lower Internals" MMP-C-RC "Removal and Installation of the Containment Air Recirculation Fan" MMP-P-MH "Reactor Containment Cranes and Associated Lifting Equipment"
- MMP-P-MH "Frequent and Periodic Inspections of Bridge Cranes" MMP-P-MH "Frequent and Periodic Inspections of Monorails and Overhead Hoists" MMP-P-MH "Frequent and Periodic Inspections of Gantry Cranes" MMP-P-MH "Frequent and Periodic Inspections of Mobile Cranes" MMP-P-RC "Inspection and/or Repair of the Reactor Coolant Pump Controlled Leakage Seals" l-OP-4.1 "Controlling Procedure for Refueling"
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APPENDIX B SAFE LOAD PATH SKETCHES
Sketch No. 1 Sketch No. 2 Sketch No. 3 Sketch No. 4 Sketch No. 5 Sketch No. 6 Sketch No. 7 Sketch No. 8 Sketch No. 9 Sketch No. 10 Sketch No. 11 Sketch No. 12 Sketch No. 13 Auxiliary Building Units No. 1 & 2, Plan El.
259'-6" Auxiliary Building Units No. 1 & 2, Plan El.
274'-0" Fuel Building Units No. 1 & 2, Plan El. 291'-10" Reactor Containment Unit No. 1, *Plan El. 291'-10",
Reactor Vessel Head, Upper Internals, Rigs and Missile Shield Reactor Containment Unit No. 1, Plan El. 291'-10",
Reactor Vessel Seal Ring and Reactor Coolant Pump Motors Reactor Containment Unit No. 1, Plan El. 291 1-10",
Removable Floor Plugs, Hatches and Grating Reactor Containment Unit No. 1, Plan El. 291'-10",
Reactor Vessel Inspection Tool Reactor Containment Unit No. 1, Plans El.
291'-lO"and El. 235'-10" Containment Recirc. Fans and Miscellaneous Equipment Reactor Containment Unit No. 2, Plan El. 291'-10",
Reactor Vessel Head, Upper Internals, Rigs and Missile Shield Reactor Containment Unit No. 2, Plan El. 291 1-10",
Reactor Vessel Seal Ring and Reactor Coolant Pump Motor Reactor Containment Unit No. 2, Plan El. 291'-10",
Removable Floor Plugs, Hatches and Grating Reactor Containment Unit No. 2, Plan El. 291'-10",
Reactor Vessel Inspection Tool
)
Reactor Containment Unit No. 2, Plans El. 291'-10" and El. 235' -10" Containment Recirc. Fans &
Miscellaneous Equipment
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,P.~L.l.!a'f(SPEIJT FUeL CASK CRAI.IE:) CRA~e P\\AII-S FOR l*MH.*CR*IS CA.'~K AFIE<>.
/
\\
(G) i SPEIJT FUEL S"TOP\\AG-1:
POOL ccaoo oooc aooa~ ooo
.o a o a o 0 0 OYe~IATl!D a Ca C FUl:L Ai:>5eMl:,Uf;5 9
FUEL BUILDIIJC:r MOVAet.E:
PLATFORM WITH HOISTS CRANE:
RAILS POP. l*MH*FH-l'a
- C~ee IJOTIE: No. I)
PLAN FUEL PIT COOl.EP.S 1-FC*E*OIA te
.ii P.OLL*UP 11"""
NE:W fUE-\\.. SPIID<;E:
CRAIJi!: l'\\AIL.S FOP.
l*MH-CPI* 2'0 LEGEND:
~
RESTRICTED AREA VU#@
CHECKERED PLATE (G)
GATE (REMOVABLE)
CR)
REMO/ABLE NOTES:
I. SAFE-LOAD PATHS FOR Tue Fl!EI-i!,UILDIIJ<,
MOVABLE PLA TFOP,M 'V/HOli:>15. l*Ml-l-Fi-H?.,
AP.Ii AN'( AR!i=AS OUTSIO& OF nll::
IOE:NTIFIE:D l'le<iiTP\\ICTEC) AP. eA!:o.
VEPCO NORTH ANNA POWER STATION CONTROL OF HEAVY LOADS NUREG0612 FUEL BUILDING UNITS NO.I AND2 PLAN EL. 291 '- KY" A
FILE NUMBER:
RAIL-(l*MH*C:11\\*I) 1-..I-~--::::~
C'e>NTAIIJMll!:NT ANNULU'S MOIST MOIJO P.AI L-(l-l,1H*CR-l'I)
PLAN EQUIPMENT HATCH O,NTAINt.1EIJT Al!Cll'\\C "SPR*lf COOLl!l'I HATC:HE-6 (4) 0
- i:
w 1-
..J j Q:
..J"O 0 LEGEND:
(H)-
(R)
RESTRICTED AREA
. GRATIN~
HATCH(REMOVABLE)
REMOVABLE SAFETY RELATED EQUIP.
NOTES:
I.
WHE:IJ HATCHES ARE: P.EMOVEP, ALTERt-lAlE: PATH~ HAV~ TO BE C:0IJ51DEFl,!!D, I
A tSSUEO tto~ C..*t.lDNlM '-ff'OI'":" L!J.~_!~-.-~.' *........_,,........__.
NI.Ill
- IWGJr>a'I t* !(,.,
_ 1.,.,...,.
r-----------~l*tJYt--=B:.::.EC:c;Hc:.TE=L..!.PO.!:e!!Y,.!::.'E!!.R~C~O~RPc!O~RA~'*..!..-l-~IO~llc.-_J
<SAFE-LOAD PA.Tl-IS OAlllB...,.O. MAl'RAkD cu. ~TOP. VllsseLHl!4Dl;RiG VEPCO t,). UPPl!R,,..T!'l>,"ALS II P.IGi c:>. "1*H1Le ~H1e1..e>
NORTH ANNA POWER STATION L-___
_...:.....:.=..::__ __
_J fleACTOR COOLA.NT.
PUMP HA.TC.H (TYP. a)
ONTROLOF HEAVY LOADS NUREG-0612 RE_ACTOR CONTAINMENT UNIT NQ1 PLAN EL 291'-10" A
- FILE NUMBER:
I I.
I I i I.
r I
\\.
I I
a,,.1'AIN~M:E::-:N-:--T-t-t~=l~::;====f\\==t,JF=:::::::'.~~]~
POL.AR C?.ANE-RAIL..(l*MH*C~-1)
, _ __,.-cc C&"lTA&NME-NT At-JNUL.U'5 1-IOIST MO-.JOl'\\AIL.
(I-MH*CR-1'11 PLAN EQUIPMENT HATCH CONTAINMENT FIECIP.C
'SPRA'f CDDL.EI'\\
HATC.HES (4)
..,--'---- SEAL Rl!slC:,.
(ALTE.RW\\TE.)
SAFE LOW PATHS ca) REACTOR v::SSEL SEAL Rlt,G Cb) RfAC'fgR COOLANT PUMP f<E-ACTOR COOL.ANT PUMP HAfC:.H_{lYP. :!,)
0 ::r:
w 1-
..J 11'.l:
..J"o 0 LEGEND:
~ RES.TRICTED AREA
[IDE]
(H)
(R)
(U GRATING
. HATCH_ (REMOVABI. E)
. RElv10Vh.BLE SAFETY RELATED EQUIP.
NOTES:
I.
W..,~N HA10-.ES ARE. P.EMOVED, AL.TERNAlE PATHS HAY~ TO ee
- COt-iS1DEREO.
§j
- BECHTEL POWER CORPORATION GARHHSIUIG, MA.ITU.ND 14L..,._11 VEPCO NORTH ANNA POWER STATION ONTROL OF HEAVY LOADS NUREG-0612 REACTOR CONTAINMENT UNIT N01 PLAN EL. 291'-10" 9Hl1l*11.-1 14569 SKETCH No. 5 A FILE NUMBER:
u?"'"TAINMENT POL.AR CFV,NE RAIL..(l*MH*CR-1) _1_~-1:::,--:=:;
C,:::>t,.ITAINMENT ANNUL.US 1-<01ST PLAN EQUIPMENT HATCH CONTAINl.iENT ~EC*RC SPRA'f C::OOLEP.
~.A.TC.HES /4)
SAFE LO,'..D PATHS REMCN48!.E FJ..ro< PU.JGS N-D HATCHES CRATING hEACTOI' COOLANT PUMP MATC.H llYP. 3)
LEGEND:
lIT.fiD (H)
(R)
(~)
RESTRICTED AREA GRATING HATCH(REMOVABI El REtv10Vl\\9LE SAFETY RELATED EQUIP.
NOTES:
WHEN HATCHE*.,=.. ARE P,EMOVEO, ALTERNATE PATHS, HAVE TO BE CO"-l'51DERl!,D.
BECHTEL POWER CORPORATION GARHI.UIUIO, MAIYU.HD -- t~:~:
VEPCO NORTH ANNA POWER STATION ONTROLOF HEAVY LOADS NUREG-0612 REACTOR CONTAINMENT UNIT NQ1 PLAN EL. 291'-10"
- =
.14569 SKETCH No.6 I A FILE NUMBER:
co,,TAINMEI-IT POL.AA CP.ANE l'IAIL./l*MH*C:F\\*1)
C-0,jTAII\\JMl:N T ANNUL.LI':, HOIST MOI.JO?,AIL.
(I-MH-CP.-1'\\l PLAN EQUIPMENT HATCH CONTAIIJME"'T RECIAC
<SPRA'I.::~01.e1=1 HATC,_.E<;, {4)
SI-FE I.DAD PATHS REACTOR VESSEL 116i'£CTIOtl TOOL
'"'E:.ACTCP COOL AIJT PUMP 1-<ATC.H (lYP. 3)
LEGEND:
[filE)
(H)
(R)
RESTRICTED AREA GRATING
_HATCH(REMOVABI E)
REMOVABLE
(~)
SAFETY RELATED EQUIP.
NOTES:
- 1.
wi-.E-s:..,ATC~Es A~E P.EMOVED, ALTERNA1E PATH~ HAVE TO BE CO"-lSIDEAf;D.
BECHTEL POWER CORPORA l ION GAITHIISSUIO, MAJYLA.HD VEPCO NORTH ANNA POWER STATION ONTROLOF HEAVY LOADS NUREG-0612 REACTOR CONTAINMENT UNIT N01
"""'-D 1*1111-l****
M&ll...,...
PLAN EL. 291"-10" 14569 SKETCH No. 7 : A FILE NUMBER:
CONTAINMENT ANNU....US HOI!:> T MON-:)R.AIL.
CI-MH-CR-19) ----,
CZ7'-"TAINME>H POI-AR CP.ANE P.AIL..(l-"'H*CP.-1),__-,-
l*RHi;;*IA 1 1-ll)4-P-IB,
(i,-)
o*
DfTACIIED PLAtJ EL 2~~*-10*
--=-~
PLAN CONTAIIJ~1EIJT FIECIAC SPR..... 'I',ooLE.R HATC.ME<:, /4)
SAFE LOAD PAT HS RfACTCi'< corHM*JMEfff REC I RC.
FAHS RHR MONORAILS f<EACTOP. COOLAIJT PUMP "'Al<.H (1YP. 3)
LEGEND:
IIDJJ (H)
(R)
(.. )
RESTRICTED AREA GRATING HATCH (REMOVABI E)
REfvlOVl\\5LE SAFETY RELATED EQUIP.
NOTES:
I.
11,'H.:IJ* 1-<ATCHES A~E P,EMOVED, ALTERNAlE PATHS HAVE TO BE CO>,,J'!:,IDERE.D t1J BECHTEL POWER CORPORATION GARKIISMJIG M.A.111.AHD VEPCO NORTH ANNA POWER STATION
~ONTROLOF HC:AVY LOADS NUREG-0612 REACTOR CONTAINMENT UNIT NOl PLANS i:~.zs;'.,.:," :. !:L. 235'- K)"
No.B 'A
- *-**-----------------------*----------*---------------*-....1.~F~l:L:.:E;,..:.;N:;,;ll.;.:M~:'_.;:.;,E;.;;R._* _______ -.J
CONTAINMl!NT.
ANNULU~ 1101:.f MONOPIAIL.
{'2 *Mll*CP.-19)
PLAN
~.~
0
- g
~ PERSONNEL HATCH SAFE LOAD PATHS (a) REl>CTOR VESSEL HEAD &RIG b)UPPER INTERNALS & RIG (clMISSLE SHIELD (d)LIFTING RIG LEGEND*.
~ RESTRICTED AREA IIllil]
GRATING CH)
HATCHCREMOVABLE)
CR)
REMOVABLE SAFETY RELATED EQUIP.
.l:JOTES:
I, WHEN I\\AlCIH!6 AP,!! l'ICMOVi'iD1 AI.Tl!?.NATR PATH~ HA.Ve TO BE<
Cc;>lo.l ~ 1011: P\\lr c.
~f-4-----=~~~~-=-i uw OAITKIIIIUIO, M..Ull.AND VEPCO NORTH ANNA POWER STATION CONTROLOF HEAVY LOADS NUREG-0612 REACTOR CONTAINMENT UNIT N0.2 PLAN EL. 291'*10" A
~---------------------_;.-----------------------------.....:F.ILENl_JM_O_E_R_: __,_ _____
J
CONTAINMENT POLAP. CMNe I'\\ AIL./2* MK*CF'.-1)
CONTAINMENT ANNUL.LI~ H015T MONO P.AIL.
('2 -MH-CP.-1'l)
PLAN C
\\Ci:._ PER9:)NNEL HATCH
\\
\\
\\ \\
SAr[ LOAD PATHS LEGEND*.
Ff},::@
RESTRICTED AREA
[IlfilJ GRATING (H)
HATCH(REMOVABLE)
(R)
REMOVABLE
(-it)
SAFETY RELATED EQUIP.
NOTES:
1* WHE'N K,t..iCHES A"IE P.eMOVlrD, A1.Te"1NA1e PATH'=>
..... vE-TO t,E CO... ":>IDl!P.ec BECHTEL POWER CORPOHA"TIO~--
o.tJTHus1u10. MAIYLAHO VEPCO NORTH ANNA POWER STATION CONTROL OF HEAVY LOADS NJREG-0612 REACTOR CONTAINMENT UNIT N0.2 PLAN EL. 291'-10*
- Of.0
- ,'-;;-;:~ 14569 SKETCH No.10 A FILE NLIMBLR:
- --*-*~¢*-*------------'
-.* \\.
CONTAINM!:NT POLA?. CP.ANe t'\\AIL.. {2*MH*'"-*1) _L-\\----rl CONH.INMEIJT.
AhlNUI..U';:, H015T 1.lONO>'IAIL.:
('2 -Mfl*CR-19)
I PLAN (j;__ PERSONNEL HATCH
\\ I
\\
SAFE LOAD PATHS RfMClV:.sL.E* FLOOR A..UGS &
HATCHES GRATING LEGEND*.
[filfil RESTRICTED AREA r.mm GRATING (H)
HATCH (REMOVABLE)
CR)
REMOVABLE
(-!;)
SAFETY RELATED EQUIP.
NOTES:
I. WHEN HA1CHes Al'\\e P.!!MOV~D, AI..T l!tl'\\IJATI= PATH":;) HAVE TO Bl:
COIJ'SIDl!P.eo GAIIKDS&OIO. MAl'n..t.MD VEPCO NORTH ANNA POWER STATION CONTROLOF HEAVY WADS NUREG-0612 REACTOR CONTAINMENT UNIT N0.2 PLAN EL. 291'*10"
*---------i...;F...;.1~.;..;'.,B~E~R-: ---~------J
CONTAINMENT POLA?. CAANE=
- i'\\AIL-(2*MH*'P.*I)
CONTAINMEIJT A'-JMULU'.:> HOl~T t.!ONOP.AIL..
{2-MH-C:Pi-19)
PLAN
\\ Cf. PERSONNEL HATCH
\\- ~Q:
~ RESTRICTED AREA IIITID GRATING (H)
HATCH(REMOVABLE)
CR)
REMOVABLE
(-ll:)
SAFETY RELATED EQUIP.
NOTES:
I.
WI-IEN HA1CHES AP,E l'.!!MOVlrD, AI..TeP,tJATe PATI-<~
1-<AYE TO BE-CC'-'SIOl?P,l!D VEPCO NORTH ANNA POWER STATION CONTROL OF HEAVY LOADS NUREG-0612 REACTOR CONTAINMENT UNIT N0.2 PLAN EL:. 291'*10
- G-t.O I u.
- .**.::* 14569 SKETCH No.12' A FILE !~UMBER:
RHR P~P lAYDCfwN AA 2.-Rll-P-IB (ti)
CONTAIN~IENl POLA?. CRAN~
I>, AIL./2* MH-CP,-1)
CONTAINMENT AI.JNUL.U5 HOl~T MONO RAIL.
('2 -Ml-l*C.P,-19)
MONORAIL PLAN
\\
G;_ PERSONNEL HATCH
\\
SAFE LO"D PATHS
~mi~." rifr9~HAIM!~IJT Rtfi l10'KJRAILS LEGEND*.
~ RESTRICTED AREA lilI1IJ GRATING (H)
HATCH (REMOVABLE)
CR>
REMOVABLE
(-l!()
SAFETY RELATED EQUIP.
NOTES:
I
'NHEt, HA1CHES AP.E! P.l!MOVErD, ALTe'<\\tJA1e PATl-4'::> HAVE TC? BE CC,t.J°'=,IOl!P..~D I
BECHTEL POWER CORPORATION GAJTHHS6U110. MAITLAND ---rd-~:*:*,
VEPCO NORTH ANNA POWER STATION CONTROL OF HEAVY LOADS l'UREG-0612 REACTOR CONTAINMENT UNIT N0.2 PLAN EL. 291'*10 *
.)
- c-to
- "*-----------------------~----------
~::,"::.;'* 14569 SKETCH No.13" A FILF. NUMBER*
...... )
(
SIX MONTH REPORT NUREG-0612 CONTROL',OF HEAVY LOADS SURRY POWER STATION - UNITS 1 & 2 VIRGINIA ELECTRIC AND POWER COMPANY
2 INTRODUCTION In accordance with letters 388 and 388A, Vepco to Harold R. Denton, dated July 1, 1981 and September 30, 1981 respectively, Vepco is providing the six month report on NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants" for Surry Power Station - Units 1 & 2.
This six month report is structured in direct response to the information requested in Section 2.1 of Enclosure 3 of the NRC letter, dated December 22, 1980, concerning Control of Heavy Loads
- 2.1.1
RESPONSE
3 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION* UNITS 1 & 2 CONTROL OF HEAVY LOADS* NUREG*0612 Report the results o:£ your review o:f plant arrangements to identify all overhead handling systems from which a load drop may result in damage to any system required f'or plant shutdown or decay heat removal (taking no credit for any interlocks, technical specifications, operating pro-cedures or detailed structural analysis).
APPLICABLE OVERHEAD LOAD HANDLING SYSTEMS Mark No.
1/2-CR*l 1/2*CR*l9 l*CR-20 &
l*CR-23 &
l*CR*24 Identification Reactor Containment Polar Cranes Reactor Containment Annulus Monorails Reactor Containment Jib Cranes New Fuel Crane Location Reactor Containment Unit 1 & 2 Reactor Containment Unit 1 & 2 Reactor Containment Unit 1 & 2 Fuel Building
1-FH-13 1-CR-2S &
1-CR-22 1-CR-8 1-CR-8A 4
Motor Driven Platform Fuel Building Trolley Decon. Building Crane 6 Ton Monorail System 10 Ton Monorail System Filter Cartridge Removal Monorails Unit #1 Switchgear Room 2 Ton Monorail Fuel Building Fuel Building Decon. Building Auxiliary Building Auxiliary Building Auxiliary Building Service Building
(
2.1.2 5
Justify the exclusion of any overhead handling system from the above category by verifying that there is sufficient physical separation from any load-impact point and any safety-related component to permit a determination by inspection that no heavy load drop can result in damage to any system or component required for plant shutdown or decay heat removal.
RESPONSE
NONAPPLICABLE OVERHEAD LOAD HANDLING SYSTEMS Mark No.
Identification and Reason
- a.
Reactor Containment 1/2-CR-5 1/2-CR-16 Reactor Cavity Manipulator Cranes -
The maximum load these cranes will lift are a fuel element with its handling tool.
This by definition (NUREG-0612) is not classified as a "heavy load."
A load drop associated with these cranes was addressed in the Surry Final Safety Analysis Report.
Neutron Detector Carriages -
These cranes are not used to lift any "heavy loads" as defined in NUREG-0612 since they do not have the load capability.
- b.
Auxiliary Building 1-CR-9 C.
Service Building 1-CR-7 1-cR-11 6
Drumming Room Monorail*
This monorail system is located in an area where a load drop would not result in damage to any system or component required for plant shutdown or decay heat removal.
Hoist Area Monorail - El. 66' This monorail is located in an area where a load drop would not result in damage to any system or com*
ponent required for plant shutdown or decay heat removal.
Machine Shop.Jib Crane Machine Shop Monorail System Machine Shop -
1 Ton Trolley Beam These monorails and crane are in an area where a load drop would not result in damage to any system or component required for plant shutdown or decay heat removal.
These lifting devices will be re*
located to the new Machine Shop Building since the Technical Support Center will be installed at this location.
The new Machine Shop Building shall not contain any safety related systems.
' d.
- e.
Turbine Building 1-CR-2A & B 172-CR-6 7
Turbine Building Cranes Steam Generator Feed Pump Motor Hoists Trolley Beams - El. 30' - Units l & 2 Trolley Beams* El 46'
- Units 1 & 2 El. SO' Electric Hoist & Trolley These lifting devices located in the Turbine Building are in areas where a load drop would not result in damage to any system or component required for plant shutdown or decay heat removal.
Condensate Polishing Building
(
Monorail Systems - El. 64' Monorail Systems El. 42' The Condensate Polishing Building does not contain safety related equipment or systems.
Therefore a load drop from these monorails would not result in damage to any system or component required for plant shutdown or decay heat removal.
. f.
8
- Circulating Water Intake Structures - High & Low Levels l*CR-21 Trash Rakes -
A load drop from these devices would not result in damage to any system or component required for plant shutdown or decay heat removal.
2.1.3 2.1.3.a 9
With respect to the design and operation of heavy-load-handling systems in the rea~tor building and those load-handling systems identified in 2~1-1, above, provide your evaluation concerning compliance with the guide-lines of NUREG 0612, Section 5.1.1.
The following specific information
~hould be included in your reply:
Drawing or sketches sufficient to clearly identify the location of safe load paths, spent fuel, and safety-related equipment.
RESPONSE: The a*ttached sketches identify the location of safe load paths, spent fuel, and safety related equipment.
The safe load paths are based on the assumption that the heavy load drop does not penetrate through the impacted structure's floor.
An analysis shall be maqe to determine the validity of this assumption.
Any* required changes to the safe load paths as a result of this analysis shall be reported in Vepco's Nine Month Report.
Safe load paths sketches shall not be generated for movement of the fuel transfer canal gates in the fuel pool.
Updated fuel pool maps will be used instead.
These maps are more accurate than one safe load paths sketch.
Additional safe load paths sketches shall be generated, as required, £or use as part 0£ new lifting procedures. The new lift procedures shall be generated from the generic procedure.
The attached safe load paths sketches have been or shall be incorporated into lifting (operation or mechanical maintenance) procedures and will be incorporated onto existing station drawings.
Safe load paths shall be clearly marked on the floor in the area where the load is handled.
2.1.3.b 11 A discussion of measures taken to ensure that load-handling operations rt!main within safe load paths, including procedures, if any, for devia*
tion from thes~ paths.
RESPONSE: Existing Surry Power Station lifting procedures (mechanical maintenance or operating procedure) are being revised or have been revised to include the general guidance and evaluation requirements contained in NUREG-0612.
A generic procedure shall be used to control the movement of heavy loads over spent fuel, fuel in the core, or over equipment that may be required to achieve safe shutdown and continue decay heat removal as required by NUREG-0612, and not covered by existing station procedures.
i The lifting procedures will require compliance with NUREG-0612 using the load paths defined in the attached sketches or sketches generated for use as part of the generic procedure.
Deviations from the defined safe load paths after the procedures are issued will require approval.
utilizing existi.~g approval methods for deviations to procedures *
- 2.1.3.c 12 A tabulation of heavy loads to be handled by each crane which includes the load identification, load weight, its designated lifting device and verification that the handling of such load is governed by a written procedure containing, as a minimum, the information identified in NUREG-0612, Section 5.1.1.(2).
RESPONSE: The attached Table 1 provides this information.
This table is consistent with the loads identified in Table 3-1 of NUREG-0612.
Existing Surry Power Station lifting procedures (mechanical maintenance or operating procedure) are being revised or have been revised to include the general guidance and evaluation requirements contained in NUREG-0612.
For equipment not covered by existing station procedures, as required, a lift procedure generated from the generic lifting procedure will be written, approved.by the station safety committee, and be used for con~
trolling purposes.
These procedures shall be in tompliance with NUREG-0612.
Load weights shown on Table 1, unless otherwise identified, do not include rigging weights or weights of any part of the load handling system, i.e.
bottom block and hook.
2.1.3.d I
- 13 Verification tha~ lifting devices identified in 2.1.3-c, above, comply with the requirements for ANSI N14.6*1978, or ANSI
!30.9-1971 as appropriate.
For lifting devices where these standards, as supplemented by NUREG-0612, Section 5.1.i(4) or S.l.l(S), are,not met, described any proposed alternatives and demonstrate their equivalency in terms of load-handling reliability.
RESPONSE: The reactor vessel head lifting device, internals lifting rig, and reactor coolant pump motor sling were designed and fabricated prior to issuance of the above listed standards.
These lifting devices were designed and built to the current industry standards using good engineering practices.
Vepco has contacted the lifting devices supplier, Westinghouse, and has requested verification of conformance of these lifting devices to the above listed standards.
Results of this analysis shall be submitted at C
a later date.
The reactor vessel head lifting device, internals lift rig, and reactor coolant pwnp motor sling are inspected in accordance with maintenance procedure MMP-P-CR-015.
The reactor vessel head lifting device and the internals lift rig a~e inspected prior to each refueling and at each containment maintenance period if they are to be used and have been idle for a period of more than six months or the last inspection has been over one year.
The reactor coolant pump motor sling is inspected prior to each refueling and at each containment ma1ntenance period if it is to be used and the last inspection has been over one month.
14 Special han~ling devices used to lift the new fuel containers, irradiated specimen, and spent fuel shipping casks are supplied by the particular cask suppliers.
Vepco shall verify with the equipment suppliers the con-formance of these lifting devices to the above listed standards.
Results of this verification shall be submitted at a later date.
Lifting devices, which are not specially designed, i.e. slings, are marked, maintained, stored and inspected in accordance with ANSI B30.9-1971.
Lifting _procedures are reviewed prior to approval and implementation for proper selection of size, length, capacity and riggine configuration of slings in order to meet all requirements of ANSI B30.9-1971.
J
2.1.3e 15 Verification that ANSI B30.2-1976, Chapter 2-2, has been invoked with respect to crane inspection, testing and maintenance.
Where any exception is taken to this standard, sufficient information should be provided to demonstrate the equivalency of proposed alternatives.
RESPONSE: Surry Power Station cranes, inside and outside containments, are inspected, tested and maintained in accordance with station maintenance procedures MMP-P-CR-015 or MMP-P-CR-017.
These procedures were revised in 1977 to incorporate ANSI B30.2-1976.
In addition to the above stated station maintenance procedures, the fuel handling system is thoroughly visually inspected and performance tested in accordance with station procedure PT-20.l prior to refueling.
Prior to initial use, all new, reinstalled, altered, extensively repaired
- or modified cranes shall be operationally tested and rated load tested (if required) in accordance with ANSI B30.2-1976.
Crane test procedures shall be written, as required, to insure cranes are in compliance with ANSI B30.2-1976.
2.1.3.f 16 Verification that crane design complies with the guidelines of CMAA Specification 70 and Chapter 2-1 of ANSI B30.2-1976, including the demonstration of equivalency of actual* design requirements for instances where specific compliance with these standards is not provided.
RESPONSE: CMAA Specification 70 and ANSI B30.2-1976 apply to the Reactor Containment Polar Cranes {1/2-CR-l), Fuel Building Trolley {l-CR-15) and the New Fuel Crane {1-CR-20, l-CR-23, & 1-CR-24).
These cranes were designed and fabricated, prior to issuance of the above referenced standards, in accordance with Electric Overhead Crane Institute, Inc. - Specification
- 61.
An analysis shall be made to verify compliance of these cranes with CMAA Specification 70 and Chapter 2-1 of ANSI BJ0.2-1976 or demonstration I
of equivalency of actual design requirements.
Results of this analysis shall be submitted with Vepco's Nine Month Report on Control of Heavy Loads-NUREG-0612.
In addition to the above referenced analysis, an analysis of the other over-head handling systems, identified in Section 2.1.1, shall be made to verify compliance with other applicable industry standards such as ANSI B30.ll, ANSI B30.16, and ANSI B30.17.
These overhead handling systems, except for the Reactor Containment Jib Cranes, were designed and fabricated, prior to issuance of the referenced ANSI Standards, in accordance with the current industry standards using good engineering practices.
The Reactor Containment Jib Cranes were designed and fabricated in accordance with ANSI BJ0.16-1973 and ANSI B30.ll-1973.
Results of this analysis shall also be submitted with Vepco's Nine Month Report.
,2.1.3.g 17 Exception, if any, taken to ANSI B30.2-1976 with respect to operator training, qualification and conduct.
RESPONSE: Surry Power Station crane operators completed a course in Crane and Rigging Operation which was conducted by an independent contractor which is accredited by the U.S. Department of Labor under 29 CFR Part 1919.
The completion of this course provides certification that the Surry Power Station crane operators have been trained, qualified and instructed in proper conduct in accordance with ANSI B30.2-1976.
Copies of the tests are available at the Surry Power Station.
(
CRANE MARK NO CAPACITY (TONS)
R.C. Polar Crane 1-CR-1 2-CR-1 (2) 125 Tons (1) 15 t.ons each crane IE 1 TABULATION OF HEAVY LOADS HEAVY LOAD IDENTIFICATION Reactor Vessel Head & Vessel Head Lifting Device Reactor Upper Internals &
Internals Lifting Rig Inservice Inspe~tion Tool Reactor Coolant Pump Motor
& Sling Reactor Cavity Inner Seal Ring CRDM Missile Shield Stud Carriers (Full)
Operating Floor Removable Plug - Plug No. 1 (largest)
Octagonal Floor Plug-El. 18'-4" LOAD WEIGHT (TONS)
(NOTE 1) 122.5* Tons 52 Tons 10 Tons 41 Tons 12.Z Tons 36.5 Tons 3.6 Tons 13 Tons 31.5 Tons LIFTING DEVICE Reactor Vessel Head Lifting D~vice PROCEDURE MMP-C-RC-040, OP-4.1 Internals Lifting MHP-C-RC-039 Rig OP-4.16, Note 2 RCP-Motor EMP-C-EPH-lA-61 Sling MHP-C-RC-037 MHP-C-RC-033 MMP-C-RC-038
CRANE MARK NO R.C. Polar Crane 1-CR-1 2-CR-1 (cont.)
CAPACITY (TONS)
TABLE 1 TABULATION OF HEAVY LOADS HEAVY LOAD IDENTIFICATION Polar Crane-Bottom Block & Hook Containment Recirc: Spray Cooler Recirc. Spray Pump Motor Regenerative Heat Exchanger Residual Heat Removal Exchanger Residual Heat Removal Pump Motor LOAD WEIGHT (TONS)
(NOTE 1) 2.4 Tons 23.7 Tons 1.3 Tons 2.4 Tons 12.8 Tons 2.4' Tons
'LIFTING DEVICE N/A
-1, PROCEDURE Performance Test PT-20.1
~Wr
T! I Page. 6 TABULATION OF HEAvY LOADS LOAD CRANE CAPACITY HEAVY LOAD IDENTIFICATION WEIGHT LIFTING MARK NO (TONS)
(TONS)
DEVICE PROCEDURE (NOTE 1)
R.C.
Annulus No Specified Loads Monorail 5 Tons-ea.
1-CR-19 2-CR-19 R.C.
8 Tons-ea.
No Specified Loads Jib Cranes
CRANE HARK NO New Fuel Crane 1-CR-20 2-CR-23 1-CR-24 Motor Driven Platform
& Hoists 1-FH-13 Fuel Bl_dg.
Trolley 1-CR-15 CAPACITY (TONS) 5 Tons (2) 2 Tons 125 Tons 10 Tons TABLE 1 TABULATION OF HEAVY LOADS HEAVY LOAD IDENTIFICATION New Fuel Container (Full)
Removable Slabs Fuel Pool Gate Spent Fuel Shipping Cask Bottom Block & Hook-125 Tons Spent Resin Shipping Container & Cask Irradiated Specimen Shipping Cask Failed Fuel Container LOAD WEIGHT (TONS)
(NOTE I) 3.3 Tons 1 Ton t.8 Tons 125 Tons (Max.)
2.4 Tons 3.7 Tons 11.3 Tons LIFTING DEVICE Note 4 Note 4 N/A Note 4 Page.* 6_
PROCEDURE OP-4.2,
OP-4.18 OP-4.J Note 5 OP-4.J OP-20.4, OP-20.1 OP-4.17 Note 3
CRA}ffl MARK NO Decon Bldg.
Crane 1-CR-25 1-CR-22 6 Ton Monorail Sytem 1-CR-8 10 Ton Monorail System l-CR-8A TABLE 1 TABULATION OF HEAVY LOADS CAPACITY (TONS)
HEAVY LOAD IDENTIFICATION 5 Tons No specified Loads 6 Tons Component Cooling Water Component Cooling Water Pump-Motor Charging -Pump Charging Pump-Motor Removable Slab 10 Tons Removable Slab
( 2-5 Tons Hoists)
Pump LOAD WEIGHT (TONS)
(NOTE 1) 2.7 Tons 3.2 Tons 1.3 Tons 2.1 Tons 4.5 Tons (Max.)
8.5 Tons (Max.)
- LIFTING DEVICE Page 5 of.
PROCEDURE
T.1 Page TABULATION OF HEAVY LOADS LOAD CRANE CAPACITY HEAVY LOAD IDENTIFICATION WEIGHT t_IFTING HARK NO (TONS)
(TONS)
DEVICE (NOTE 1)
Filter Cartridge 2 Tons No specified loads Removal Monorail Unit Ill 2 Tons Motor-Generator Set-Motor 2 Tons Switchgear (Max.)
Room Monorail NOTES:
Crane uses lifting devices which are not specially designed such as standard slfngs, shackles, and spreader bars.
As required, a lift procedure will be written, using the generic lift procedure as a basis, to govern implementation.
- 1.
Load weights, unless otherwise identified, do not include rigging weights or weights of any part of the load handling system, i.e. bottom block and hook.
- 2.
Installation and use of this tool a~e controlled by Westinghouse supplied procedures.
- 3.
Station procedures are being developed.
- 4.
Special handling devices are supplied by shipping cask supplier.
- 5.
Vepco is considering using alternate spent fuel storage and shipping casks with a maximum weight of 125 tons.
/
6*
PROCEDURE
l P(R~CNNCL HA1CH -
\\
OUTLIIIIE OF CONCRETE SLAB A1" EL lei'- 4 11 WOkK 2'CN(H:i, _:
PORTA.BL[
W[LDINQi UNIT r-'S.TORA.Gt. fiPAC.C ~~
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FOR.
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REFERENCE DW(:iS:
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RE:ACTOR COl>ITAINME'IJT ANNULUS MONORAIL I.
TRAVEL.
REACTOR CONTAINMENT JIB CRANE T~AVE.L LIMITS ADDITIONAL NOTES:
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POS1T10M
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- 1 SURRY POWl:R STATION UNIT 2 13g30;1'2-MSK-1
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WITH f2ZI IDENTIFIES VERTICAL MOVEMENTS
~
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REACTOR HEAD VERTICAL LIFT PATH
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SCALE, NTS DATE, 12-14-81 SKETCH NUMBER 13930.12-MSK-10
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