Patent Number: 
Section: claims

1. A repair apparatus for repairing a shroud in a nuclear reactor pressure vessel, the reactor pressure vessel comprising a core shroud having a plurality of shroud lugs around the circumference of a first end of the core shroud, a shroud support structure arranged to support the core shroud inside the reactor pressure vessel so that the shroud and a side wall of the reactor pressure vessel define an annulus therebetween, a second end of the shroud is coupled to the shroud support structure, said shroud repair apparatus comprising: an upper stabilizer assembly configured to couple to a shroud lug, said upper stabilizer comprising a stabilizer block and an upper stabilizer wedge slidably coupled to said upper stabilizer block;  a lower stabilizer assembly, said lower stabilizer comprising a stabilizer block and an lower stabilizer wedge slidably coupled to said lower stabilizer block, said lower stabilizer block configured to engage the shroud; and  a tie rod having an outer surface, said tie rod extending between and coupled at a first end to said upper stabilizer assembly and at a second end to said lower stabilizer assembly. 2. A repair apparatus in accordance with  claim 1  wherein said upper stabilizer assembly further comprises a jack bolt, said jack bolt extending through a jack bolt opening in said upper stabilizer wedge and threadedly engaging a jack bolt opening in said upper stabilizer block. claim 1 3. A repair apparatus in accordance with  claim 2  wherein said lower stabilizer assembly further comprises a jack bolt, said jack bolt extending through a jack bolt opening in said lower stabilizer wedge and threadedly engaging a jack bolt opening in said lower stabilizer block. claim 2 4. A repair apparatus in accordance with  claim 3  wherein said upper stabilizer wedge and said lower stabilizer wedge each further comprise a ratchet lock spring configured to engage said corresponding jack bolt. claim 3 5. A repair apparatus in accordance with  claim 1  wherein said lower stabilizer wedge further comprises a horizontal stabilizing spring configured to engage the side wall of the reactor pressure vessel. claim 1 6. A repair apparatus in accordance with  claim 1  wherein said upper stabilizer wedge further comprises an integral leaf spring portion configured to engage the side wall of the reactor pressure vessel. claim 1 7. A repair apparatus in accordance with  claim 1  wherein said tie rod is attached to said upper stabilizer block with a tie rod nut and a spring washer, said spring washer positioned between said tie rod nut and said upper stabilizer block. claim 1 8. A repair apparatus in accordance with  claim 1  wherein said tie rod comprises a plurality of longitudinal grooves in said outer surface. claim 1 9. A repair apparatus in accordance with  claim 1  wherein said tie rod comprises a sleeve attached to said tie rod outer surface, said sleeve comprising an outer surface having longitudinal fins, said sleeve covering at least a portion of said outer surface of said tie rod. claim 1 10. A repair apparatus in accordance with  claim 1  wherein said tie rod further comprises a limit stop at said first end, said limit stop configured to engage the shroud, said limit stop comprising at least one shear pin configured to engage mating holes in a bottom surface of said upper stabilizer block. claim 1 11. A nuclear reactor pressure vessel comprising: a core shroud comprising a plurality of shroud lugs around the circumference of a first end of said core shroud;  a shroud support structure arranged to support said core shroud inside said reactor pressure vessel so that said shroud and a side wall of said reactor pressure vessel define an annulus therebetween, a second end of said shroud is coupled to said shroud support structure; and  at least one shroud repair apparatus positioned in said annulus, each said shroud repair apparatus comprising:  an upper stabilizer assembly coupled to a shroud lug, said upper stabilizer comprising a stabilizer block and an upper stabilizer wedge slidably coupled to said upper stabilizer block;  a lower stabilizer assembly, said lower stabilizer comprising a stabilizer block and an lower stabilizer wedge slidably coupled to said lower stabilizer block, said lower stabilizer block engaging said shroud; and  a tie rod having an outer surface, said tie rod extending between and coupled at a first end to said upper stabilizer assembly and at a second end to said lower stabilizer assembly. 12. A nuclear reactor pressure vessel in accordance with  claim 11  wherein said upper stabilizer assembly further comprises a jack bolt, said jack bolt extending through a jack bolt opening in said upper stabilizer wedge and threadedly engaging a jack bolt opening in said upper stabilizer block. claim 11 13. A nuclear reactor pressure vessel in accordance with  claim 12  wherein said lower stabilizer assembly further comprises a jack bolt, said jack bolt extending through a jack bolt opening in said lower stabilizer wedge and threadedly engaging a jack bolt opening in said lower stabilizer block. claim 12 14. A nuclear reactor pressure vessel in accordance with  claim 13  wherein said upper stabilizer wedge and said lower stabilizer wedge each further comprise a ratchet lock spring configured to engage said corresponding jack bolt. claim 13 15. A nuclear reactor pressure vessel in accordance with  claim 11  wherein said lower stabilizer wedge further comprises a horizontal stabilizing spring configured to engage said side wall of said reactor pressure vessel. claim 11 16. A nuclear reactor pressure vessel in accordance with  claim 11  wherein said upper stabilizer wedge further comprises an integral leaf spring portion configured to engage said side wall of said reactor pressure vessel. claim 11 17. A nuclear reactor pressure vessel in accordance with  claim 11  wherein said tie rod is attached to said upper stabilizer block with a tie rod nut and a spring washer, said spring washer positioned between said tie rod nut and said upper stabilizer block. claim 11 18. A nuclear reactor pressure vessel in accordance with  claim 11  wherein said tie rod comprises a plurality of longitudinal grooves in said outer surface. claim 11 19. A nuclear reactor pressure vessel in accordance with  claim 11  wherein said tie rod comprises a sleeve attached to said tie rod outer surface, said sleeve comprising an outer surface having longitudinal fins, said sleeve covering at least a portion of said outer surface of said tie rod. claim 11 20. A nuclear reactor pressure vessel in accordance with  claim 11  wherein said tie rod further comprises a limit stop at said first end, said limit stop configured to engage said shroud, said limit stop comprising at least one shear pin configured to engage mating holes in a bottom surface of said upper stabilizer block. claim 11