Patent Number: 055027547
Section: description

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS The core plate wedge assembly in accordance with the invention may be used in conjunction with a shroud restraint assembly of the type shown in FIG. 2. This shroud restraint assembly comprises a tie rod 54 having a circular cross section. A lower end of tie rod 54 is anchored in a threaded bore formed in the end of a spring arm 56a of a lower spring 56. Tie rod 54 extends from the end of spring arm 56a to a position adjacent the outer circumferential surface of the top guide support ring 18c. The upper end of tie rod 54 has a threaded portion. The lower spring 56 is anchored to a gusset plate 58 attached to the shroud support plate 52. The gusset is part of the original construction in some reactors, or is otherwise bolted in place as part of the repair. The bottom spring has a slotted end (see FIG. 9) which fits over the gusset plate 58 and forms a pair of clevis hooks 56c. The clevis hooks 56c hook under opposite ends of a clevis pin 60 inserted through a hole machined in the gusset plate 58. Engagement of the slotted end with the gusset plate 58 maintains alignment of lower spring 56 under the action of seismic motion of the shroud, which may be oblique to the spring's radial orientation. The tie rod 54 is supported at its top end by an upper support assembly which hangs from the top edge of the shroud. In accordance with the installation method of the present invention, a pair of notches or slots are machined in the shroud head ring 28a of shroud head 28. The notches are positioned in alignment with a pair of bolted upper support plate segments 62 of the upper support assembly when the shroud head 28 is properly seated on the top surface of shroud flange 18a. These notches facilitate the coupling of the tie rod assembly to the shroud flange in accordance with the invention, as described in detail hereinafter. The preferred machining technique is electrical discharge machining, although any other suitable machining technique can be used. Machining of these notches may be performed with the shroud head removed from the reactor, avoiding delay of in-reactor outage work. The pair of notches at each tie rod azimuthal position receive respective hook portions 62a of the upper support plates 62. Each hook 62a conforms to the shape of the top surface of shroud flange 18a and the shape of the steam dam 29. The distal end of hook 62a hooks on the inner circumference of shroud dam 29. The upper support plates 62 are connected in parallel by a top support bracket (not shown) and a support block 66 which forms the anchor point for the top of the tie rod. Support block 66 has an unthreaded bore, tapered at both ends, which receives the upper end of tie rod 54. After the upper end of tie rod 54 has been passed through the support block 66, a threaded tensioning nut 70 is screwed onto the threaded portion of tie rod 54. The assembly comprised of support plates 62 with hooks 62a, support block 66, tie rod 54, lower spring 56, clevis pin 60 and gusset plate 58 form a vertical load path by which the shroud flange 18a can be anchored to the shroud support plate 52. In the tensioned state, upper support plates 62 exert a restraining force on the top surface of the shroud flange 18a which opposes separation of the shroud at any assumed failed circumferential weld location. The upper restraint spring 72 is a double cantilever "wishbone" design, to react the lateral seismic loads without adding bending load on the top support. The spring 72 is rotatable relative to the upper support assembly. The end of the outer arm of spring 72 has an upper contact spacer 74 mounted thereon. Upper contact spacer 74 is designed to bear against the inner surface of the reactor pressure vessel wall. The upper spring assembly is installed with enough elastic preload to prevent mechanical wear of its parts due to reactor vibration. In the event of seismic loading at some oblique angle, the spring 72 can rotate on its axle mounting to absorb the azimuthal motion component, without transmitting oblique loading into the support block 66. Cantilever torsion arms on each side of the upper spring 72 restore the rotational alignment of the spring after seismic deflection. The upper contact spacer 74 which bears against the vessel 10 reacts the restraint load from the vessel and pivots to follow the spring rotation. The spring arm 56a of lower spring 56 laterally supports the shroud 18 at the core plate 18e, against the vessel 10, via a lower contact spacer 76. The lower spring assembly is installed with a controlled preload, obtained by machining lower contact spacer 76 to match the measured assembly fitup. The top end of spring arm 56a has a threaded bore to provide the attachment for the bottom of the tie rod 54. The member 56d connecting the upper wishbone spring 56a, 56b to the clevis hook 56c is offset from the line of action between the lower end of tie rod 54 and the clevis pin 60. Axial loads in the tie rod therefore cause bending of the lower connecting member 56d and associated pivoting of the clevis hook 56c about the clevis pin 60. The specific configuration is designed to add the desired axial flexibility to the assembly to minimize thermal expansion loads. This flexibility is adjusted along with that of the upper and lower lateral springs to tune the dynamic frequency response of the reactor internal structure to minimize lateral seismic loads. The lateral seismic loads from the main mass of the reactor core are reacted (for a cracked shroud) by the upper and lower springs at the top guide 18c and core plate 18e, respectively. Gross motion limit stops are also mounted on the stabilizers to limit lateral displacement of other segments of the shroud due to circumferential weld failures. Each upper support block 66 has a limit stop which blocks gross lateral deflection of the middle shroud wall 18d relative to the top guide support ring 18c in the event that the welds between top guide support ring 18c and middle shroud wall 18d become severed. If left unchecked, gross lateral deflection of middle shroud wall 18d could damage peripheral fuel assemblies in the fuel core. A middle support 78 may be used to provide a limit stop, as shown in FIG. 4, if the middle shroud wall 18d has a circumferential weld in its middle. To facilitate mounting of the middle support 78, a mid-support ring 80 is secured to the tie rod 54. The middle support 78 has a section of an annular recess which form fits on collar 80, thereby preventing lateral shifting of middle support 78 relative to tie rod 54. The middle support 78 is preloaded against the vessel wall at assembly by radial interference which bends the tie rod 54. Thus it provides both a limit stop for the middle shroud wall 18d, and a mid-span support for the tie rod, improving its resistance to vibratory excitation failure. Further, each lower spring 56 has a limit stop 82 which blocks gross lateral deflection of the lower shroud wall 18f relative to the core plate support ring 18e in the event that the welds between core plate support ring 18e and lower shroud wall 18f become severed. Gross lateral deflection of lower shroud wall 18f and shroud support 51 welded thereto could, if not checked, cause damage to the control rod guide tubes located underneath the core. Lateral displacement is limited by the radial clearance between arm 56a of lower spring 56 and limit stop 82 mounted on arm 56b of lower spring 56. The gusset 58 limits displacement of the shroud support 50. The present invention is an apparatus for restraining a core plate, and the fuel assemblies seated thereon, against lateral deflection relative to the core shroud. This repair is preferably used in conjunction with the above-described repairs which restrain the core shroud against lateral and vertical deflection relative to the reactor pressure vessel. In accordance with the preferred embodiment of the invention depicted in FIG. 3, the core plate 21 is restrained against lateral deflection relative to the middle shroud wall 18d by a core plate wedge assembly 84. The method involves the placement of a plurality of core plate wedge assemblies (e.g., four) in the gap between the circular outer peripheral edge of the core plate and the circular cylindrical inner surface of the middle shroud wall 18d at respective azimuthal positions. These core plate wedge assemblies are wedged into place to maintain the spacing between the core plate and the shroud, thereby maintaining the alignment of the fuel assemblies. The core plate wedge assemblies are preferably located in azimuthal alignment with the shroud restraint assembly. Thus, the core plate wedge assembly in conjunction with the corresponding lateral shroud restraint assembly form a direct path for transmission to the reactor pressure vessel of a load exerted laterally by the fuel core. Referring to FIGS. 4A and 4B, the core plate wedge assembly 84 comprises a core plate wedge 86 and a core plate wedge clip 88. The core plate wedge 86 has a planar mating surface 86a and another planar surface 86c parallel thereto. The core plate wedge clip 88 has a planar mating surface 88a and another planar surface 88d which is at an oblique angle (preferably 6.degree.) relative to surface 88a. In the untrimmed state, the surface 86d of core plate wedge 86 is parallel to the 86a. Prior to assembly of core plate wedge 86 and core plate wedge clip 88, the gap G between the outer circumferential surface of core plate 21 and the inner circumferential surface of the middle shroud wall 18d (see FIG. 3) is measured. Then the core plate wedge 86 is trimmed as shown in FIG. 4A to form a new surface 86d which, when core plate wedge 86 is coupled to core plate wedge clip 88 in its final wedged position, will be parallel to surface 88d and separated therefrom by a distance which increases to approximately G as the bolt is tightened and parts 86 and 88 slide against each other. To assemble the core plate wedge assembly 84, the mating surface 88a of core plate wedge clip 88 is placed flush against the mating surface 86a of core plate wedge 86 and then a wedge bolt 90 is used to couple the core plate wedge 86 and the core plate wedge clip 88. The core plate wedge 86 has a first unthreaded circular cylindrical bore of first diameter for receiving the circular cylindrical head of wedge bolt 90 and a second unthreaded circular cylindrical bore of second diameter for receiving the threaded shaft 90a of wedge bolt 90. The bore of first diameter communicates with the bore of second diameter at a shoulder 86b. Longitudinal displacement of wedge bolt 90 relative to core plate wedge 86 is prevented by shoulder 86b, while allowing wedge bolt 90 to rotate freely relative to core plate wedge 86. The core plate wedge clip 88 has a threaded bore 88b which threadably engages the threaded shaft 90a as the wedge bolt 90 is screwed in. As the wedge bolt 90 is rotated in the direction of tightening, the core plate wedge clip 88 slides relative to core plate wedge 86 along the bolt axis. To facilitate mutual sliding of mating surfaces 86a and 88a relative to each other, a lubricant may be applied to one or both mating surfaces prior to assembly. In the initial configuration of the core plate wedge assembly 84, the core plate wedge clip 88 engages only a small portion of the threaded shaft 90a of wedge bolt 90 and occupies an initial axial position relative to core plate wedge 86. In this initial axial position, the distance separating surfaces 86d and 88d is less than the gap G by an amount sufficient to allow the latching projection 88c on core plate wedge clip 88 to pass through the gap. The core plate wedge assembly 84 is then held at an elevation such that when the wedge bolt 90 is tightened, the latching projection 88c will hook underneath the core plate 21, as seen in FIG. 3, as the core plate wedge clip 88 travels axially toward the bolt head. At the same time, the distance separating surfaces 86d and 88d increases. When the distance separating surfaces 86d and 88d equals the gap G, the surface 86d contacts the middle shroud wall 18 and the surface 88d contacts the core plate 21. The wedge bolt 90 can then be tightened until the desired preload is attained. Once the core plate wedge 86 has been trimmed, the amount of preload is a function of the distance which core plate wedge clip 88 travels relative to the core plate wedge. In this state the core plate wedge assembly 84 maintains the spacing G between the core plate and the shroud and transmits a load from the core plate to the shroud. This mounting allows simple installation and subsequent removal, if required for reactor servicing access. When the desired amount of preload has been attained, the wedge bolt 90 is locked against further rotation relative to the core plate wedge 86 by engagement of a pair of wishbone spring latches 92. As best seen in FIG. 4B, each spring latch 92 has a short leg with a projection 92a that interlocks with the core plate wedge 86 and a long leg with a key 92b that interlocks with one of a multiplicity of longitudinal slots 90b (see FIGS. 4A and 5) formed on the outer circumference of the head of wedge bolt 90. The tip of the long leg of spring latch 92 has a surface 92c which is oblique relative to the leg axis. This oblique surface is contacted by a portion of a tool (not shown) which is used to screw and unscrew the wedge bolt 80. The tool surface bears against the oblique surface, thereby camming the key on the long leg to a position where it will not interfere with the head of the wedge bolt during wedge bolt rotation. As seen in FIG. 5, the head of wedge bolt 90 has an axial recess 90c of hexagonal cross section for receiving a form-fitting portion of the tool to rotate the bolt and transmit preload torque. Only the insertion of the torquing tool is required to disengage the locking latch so that wedge bolt 90 is free to turn. In addition, the short leg of the spring latch 92 has a projection 92d which can be gripped by a remotely manipulated tool in the event that spring latch 92 must be removed. To remove the spring latch, the short leg must be displaced toward the long leg by an amount sufficient to enable projection 92a to clear the interfering portion 86e of the core plate wedge 86. Two views of the spring latch are presented in FIGS. 6A and 6B. In accordance with the preferred embodiment, the core plate wedge and core plate wedge clip are made of austenitic stainless steel (e.g., Type 316). The wedge bolt and associated spring latch are made of Ni-Cr-Fe alloy X-750. Both are specified and fabricated with controls to assure maximum corrosion resistance in the BWR environment. In accordance with the preferred arrangement, four core plate wedge assemblies are installed at respective azimuthal positions distributed at angular intervals around the core plate circumference. However, the concept of the invention is directed to the installation of three or more core plate wedge assemblies and is expressly not limited to an arrangement of four. The preferred embodiment of the core plate wedge assembly in accordance with the invention has been disclosed for the purpose of illustration. Variations and modifications of the disclosed structure which fall within the concept of this invention will be readily apparent to persons skilled in the art of mechanical engineering in the boiling water reactor environment. All such variations and modifications are intended to be encompassed by the claims set forth hereinafter.