ML20207E662

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Rev 1 to PGE-1076, Trojan Nuclear Plant SAR for Reactor Vessel Package
ML20207E662
Person / Time
Site: 07109271
Issue date: 06/01/1999
From:
PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20207E649 List:
References
PGE-1076, PGE-1076-R01, PGE-1076-R1, NUDOCS 9906070097
Download: ML20207E662 (41)
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{{#Wiki_filter:e l l i-ATTACHMENT 11 to VPN-048-99 PGE-1076," TROJAN NUCLEAR PLANT SAFETY ANALYSIS REPORT FOR REACTOR VESSEL PACKAGE," REVISION 1 i i ) l l l. i. 9906070097 990601 7 j PDR ADOCK 07109271} C PDR 3

( [ r Trojan Reactor Yessel Package - Safety Analysis Report LIST OF EFFECTIVE PAGES Page Number Revision Table of Contents i through xii 0 xiii and xiv-1 Page 1-1 0 J Page 1-2 1 l Pages 1-3 through 1-20 0 l ' Tables 1-1 and 1-2 0 i l Figures 1-1 through 1-6 0 Pages 2-1 through 2-37 0 Pages 2-38 through 2-40 1 Pages 2-41 through 2-62 = 0 Tables 2-1 through 2 0 Table 2-5 1 Tables 2-6 through 2-18 0 Figures 2-1 through 2-7 0 Pages 3-1 through 3-11 0 Tables 3-1 through 3-4 0 i Pages 4-1 through 4-6 0 Pages 5-1 through 5-11 0 Tables 5-1 through 5-12 0 Figures 5-1 through 5-3 0 Page 6-1 0 xiii Revision 1

' Trojan Reactor VesselPackage-Safety Analysis Report Page 7-1 0 Page.7-2 1 Pages 7-3 through 7-8 0 Figures 7-1 through 7-3 0 Pages 8-1 through 8-11 0 Table 8-1 0 xiv Revision 1

I Troian Reactor Vessel Package - Safety Analysis Report 4. The reactor vessel external attachments will be removed and all penetrations will be sealed with welded closures. 5. Shielding will be installed on the exterior surface of the reactor vessel, as i necessary, to ensure compliance with the dose rate limits of 10 CFR 71. 6. Impact limiters will be attached to the RVP to limit stresses to values well below yield for the impact (drop) loads. 1 After preparation as a Type B (as exempted) shipping package, the RVP will be loaded onto a transporter and tied down and transported as an exclusive use shipment. The transporter is a hydraulically leveled platform designed for transporting large, heavy loads. Once loaded onto the transporter and tied down, the RVP will remain attached to the transporter until the RVP is off-loaded at the disposal site. The RVP on the transporter is shown on Figure 1-1. l The loaded transporter will be moved from the Trojan Industrial Area to the barge slip on the TNP site where it will be moved onto the barge and secured. The loaded transporter will be barged to the Port of Benton in Washington. The loaded transporter on the barge is shown on Figure 1-1. The loaded transporter will be moved off of the barge and transported by road (less than 30 miles) to the disposal facility operated by US Ecology, near Richland, Washington. The RVP will be then be off-loaded from the transporter at the disposal facility. 1 i The quality assurance requirements of 10 CFR 71, Subpart H, applicable to the design, i fabrication, and use of packaging for radioactive materials are covered by TNP's NRC-approved 10 CFR 50, Appendix B quality assurance program (PGE-8010). PGE-8010," Trojan ~ Nuclear Plant Nuclear Quality Assurance Program," was approved by the NRC for application to design, fabrication, assembly, and modification of transportation packages by NRC letter dated i April 28,1999," Quality Assurance Program Approval for Radioactive Material Packages No. 0327, Revision No. 9." 1.1.1 APPLICATION APPROACH l The PGE application is based on alternative transport conditions due to the uniqueness of the RVP and its one-time shipment. Therefore, this PGE request requires NRC approval pursuant to i 10 CFR 71.41(c) or alternatively,10 CFR 71.8. The 10 CFR 71 regulations provide the NRC with authorization to approve packaging and shipments based on alternative transport conditions. These regulations recognize that special controls imposed by the shipper may provide equivalent safety as those specified in 10 CFR 71. 1-2 Revision 1 i

L i i Trojan Reactor VesselPackage-Safety Analysis Rer> ort than for an oblique orientation. Therefore, the secondary crush distance is also not governing. Impact calculations are performed using initial and environmental conditions which result in the maximum impact severity for the RVP. Subsequent evaluations of the ability of the package to withstand these loads without compromise of the containment boundary utilize minimum material properties. Thus, all conditions of applied loading and structural strength are conservatively bounded. The maximum impact conditions correspond to the maximum mechanical strength of the polyurethane foam energy absorbing material, and occur at the minimtun ambient temperature of-20 *F and without insolation, in accordance with Regulatory Guide 7.8. Additional calculations are performed to determine the maximum deformation under warm conditions, in order to demonstrate that the maximum impact level obtained under cold conditions is not exceeded by excessive crush of the polyurethane foam or by contact of a "hard peint" (i.e., uncushioned contact) with the ground. Since impacts on the ends of the RVP are not credible, as discussed above, the impact limiters l . are required to protect the package in only side and relatively shallow oblique impacts. The impact limiters are, therefore, constructed in the shape of annular rings and fastened to the RVP as shown in Figure 1-6. The outer diameter is 336", and the width is 58", dimensions which do not include the %" thick structural angles on the outer corner seams. The inner diameter of the lower limiter is based on the outer diameter of the shield, approximately 202". The inner L diameter of the upper limiter is based on the outer diameter of the upper flange, or 205". These two inner diameters,202" and 205", difTer by an insignificant amount, and a value of 205" is used conservatively for both. The outside edge of the upper impact limiter is located 99" above. the nozzle centerline, and the outside edge of the lower impact limiter is located 246" below the nozzle centerline. The inside face of each impact limiter is buttressed by a steel structure to prevent the dislodging of the limiter in a drop event. The impact limiters are retained against the inboard buttresses by means of tie rods through their thickness. No welding is performed to the material of the vessel. The impact limiters are encased in %" thick steel shells of ASTM A516 Gr 70, but due to the ease with which buckling may occur, this material does not add to impact severity. See Appendices 2-7A and 2-9 for further description of the impact limiter structure and impact stress analysis, j The maximum RVP protrusion is the inlet nozzle, which is conservatively taken as extending 41.13". from the vessel wall. Since the vessel wall outer diameter is 192", the maximum protrusion diameter is 192 + 2(41.13) = 274.3". However, a distance of 275" is conservatively used. Since the impact limiter outer diameter is 336", the minimum distance from the limiter o.d. to the nearest protrusion is (336 - 275)/2 = 30.5". In the oblique drop case, the upper head attachment stud is nearest the ground. The studs are nominally 7" in diameter and located on a 95.94" radius, and the outer end typically extends above the sealing surface a maximum l i 2 - 38 Revision 1 I

Trojan Reactor VesselPackage-Safety Analysis Retrort of 47.5." Due to installation complexity, one stud extends approximately 49" above the sealing surface. However, adequate clearance is maintained during the drop analysis. The design weight of the RVP, including the impact limiters, is 2.04 x 106 lb. The CG is located approximately 155" below the sealing surface, which is essentially equidistant between the two impact limiters, at the geometric center of the package. The free drop analysis is performed using the proprietary code CASKDROP, which is described in detail in Appendix 2-7B. In brief, the crush area of the impact limiter at each deformation step is calculated. The area is subdivided into equilateral cells, and for each cell, the strain is calculated. :The force corresponding to each cell at the calculated strain is found using the foam stress-strain data, and added up to give the total force of the impact limiter at each deformation, i CASKDROP uses a quasi-static energy balance approach, in which the amount of energy consumed is the cumulative sum of crush force times deformation increment. When the total energy absorbed equals the total potential energy of the drop (including crush distance), the solution was complete. The impact force is equal to the total maximum crush force divided by 1 the package weight. The results of the free drop impact analyses are given in Table 2-15. All impact values are given for the package CG, defined in units of g, and are normal to the ground. For the horizontal drops, the package remains in a horizontal position throughout the drop event. The crush distance is defined as the total deformation of each limiter in a direction normal to the . package axis. Maximum strain is the maximum value of the ratio: crush distance / original distance for the limiter. Strain has no absolute upper limit, but the values reached in this analysis are well below any strain hardening limit. The resulting maximum impact is 20.lg for the cold, -20 *F case, and the minimum clearance over the inlet nozzle is 6.4" in the warm case. . These values are conservatively approximated for use in the free drop stress analysis as 22g and 6.0". Since the impact limiter forces are well balanced and the package remains horizontal, no forces are developed which would tend to dislodge the impact limiters from the package. Note also that, due to the relatively small strain, the global deformations of the impact limiters are small, and the overall integrity of the impact limiter structure is not significantly degraded. In the oblique drop case, the initial pivot point on the end of the lower hemispherical head is i assumed to exist throughout the primary drop event. ' For a free drop height of Il' for the distant limiter, the CG drops 85.3", or 7', and has an initial impact orientation of 19 to the horizontal. The package continues to rotate throughout the impact until it comes to rest, but the added rotation is relatively small. The package can, therefore, be assumed to undergo the drop event at a constant orientation to the ground equal to the average of the initial and final crush angle, or an average of 22.5'(warm case). The results of the analysis are also given in Table 2- .15..The maximum crush distance and corresponding strain are given for the edge of the limiter i which is crushed the most (i.e., toward the upper head) and are measured normal to the ground. 2 - 39 Revision 1

Troian Reactor Vessel Package - Safety Analysis Report Relative to both impact severity at the package CG and to minimum ground clearance over uncushioned structure, the oblique drop event is not governing compared to the horizontal drop. 2.7.1.2 - Reactor Vrssel Free Drop Stress Analysis The RVP is analyzed to show that, when exposed to the impact levels determined in Section 2.7.1.1 (22g for HAC horizontal drop), the acceptance criteria established in Section 2.1.2 are satisfied for the containment boundary. These criteria are, that stress remains elastic in the sealing region of the vessel body and upper head; that attachment stud preload is not significantly affected; and that, in accordance with Regulatory Guide 7.6, stresses in the vessel components satisfy the following: P < 2.45, or 0.7S,, whichever is less P, + P < 3.6S, or S,, whichever is less 3 In addition, Section 2.7.1.4 demonstrates that the maximum possible hypothetical flaw in the vessel containment boundary remains stable under the bounding conditions of ambient temperature, material toughness, and applied stress. The following analyses are performed and described in Appendix 2-9 to demonstrate the adequacy of the RVP design under free drop conditions. 2.7.1.2.1 ' Containment Boundary Stress Stresses in the RVP shell due to the governing 22g side drop impact are determined by means of the finite element model described in Appendix 2-9. The resulting maximum stress intensity in the vessel shell, P, + P., is 26,438 psi, located near the bottom of the vessel, on the outside surface, beneath the lower impact limiter. Since this stress includes bending components, the allowable stress is the lesser of 3.6S, or S,. For the vessel wall material of SA-533 Grade B, Class 1, S, is governing and is 80,000 psi at the core region bounding temperature of 200 'F. The margin of safety is MS= -1 = + 2.03 26,438 l The maximum membrane stress intensity, P., is 14,700 psi, located in the region just below the sealing flange, above the nozzles. In this case, the allowable stress is the lesser of 2.4S or 0.7S,. For SA-533, at 175 'F (outside the core region),0.7S, is governing, where S, is again 2 - 40 Revision 1

1 Trojan Reactor l'essel Package - Safety Analysis Report Table 2-5 Range of Minimum Mechanical Properties of Steel Materials (-40*F - 200"F)' 1 1 Young's Yield Tensile Material Application Modulus Strength' Strength Specification E (x 103 ksi) S (ksi) S,(ksi) y SA-533 Gr.B Reactor Vessel Shell, Top 29.6 - 28.5 50-47.2 80 Class 1 Head SA-508 Inlet and Outlet Nozzles 28.2 - 27.1 50- 47.1 80 Class 2 SA-240 Type Nozzle Closure Plates 28.8 -27.6 25 - 21.3 70 - 66.2 304L i i SA-336 Nozzles Safe Ends 28.8 - 27.6 30 - 25.8 70 i Grade F316(F8m) SA-540 Grade B24 Reactor Vessel Head Studs 28.2 - 27.1 130-121.5 145 i Class 3 ] 2 SA-516 Grade 70 2" and 5" Main Shielding 29.9 - 28.8-38 -34.6 70 5/8 inches Penetration Closures 2 Other Shieldine Notes: 1. HAC thermal (fire) metal temperature values are not included. See Appendix 3-1. 2. Normalized, to fine grain practice. l l l 1 Welding consumables: Allowable stresses / stress intensities for welds are based on lower of the two base metals as referenced in Section 2.1.2.2. i i Revision 1 l l l l

I- ' Trojan Reactor VesselPackaee-Safety Anahsis Report Once loaded onto the transporter, the RVP will not be removed until it is off-loaded into the disposal trench at the disposal site (US Ecology). The loaded transporter will be moved from the package preparation area in the Trojan Industrial Area to the barge slip on the TNP site. Transporter speed will be limited to 5 mph. It will then be moved onto the barge and secured by an engineered tiedown system. This tiedown system is designed to meet the requirements of ANSI N14.24-1985, except that the transverse collision acceleration loading was increased from 0.5g to 1.6g based on the probabilistic safety study for l river transport (Appendix l-1). Figure 7-1 shows the on-site transport route. The barge will then travel up the Columbia River approximately 270 miles to the Port of Benton in Washington - where the loading process will be reversed (i.e., the loaded transporter will be moved off of the barge). Figure 7-2 shows the river transport route. The loaded transporter _will be transported less than 30 miles by road to the disposal facility operated by US Ecology near Richland, . Washington. Figure 7-3 shows the overland transport route from the Port of Benton to the US Ecology disposal facility. The RVP will then be removed from the transporter for disposal. The shipment will comply with the specifications of ANSI N14.24-1985, "American National Standard for Highway Route Controlled Quantities of Radioactive Materials - Domestic Barge Transport," and with the applicable requirements of 10 CFR 71 - Packaging and Transportation of Radioactive Material,33 CFR - Navigation and Navigable Waters,46 CFR - Shipping, and 49 CFR - Transportation. 7.2 PREPARATIONS FOR TRANSPORT The RVP will be prepared as a Type B (as exempted) shipping package that meets 10 CFR 71 requirements prior to transport from the TNP Industrial Area. A discussion of the preparations required to achieve compliance with these requirements is provided in Chapter 2. Chapter 8 describes the inspections and tests that will be performed to verify the package has been properly constructed. Sections 8.5.9 and 8.5.10 discuss the radiation surveys that will be performed to ensure compliance with 10 CFR 71 requirements prior to shipment. Additional surveys required by 49 CFR 173.443 will also be performed. Package markings will meet the requirements as stated in Section 8.4. The transporter and prime mover will be inspected to ensure the vehicles are working properly and to ensure conformance with applicable state and federal standards. The structural adequacy of the transporter will be demonstrated by analysis and the transporter will be loaded in accordance with the manufacturer's specifications. Prior to transport of the RVP, the entire transportation route, onsite and offsite, will be evaluated to confirm that it is structurally capable 7-2 Revision 1

r PORTLAND GENERAL ELECTRIC COMPANY TROJAN NUCLEAR PLANT APPENDIX 2-10 RPV EXTERNAL SHIELDING STRUCTURAL INTEGRITY ANALYSIS PORTLAND GENERAL ELECTRIC COMPANY May 10,1999 aoh No. HM E rd M 3L2-2. Lenw No. O r,g;D 497 d9I g EWMM3 SUPPLIER DOCUMENT STAMP ginal submittal 2 o Work may proceed. Submit final docu-ment 3 o Revise and resubmit Work may proceed Prepared By". subject to incorporabon of changes indi-cated. 4 o Revise and resubmit Work may not pro-Zdenck Studnicka coed. 5 o Review not required. Work may proceed. ' " O'h" - Checked & Approved By: Permission to proceed does not coresmule .ccepience or approvai os dosion detaine, y c.icuwsone..nw ees, ioet methode. or me-Norman Lacy r terlak developed or eclected by the supp-lier and does not relieve suppner from full / compnence with contractuoi ohne.none. Approved By: /pg O INFORMATipN OtlLY.,, f - 7 h f1MI' Robert Morgan prepared by6I M = J Date Concurred b[7 -// - #k/M / b^ oat. PGE 1692 (Jul 86)

APPENDIX 2-10 Rev. 3 Table of Contents For RPV EXTERNAL SHIELDING STRUCTURAL INTEGRITY ANALYSIS FIGURES 2-10-1 Reactor Vessel Shielding Details (three shr et6 Reactor Vessel Supplemental Shielding, Attachment Detail at Main Shielding Closure Plates Reactor Vessel Supplemental Shielding, Alternate Attachment Detail at Main Shielding Closure Plates Reactor Vessel Nozzles Supplemental Shielding Details Total pages in this appendix = 51 Revision Record: Rev.1, initial SAR issue; Rev. 2, added pages 44 and 45, Supplemental Shielding Attach-ment Details at Main Shielding; Rev. 3, added new pages 33a through 33e and 42,43,43a I to cover shielding figure updates and design of the supplementary RPV nozzle shielding, and updated title page and pages 11,4,16,17 and 38 to agree with as-built dimensions and welding details. d.mpfstropn shid,sar doc ii

App:cdix 2-10 Rev. 3 from the HAC's (oblique drop) 4.7 g LAF times the weight of the entire package, a.s the 10 g LAF longitudinal load from the NCT would be applied only to the weight of the shielding. A finite element analysis was also perfomied on the shield plates to determine the maximum bearing pressure and the Maximum Stress Intensity. The concurrent stresses in the reactor nozzles are also specified by this calculation, since they are equal to the stresses in the shield plate. The loads used in this analysis are fully described in the results table of section VII of this appendix. The 5" plates were also analyzed for the bearing stresses (local membrane plus bending stress intensity (P + P )) induced at the cradle location at the bottom of the RPV. The cradle bear-i 3 ing stresses were increased by a LAF of 1.6 g to account for the normal transportation loads that the cradles will see. This condition does not govern any of the design, but was analyzed for comparison purposes. B. Shield Plate Seam Weld Sizing for the Worst Case Loading - The 2" and 5" shielding jackets are designed not to break apart or separate from the RPV, under any NCT event or any HAC event (including the 11' drop). There are two specific weld types that are important to the overall integrity of the primary shield assembly (the 2" and 5" plate jacket). The first weld type is the longitudinal (seam) weld in the main 2" and 5" shield plates (welded longitudinally as the vessel sits in the horizontal). In the case of the l 5" shielding, three seam weldsjoin three 120 shield segments together in this manner. For the 2" shielding, eight segments arejoined with these longitudinal seam welds. The second weld type joins the 2" shield plates to the 5" plates circumferentially around the RPV. To size the longitudinal welds, it was necessary to examine what forces might act to tear the plates apart from each other. For the HAC event, the worst case would be for the rnaximum impact LAF applied to separate one of the plates from its attachment weldjoints. Based on the impact analysis of Appendix 2-7, the worst case is the 4.7 g LAF resulting from the resul-tant from oblique drop from Il' The longitudinal welds for both the 2" and 5" plates have been sized by applying an LAF of 4.7 to the total package weight of 1020 tons. The circumferential welds are analyzed for the application of the 10 g (NCT) longitudinal load as the bounding case. The analysis is based on the weight of the total shielding (maximum, plus spot shielding) and both impact limiters. C. Contact Local Stresses Between the Vessel Wall & Shiciding - The RPV is jacketed by two sections of steel shielding that is 2" thick in the reactor nozzle area and 5" thick in the core region. As a result of fabrication tolerances in both the reactor j and shield manufacturing, it is expected that there will be geometrical deviations in the ves-1 sel's cylindrical shape. During transportation and vessel handling, it is essential that the there be no relative motion between the RPV and the shielding jackets, so that the whole assembly l acts as a rigid body. This motion can be eliminated by a combination of shimming and com-l pressing the shield against the vessel wall. Two engineering concerns need to be addressed: l d %pf trojanishld.sar doc 4 i j

T Appe:dir 2-10 Rev.3 B. Calculation for the Shield Plate Seam Weld Sizing for the Worst Case Loading - Weld sizing for cylindrical shield s1 = 5" and s2 = 2" thick. The design requirements are specified as follows: The total shield weight was calculated as being 241,292 lbs (including the skirt), the added supplementary shielding plates total of 14 tons, and the maximum impact limiter weight total of 73 tons. Circumferential and Longitudinal Welds: Shield, as discussed in previous section, has two basic thicknesses AAer assembly of 5" thick sections, the 2" sections are circumferentially welded to the bottom - 5" shield cylinder. The sizing of the circumferential weld is shown bellow. Circumferential Weld Sizing The worst case longitudinal design load that acts upon the circumferentialjoint is based on the NCT 10 g LAF event acting on the total weight consisting of the main shielding, supplemental shielding and the two impar limiters. WTiong := (241292. (14 + 73'

0) 10 Weld Design Load (Ib) for NCT 10 g LAF,14 tons spot shielding and both of the impact limiters (73 tons)

WTiong = 4.153 10' (Ib) u 196.125 (in) RPV max OD plus 2" shield thickness y,,2xD - 12 Awe = 604 145 (in) Treating weld as a line, the Awe is conservatively 2 reduced by 12.0" to account for possible variance between the 2" and 5" shield final seam length. Weld lineload fwc: twc= W ng 3 fwe = 6 874 10 (lb/in) Awc sm = 23300 Jef4 0.5 ASME allowable stress for SA-516 Gr. 70 & fillet weld jomt eHiciency. Weld NCT allowable stress limit: t = sm.Jef t = 1.165 10 (psi) 4 Fillet Weld throat: p = = m=> l p m. nao y e, e =0 835 (in) ff \\ twc 0.707-t Use co =7/S" min. fillet weld all around 5 J$ y h 7 m (psi) pawmana l mact.: - tact = t 8 mact tact = 1.111 10' Actual stress in the weld due to these loads. Alternately, a single 7/8" groove weld may be used to replace the 7/8" fillet weld. This is conservative, as the joint efficiency for the groove weld is 1.0, whereas that for the fillet weld is { 0.5, and both welds are applied through the same circumferential length. shid_sar.med 16

App = dix 2-10 Rev. 3 Longitudinal Shield Welds Under the Longitudinal HAC Drop Load Effect. Five inches shield longitudinal welds: L = 206.5 Length of 5" cylindrical shielding between lower head and bottom of nozzles (in) m := 96 Length of 2" cylindrical shielding between lower flange and top of nozzles (in) 31 := 5.0 Wall thickness (in) s2 = 2.0 Wallthickness (in) s3 = 1.0 Wall thickness (in) WTri = Ns WTri = 9.6 10' (Ib) HAC oblique event load (4.7 g's) p=6 Number oflongitudinal welds "L" long (Note: three lapjoint plates with two fillets welds AwS=pL AwS = 1.23910' (in) each). f5 = " 3 f5 = 7.748 10 (lbTm) Tensile strength of SA-516 Gr.70 material: Aw5 Su = 70000 t = 0.6 0.7 Su t = 2.94 10' (psi) Weld allowable limit e5 = e5 = 0.373 (in) 0.707-t mact =.375 Use 3/8" min. fillet weld conservatively e5 d tact = t tact = 2.922 10 Actual stress in the weld due to these loads i mact Two Inch Shield Longitudinal Welds: { q = 16 Number oflongitudinal welds "m" long (Note eight lap joint plates with two fillets). 3 Aw2 = q m Aw2 = 1.53610 a=* c -6.25 10' Tensile strength of SA-516 Gr.70 material: Aw2 Su = 70000 t = 0.6 0.7 Su t = 2.94 10' (psi) Weld allowable limit U m2 = m2 -0.301_ (in) 0.707 t mact s.375 Use 3/8" min. fillet weld conservatively m2 tact = 2.357 10' Actual stress in the weld due to these loads tact - x mact shld sar.med 17

Appendix 2-10 Rev. 3 Individual " Cans" Like Shielding: Shield Geometry Parameters for the nozzles: ds / dd a x Note: ~# Discharge 's" Suction L i h ps / pd ) \\ h rs / rd wi 1 1r j y l i W3 l +-+ w2 i l t I Suction Nozzles: Four to be covered by "can" shielding with dimensions as shown below: Ds 512 - 2.5 ds = 3 12 + 3 8 wls =.5 rs = 312 + 11 + N - 8.5 w2s =.5 32 w3s =.5 Ps = 8.5 rs = 39.094 Note: All dimension in (in) w4s.= 5 Discharge Nozzles: Two to be covered by "can" shielding with dimensions as shown below: Dd = 412 + 9.5 dd = 3 12 + 1 + d wid =.25 8 w2d =.25 rd = 3 12 + 5 + 9 - 8.5 w3d =.25 16 Note: All dimensionin (in) w4d =.25 pd = 8.5 rd = 33.063 p = 0.282 (Ib/in3) Density shid_sar.med 33 a

F l Apprdix 2-10 Rev. 3 j: - Total Weight Calculation: W1 := { f Ds - (Ds - 2 w2s)2)-(rs p 4) + 2 -[Dd - (Dd - 2 w2d)2)-(rd)p2 2 Bottom cans W2 = 1(Dd* - dd*) w3dp2 + 1(Ds i ds ) w3sp4 2 2 Semicircular plates 4 4 W3 = 1[dd - (dd - 2 wld)2)-(pd)p2 + 1[ds - (ds - 2 wls)2)-(ps) p 4 2 2 Top cans 4 4 -(Dd ) w4d p 2 + (Ds ),,4, p,4 2 2 W4 = Top closure (added conservatively) W6 cans = (W1 + W2 + W3 + W4) W6 cans = 9.265 10' (Ib) = 4.633 (ton) 2000 Evaluation of the "can" shielding for structural integrity. The cylindrical shell and plate bodies are judged to be structurally integral by comparison. The failure may rather occur at the weld attachment between the can assembly and the 2" shield. The sizing and weld design is l presented next. Weld Sizing: Loading: The loading is related to the can weight assembly amplified by applicable "G" value. Glong ^= 10 Overt = 0 Glateral = 0 Load for Suction Nozzle most critical can geometry: Wbc = 1f Ds - (Ds - 2 w2s)2]-(rs p) Wbc = 1.074 10' (Ib) 2 4 Wpl = 1(Ds - ds ),,3,.p. Wpl = 286.056 (ib) 2 2 4 h/tc = Ef ds - (ds - 2 wls)2]-(ps) p 2 Wtc = 135.077 (Ib) 4 Wtpl = b(Ds ).w4s p 2 Wtpl = 432.583 (Ib) L -4 l Location of can CG in axial direction with respect to bottom (weld between the large can versus 2" shield) most critical weld. Wtpl-(ps + rs) + Wte l + rs ' + Wpl rs + Wbc- '~ As = As = 30.411 (in) Wbc + Wpl. Wtc + Wtpl i shid_sar.med 33 b L )

l Appe: dix 2-10 R:v. 3 Weld is subjected to bending and shear loads. Design Loading: 3 Ws - Wbc + Wpl t Wtc + Wtpl Ws = 1.92710 (Ib) One can most critical weight Giong = 10 4 Wsdes = Ws Glong Wsdes = 1.92710 (Ib) Weld design load j Bending: Load vector is applied at the CG of the can assembly: Msdes : As Wsdes Msdes - 5.861 10 (in Ib) ' Bending at the weld root 5 3 Ssw^{Ds 2 3 Ssw = 3.06810 1 fbs ~: Msdes ibs = 191.048 I g,-- Shear: ) i i Aws e x Ds Aws = 196.35 ) I fss ': Wsdes fss = 98.161. 4 g Resultant line force: 1. i Using the fillet weld efficiency: eft = 0.5 fsresul = (fbs, g,3 ;2 2 2 fsresul = 214.79 Using the groove weld efficiency: erg = 1.0 Fillet weld size (minimum required): ASME Section Vill. fillet weld efficiency ASME material allowable for SA-516 Gr 70 Sm.= 23300 t : Sm eff l mscan = mscan = 0.026 (in) 0 1 Use = 0.125 (in) Fillet weld all around between the large diameter can versus the 2" shield, g otherwise use 1/16" fillet except as noted. Groove weld size (minimum required): Sm 23300 t " Sm efg fsresul mscan = 0.013 (in) mscan a g,- 1 Use g =0.063 (in) groove weld all around, where specified shid_sar.med 33 e i i i

l Appendix 2-10J Rev. 3 Load for' Discharge Nozzle most critical can geometry: ~ ) Wbe '= E-[Dd - (Dd - 2 w2d)*)-(rd p). 2 Wbe = 419.228. (Ib) ~ 4 Wpl := E-(Dd. - dd )jw3d p Wpl = 105.722 (Ib) 2 2 4 Wtc = 3-[dd - (dd - 2 wid)2]-(pd) p. Wtc = 69.892 '- (Ib) 2 4 Wtpl := E-(Dd ) w4d-p : Wtpl = 183.069 < (ib) 2 4 Location of can CG in axial direction with respect to bottom (weld between the large can versus 2" shield) most ' critical weld. Wtpl-(pd + rd) + Wte- + rd + Wpl rd + Wbc-Ad = 'Ad = 26.536 (in) Wbe + Wpl + Wtc + Wtpl Weld is subjected to bending and shear loads Design Loading: - Wd = Wbc + Wpl + Wtc + Wtpl Wd = 777.911 ' (Ib) One can most critical' weight Olong = 10 Wddes '= Wd Glong Wddes = 7.779 10' (Ib) Weld designload Bending: Load vector is applied at the CG of the can assembly: 5 Mddes = Ad Wddes Mddes = 2.064 10 (in Ib) Bending at the weld root . Swd = E Dd Swd = 2.597 10 2 3 4 j T Modes fbd.s g,79, Swd Shear: Awd = x-Dd Awd = 180.642 fsd : fsd =43.064 Awd Resultant line force: Using the fillet weld efficiency; eff = 0.5 (dresul = (fbd. fsd )2fdresul = 90.409' Using the groove weld efficiency: efg = 1.0 2 2 . shid_,sar.med : 33 d a

Apperdix 2-10 Rev.3 Fillet weld size (minimum required): ASME Section Vill. fillet weld efficiency Sm.= 23300 t u Sm eff ASME material allowable for SA-516 Gr 70 edcan ': foresul-edcan = 0.011 (in) i Use = 0.125 (in) Rilet weM all around Ween me largo dameter can mus me 2" sNeld, g otherwise use 1/16" fillet except as noted. Groove weld size (minimum required): Sm = 23300 t r Sm efg fdresul mdcan = g 7g udcan = 0.005 (in) 1 . Use jg = 0.063 (in) groove weld all around, where specified i i shid_sar.med 33 e

3 g e e n s v h h - ne e n ut 3 v g r-gt me gt me i s oe govt o 1 al 2 o t l R o s oe 0 a iut o f e d f (s nd e ri gs ny ngvd nh d f (s r 1 r t l , e c n e l i an an oet n n nit s o s n ne or e e s o ut i vb v gi l a r n. i ut vt s r i e r l ea e t d ol r d ol r i or s t a e a e ut s n gf et e u a e u a d s t et nh pm sd sb sb n i s n )n n )n e5 nv e S u r e e a n ol at oi e s v o n t e ur e a t x r e egwgo K or i t si is s i v e )t n n s c o or c o t r l s t r no u nd o t l sdC 0 o R s a s a e oo ndi s e r t t t p s A ad h pc ad h pa s pf a a a 1 h o e n "e p ) p la nm u r o ras s b et c ct M e oi b et oi nom( pg e p ua cc e rl a cpron h miqs 6 o Hu e o 1 i s r f s r c o e r o c ncidi ncidi r 2 h oad E l o x s "e o x s "e o et ne a t l i y S R ea ea a i i odl s ob dt h onyyn l l t t b c b c sd r i c oa a S lah u ah u I mia e e a t ad ea dd" og eotal hh t r l r i nqo nqo o h c c t u i gi f u i gi f f chi Fl Tt n a a el n r r r uTt Y chi o l l af Al oohl o m. n,n i i L l l a wsb awsb LaChn N u 's at I I l l t e e g u c ed pi s og F d "o F d "o c c g gl mt a s es sFi e e A e t e t a c p e c n i gi eo t N hA7.hN hA7.hN 0

7. i oAm h uagAa n

s d e o e o 0 uhh n e iLmd r r TL4t TL4 Tdt 4df (i t 1 t t t 1 A Y C . A C F A A B B p2 t T L ceI &I E I I I I p - A R V V V V A 2 I SV V R C GE E r r i r. r a i i s. i r i s s k s s 0i T L kG kG G kG kG 1 r 5 s e N BS) 6) 06) AT5 416) 06) 66)

4. 1 i r t l

l l l l 1 a 1 a a 8 a eh ei I 1 r 9 a 0 e 5i 5i 5i 9 5i 5ih pc 1 t L WIMto g 2 r 7 r r 2 - r 3 r t rl 1 e e e e e s oa1 n = At = At = At = At = Ataifi7 OI A L L (n ,S m a a a a r d ,S m w m ,S m ,S m ol eR i S ,d R er r or t l or or L U A n, fo0 afo0 nfo0 %, fo0 of e n n o0 u.i aF e h S( 7 S( 7 T ( 7 t (7 S( 7S ymC i T S C U "5 d d " e 8 d ni l R d a n l s 3 u el 8 nd ei k l i I e n nt si w wi 3 ol ws s5 / s T S a ic s s e r .k e3 = ai ek s S T .d "8 .k s w,wx7 o r r o x 8 e ,k 5 G L 2 s s s t t e a5 S / a9 ui1 S 2 7 U e 8 vm3 t s m0 s n r N S y6 m3 m ,1 ml o ,2 m1 d Pi i E a s a0 u= ud u e od u = l I D R M gk a7e 3. E. s. i t imr m wr e = my n a= my e = n gr 5 s s i t L i i i i t r s u s xi xi n us n e "4 s e e E qr a n e a n qr i l i r l B6FP Mt Mret Mi 3 r s Mt / et e e l s f l i S s s gg L L L L mi05 d. s1 ,n I I I o a A NS 6 6 6 0 f xs a l r N GD D 7l 2l u n e,l 7l 7l t s a A E 0 a g 0 a g 0t g 0 a ois c a nn ed ri I t t t e R S S 2 o n) 2 o in) 2 o n) 1 o g )t a o nu et EO U x (tidh x (t dh x(dh x (t ah t t i t r t t t v E DL gs ei gs ei gs ei gsk g u0tais es l t g g g g l l l 7 nie 7 nie nie 7 nci s2 n vd T l e e0 un a oh oh w oh w 4t pw R1 mlorago 0 o a X 4 t s w 4 2l t s 1 t s t E l t V D e a c vt d n a l s e e e P E i t n s f i t R DZ V ai n t s n d nl a s oi e u od NY P .e g s v g od it a l i b c a TAL R s a s sf n r jl r e g t c di N s n eio e izleh o cb e E N A d e og. t n k y s h is l r N O N n r n s si nt s a sdi e s ot ,w" ,g jd a t a c A edl yi s I n sl 5 s n l c a 0 OT s gsl z sl t a ei l e e na ie z e a oi e it r PPN z o t t t aibh o a nma 1 ai e u s t a O nt r g lpe n pt s MIRI s h d i OCT eif l pA lpa s s n l l d 2 e a n h / r o d n s CS ldb s oe d. v g d ei l i ldi x \\ si s n s ns e et n s. l f t I i s l ,i c e o e e ja E D e d ai e e me eyoe i it s ij i s o dl i e D N ih zl i v hi ei z h un e h d h i n l l s t\\ c sl s e lp at s s r i z s c nt s z p O noe n r a e r ol e nh o "2 i c p 2 w 5 s A 2 nAmh "2 o t w p C t t os n c A d m e

App ndix 2 - 10 gg Rav.3 E 6 o er Z8 "s -=

n N
  • 3 g

\\ y,e s s 5 d I ww 5 Eg h s m e-t k J gg \\* e5 je?@_ E yg -3 = 2-A e4 si 1/

  • Nw

.a ee a o 5 s5 a W l5

  • dlW b

ga! r) v r u .-W5 0$ $$ Oc {0 U) l E!. N l d d a 5e e5 3 we r, 1 O M f Uf \\Mh -a e

u. Z O6 "w

/ )/ zi i u) U) b4 N \\. z= a j WW / E U) D U) / i / O >W E m _.p e iO ) .t 9 e( ,is a v/ g <*o C /0 ~_ W$ Er y,.c 00 ER E Ip. e_s n g* a

eit gis

.a Barr esE $2d uses ,eg g rar W W CWe g 42

3 Ap o 2-m 2ND L AYER V2' t, AS REOUIRED Rev.3 F-IST LAYER V2' t. AS REOUIRED ADDITIONAL LAYERS (/2' %) N. N4 ___J 12 0 (/ / s. \\ % / 2 - 12 SURFACE OF 2' OR 5' Shit'.t.C'NG INSTALLED AROUND REACTOR VESSEL MT (TYPICAL) SECTION A-A ADDIT'ONAL V2' L AYERS/ SPOT SHIELDING TO BE ADDED AS REOUIRED. SEE NOTE A IST V2' LAYER 2ND V2' LAYER = 3 '- 0* m---- ~~ p 'v/ n N H u o n o H W H u n n. k 3 T ji. s.N a n l n 5' THICK MAIN 's SHIELD PLATE ,e ll \\ s i j. .h y O e II .I / \\ 8 U v/ N H H n u n u n w o u w T F)11..<' i A 1 NOTE: ENTIRE WEIGHT OF SPOT SHIELDING g/ CAN BE SUFPORTED BY 16'-O' 0F %' FILLET WELD. ACTUAL WELD USED WILL BE PROPORTIONAL TO THE AMOUNT OF SPOT MT SHIELDING INSTALLED. } I FIGURE 2-10--1 (SH.2 OF 3) REACTOR VESSEL SUPPLEMENTAL SHIELDING DETAll 998100/5K6 43

App;ndfx 2 - 10 RIv.3 S'-2Vz's FIELD CUT TO SUIT %' AND V2' PLATES = = 3'-l%.e TO AVOID INTERFERENCES WITH IMPACT LIMITER BRACKETS. Ve V NO WELDING AT THESE PLACES. It a .:;........... ;.1 DETAll 9 / s m W X _Q U. .. '_ 3'-O%'e[\\ 9 k ,.... '. ::. "~... :p... g f.. ,r'... \\ n u \\ i j DETAll 8 .:L g F g 'i U M ll . ~. ....-l...,. l l tl l \\

  • tl l

\\ l 1. n

  • 1

\\ W>"* * .j, DET All 8 INLET N0ZZLE D--;.)..-,. ~ (TYP OF 4) i N.T.S. ^ A'-9V2*e ~ Qh __ 3'-2%'e - min.45' hm= s ag 1:.... :;::...:: y,. y g g.h C 3'-1%'eT1., J N p' ....................'g g b a st.) h 3 b l j WV p y U l l ll min. g g.., Sl %V j min. f \\/ s .) '/s - V2' SUPPL / SPOT %.THK t SHIELD FIELD CUT, AS RE0'D. (T YP) (TYP). DETAll 9 ET N0Z Ulpyp o 2 WELDING DETAllS N. T.S. TYPICAL FOR OUTLET N0ZZLES AND INLET N0ZZLES N.T.S. FIGURE 2-10-1 (SH 3 OF 3) REACTOR VESSEL NOZZLES SUPPLEMENTAL SHIELDING DETAILS 430 hz

p-- 1 INCORE PENETRATIO - REACTOR VESSEL ,7,, CLOSURE PLATE w PT U hrh _2_%. " DI A

g z

s CLOSURE +'/s") b I PLATE 4 FIGURE 1-4 INCORE INSTRUMENTATION PENETRATION a l 2 as//8/99 PJJ 'ifk) h

1. CLOSURE PLATE MATERIAL: ASME SA-516 GR. 70.

1 08/05/98 PJJ BW l/JMM REV OATE BY CHK APPD j PGE TROJAN y NUCLEAR PLANT g DWG NO M-9258 REV SHT.5 0F 8 2 t

git l if S d bJ( b M F T E T M P N 2 A H J J L / A T P O T L B" u d W W NP Y 5 - bL f B B 2 i R g) OD I JR T A F / yF N M N T J J J OA O V r D P P P TL A S D PIM",NI D V E J J J RE % 2" 0 l I w D 8 7 C E R L L 9 9 9 U T T O M E A T ~ W 9 / / N H / 5 4 S L DD E P LL D L g 0 2 IE A / / / / I / EI E HH D R 'c SS L N S 8 3 T f E 0 0 U n,,,, S N RR E W R D O EE E 2 0 L t PW L 1 E F L C g PO A e h UL H N S L U M E I E C ) T D l R _ G Eh A S A U R h I T E S N L P C O'L L u G P w E N U I _ AO MM)K" A R O I L 2" U MS P EL i1 E n1 T A [ SC 7 1 w[Y3w J l J L D '1 5ixW t i u 'Oo G m X L N R H 7 P P Y P T A O I D f L E O I 5 H / S 1 / N E A I R A U M G N L I F E ~ S N S E V R Y_ r O i T / P^ C T s O' A D LA LE S E N AT / 1_ L I ) i I D D NO S' R A IN R T U E M E L NE T R C I OE Y^ lg - E AA I U NS A T Ag-R N Q I L"' L g^ E O E EW AL P F R RR "2 M E S AE '/ 0 U g-R A H g^ C U R ST L t Fl O NE IS NO A s. CO i )T c D L LEl P IS LC TRU Y O S O'R A S I A'U N C TS T T E IM PA Q

E I

L D E E M YE RL T IN DE TS DU A. R -E O 2 3 N 1 (

i 2ND LAYER " [, AS REQUIRED l 1-1ST LAYER E, AS REQUIRED ADDITIONAL LAYERS (k2" E) s [ \\, s b. _.12.0 M \\ il \\ N / / ss, I / (TYPICAL)\\ \\ /h [ 2-12 SURFACE OF 2" OR 5" SHIELDING INSTALLED AROUND REACTOR VESSEL MT SECTION A-A ADDITIONAL " LAYERS / SPOT SHIELDING TO BE ADDED A AS REQUIRED. SEE NOTE 2 n 1ST %" LAYER 2ND " LAYER 3'-0" =l 'v/ // / // HHHHHH HH 5" THICK MAIN i \\ SHIELD PL ATE / \\ j .f __ p.. _. _1. D .I l N i / / ( F i ;... - y \\H HHH H H H HHHH HH HH s. A / s M mV N FIGURE 1-5 REACTOR VESSEL SUPPLEMENTAL SHIELDING DETAIL NOTES:

1. DIMENSIONS ARE NOMINAL UNLESS OTHERWISE NOTED.

2 '5//sf99 PJJ h 1 08/05/98PJJ BW fJMM V

2. ENTIRE WElGH OF SPOT SHIELDING CAN BE SUPPORTED 0

03/24/97PJJ BW JPF ] BY 16'-0" OF 6" FILLET WELD. ACTUAL WELD USED REV DATE BY CHK APPD ' WILL BE PROPORTIONAL TO THE AMOUNT OF SPOT TROJAN i NUCLEAR PLANT k SHIELDING INSTALLED. PGE j M-9259 REV . 3,1" THICK SHIELD AT BOTTOM OF VESSEL WILL BE EITHER OWG NO CONICAL OR CYLINDRICAL SHAPE. 2 SHT.2 OF [

5'-2W" DIA FIELD CUT TO SUIT %" AND %" PLATES = =- 3'-1%" DIA TO AVOID INTERFERENCES WITH IMPACT = s LIMITER BRACKETS. V NO WELDING AT THESE PLACES. g g \\' ' " '. - DETAll 9 I..-l_.. l [5 . O 3'-O%" [. / 0A 'z f f l' n N i \\' l DETAIL 8 y p \\ ~ Y af l ,..~~~"~~~m \\ j l - _j. p' ...y' u g ( l j \\. s \\ \\ r i l i f ./D's..' \\. '\\ \\ l ) f " THK Q 'g / 's,1 N \\ i s (TYP) '\\ I \\ a ?h. sN gj d D ' 'y ' DETAIL 8 s INLET NOZZLE '5$ ~ ~ ~~~ - -- (TYP OF 4) .h I Z6 N 4 '- 9 " DIA _- (MIN.) 4 5* -3'-2%" DIA ( r . _ Zs" (MIN.) d d j V ) h h @:A DIA-C 3 -lfs ~]. m 76 ? l ZsV N(MIN.) Ub b [ y ((MIN.) gg y \\\\ ig .. ~, l \\/ N..-[\\ x ,= %/\\ -{ - l -- %" ELD FIELD SUPPL / SPOT SHI i i CUT, AS REO'D. %" THK q (TYP). (TYP) DETAIL 9 WELDING DETAILS OUTLET NOZZLE TYPICAL FOR OUTLET NOZZLES (TYP OF 2) AND INLET N0ZZLES FIGURE 1-5 REACTOR VESSEL N0ZZLES SUPPLEMENTAL SHIELDING DETAILS l NOTES: O Sh3/49 PJJ 'l!!T4 % j REV OATE BY CHK APPD

1. DIMENSIONS ARE NOMINAL UNLESS OTHERWISE NOTED.

PGE NUC

l. ANT I
2. SPOT SHIELDING WILL BE FORMED FROM %" PLATES.

DWG NO M-9259 REV f 0 SHT.3 OF 6 m

I 1 MULTIPLE OR SINGLE LAYERS OF SPOT I 1"x4" SEAM CLOSURE PLATE SHIELDING, ADDED AS REQUIRED LENGTH AND WIDTH, CUT TO SUIT SHIELDING REQUIREMENTS / j' \\ 'N6 / 2-12\\ J \\ L 2" OR 5" MAIN SHIELDING PLATE W ^ REACTOR VESSEL SUPPLEMENTAL SHIELDING ATTACHMENT DETAIL AT MAIN SHIELDING CLOSURE PLATES MULTIPLE OR SINGLE LAYERS OF SPOT SHIELDING, ADDED AS REQUIRED FOR 1"x4" SEAM CLOSURE PLATE SHIELDING AND THICKNESS NEED MT LENGTH AND WIDTH, CUT TO SUIT-SNIELDING REQUIREMENTS (TYP) \\ (TYP) N6 / 2 -12 MT \\ k / q__ -I, E J \\ O 1 N6 V 2-12\\(TYP) r " OR 5" MAIN SHIELDING PLATE (CHAMFER AS REQUIR (TYP) REACTOR VESSEL SUPPLEMENTAL SHIELDING ALTERNATE ATTACHMENT DETAll AT MAIN SHIELDING CLOSURE PLATES FIGURE 1-5 g NOTES:

1. DIMENSIONS ARE NOMINAL UNLESS OTHERWISE NOTED.

1 '5//8/99 PJJ 1rJ W-E

2. SPOT SHIELDING WILL BE FORMED FROM

" PLATES. RV A BY CHK A PD TROJAN s PGE 4 NUCLEAR PLANT 4 DWG NO M-9259 REV SHT. % 1 /E~~~

l i NOTES:- l 1. THE EDGE WELDS (ie,2" IN 12") FOR THE FIRST LAYER ARE SIZED TO SUPPORT A SECOND AND A THIRD LAYER OF " PLATE, THE ACTUAL CONFIGURATION MAY CONSIST OF A DIFFERENT' COMBINATION OF PLATES AND WELD SPACING. 3

2. CONTINUOUS /s" FILLET WELDS ALONG THE TOP AND BOTTOM EDGES OF THE

" PLATE MAY BE USED IN LIEU OF INTERMITTENT FlLLET WELDS.

3. SHIELDING CONSTRUCTED OF ASME SA-516 GR. 70 MATERIAL.

1 FIGURE 1-5 i REACTOR VESSEL SHIELDING DETAIL NOTES i 2 SilE N9 PJJ nsb % 1 08/05/98PJJ BW fJMM f ~ l 0 03/24/97PJJ BW 'JPF [ ] REV DATE BY CHK APPD [ l PGE NUCL LANT l D G NO J M-9259___ REV j SHT,f5'OF'G] 2 a

u NOTES: L 1. WELDJNGISHALL BE[PE'RIkb'RYED1IR ACfDRD_ANCE_ _WITH CTHE ~ d(~AND' SECTFON llF,YUY-SECTION NV ~AY APPROPRIATE. ^@@OCA8M MNdDS AND_ _GU_IO^NCC PRdVID&Dil:N)SEC1 ION Vill-2. _ _ ELD _ NDE_SHALL BE PERFORMED IN ACCORDANCE WITH -THE W APPLl A L METHODS AND GUIDANCE PROVIDED IN ~ASME ION lil, SUB-SECTION ND, OR ASME SECTION Vill AS f APPROPRfATE. ' 3. WELDERS AND WELDING ~ PROCEDURES SHALL BE IN ACCORDANCE WITH THE GUIDANCE OF ASME SECTION IX. ) 1 WELD SYMBOLS: i V \\ \\ FILLET WELD FIELD OPERATION - MT \\ \\ ALL-AROUND MAGNETIC PARTICLE ~" \\ f\\ \\ LIQUID PENETRANT TEST BEVEL GROOVE WELD /\\. V WELD 4 FIGURE 1-5 GENERAL NOTES FOR FIGURES 1-4 AND 1-5 2 S//6M7 PJJ dsJ h 1 08/05/98PJJ BW /JRM 0 03/24/97PJJ BW JPF I REV OATE BY CHK APPD l POE TROJAN I NUCLEAR PLANT f OWG NO M _9259_ _ 2 I l REV g SHTJ6 OF Gl g _ _=-

DET AIL 2 (TYP) \\. / I 1 DETAA. 8 2 CLOSURE PLATES NOT SHOWN FOR CLARITY y, U '. *'~. t.o-(TYP) O } .Y"....

4.., ' '.

y'. - +4*g .i r e, - \\ / ,e ) \\ / s /'.Y \\ / ' ('. s / \\

  • 4

\\ ,/ + 9 f g \\ ,/ 'N N j 4, / g [ 'N. \\ \\ ,/ ,/ g/ f a.e,,'s,N g 7 ,/ / g..w' R s of y[

  • ks

\\ / 4, \\ % ,/', t \\ 'N, p' ,/ r .o pe 'g 4 e / \\ j p / i r '/ / \\ 4 a ...] I \\ l \\ s / e', / \\

  • e
  • g*s '

/ .-n } ~. I r .. ' * +. ,. 4 * * \\. '. ' s s .af '.t. .h: DET AA, 7 (TYP) I, i s l 1 FIGURE 1-6 IMPACT LIMITER CASING ASSEMBLY VIEW FROM END 2 5//pi/99 PJJ 72th b @E 1 08/06/98 PJJ BW /JMM N g: O 03/24/97 PJJ BW JPF i REV OATE BY CHK APPO 1. DIMENSIONS ARE NOMINAL UNLESS OTHERWISE NOTED. PGE TROJAN NUCLEAR Pl. ANT 8 OWG NO y.9260 REV i SHT.10Fh 2 hX

1 DET All 1 y=7(TYP)

  • \\

3', P E SC(i4'0ItiYP) S E NOTE 9 (TYl'% 2" THRE ADE HOLE IN 2". THREADED ROD \\ BRN SE W) (7* 2" LONG) (TYP) A g7 4 2" HEX NUT (TYP) ..p... g E_ . - _.. x '. U...,:,s. A TIEDOWN $1 RAP E _._.,_-.A., a '4 ,6 v. KEEPER (TYP) g y ,l } mm J. 2" WASHER (TYP) 'I

j J " *y* * *.. g

,.x w ,.,IM. q _ .l - -N,g _,: -- -- - t - - 1 4__

?

^ ] Ac*_ WTERNAL CER_ a f,g. emyvM-ST R AP-m=* :l -' %/j . :s ; (T YP;- j,j TitoOwN: {;. ] l t ~D .l; l 1* l* 3

  • g*

6 ~ i% V a '...l... '. - i i D ,{ h,- (( , [l 7: / "" ' oE,,, u7 OR p; 7 N HYP)

, ggggggq
    • '"*{~~~

~

ik 7

~~~! ~' [ VESSEL (CC) / i: l- ...i..

a i

a , l.-7.*~,a.. 3:_,h 6.- u '.s i a l

n
a i

/. ' uh. ~ : ~ m,.-_ y. 3 h; l 41. - s p w C= R ..L.,. ..,4:..'y l 1 P' / -..j..- svf e 8 WT @ PT (ON CASING FACE. I h. l THIS SOE ONLY) g li ( l 2 l._ 4 10" 3' 2" _l. '2 FIGURE 1-6 IMPACT LIMITER CASING ASSEMBLY REACTOR HEAD END (ELEVATION) 2 shs/qq PJJ1l$)k 1 08/06/98 PJJ BW 'JMM i NOT($: 0 03/24/97 PJJ BW JPF - : 3 REV DATE BY CHK APPD j 1. DIMENSIONS ARE NOMINAL UNLESS TROJAN s OTHERWISE NOTED. PGE NUCLEAR Pl_ ANT { OWG NO M-9260 REV 8 SHT.2OFM 2 l.2.CV

i 13 4 * (TYP) DET AJL 2 I, (TYP3 ,f r..; - 1 l i CLOSURE PLATES NOT l snoww roa etery (TYP) ,. ;

  • e Qt P :.y 3:. s

'O : / e \\ / p/ ...,/ = ~ \\ s' . ~.

  • Q.. '

r i ',.'#- y h. hf. s\\[\\ I. N\\ Ns \\ / / g\\ \\ / /e 'Q / j', ' y.W R '.E i 7 gif# i 2:3* m t-g _ g g j g ; --p__. f.h ;e 2 / 'g' l9 /t \\ \\ ,:e, /, s r / \\ yN l ,'/ l p s i r \\ \\ N i. / ,/ / 2, 's '\\, 's.c'

  • *g 5

'\\, ,..\\. / - 2" SHIELD \\ .\\ g .j /. PtATc g i \\ 7- ... K Q = \\~) s \\ / * / + 1 ' N ..? T* DETAIL 7 l (tYP) I i i 1 FIGURE 1-6 IMPACT LIMITER CASING ASSEMBLY REACTOR HEA0 END (ELEVATION) 2 S//gM9 PJJ 1b g 1 08/06/98 PJJ BW '0MM g N_plfjj: 0 03/24/97 PJJ BW JPF g REV DATE BY CHK APPO 5 1. DIMENSIONS ARE NOMINAL UNLESS OTHERWISE NOTED. PGE TROJAN 5 l NUCLEAR PLANT DWG NO M-9260 REV SHT.3OF[]2 j /2Y"

13 4

  • i TYP) s.,

10' .E C PT w l TO CLE OTHER COMPONENTS l N FOR CLARITY .s / f \\, / ,~~ s- \\ \\ .N w 4 'N, \\ N N Y / ,/ ,/ s~, x \\\\ /,- / N s 1 4 e / 's's. 's N \\l ,/ ' ff*. pf,, %s 'N N ii / p' m IT YPJ 'N '\\ \\ h' I' s - - - - - - - - -.-ey - +y- - - - - - - - -...-. g : I 's's s mx l \\\\ 's / j s \\ e i s / l \\\\ @g" 5,5.# f 2 N ,/ g 7[ 5" S LD g s. .y l b <s, (PW,' ' u,u 1 i i i i I 8 FIGURE 1-6 IMPACT LIMITER CASING ASSEMBLY REACTOR BOTTOM END (ELEVATION) e 2 5/24/99 PJJ N h W 1 08/06/98 PJJ BW 'J AM 3 NOTES: 0 03/24/97 PJJ BW JPF s REV DATE BY CHK APPO 8 1. DIMENSIONS ARE NOMINAL UNLESS TROJAN W OTHERWISE NOTED. PGE NUCLEAR PLANT DWG NO M-9260 REV i SHT.40Fh 2 g ar L

  • fifl0 '

\\ n y j rh tPM*ER _ _

  1. 2
  • PIPE'tSCHED.~40I(TYP) oETa 3

= SlE,WTE9 p E?es"&")*% be I [.... ...(p J- ~~~ rp M _________m OR PT \\ - Mig 2 g---*- } 3 p b_.. 1 d ^ f' TEDOWN 's

/

Y [ o,,, ${ w m P m _ _ _i A 5 '"" " 2 f/riefe TScTiE6. 40) tivs

== _ _ _ 3)_ --_----.--gyy63, - -cwm2.=-v., } WT OR PT ) %V m;; l WT OR PT

  • E* E* E "

~

  • NYi"""' * (

/ i . g : :::::rz : a + - +m +:+. + J s'(fflg 9 2 . -. - + :- + q, \\ g %V WT CR PT qREACTOR CON CASING FACE, NOZZLES TMS SOE ONLY)(TYP) f U l i __ w.en. 2 FIGURE 1-6 IMPACT LIMITER CASING ASSEMBLY REACTOR BOTTOM END (ELEVATION) 2 6/18 /99 PJJ lb) M 1 08/06/98 PJJ BW /JMM E NOTES' O 03/24/97 PJJ BW JPF 'g ITE'Q DATE BY CHK APPD 1. DIMENSIONS ARE NOMINAL UNLESS TROJAN I OTHERWISE NOTED. POE NUCLEAR PLANT l DWG NO M-9260 REV 3HT.5 OF 2 L1 Y i

1 WT OR PT /"V n i % ":a p 2x2xs .[j~- sd*!!L 2 Ig j [ [ s i y "#'!uTs n fen*"- \\% v Mt FOR WELOWC Fif-UP LWT OR PT DETAIL 1 DETAIL 2 - E- .h" [" d / ] 1 W, OR PT t f ~

"'s'a=g/rI*E "'

J==#" f / g[Mt1;gign i;AC#MToc"$v" 1 "" ~~ ~~ CATALOC 90,PWtf 5000) u*s"sEYs> g /, C & =- =- -w-a ni i \\ Q~i:~i: :~:B DETAIL 3 s J RO&?#,'ra'1.)6. iTv OF 3 s.. WT OR PT V {W///4h _/ ' %QJ L 4X4X% WT OR PT DETAIL 5 DETAIL 4 ' ANCLE ROTATED FOR CLARITY (TYP FOR BOTH NPACT LNITERs) FIGURE 1-6 IMPACT LIMITER CASING ASSEMBLY ASSEMBLY DETAILS 2 6//8tW PJJ1EL) h 1 08/06/98 PJJ 'B W /jMM g NOTES: 0 03/24/97 PJJ BW JPF s REV DATE BY CHK APPD l 1. DIMENSIONS ARE NOMINAL UNLESS NUCL LANT h OTHERWISE NOTED. POE DWG NO M-9260 REV ! SHT.6OFM 2 i LAY.

s12teis?e taw"'" A -,,,,,,,,,, c T T r,.g.g,. -Kk. -"ruc,,urc,f"asb / " "* " QrLf** "-"-"-"-"----"-"-"-"-"-r"- b"5%uf a"c9"'" R2 o FM ut oa' at (* My T [. $- \\

  • I'

. _.. g",, ;to= h' QQ"ha,1c .. o,tc,, f.-_ ro, =1ca~a u x1cos,1c s,to,ctos. <oc scc 1 c.c i o T.a'.a.ol..esss _. B C B M M M ...J f PLAN VM/MW W "' " " N e t s : :s : -, %V i SECTION B-2 V////W%% "M"$I

  • 41
  • ErE' os SECTION(C-C 2

WT oN ~* 2 2" THRcADc0 HOtc (TYP) aw -+ $y ? N ,5 f / j, / ? 7 [2* stect0 PLATc D. ,/. o D MA o r a -t+ -g V"' m r w nn ny PLAN SECTION D-D 2 DET AIL 6 "Tr*v'e' E p'tcE*"' FIGURE 1-6 IMPACT LIMITER CASING ASSEMBLY ASSEMBLY DETAILS 2 9/g/99 PJJ TL)U)4u. NOTES: 1 08/06/98 PJJ BW /JMM y 0 03/24/97 PJJ BW JPF 2

1. DIMENSIGNS ARE NOMINAL UNLESS REV DATE BY CHK APPD I OTHERWISE NOTED, TROJAN h

PGE NUCLEAR PLANT g DWG NO M-9260 REV i SHT.70FM 2 { L2r

L 2x2X% / WT OR PT3 f zs\\ % / \\ s ~~ 's, s ~~, ~~~,,'s-s ~,s 4 s PLATE %" X 8* \\ A (LENGTH AS RE N tNCTH AS REQUWtED) SECTION A-A / s L 2x2x% T OR PT PLAN DET All 7 A %" PLATE E wN STRAP gy) ] <!/c Tw PLATE 2%" DIA HOLE e .$ _ _E_ 27g,,- Hott .iuPAcT OdiTE.8 2 2" THRE ED y _ j'~ ROD (TYP) c

__-4 l

(., - .[

j. - - - - -. - -g-

... 4 l f DETAIL 8

  • c --- - M (T YP DETAIL 9

< TYPICAL 23 PLCS) FIGURE 1-6 IMPACT LIMITER CASING ASSEMBLY ASSEMBLY DETAILS 2 shs/99 PJJ 8 60 h 1 08/06/98 PJJ BW /JMM y NOTES: 0 03/24/97 PJJ BW JPF 1 DIMENSIONS ARE NOMINAL UNLESS REV OATE BY CHK APPD ! OTHERWISE NOTED. TROJAN y PGE NUCLEAR PLANT OWG NO M-9260 REV l SHT.8OFh 2 j m

e )

1. FOAM CASING STEEL IS SHOP FABRICATED TO FORM THE ANGULAR SEGMENTS.
2. CASING IS CONSTRUCTED OF %" CARBON STEEL, SA-516 GR.70 SUPPORTING BRACKETS CONSTRUCTED OF SA-516 GR. 70 MATERIAL.
3. IMPACT LIMITER FOAM IS CLOSED-CELL POLYURETHANE L AST-A-FOAM FR-3720 WITH A DENSITY OF 20pcf +/- 10X IAW BURNS AND ROE ENTERPRISES, INC. FOAM IMPACT LIMITER TECHNICAL SPECIFICATION 2030-M002.
4. IMPACT LIMITER FOAM JOINTSOMAY EE_ JQlNED WITH MANUFACTURER APPROVED EPOXY MATERIAL (A,S,R,Epgl RED)
5. ALL FOAM ENCASING STEEL SEAMS'WILL' BE CLOSED BY WELDING.
6. IMPACT LIMITER WILL BE ASSEMBLED OUT OF TWO (2) 7R CT

' SE'l RNOE'LII d 'b' ' EDG5 SHA L BE du ' F I ITH FLMGEJU,RF A,CE,AS, PR,ACT,1 CABLE, BEF, ORE IMPAqT, LIMIIER INST,ALL A, TION.

8. ALL' WELl)' SIZE 5 'ARE 'NOTAIN AL' ' ' ' ' ' ~ ~ ' ' ~ ~ ~ ~ ~ ' ' ' ' ' ' ~ ~ ~ ~ ~ ~ ~

9.iNE'Y$5'lHN[MIi[ND['hD3(([IShikbhhdkUl 3N[O ^ TO' SECURE TMFACT LIFwTER' ASBDELY.~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 10 5IEI.DN[3A 'LL' S2 ' PIE'dkiliUD'IN 'AfC6R'DdCYTVif((A[~APPI_lbABL ^ METHODS AND GUIDANCE PROVIDED IN ASME CODE SECTION Vill _ _ 3C,pS,p1 AS, AffRO,PJATE,, ,A

11. WELD NDE SHALL BE PERFORMED IN ACCORDANCE WITH THEDPPl!Ce&LE METHODS AND GUIDANCE PROVIDED IN ASME SECTION VillOR AFSC Aw3 01.1 AS APPROPRIATE.
12. WELDER QUALIFICATIONS AND WELDING PROCEDURES SHALL BE IN ACCORDANCE WITH THE GUIDANCE OF ASME SECTION IX OR AISC AWS 01.1 AS APPROPRIATE.

J ' N N FILLET WELD FIELD OPERATION - ur N MAGNETIC PARTICLE ALL-AROUND f\\ \\ -n BEVEL GROOVE WELD - LIQUID PENETRANT TEST ^ \\ FIGURE 1-6 V *E' IMPACT LIMITER CASING ASSEMBLY NOTES 2 5/r8/99 PJJ O% f 1 08/06/98 PJJ BW /J'MM y 0 03/24/97 PJJ BW JPF l ) REV OATE BY CHK APPD g j PGE TROJAN g NUCLEAR PLANT g DWG NO y.gygo_ _ REV j SHT 6 0V 4 2 a 72\\

pz i ATTACHMENTIII i to VPN-048-99 PROPOSED CHANGES TO GENERAL LICENSE CONDITIONS INCORPORATED INTO NRC LETTER DATED OCTOBER 29,1998, " AUTHORIZATION OF THE TROJAN REACTOR VESSEL PACKAGE FOR TRANSPORT" i

e Attachment'III. VPN-048-99 i June 1,1999 a Page1of1 Proposed Changes to General License Conditions Incorporated Into NRC Letter Dated October 29,1998, " Authorization of the Trojan Reactor Vessel Package for Transport" 1 By NRC Jetter from W. F. Kane to S. M. Quennoz, " Authorization of the Trojan Reactor Vessel - Package for Transport," dated October 29,1998, the NRC provided authorization of the Trojan Reactor Vessel Package as an approved package for shipment under the General License issued in 10 CFR 71.12, subject to specified conditions. PGE requests that these General License Conditions be revised to reflect the NRC's approval of proposed changes to the Safety Analysis Report (SAR) for the Trojan Reactor Vessel Package, PGE-1076. PGE also requests that these conditions be revised to reflect the recent Revision 1 to the Transportation Safety Plan, PGE-1077. 1 Specifically, PGE proposes an amendment to General License Conditions 1 and 4 to incorporate ) the Reactor Vessel Package SAR changes as described in VPN-048-99, Attachments I and II. General License Condition 3 would also be changed to reflect the recent Revision 1 of PGE-1077, " Trojan Nuclear Plant Reactor Vessel and Internals Removal Project Transportation Safety Plan," which was forwarded by PGE letter VPN-046-99, dated June 1,1999. The revised General License Conditions 1,3, and 4 would read as follows. 1. The TRVP as configuredfor shipment must comply with thefollowing Portland General Electric Company Drawings: M-9257, Sheet 1, Rev.1; Sheet 2, Rev. O M-9258, Sheets 1-4, Rev.1; Sheet 5, Rev. 2: Sheets 6-8, Rev.1 M-9259, Sheets 1-2, Rev. 2; Sheet 3, Rev. 0; Sheet 4, Rev.1; Sheets 5-6, Rev. 2 M-9260, Sheets 1-9, Rev. 2. 3. The TRVP must be transported in accordance with Portland General Electric Company's Transportation Safety Planfor the Reactor Vessel and Internals Removal Project, PGE-1077, Rev.1. 4. The TR VP must be preparedfor shipment and operated in accordance with Sections 7.0 and 8.0 ofPortland General Electric Company 's Safety Analysis Reportfor Reactor Vessel Package, PGE-1076, Rev.1. i}}

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