ML20046B829

Forwards Response to NRC Request for Addl Info Re Util Application for Transportation Cask Certificate of Compliance 9256

ML20046B829
Person / Time
Site:	07109256
Issue date:	07/30/1993
From:	Thayer J YANKEE ATOMIC ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYR-93-052, BYR-93-52, NUDOCS 9308060277
Download: ML20046B829 (47)

Text

..

YANKEE ATOMIC ELECTRIC COMPANY

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L W ;$)1 580 Main Street, Bolton, Massachusetts 01740-1398

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July 30,.1993 l

BYR 93-052 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

}

Attention:

Mr. Cass R. Chappell, Section Leader l

Cask Certification Section Storage and Transport Systems Branch Division of Industrial and Medical Nuclear Safety Office of Nuclear Materials Safety and Safeguards

References:

(a)

Docket No. 71-9256 (b) 12tter, C. Chappell, Nuclear Regulatory Commission to J. Thayer,-

Yankee Atomic Electric Company, dated June 17,1993 l

(c) letter, J. Thayer, Yankee Atomic Electric Company, to R. Bernero, l

Nuclear Regulatory Commission, dated April 12,1993 j

l

Subject:

NRC REQUEST FOR ADDITIONAL INFORMATION - CERTIFICATE -

l' OF COMPLIANCE l

In Reference (b), the Nuclear Regulatory Commission (NRC) requested additional l

information regarding the Yankee Atomic Electric Company (YAEC) application for a transportation cask Certificate of Compliance (Reference (c)). Attachment 1 provides-

[

responses to each NRC question. Attachment 2 contains the replacement pages for the l

Safety Analysis Report submitted in Refeience (c). If you should have any questions regarding the information provided, please contact Ms. Jane Grant at 508-779-6711.

l Sincerely,

~

YANKEE ATOMIC ELECTRIC COMPANY -

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ay K. Thayer Vice President and Manager of Operations ll' 0400E0:

p 9308060277 930730 D

PDR ADOCK 07109256' p

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l U.S. Nuclear Regulatory Commission Docket No. 71-9256-July 30,1993 COMMONWEALTH OF MASSACHUSETTS)

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WORCESTER COUNTY

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Then personally appeared before me, J. K. Thayer, who, being duly sworn, did state that he is a Vice President and Manager of Operations of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing document in the name and on behalf of Yankee Atomic Electric Company and that the stetencents therein are true to the best of his knowledge and belief.

}

YOx -L4+- -

Kathryn Gates Notary Public My Commission Expires January 24,1997 i

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Document Control Desk (Original + 10 copies of Attachment 2)

M. Fairtile, NRC, NRR E. Kelly, NRC Region I a

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U.S. Nuclear Regulatory Commission Docket No. 71-9256 July 30,1993 t

ATTACHMENT #1 RESPONSE TO JUNE 17.1993 REOUEST FOR ADDITIONAL INFORMATION CONTENTS 1.

Most of the radioactive contamination is present in the tube bundle region of the steam generator. Revise Table 1.2 to show that the radioactivity meets the concentration requirements for low specific activity, excluding the mass of concrete present in the steam drum and in the channel head.

t RESPONSE: Page 1-5 has been revised to explain that compliance with the low specific activity concentration limits has been determined using the volume and mass of the low density concrete in the tube bundle region only. Table 1.2 has been revised based on a low density concrete mass of 5140 kilograms. Results show that the contents of the steam generator in the tube bundle region are 79.9 percent of the low specific activity limit.

1 REVISED SAR PAGES: 1-5;1-6;1-8 2.

Provide copies of references 5.6.2,5.63, and 5.6.4.

RESPONSE: Copies of references 5.6.2,5.6.3, and 5.6.4 are provided as Enclosures 1,2 and 3.

REVISED SAR PAGES: None i

l l

i U.S. Nuclear Regulatory Commission Docket No. 71-9256 July 30,1993 ATTACHMENT #1 (CONTINUED)

STRUCTURAL 1.

Table 2.1 specifies the total weight of the impact limiters and the tie-down system.

Revise Table 2.1 to specify individually (1) the weight of the impact limiters and (2) the weight of any tie-down components which are a structural part of the package. The package weight should include the weight of the impact limiters

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and the weight of any tie-down components which are a structural part of the package. Revise Table 2.1 to specify the maximum weight of the package (note that the weight of the concrete is based on the minimum concrete density).

RESPONSE: Table 2.1 has been revised to specify individually the weights of the impact limiters and shear key assembly, which is the only part of the tiedown system that is a structural part of the package. For conservatism in calculating the weight of the package, the low density, concrete weight has been recalculated 3

based on a density of 24 lbs/ft. Procedural controls will be in place to ensure an 3

3 average concrete density of between 21 lbs/ft and 24 lbs/ft.

REVISED SAR PAGES: 2-9; 2-23 2.

Show the derivation of the equation X = [ D (2R,- D) ]" given on pages.2-18 and 2.10.5.1-5 of the application.

RESPONSE: The derivation of the subject equation is as follows:

2 2

X + ( R - D )2 = R o

o 7

X=[R - ( R, - D )2 )n 2

o l

2 2

2 n

no X=[R -(R - 2R D + D ) jn o

o o

R X = ( 2R D - D )w

& f J o-D 2

o DU il*i X = [ D ( 2R, - D ) ]"

i REVISED SAR PAGES: None s

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l U.S. Nuclear Regulatory Commission Docket No. 71-9256 July 30,1993 i

ATI'ACHMENT #1 (CONTINUED) 3.

The shear key design should be based on the base metal mechanical properties instead of those of the deposited weld metal. Also, the average bearing stress on the shear key should not exceed the yield stress of the base metal. Revise the tie-down analysis accordingly, i

RESPONSE: The shear key assembly has been redesigned in response to this comment. Three longitudinal shear keys, which are 6 inches wide and 26 inches long, will be welded to the shielding plate. The shielding plate will be welded to the package such that the middle key is located on the centerline of the package in the horizontal orientation, with the other two keys spaced six inches on either side of the middle key. The three shear keys will be capped on both ends by i

3-inch thick plates. The adequacy of this shear key design is provided in Revision 1 to Appendix 2.10.8, " Tie-Down Analysis," which is contained in Attachment #2.

REVISED SAR PAGES: 2-3; 2-12; 2-26 (Table 2.4); Drawing C-110-B-46063-1 (Chapter 1); Appendix 2.10.8 (in total) i l

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l u U.S. Nuclear Regulatory Com. mission Docket No. 71-9256 ' July 30,1993 -l ATTACHMENT #2 l i Replacement pages for the responses provided in Attachment #1 are included in this Attachment. The following are the instructions for Revision 1 of the Safety Analysis { Report for the transport of the YNPS Steam Generators. h REMOVE INSERT j (REV. 0) (REV.1) Title Page (Insert prior to Executive Summary) j List of Affected Pages - Revision 1 (Insert after l Title Page, but before Executive Summary) l 1-5 1-5 1-6 1-6 1-8 1-8 Drawing C-110-B-46063-1 Drawing C-110-B 46063-1, (Chapter 1) Rev 1 (Chapter 1) 2-3 23 29 2-9 2-12 2-12 + 2 23 2-23 2-26 2-26 Appendix 2.10.8 (In Total) Appendix 2.10.8 (In Total) l 1 i l i j ~,

O i l Safety Analysis Report for l Transport of Yankee Nuclear Power Station Steam Generators i i ) i i Revision 1 O 6 July 1993 ) 1 l i O

Docket No. 71-9256 Rev.1 ,a s LIST OF AFFECTED PAGES Revision 1 Chaoter 1 1 -5, 1 -6, 1 -8 Drawing C-110-B-46063-1, Assembly Outline, YNPS Steam Generators Chanter 2 2-3, 2-9, 2-12, 2-23, 2-26 Appendix 2.10.8 0' o O i

Docket No.-71-9256 Rev.1 J i _r~ by the low density concrete added to the interior of the steam generators. Reference 1.3.2 contains information concerning the radionuclide distribution in the contamination layer inside the steam generator U-tubes. A sample was taken in 1992 from an area surrounding a then open primary side manway of a steam generator. This sample was subjected to a series of isotopic analyses that determined the activities of the activation products, fission products and transuranics in the contaminate material. These activities were divided by the total activity of the sample to determine the fraction of total activity for each l nuclide. These data were compared to similar data taken directly from the primary side of a l steam generator during an outage in 1985. The radioactive nuclide fractions were found to be consistent between the two samples. However, the 1992 sample is more conservative and, therefore, was used to determine the maximum total curie content in each steam generator. Reference 1.3.3 contains the finalized nuclide distributions used to characterize the source term in the steam generators. These distributions have been decayed to July 1,1993. The radioactive source activity by nuclide is shown in Table 1.2. This table also shows the A, value of each isotope from Appendix A of 10 CFR 7? and the allowable concentration per gram of contents for each isotope determined using the definition for low specific activity material given in 10 CFR 71.4. These O-data are used to determine the total number of A values in each steam generator, 2 and the fraction of the low specific activity limit for the contents. The value used for the mass of the contents is calculated using the volume of the steam generator interior over the 18-foot length of the tube bundle multiplied by the concrete volume fraction calculated in Section 5.3.2.1 (86.4%). The mass of the concrete in the tube bundle region is calculated to be 11,300 lbs (5,140 kg). Based on the given values, the number of A values in each steam generator is 108, and the 2 contents are 79.9 percent of the low specific activity limit. Because the number of A values is greater than one, the contents are classified as a Type B quantity of 2 radioactive material (10 CFR 71.4). However, because the low specific activity limit is not exceeded, the steam generator packages are exempted from certain l requirements for Type B packages, as discussed in Section 1.1.

1.3 REFERENCES

1.3.1 " Source Term Characterization of Yankee Rowe Steam Generators", Curt - Lindner, CNSI Design Document NU-252, March 1,1993. i 1.3.2 "Nuclide Fractions in the Steam Generators and Pressurizer", Pete Hollenbeck, YRP 69/93, February 17,1993. + O i 4 d 1-5 i

Docket No. 71-9256 Rev.1 1.3.3 " Characterization of the Steam Generators and Pressurizer", Pete pv Hollenbeck, YRP 82/93, March 2,1993. 1.4 ASSEMBLY DRAWINGS i The following drawings are provided at the end of Chapter 1: C-110-B-46063-1 Assembly Outline, YNPS Steam Generators C-110-B-46063-2 Nc2zle Containment Details, YNPS Steam Generators (Sheets 1 thru 4) C-110-D-46063-3 Impact Limiters, YNPS Steam Generators (Sheets 1 and 2) C-110-A-46063-4 General Notes O i O 1-6

Docket No. 71-9256 Rev.1 Table 1.2 YNPS Steam Generator Source Characterization Isotope

Activity A2.

LSA Limit Spec Act* Fraction of M of. Cl I m CI ' Vaive mci /g m Ci/g LSA Limit A 2's Am241 4.21 E-02 4.21 E + 01 0.008 0.0001 8.19E-06 8.19 E-02 5.26 Ce141 1.04E-05 1.04E-02 25 0.3 2.02E-09 6.73E-09 Ce144 2.93 E + 00 2.93 E + 03 7 0.3 5.70E-04 1.90E-03 0.42 Cm242 6.17E-03 6.17E + 00 0.2 0.005 1.20E-06 2.40E-04 0.03 Cm243 2.58 E-02 2.58E + 01 0.009 0.0001 5.02E 06 5.02E-02 2.87 Cm244 2.58 E-02 2.58E + 01 0.01 0.0001 5.02E-06 5.02E-02 2.58 CoS7 4.29E-02 4.29E + 01 90 0.3 8.35E-06 2.78E-05 CoS8 1.68E-01 1.68E + 02 20 0.3 3.27E-05 1.09 E-04 0.01 I Co60 9.31 E + 01 9.31 E + 04 7 0.3 1.81 E-02 6.03 E-02 13.30 Cr51 5.12E-05 5.12E-02 600 0.3 9.96E-09 3.32E-08 Fe55 2.29E + 02 2.29E + 05 1000 0.3 4.4 6E-02 1.4 9 E-01 0.23 i Fe59 7.28E-04 7.28E-01 10 0.3 1.42E-07 4.73E-07 Mn54 7.32E + 00 7.32E + 03 20 0.3 1.42 E-03 4.73E-03 0.37 Nb95 3.45E-02 3.45E 4 01 20 0.3 6.71 E-06 2.24E-05 N 59 8.78E-01 8.78E + 02 900 0.3 1.71 E-04 5.70E-04 } NiS3 1.02E + 02 1.02E + 05 100 0.3 1.9 8 E-02 6.60E-02 1.02 5 Pu238 2.50E-02 2.50E 4 01 0.003 0.0001 4.8 6E-06 4.8 6E-02 8.33 Pu239 3.77E-02 3.77E + 01 0.002 0.0001 7.33E-06 7.33E-02 18.85 Pu240 3.77E-02 3.77E + 01 0.002 0.0001 7.33 E-06 7.33 E-02 18.85 Pu241 3.53E + 00 3.53 E + 03 0.1 0.005 6.87 E-04 1.37 E-01 35.30 Rul03 2.03 E-04 2.03E-01 25 0.3 3.95E-08 1.3 2E-07 Rul06 1.81 E + 00 1.81E + 03 7 0.3 3.52E 04 1.17E-03 0.26 Sb124 1.8 4 E-03 1.84E 4 00 5 0.3 3.58E 07 1.19E-06 Sb125 1.94E-01 1.94E + 02 25 0.3 3.77E-05 1.2 E E-04 0.01 I Zr95 1.29E-02 1.29E + 01 20 0.3 2.51 E-06 8.37E-06 IOTALS 441 Curies 0.799 107.69

• Based on a content (low density concrete) mass of 11,300 lbs (5,140 kg)

(Section 1.2.1.2). 1-8

5 1 4 l x( SHIELD PLATES'(AS REQUIRE IMPACT LIMITER (C-110-D-46063-3) 2-1/2" THICK (MAX.) 5/8(MAX n 6 . m' / 1 i 1 l l i g j s s 7 \\ __._g_._ e g i s w s / 3/4 l !;'L_.L!.L W n p HAND HOLE (2) 44 (REF.) = 3/4 q + 208 REF. (17 ft. 4 in.) r c 409 REF. (34 ft.1 = 487-3/8< i NOTES: [ 1.) GENERAL NOTES PER CNSI DWG. C-l 2.) PENETRATION COVERS, PLUGS, SHIE n - - + - - - TO BE FABRICATED FROM ASTM A-I / 3.) FILL INTERNAL VOLUME, BOTH PRIM 4g_)74 LOW DENSITY CONCRETE (MINIMUM 4.) COAT EXTERNAL SURFACES. E l f 6 (TYP.) SHEAR KEYS -=-. IMPACT LIMITER NOT SHOWN 6 (TYP.) g _y&. y f

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i / gy g-4 -m e 44 (REF.) ___l 3/47 32 = = INtIT SHEAR MEY k 208 REF. (17 ft. 4 in.) r = 409 REF. (34 ft.1 c.) { r c e i i 487-3/8 (40 ft. 7-3/5 in.) i NOTES: [ 2.) PENETRATION COVERS, PLUCS, SHELDING AND SHEAR KEYS l l PROPRIETARY l N NON-PROPRIETARY l 1.) GENERAL NOTES PER CNSI DWG. C-110-A-46063-4 ]I~"' --~ ~~~ ~ TO BE FABRICATED FROM AS?W A-516 GRADE 70 MATERIAL f . J.) ru mtRNAL votuwE. mm PR=ver wo sEcoNDmy, wTa 7 l7,o,1 54653 CHEM-NUCLEAR SYSTEMS, INC. tow otNsin c0NcREtt (unuuu 2i ts/co. n. oENsny). 4._,f, j y 4 coAr ExitRNAL suRrActs. ASSEMBLY OUTUNE a /"YEla.ydk YNPS STEAM GENERATORS "An 'MW m

• ("P-) A d S"Em1m

")-7 J 54' ~ B C-110-8-46063-1 1 e cnr.) _.J wrAct tuntR Nor sno.N = NcrscAtt mut -a__a. a. x a_,, J 1ge u y-o, i i,,, f <J ~ ~. -

Docket No. 71-9256 Rev.1 O conform to the outer surface of the steam generator, and attached by welding. As shown in Chapter 5, the maximum thickness of shielding that will be required to meet the limits of 10 CFR 71.47 is 21/2 inches. Impact Limiters impact limiters are provided to protect the package in the unlikely event of a one foot drop condition as specified in the Normal Conditions of Transport. The impact limiters protect the package in two ways; by limiting the stresses in the steam generator shell, and by ensuring that none of the containment penetration covers strike the impact surface. The impact limiters consist of a welded carbon steel shell which is injected with polyurethane foam. In case of an impact, the impact limiters will strike the surface first and deform to absorb the energy of the impact. Their depth has been sized so that the crushing during impact will not be great enough to allow penetration covers to strike the surface. Two impact limiters will be mounted on each of the packages. Each one is toroidal-shaped, and has a rectangular cross section. The impact limiter used on the steam drum end (herein referred to as " Impact Limiter No.1")is 24 inches wide and 16 inches deep. This limiter will be centered approximately 71 inches from the steam drum end of the package. The impact limiter used on the channel head end (herein referred to as " Impact Limiter No. 2") is 24 inches wide and 18 s inches deep. This limiter will be centered 44 inches from the channel head end of the package. Each impact limiter will be fabricated in four circular segments that will be bolted together around the circumference of the steam generators, and will be held in place by botting attachments on the impact limiter shell to the trunnion mounting plates on the steam generators. The adequacy of the impact limiters is demonstrated in Section 2.6.7. Shear-Key Assembly The longitudinal movement of the package during transportation is prevented by the shear-key assembly. Three longitudinal shear-keys, which are 6 inches wide and 26 inches long, are welded to the shleiding plate. The middle key is located on the centerline of the package in the horizontal orientation, with the other two keys spaced six inches on either side of the middle key. The three shear-keys are capped on both ends by 3-inch thick plates. The adequacy of the shear-key assembly is demonstrated in Section 2.5 of this SAR. 2-3

Docket No. 71-9256 Rev.1 in accordance with these requirements of 10 CFR 71.45(a), any structural parts of the package that could be used for lifting the package during transport will be rendered inoperable. i 2.2 WEIGHTS AND CENTER OF GRAVITY i The total weight of the YNPS steam generator package, including shielding, concrete, impact limiters and the tie-down components which are a structural part of the package, is approximately 273,000 lbs, or 136.5 tons. Itemized weights of the various components are given in Table 2.1. e The center of gravity of the package is located on the longitudinal centerline, approximately 17 feet - 4 inches from the end of the channel head. The calculation for the location of the center of gravity is provided in Appendix 2.10.1. 2.3 MECHANICAL PROPERTIES OF MATERIALS The materials of construction for the components of the steam generator package are shown in Figure 1.1. These materials and the minimum specified mechanical properties for these materials are given in Tables 2.2 and 2.3. The values for these mechanical properties were derived as follows- ? (q t / ASTM A-212. Gr.9: ASTM A-212 is no longer a material listed in the ASME Code. Under these circumstances, Regulatory Guide 7.6 (Reference 2.1) states that the ASTM Specification for the material should be used. Accordingly, the mechanical properties for ASTM A-212 were taken from the ASTM Specification for that material (Reference 2.4). ASTM A-266. Gr.Il & ASTM A-516. Gr. 70: Mechanical properties for these materials have been taken from the ASME Code, Section ll, Part D, Subpart 1 (Reference 2.5). E70 Electrodes: Mechanical properties for the welding electrodes were taken from ANSI /AWS D1.1, " Structural Welding Code - Steel" (Reference 2.6). l The design stress intensities (S ) for the component materials constructed of ASTM A-266 and A-516 were taken from the ASME Code, Section 11, Part D, Subpart 1 (Reference 2.5). The design stress intensity for the ASTM A-212 material was established using the method given in the ASME Code, Section Ill, Appendix 2. 2-9 r

Docket No. 71-9256 Rev.1 OV 2.5 LIFTING AND TIE-DOWN STANDARDS FOR ALL PACKAGES 2.5.1 Liftina Devices The steam generators will be placed in a horizontal position while being prepared for shipment, and will not be lifted or moved into any other orientation during transport. Lugs on the steam generators will be rendered inoperative prior to transport. Therefore, there are no permanent mechanical or welded attachments to the steam generators that can be used in lifting the steam generators while being transported off site. 2.5.2 Tie-Down Devices During transport, each steam generator package will rest on two saddles made of structural steel as shown in Figure 2.1. Saddle No.1 is located near the tube sheet and Saddle No. 2 is located near the transition cone. The steam generator package will be secured to Saddle No.1 and to Saddle No. 2 by five,13/8-inch diameter tensioned cables. Each saddle will be secured to the trailer / railroad car bed with clamping blocks attached to the transport vehicle. These transport vehicles will preclude movement of the saddles during transport. The saddles, along with the tensioned tie-down cable, will resist inertia forces associated with transverse and vertical accelerations. Three longitudinal shear keys, made of 26" x 6" x 2" plate, will be welded to the supplemental shielding which, in turn, will be l welded to the steam generator. The longitudinalinertia load will be transferred from the steam generator to the shear keys to an assembly of wide flange blocking beams adequately secured to the trailer / railroad car bed. Figure 2.1 shows schematic sketches of the tie-down system. The longitudinal shear keys are the only parts of the tie-down system that are structural parts of the steam generator packages. These shear keys are designed to withstand inertia load associated with the 10 CFR 71 specified longitudinal acceleration value of 10 g. The parts of the tie-down system that are not a structural part of the package have been designed in accordance with the acceleration criteria of ANSI N14.2, " Proposed American National Standard For Tie-Down For Truck Transport of Radioactive Material" (Reference 2.7). Additionally, the allowable stresses in this part of the tie-down system will be i based on the AISC standards, which are more conservative than the corresponding allowable values in the ANSI N14.2 standard. The complete structural analysis of the package under the loading specified in 10 CFR 71 is provided in Appendix 2.10.8. The summary of calculated stresses and a comparison with allowable values are listed in Table 2.4 All of the calculated stresses are less than the allowable values. 7 2-12

2 Docket No. 71-9256 Rev.1 1 Table 2.1 Calculated Weichts - Steam Generator Packace and Convevances l Component - Calculated Weight, Ibs ' Steam Generator and Internals 187,200 i Water in Plugged U Tubes' 600 Shielding 49,200 l 2 Concrete 31,200 Shear-Key Assembly 800 Impact Limiters 4,000 1 Total Weight of the Package 273,000 = 136.5 tons j 1 I Notes: i The plugged U-tubes are most probably filled with air. However, as a conservative measure, it is assumed that all the plugged tubes contain l water. 2 The weight shown is the maximum weight to be added externally to the packages. The actual weight will depa-upon the amount of shielding actually 6dded to the packages, based m final radiation measurements. 1 Using the maximum concrete density of 24 lbs/ft. l I f i t ] I l 2-23

Docket No. 71-9256 Rev.1 O Table 2.4 Summary of Stresses in the Structural Components (Shear Kev Assembiv) of the Tie-Dawn System item Stress Allowable Calculated Category Stress" ' Stress ' Allowable (ksi) (ksi) Stress"' Shell Shear 22.8 7.0 30.7 Bending 38.0 23.8 62.6 Shear Key to Normal 38.0 22.18 58.4 Shield Plate Weld Shear 22.8 18.96 83.2 Shield Plate to SG Normal 38.0 29.3 77.1 O Shell Weld Shear 22.8 21.2 93.0 I Notes: (1) See Table 2.2 for the yield strength. (2) Allowable stress in shear = 0.6 x yield strength. (3) See Appendix 2.10.8 for the detailed calculations of the stresses. (4) Calculated stress / Allowable stress x 100% i i i t h O 2-26 ~f r v . - - =

O APPENDIX 2.10.8 TIE-DOWN ANALYSIS Revision 1 O I e G l t 9 I O

e CNSI Project #46063 Chem-Nuclear Systems, Inc. %*l** N 2 1,4. 7p, TITLE PAGE OF fob No "" 3* Q BY lMN OATE 1IMIB g STRUCTURAL mECHARICS couwswTs Transportation of V DATE1I I D- """""""* RSSOCIRTES Yankee'Rowe Steam Generator CHKD.BY v '- FIEF. 1. OBJECTIVE: To perform steam generator tie-down analysis. II. DESCRIPTION / LOADING CRITERIA During transport, each steam generator package will rest on two saddles made of structural steel as shown in Figure 1. Saddle No. 1 is located near the tube sheet and saddle No. 2 is located near the transition cone. The steam generator package will be secured to saddle No.1 and to saddle No. 2 by five,1/," diameter-prestressed cables. Each saddle will be secured to the trailer / railroad car bed with clamping blocks attached to the transport vehicle. These clamping blocks will preclude movement of the sacdles during transport. The saddles, along with the prestressed tie-down cables, will resist inertia forces associated with the transverse and vertical accelerations. A longitudinal shear-key assembly has been provided at the bottom of the steam generator to transmit longitudinal inertia load from the steam generator to the blocking beams which are adequately secured to the trailer /railcar bed plate. The longitudinal shear-key assembly consists of three 26" long x 6" wide plates welded to a 2%" thick 5 shielding plate which is welded to the steam generator with /," fillet weld. Figures on page 2.10.8-3 and 2.10.8-4 show the schematic sketches of the tie-down system and longitudinal shear-key assembly. l l The longitudinal shear-key assembly is the only part of the tie-down that is a structural part of the steam generator package. This assembly is designed to withstand the inertia load associated with the 10 CFR 71 specified longitudinal acceleration value of l 109. The parts of the tie-down system that are not a structural part of the package have been designed in accordance with the acceleration criteria of open-top loading of the railcar, which is more stringent than the ANSI N14.2 (" Proposed American National Standard for Tie-Down for Truck Transport of Radioactive l Material") (Ref.1). Additionally, the allowable stresses in this part of the tie-down system are based on the AISC standards (Ref.2), which are more conservative than the corresponding allowable [ O values in the ANSI N14.2 standard, i r I l u

e CNSI."roject #46063 Chem-Nuclear Systems, Inc. 'LA * *I

• /. alo.

CHD1003. 3 p O k ^'"3 " CJ *""Y p' DATE 7I 1 93 - RSSOURTES Yankee'Rowe Steam Generator CHKD,B W-REF. Ill.

REFERENCES:

1. ANSI N14.2 (Draft), "American National Standard for Tie-Down for Truck Transport of Radioactive Material", September 1986. 2. AISC Manual of Steel Construction, Eighth Edition. 3. " Design of Welded Structures", O.W. Blodgett, The J.F. Lincoln Arc Welding Foundation. 4. " Local Stresses in Spherical and Cylindrical Shells due to External Loadings", Welding Research Council Bulletin No. 107, K.R. Wichman, et.al., August 10,1965. IV. ANALYTICAL METHODS The longitudinal shear-key assembly is the only part of the tie-down system which is a structural part of the steam generator package. The shear-keys and the end-plates are welded to the shielding, which in turn is welded to the steam generator with 5/8" fillet welds. Stresses in the welds have been evaluated using weld analysis method described in Ref.3. The maximum stresses in the shielding plate have been evaluated using analytical methods given in Ref.4. The stresses in the steam generator wall, which is thicker than the shielding plate, are enveloped by the stresses in the shielding plate. O I

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• N #

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i e CNSI Project #46063 PAQ[b.8 OF4 2'lD'P[Ob No CHD1003 Chem-Nuclear Systems, Inc. TITLE ~gg STRUCTURRL y I; Husaw cars 7lbIS3 mECHR0lCS COMMENTS Transportation of 'j """""""" RSSOCI ATES Yankee 'Rowe Steam Generator 7 2s 93 1 y-CHKD.BY DATE f MEEhl Y EM b E 1 M L.5 REF. Pl' E JD ppe%y m- / ,/ e I J G =4.~ - r, ' j.w.a_q-. ir y_ = f ?!:2 g', M,- .; _y c-i i sc- = t== = n=3w c=l= -:21 w=:- m==ew.w , u = .w,,qu-v =a: %3 . _ _ '..;jm t l. \\ \\,w o ( q y .?u+ / )_ v-a. mp. .e s. ), g~ _ L _/ Ji

f.

nin IL [ _3 'f13-1 l h-d. 7' / W "i m.a% t's (

N N

./ L+ f l D s .,= f =N.-l lr ",O "2 h __l-O ! l [. "f JI's ; yp imu% R& f -[-- w _; L . _ I _. _J / L_. _I s' .me '/ trcnm A-c i Y 9 i luy / Shdl L.] l .c 5 hear \\/ -_e i \\ i i i i 4 +- /\\ \\,,/\\ / g g i NN 3./ / \\x y 7 J / 9 C ,l _/'. d x'N /C F m. x s s 'N 2'N _tM*' l / st i < tn x m h ~i w/ w p 7D 7/% w / _R \\@l / 7 _1 A 4 sw j jL = i. ) m.a sw a w ^{ scum i 3 rs - w its. 2 6 Y b,x 6kpu K.4 y 3 i Mr4x. Ecccabfcih Eg: _e.gt+4,ig) zgs 3, g, g s f d O t " e ham 6 m 4 M n sguq % := soxt.75 =. 32 55 2. V tn w m nr.e, u% u w.a n up Ge@= MsizyQ z

== 5 %% at /r 8 4 if / ef // @ --r.y.kdH 5'29/2 "' E' CM

4 CNSI Project #46063 Chem-Nuclear Systems, Inc. H 0+F-5 24e.e L o VITLE PAGE OF Jof> No CHmdO3 g STRUCTURAL 3156.,3_ mECHR0lCS couuENTs Transportation or l bS*4AjA DATE 2 SY OCHKD.BY W RSSOCIATES Yankee Rowe Steam Generator DATE 1 bl 2 REF. E N tJ f\\ L'( 7 \\ c f\\L C EL cut A7 TONS Y.1 b ETs \\ Gtt LoAb5 Steam Generator Calculated Weights

Component '

Calculated Weight, Ibs Steam Generator and internals 187,200 Water in Plugged U-Tubes' 600 2 Shielding 49,200 Concrete' 31,200 Shear-Key Assembly 800 Impact Limiters 4,000 Total Weight of the Package 273,000 = 136.5 tons besrgm A cc e kro boe }w L%ghbl %er Ke ys: 10CFR71.45 lorss i t ud a r.41 108 wi thout, materi al yielding. Lou (4t;Jf M Lc.w J V = zu. o 'x i o = 2 7 3. ), oK g y i l .I O

a CNSI Project #46063 Chem-Nuclear Systems, Inc. 'I O'0*h Ll* f *,# p CHEM 003. I. sy 1, h sm A Days 1 i i IE iTIECHRnKS COMMENTS Transportatico of l ND """"" RSSOCIATES a ee R w steam cenerator l CHKD.BY DAyE lI I W" EZ DESTCd OF LOM6riTuhdAL S HEAR key 3 ag, 3 " Tu s tK setbM E et3h P LkTES ; 8 c our mg tai de (At h %c3 iq, bs e 2 75" 1 B 4 0x0w [\\y_co - 3 o y 7,,.75 5 61 5 W 6 7_7 3 o o - ' S + tg ~ re.53 ~ 0 Sz S 33.t K ST 2 IA \\ \\ o WrAN E hT t %) esl C Fq n 3 6, o \\tT '3 L s oo = ST 1 ]s

• /, k i,

= y ss.o 16 "y G Ix 1 S e e-fa WW S,' O' D hbeu u L 4 Sbe *Y sm, ~ hv, 2 o 6 66m g { 6. bl+ /+ 1 (,} 7 7 b YEA be.k LOEt AA Ib W CMS

• SIN

( 3. 3 sa us) +3 1 s _b 1 ) G. 'tf \\ N '1 = 5 9 ' W Y \\ ND 'Tobd b.R n e t u (\\rPA = 2.730io ~ M oy, broccl us 5 TE 5S " ,{g 34.3 N lo o{ M io w A A,, 34 3 y)oo if 2 56 o 90 3 /D I

CNSI Project #46063 { Chem-Nuclear Systems, Inc. PAoD ' Obr

• b No """ 3 TITLE g g STRUCTURAL Sy \\ 4 WO-DATE 7:\\ ): s i IECHRRICS coWWENTS _ han8Portation Of

/ CHKO.SY DATE7I*l - RSSOCIRTES WN vanx.. now st... cenerator i T.3 5 HEW WE4 f 5 H \\ELb %, LJEELb REF. 5 M ht V-E4 bescR\\P Tt o ra, LE 26'k("x YTitice PL Alt 3 um 3/.4 I m 1 A LoAb5 g ,g y get g gg pq V = Y*o - 31 o. o K. L 3 Eccmhtci43 e = g [ 5 62 44r 1 Q 7 75 -2 5. 615 L v q d w h d M o m w i-M u - 91 cn3 415 = K Loi, v b = Z. 6 A ~ 3 'p /.1 " 3-w et a Q sa

1. 1_

y b cC31h/C_ b4' C,N-Mg $g {c 0 75 ~ (Qc fp A.GL 4 042') Froe I%p 17_-Boj Re}. 3 TABLE 2-Properties of Thin Sections' Where tMckness (t))s sinall, b = man width, and d = mean depth of section V i [< [ V y 7 seo.on e l s-if r b + d) N (3 b + di t d'(2 b + d) t d*(4 b + d) t d8 f 4 b + d) t ters-7' 12(b + d) 32 6 3 (b + 2 d) 3 2 (b + d) ~ t d'(4 b + d) 1$(2 b + d) 1 -(4 b + d) 6 :2 b + d) 3 6 [(4 b + d) (6 b + d) (3 b + d) g, i d* ( b + d) t d' (4 + d) 6 3 (b + d) 6 (2 b + d) e bottom

• bottom
• top 1,

. g (b + 3 d) $ (b + 6 d) tM t b8 12 6 6 13 12 (b + di t b'(b + 4 d) 6 (b + 2 d) g, L b (b + 3 d) N.(b + 6d) rigbt side t b' t b8 8 8 8 M ( b + 4 d> 6 left side * [D 1 uletJ brea : Em> o.~15 A Q b&'l(o) :: 4r8 O l'n g % noh ks L = c 75 y 2 L t 3x L+20/3 o = 2 e co (%,3

i CNSI Project #46063 chern-Nuclear Systems, Inc. , 'Io E 7.io.yio No cnotoca. Tm OY I. U b < ruv DATE 7120t'15 mECHRniCS couuexTs Tran8Portation Of OCHKO.SY DATE 7l**193 """""" RSSOCIATES W aum'W% Yankee Rowe Steam Generator REF. "'9 ' shear stvets e ue u h b Vu =

e. o (v = 159GKsi Tews 1 6 h ess tw v)e)J b b. Mg =.

3 190 2so k=11.s KSC c=%d ued shess = (@ QYL e {oe.%M n.sf} E oo \\ q. KSE mu %s% wo mwa=s=o.. es {q",j c c,o me ewm = o.h h s%r = o. L y G o = M u W 73 D[ hMo*UC key C w hAvud UJEN SA 6#5'S [ 22AE 73 y

't g,,

6> o. o S h e_o y sh e55 '/ 4 'e ej yf90 :- 52. ] O C ' ~' 9 i y fe\\1 Shve M hh tg 33,o y. n n. c m =ms g + + '^ """ " " ""~'" " *"~"=T' E ? O foY w g 52 4

== 5 6 r w eiA s + r e s _" 18

• w iw 17 8

== % 3.1 (a *lo y 52.*7 y ..m.

e CNSI Project #46063 Z 10 S'-\\3 2 qo.g. Iob No C" 03 Chem-Nuclear Systems, Inc. o TITLE STRUCTURAL PAGE OF BY l.Ntt h AAA DATE7 Ih1% ITIECHROICS couwswis Tran8Portation Of D b, W ASSOCIATES Yankee Rowe Steam Generator I min 1I i CHKD.EY DATE l Table 5-Cornputation Sheet for Local Stresses in Cylindrical Shells REF. P M cfyL M C V M

1. Appl 3.d L...s

• 3.

G meenc P.n.m.t.es C 45 E - r), go _ L/ [V R. dial t..d, P lb. R. = 7 t i Circ. me at, .c - in. Ib. T g,r'O Du' Y JN.K D e ROUND L.. w... s. .t T...i. sa. Ib. tv - (o.875) 2, ATTACHMENT = sk, L d,

v..

16. R. Au g, g sk, L..d. vt, S D ~ M, j 5 - y-'n f see.ss C e.ne,.,;.a do...: I 1

2. G

.+ry .). bron. l..d. Ka - - 0 lg AL ^ 5 0,,, u 6 d4.,i..d.L6 - R. Cu C h/ v..s.:, hic k..ss, T L in.

• NM L Ent.e.ll force I e.s in An.ch., e.d.ve,

= Vess.1 e. dies, R M* Den. .cc.ed.ac e wish. ion coa.eaei.a g F r.* R d c.,..s Compur. 6s.lve...l s of $T R E15ES - el i..d is.pp.shte th.t shown, e...,s sign. shown F l e. 4.e ste.se.ad entee e sule * ~1. .L Bu BL C. CL 09 DL )*RmT ac "a P/Rm P/R. (,.*). s. 6P ,uf R. ~ .a .a f3 ../ R f R. O T ~ L- -L::o)R:"JT. - MMM@ .L/ R.#d .L/ R aff R. f T b + C MMWAM a::: -L::u) R e .o+......_ . y . s... e4 f 4C K. \\PfR.! R.T P / Rs. -(9).g. ,c -(.., ,) Rch, - MMPXdR ..";R.., 4. -l A ) R2,. - DJslPjglMMg .y @6%)fCF . ";..o - -( ' a) R.%, - -m $$llMRRRlPgd '::t.:l-y- - L ::y) R 2. - -ss .,R......... . r.g ggggggygg . a: - ... - s YL 7 - O +10 + 7. 0 ~ re T Add.lg.bea6e.tly 6.e s - '.n .. si.; s....,. 7.o 7o '). o ~1. o Co.BINED STRESS iMTEN517Y,5

6.. 4 e f(np - c P + 4 a

5= i;f $ & Wa N n n r-o s. w,..e,e..., I og - n. I 2.M 8 8 1

3) who.ap & a, Ir 4ra 6,,,,, ts,.3,,,

g top - n.): {

CNSI Project #46o63 Chem-Nuclear Systems, Inc. STRUCTURAL PAGE2.lo,y.bF"2 ' t o

• Tr-10 cu m o'os.

ME Job No I' DATEl IM 115 mECHR0lCS couuENTs Transportation or BY CHKD.BY DATE 7Ia 93 """"" RSSOCI ATES nurl ~ I W-Yankee Rowe Steam Generator REF. 3 4-f TRESSE5 i hi 2 6 "TM )C.vt $; HEh9. W SHIELb lt, as \\ ta cx bJ R C i 07 METMOh5 Er f:ach zc"x vyf " Pa>, SWV Load %=O K y, g,\\d vJ L o+.A Fy: = %d g =- 91 o x 3 615 = 5 2 > 0 % I"- %vs Re k emcr & Table 4--Sign Convention for Stresses Resulting from Radial and Moment Loading on a Cylindrical Shell "L*Wu 1/ WQ' C s== Q=3 NQ i i re, C 2 -= 2G_ : )3 'j O i e. g* x PECTANGUL AR ATTACHMENT 4.2 Parameters The results of Bijlaard's work have been plotted in terms of nondimensional geometric parameters by use of an electronic computer. Hence, the first step in this procedure is to evaluate the applicable geometric parameters y and B. 4.2.1 SHELL PARAMETER (y). The shell param-eteris given by the ratio of the shell mid-radius to q

• _' 86 + Z c5 shell thickness thus:

L T y = R,/T = 45 * *7 5 T = 2. c.> " 4.2.2 ATrACHMENT PARAMETER ($). For cylin-y _,._ e 75 - g3,9 o drical shells, either round or rectangular attach-ments may be considered in the following manner: E'S 4.2.2.3 Rectangular Attachment Subject to Radial Load (P): For this case s is evaluated as follows: Bs = -f On = - ( E="

0. o 6 g(,

As 73 f3 c.ugt = 2 S i o.ocac n %2= c-c. LO l +s.73 = 4.n3 t

CNSI Project #46063 Chem-Nuclear Systems, Inc. .j o.g. z.gog $$ No Camo63. Tarts STRUCTURRL PAG I~ b% oars 711i193 ITIECHRnlCS couwsNTs Tran=Portation of cY O CHKD. BY """""" RSSOCIRTES W6 DATE I I W-Yadee Rowe Steam Generator REF. 4.2.2.5 Rectangular Attachment Subject to Longi-tudinal Moment (Mz). 4.2.2.5.1: When considering membrane forces

• (N,): # = #g, g,s.

Then multiply values of N,/(M,./R.'#) so determined by (Cz) from Table 8 (see para. 4.3). 4.2.2.5.2: When considering bending moment (M,): B = K,.fg,g,2 where K,. is given in Table 8. Table 8-l.ongitudinal Moment (M ) t th/p. Ki for e Ks for Me Ks for M, Cs for N+ Cs for Na Ii1 d.-- NRA- !'.!ab N e e, $fb h$ Nors: The values in parenthesis determined by an approximate solution. Ftr ce s, ( N t' ) . Fo r Medw a b* 0 o68G.( o.2.971[ = C. I 623 r by 'q C M,= o 6 75 4 L t by taxe i.\\95 For b~diq Mowogt (tq() t P = k t_ f F [L [ 2-o.\\&7_.3 K _ L i e Fe c Mo K u.

o. gcr7

= (5 = 0 697 x o.18 2.'3 c-c. T (,. ~5 E:, bc Mx E = 1 2. 3 G 5 - @ = \\. 23 G G x o,16 z3== o, 2.2_5 4 5 4.3.3 STRESSES RESULTING I' ROM LONGrrUDINAL MOMENT, Mr. 4.3.3.1 Cirrumferential Stitsses (a ): Follow the 5 steps outlined in 4.J.2.1 except that [N /(Mr./ R.2#)] is obtained using Fig. 3B; and [M /e (Mr./R 8)], using Fig. IB or IB-1. It follows that: \\ N, ~ N, ~ ~ Mz ~ 5

• M /R.*p.,

R.*T6. t l GM; M, ~ ~6M ' t 5' ".M /R.B. .R.BT t

CNSI Project #46063 Chem-Nuclear Systems, Inc. ~l 8 0 +-1 7 lo,P-}ob No CH MO53. o TITLE STRUCTURAL PAGE F 1 svIb43 oATE7 IMt94 mECHR0lCS COMMENT 8 han8Portation Of OCHKD.SY NT """"" RSSOCI ATES DATElI I W-Yankee Rowe ;, team Generator REF. I From Ft gtive 3 E, Py 7. i o. g T 't , Wr S== o \\ B 23 V= \\7 5 o y \\,9a , C u.= o. 4 7 5 fg[Jp_ = N, N, Af,, - Y ~ Mt/R.,'p_ _ R,,, r d ~ X l- \\* 9 o X 32 9o xo,673 1 C dr. 84 Y-5( ( D 7 53 y 2 5 ay o. t $ 7,3 fro m Fio u re i S, P$t 2ios-t7, Ftre S = o l G 53 g ~ Af ~ 7 -:= 1 ~l s o 4 . Af,/R.S.

GAf,

. M,_ - sy,- T* _Af /R.B. _ R.B T'. t D 04'5 x 6 x 'LZ'10 b' 43 75 x o R I 5 X (?_< 5M ~ \\ 9 0 4.3.3.2 Longitudinal Stresses (er,): Follow the 5 steps outlined in 4.3.2.1 except that [N,/(Af,./ R.24)J is obtained using Fig. 4B; and [Af,/ ( Af /R,,,d)], using Fig. 2B or 2B-1. It follows t that: N, F N, M - j t ~ (.M lR]B _R,,,'S T. T t GM, M, ^ ~ G M z. ' T' M /R,,0. _R,,,6 T*. t Fi g u ve +Ys, Np E t o e,- t o, b @ = \\"3 From Y = %5 6 O ~ N' ~ , C u== i 195

0. Go

.M /R,,,*p. t Nr ~ Nr ~ ~ Mr ~ g~ o. 6 c x 3L 9 0 x \\.195

== 9 '] m T .M /R.*B. _R.*BT~ ~ '{qLlS)Ly0.1823y z,,5 t i

s CNSI Project #46063 Chem-Nuclear Systems, Inc. 2* lot-17 240t-7_o Cu m o'os TITLE STRUCTURAL PAGE OF Job No I Mv W oATE~1IRI93 ITIECHRniCS couwexTs Tran8portation of my CHKD.SY DATE 7 l 2 l 93 y_RSSOCIATES yonx. noy, sto,, con,7,to, REF. frOMA kpc 2.T> [y 1 to. g - lB, fW =0 ?26@ D : Ile E Af> o.o 57 =. _hi /R 6. t G M, ~ M,

• GM ~

t T' . M t /R,,,0. .R pT*.

o. 0 5 7 x 6 y 37-9 o

_ __ \\83 Wsi _~ tu. 75 y e 215+x (2 507 4.3.5 STRESSES RESULTING FROM SHEAR LOADS, V,AND V. Bijlaard has proposed

• that shear t

force (V) can be assumed transmitted to the shul entirely by membrane shear force. Therefore stresses in the shell at the attachment-to-shell juncture can be approximated as follows: 4.3.5.2 Rectangular Attachment V e - e Vi t = 4c,T vu=q300 x c _, _ p a 3 ",. 7 = 2. s o i V i I r,, 4c,T c; j o, c, = = 1.o up 4 x 13 X 7_ S o )

a ~ CNSI Project #46063 Chem-Nuclear Systems, Inc. g.iot 4 ?. 4 % O CIIEM003. p sY \\ ' b C8dh DATE 712693 mECHRnlCS couMENTS Transportation of 1 ~7 2'31 91 fankee Rowe steam cenerator 1 W" CHKD.BY DATE REF. Sa F u t_e T ue Lt> bema em 2.s" 7 mcg E5 f B E A Y-t7-S H ELb 1. tb 5 TE AM &a4EEATOR yh/2 = \\7 " .m' , _;. m

• a' lld u

) /[ 5/ / 8 k i l- } -}? EQechw 'TWe%wcM' j hc o G o'7 x 5 c-D. LW 19 v4 I \\.;J t ) Ecc eo [4s : o. 4 4 ) 9 ( \\ 'LA ' 5 + 2 x@ 7_ = 12 6 5 9 M i $ 2 c.h w R e lu\\u3 $ w :- o. M i i > @ O * ~ lt O

3., LY L,2 i 2 b I"3 2-730*

E LoNdtdtud 6hs L as,\\ o, E c cedg ay e c 6's-&2S Mo + M + s,ts 1 25 'L-2_ 5. G 'L 5 " De N}# R6vMwI ~" 2-7 0 * $krcGS. M M VM d ';~ 2_g30 0,g[ \\'d csy, $ hoy -- 2 \\, 2 o W -N St(' ,d A A b b M c.q,'; G 1, ') 5 ( '/ ff if ,g 10.2 \\@ O MbiLAJLk Mh dYf J-S :: k),2. -(24 2-h 21 3 Ksl ) I

3 CNSI Project #46063 Chem-Nuclear Systems, Inc. 2.< fo,S-16 1 lo. CHEM 003. O \\. ASDAA - DATE 712.cl93 mECHROKS COMMENTS Transportation of 3Y CHKD.BY DATE7 1 3g91 , _ R E CATES y nxe now, st, conor,to, 2 REF. i C b O. Cd W O bf C 4 bf V E. \\ IOA Q1e* sk wc nu sw = o.t6 . a. 6 v_ L o = 3 6,o W Fo tr bac. AW ytdA stv2.rs v6 = 33,o% z G o. o V& 't 'i 't = o G Y 56 < c) Sh.or 'l 'i 'i = u t wW LE6.or.>g b O '- M w /, 4 msm a s,9x a~u-; v3eu y o % 7'. 3 sisesa== 2' 3 3r YY Y b N) 'g' // If // o/ Z l, = 91 o /0 12,Fo O I

v s CNSI Project #46063 Chem-Nuclear Systems, Inc. mte P A Gl.) o.f(-l h., 7.t o.t-?_o camoo3. g STRUCTURAL c Job No sy\\<Husma DArs 7 l'7493 MECHANICS COMMENT 8 han5Portation Of DN """""" ASSOCI ATES n# s CNXD.sY DATE I I W-Yankee Rowe steam Generator 13L. .6 uF) M hky o F RE S ut 75 REF. omyo we# /gEygs s o wwe vawe nao-uc Vcriaa 3 " thick FEA Ruw EOb R.5, MM E-enty Skycss (wsg 3, '2_C'<6"y4_ gy;g s g w a s M 4 Scarrg shreM (Es0 34 0 37,o cJ o.2 2p". ~1 (AELbg ikhoce vi S h Ehk KW 5 LK SB\\G LD R. N d)L. 5htpy $brer.S 1 Ih W{ d bbSi) IE*% 77 90 8 3. @ O mm_1mosus aso m ss,e es.4 z.b." T eic' 5 ycht it W )s aiELb VL. May. Mewdnaue. + Bhdmg Shec53 7 .t 3 7,00 s.a (_ LSQ /< S h e > 'r Sk WS Chh 1o 'Z.1. t'o 30 7 5gpgutg1 uELb E v_%x E n 5 MEhR. ge( 56\\Ei D R. 4 57 t=M\\ GV U-t'k y. Sh-e ox sh YCG [_ E b4') ?I.2 'Z 2 > T O 41 0 emw;d adA stress Cub 29.2 3 7< o ni I I

a CNSI Project #46063 Chem-Nuclear Systems, Inc. 1 STRUCTURAL PAaE @8-TITLE Llo O o o No CHDiOO3 OLd DATE 7 m 63 mECHA0KS CO W ENTS Transportation of sy Ml8 DATE 7 pg % "'"='"""" ASSOCl ATES g ' WN Yankee'Rowe Steam Generator CHKO.SY REF. ': n r g_.% j a_ R.__ i v 96

=

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== .w. = a=-='= :-q=.1 y =:-

. 24

-2 = =

p : =

.- p i i

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c 4

m.. ~ ~ ~ ~h: !* --~ c. s., my l a_ -- a =

== a =- 4 4 a 1 = = = = as' L

C

= 9 T a ~ ~ N:& s jW g g4 '.; s2r_ =7E5UU 5.1 --'i

.=._

- l 5 a = F~ = $5 ' '-K-- - --644 j-3 J Er -- '#W W t'<> h W "'~+i

C r

= = 3: = o'o4 3 .-n ---a-,as

vzp..p.g%

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1. imMewmr mag N:x s

p+g .w 24 2, - -e

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;P i

E 'N 2 l' 1 m mo, u*o-4 9 a 2, c E -- *= 1 4 'E -t i '*:r: #91 ?'NF7 i4 'S ij n5-f }id r 2% r = 4':- = = g_y_ ST E= = y ) .E-E =5. u2:' a fi i=k%_qgzhi% ) i_ ': iq=,5 ? [Eu= p3=' +'E =-1 ? as o ic a-1 ana m_ -9, 3 em,.<mse >.~.;m4" s .nnac v,- a o e. n a=-_< ? ' =3 um J x-u e h 4C j. i._[ [~ h g~ i 5 ? w5_ g:; h =% l B" 'h 1 3 i &. : Wh -: +? =i v-s 2 s? =i t..,-=: _q:g... g Q"=Tj-h.h'ty....3- -;= -( E==sz 4 ,= =, .:===-:-r=

== = . jg -;gjgy_ ,;y g

z7.:: : ::.

= annxgh s -y---- -q::::-car

=

c dd: ny-tzg:-rt+m -2::: .h m 2 n g-;g-4 i-H l ' d: 1 -d INi -_.T.I, ' I I I 1 I 1 f l 3m ' I i. E H T E.'N '"'i4'.- 1 hj ,A1 Y j m 2%.- '_t i _3 ii. 1'A 1 e_ . A: a M'M -- -. b 'I S ---6 f- _-.i= _ c_. _, p.u.- -- ej.c. 2p ,.s.- y cy:-- :. -._r..-.4_ 5 [( [5 l ;d) h J.pd

'uj-j ' f5 :-1:~' yj.".j. ;----i:litt=

= E _~-[ j-.ig-f r 7 Q:

w ?'

i9mi sqqisi f

~ - ;MeRa = ? 1 s+%2 y , 7 4 r a ha aR-; 42-1442 u ds:-i - - #4 L-L l ^ a e O s.. a @dd2. g_i.4'i Z..[ _.:ild -i .M 7 .gr -(_p i 3r

i 2

p Hj: - se 4sE4MM.Mdhg +tM:MiE4E= W ism-%: rdpa%da _r+-

t--t -r, t

- T' r tr d: ._.m -+ f . +- ^ 4 I I I o om 0;o ge, o c2s o so on oso oss oso 1 xternallongitudinaGrr.oment'M on a circular cyhnder) Stress on the k>ngitudmal Fig. IB-Moment M,/(M /R $) due n i 6 plane of symmet'y) 42 Strenca in Shells

no u o. O s n Q N e z o a o u w e o e e m C a~ w O .O. 2 u o 4 Po00 9 R @ H"O k 4 "' O W .n O Q. u& = m O g f., e a N }4 3 M M h eg O i.~ m

o. a nigiqu a.u w ( m_. m.u,ik-o4 wt xm.

a +4.. - r r. m..u mmEh. 'o m m ..mHrd',r F,- m mnr,r+m o. inw w:ew u pl mm' ; y# a e s.w a i-f v r m+, ~ ',wv.ntwn m new 3 uo r. -- r i:. if +4 .tv

• ThW"@. c a.t 1--

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1. e Pm

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1. n y >=

7 4M,mg/ 4 -m,. @nMF A e En.+t-nn.igiw&iiHR- .quh NOi; + Hj a - 74? em y T,- u fim rm ~r+v, 94 o n-n,r n e,e,re* pti-- w o rr - mw mm e y . *Ar O -gh. m . w m4 m . h 11 -.nr em l.+f~ ~"o = r gs d-ih "mn v m ttt tt O e ,p*r rM trrtH"+t*hM~Wh+ t-i. r / b mr e .eti b a. o 4 r r r-a r s V W+% +% c 3.. @ My/ mj*H qt %*MW JF { 4%WR i 4r - .r -t~:ttr e"Qyt*- 9 #M a ct) "-+rr *'""*", t + t* P n 1 mt* m, ... 1 7 ~f ig"r 7 7 ~h,:?k-a IT g (v_g) W q1 n '?? 't** ,a..p . + t- *tM j 'h qt. t TS . r. --f4 g' '

• v-

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7ttp" wp.$ an M

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• -,#. 7,. '. '4'.M.

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rith d

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1. }

u a. >= t~ a T. w$ .a o J Y t: 6 = e a 9 O 9

m O k 'or o n M e x o = 4 e ,.o u. e m o o a. w w Z 0 p g O DE 4 Ili . g "o k e .n g "3 o e O 6 Q. M pi. O-(D U3 M C a e H p p 3 v3 g, t* O* ty O = +.: .i, y.4pm - wumm @"g.. a g - m g w - e m, swm - mmfbp .m ij q.; m q ..h;. g .q,g 1r -- m . m,r-a m g n m x y , -m n,. 7 m n e,in yn 3 ~ 1, m h :*M mg drtt1 H y pm - m + mm i ib-i .s W [ s ipqij r PM,T l.- " 6,W n %g-- - % -mi 1 s mT; {4gn"it

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q y

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:, a m t n

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