ML20128E564

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Forwards Revised Pages to Convert Rev 10 of OH-142 SAR to Rev 11.Polyurethane stress-strain Upper Bound Curve Revised to Include Response Noted from Recently Fabricated Overpacks
ML20128E564
Person / Time
Site: 07109073
Issue date: 06/12/1985
From: Temus C
NUCLEAR PACKAGING, INC.
To: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20128E257 List:
References
25415, NUDOCS 8507050374
Download: ML20128E564 (29)
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Text

{{#Wiki_filter:^ a 7/- W'za ~ Mf73 NUELERI PR[KRGIMG ~~ cn June 12, 1985 File: OH-142[ 4108 Ref: Mr. Charles E. MacDonald, Chief Nuclear Regulatory Commission f ygg) / Transportation Certification Branch Washington, D.C. 20555

Dear Mr. MacDonald:

Enclosed please find eight copies of the revised pages to convert Revision 10 of the OH-142 Safety Analysis Report to Revision 11 of that report. Also enclosed is the required check for $150 to initiate the minor revision process. The changes made to the Safety Analysis Report are of three types. First, the polyurethane stress-strain upper bound curve has been revised to include the response noted from recently fabricated overpacks. The new upper bound has been analyzed in Appendix 1.10.2, with margins of safety being affected only very slightly. Second, a customer has requested the option to mount the primary lid seals on the cask body rather than on the cask lid. The drawings have been changed to allow this option. Finally, the maintenance section has been changed to allow the user to apply any halogen leak test that meets the same technical requirements as our NuPac-specific test. This revision, including the revised drawings, has been copyrighted. This entire submittal contains proprietary information per the notice on the flyleaf of this report. We are aware of your requirements to place this submittal in the Public Documents Room. This may be done with our permission; however, this permission should not be construed as a waiver of or in any way prejudicial to our lawful proprietary rights to this material. It is done only to facilitate the issuance of a Certificate of Compliance. k=Y [ (o (j@$./HD."Qfh[p[,;y; s ,T 'e wc e q a un ) ,,c.gx-y ,m Mb Y e,tr110M 'l k LOCRti CLEM y s 8507050374g5h73 gg,(d (( W.T '/ DR ADOCK 7 PDR Nuclear Packaging Inc.1010 South 336th Street Federaf Way Wavam;Mn 9300J C06 87 2 2235 Tele 206397 PANS UR 1G AV I(! h

4 June 12, 1985 Mr. Charles E. MacDonald, Chief Nuclear Regulatory Commission Page 2 Photontatic copies of this copyrighted material may be made by NRC review personnel for convenience and for record purposes within the Commission's files; however, permission to copy the material is expressly denied to persons other than Commission personnel or for any other reason. Copies of the material may not be released by the commission except to the Public Documents Room. If you have any questions, please do not hesitate to call either myself or Stephen Goetsch. Thank you very much. Very truly yours, NUCLEAR PACKAGING, INC. M'I v q; Char es J. Temus Tec nical Director

Enclosure:

As stated cc: Francis Dewberry, Westinghouse Hittman 1

s' 4 1 DOCKET NO. d 2,1 CONTEOL NO. oi mem -~ i, <sw ~5 DATE OF DOC._ d([/ (( DATE RCVD._ Oh }398[ FCUF__ PDR. FCAF LPDR_ WM_ I&E REF. WML'R SAFEGUARDS FCTC OTIIER__ DESCRIPTION: fdWOJ rg l 8 _ INITIAL _

~ g& .e NRKLEARpw e PAC <FETNG A PacefH: Nuclear C AmDany June 12, 1985 File: OH-142 Ref: 4108 Mr. Charles E. MacDonald, Chief Nuclear Regulatory Commission Transportation Certification Branch Washington, D.C. 20555

Dear Mr. MacDonald:

Enclosed please find eight copies of the revised pages to convert Revision 10 of the OH-142 Safety Analysis Report to Revision 11 of that report. Also enclosed is the required check for $150 to initiate the minor revision process. The changes made to the Safety Analysis Report are of three types. First,.the polyurethane stress-strain upper bound curve has been revised to include the response noted from recently fabricated overpacks. The new upper bound has been analyzed in ' Appendix 1.10.2, with margins of safety being affected only very i slightly. Second, a customer has requested the option to mount the primary lid seals on the cask body rather than on the cask lid. The drawings have been changed to allow this option. Finally, the maintenance section has been changed to allow the user to apply any halogen leak test that meets the same technical requirements as our NuPac-specific test. This revision, including the. revised drawings, has been copyrighted. This entire submittal contains proprietary information per the notice on the flyleaf of this report. We are aware of your requirements to place this submittal in the Public Documents Room. This may be done with our permission;' however, this permission should not be construed as a waiver of or in any way prejudicial to our lawful proprietary rights to this material. It is done only to facilitate the issuance of a Certificate of Compliance. 9 e 4 [g RECEIVED. 3 1 2 JUN 13 GS5 > \\[ (f.S. NUCLEAR REGULATCRf .}. C0!nSSION \\ t;E3 l%! kct c4 g W (n y, Nuclear Packaging Inc.10to South 336th Street Federal Way Wa shington 98003 (206)874 2215 Telex 296397 PANS UH a )

y June 12, 1985 Mr. Charles E. MacDonald, Chief Nuclear Regulatory Commission Page 2 ~ Photostatic copies of this copyrighted material may be made by NRC review personnel for convenience and for record purposes within the Commission's files; however, permission to copy the material is expressly denied to persons other than Commission personnel or for any other reason, Copies of the material may not be released by the commission except to the Public Documents Room. If you have any questions, please do not hesitate to call either myself or Stephen Goetsch. Thank you very much. Very truly yours, NUCLEAR PACKA ING, INC. Y. Stj, Char es J. Temus Tec nical Director

Enclosure:

As stated cc: Francis Dewberry, Westinghouse Hittman

NEPa3 OH-142 SAR Rev. 11, 6/85 MODEL OH-142 SHIPPING CONTAINER s REVISION 11 ~ DELETION AND INSERTION INSTRUCTIONS Delete Insert 4 1-3 1-3 1-7 1-7 Dwg. No. Y-20-201D Rev. N Dwg. No. Y-20-201D Rev. M Sheets 1 thru 2 Sheets 1 thru 2 Dws. No. Y-20-202D Rev. E Dwg. No. Y-20-202D Rev. L Sheets 1 thru 2 Sheets 1 thru 2 Dwg. No. Al-20-202 Rev. H Dws. No. AL-20-202 Rev. J Sheets 1 thru 3 Sheets 1 thru 3 Dws. No. A1-20-203 Rev. G Dws. No. AL-20-203 Rev. H Sheets 1 thru 2 Sheets 1 thru 2 1-147 thru 1-159 7-3 7-3 7-3-a 7-16 7-16 l l l l {

MnPa3 OH-142 SAR Rev. 11, 6/85 package is located at the' approximate geometric conter of gravity. A refer-ence point for locating the conter of gravity is shown on Drawing Y-20-200D. 1.3 Mechanical Pronerties of Materials The Model OH-142 packaging uses an outer and inner shell fabricated of various thicknesses of low carbon hot rolled steel. Material properties of the steel are as follows: A-516 A-516 A-36 (Grade 60) (Grade 70) Per MIL-HDBK-V ASME ASME 55,000 psi 60,000 psi 70,000 psi F = tu 36,000 psi 32,000 psi 38,000 psi F = ty 35,000 psi 36,000 pst 42,000 psi F,, = 90,000 psi 90,000 psi 90,000 psi F = brg Rigid polyurethane foam fills the cavity between the steel shells of the overpack. This material will have a density of approximately 20 pcf and be of a self-extinguishing variety. Figure 1 represents the stress-strain curve for the NuPac NPI.F6 foam used for this package. The curve provides both minimum and maximum compressive properties derived from over 8 years of testing. A 95% probability factor was applied to the standard deviation to establish the spread shown. Foam Specification NPI.F6 defines the detail foaming testing procedure. It specifies that foam samples will be taken during the actual foaming process and tested to verify that they are within the two curves at 10%, 30% and 60% strains. Typically one sample is tested per batch of foam, and one overpack may include as many as 6 or more batches. Occasionally, a data point from the test of one sample may f all outside the range specified. In such a case, several more samples are prepared to verify that 95% of the foam tests do fall within the curves at 10%, 30% and 60% strain. 1-3 i

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e3 ._..w.....- ~., ~% / )s;' D 2. MATERIAL : ASTM-A514 on A517 i . [' ^ 3. FOAM: 1,000 PSI CRUSH STRENGTH RIGID POLYURETHANE. PER NUPAC FOAM SPECIFICATION NP!-F6. [ A i 4. LEAL: PER FEDERAL SPECIFICATION QQ-L-171E, CRADE A OR C. ~' P ~ M h OI 5. REMOVED 6. REFERENCF DATA: CASK WT: 54,000Las. PAY LOAD: 10,000tss. e '5 GROSS WT: 64,000Las. 7. REMOVED 8. ALL WELDING PROCEDURES AND PERSONNEL SHALL BE QUALIFIED IN ACCORDANCE WITH ASME CODE, SECTION IX. C ~ 9. ALL WELDS SHALL BE INSPECTED VIA NDT METHODS AS FOLLOWS: LIFTING LUG AND CIRCUMFERENTIAL CONTINU0US TCP VIE 1 SHOWING OPTIONA WELDS: MAGNETIC PARTICLE PER ASME CODE SECTION III, DIVISION I, SUBSECTION NB, ARTICLE NB-5000 AND SECTION V, ARTICLE 7. LONGITUDINAL SHELL WELD: RADIOGRAPHIC PER ASME CODE SECTION !!!, DIVISION I, SUBSECTION NB, ARTICLE NB-5000 AND SECTION V, ARTICLE 2. 10.ASANOPTION,12GA.NO.304STAINLESSSTEELCLdDDINGMAYBEINSTALLEDON THE INTERIOR & EXTERIOR SURFACES OF THE FLASK BODY 8 INTERIOR SURFACES OF ograit 9 ) [ogran,. THE UPPER LID, & SEAL WELDED ALONG ALL EDGES a SEAMS. r - u _,.;._..

11. PAINT ALL EXPOSED CARBON STEEL SURFACES WITH ONE COAT CARBR0 ZINC !!

j s ONE COAT PHENGLINE 305, OR ONE PRINER C0AT (5 MILS) ( g,. MOBIL CHEM EP0XY NO. 80W9 4 ONE FINISH C0AT (5 MILS) MOBIL CHE'i E? OXY yng NO. 89W9. kl6 -

12. COAT ALL EXPOSED EXTERIOR SURFACES OF FLASK BETWEEN UPPER AND LOWER OVERPACKS WITH ONE (1) C0AT (MIN 3/16 THK) "ALBI-CLAD" NO. 89. AS AN OPTION, A 10 GA. NO. 304 STAINLESS STEEL THERMAL SHIELD MAY BE INSTALLED PARTIAL SECT A. A SHOWING OPTIC BETWEEN THE GVERPACKS.
13. FLASKS FAERICATED PRIOR TO 3/84 MAY BE MADE USING ASTM-A36 MATERIAL.

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NmPas 08-142 SAR Rev. 11, 6/85 t APPENDIX 1.10.2 EXPANSION OF ACCEPTABLE STRESS-STRAIN RANGE FOR IMPACT LIMITERS 1.10.2.d Introduction Due to minor changes in the formulation of the NPI.F6 polyurethane foam used in the OH-142 overpacks, it has become apparent that some foam placed in accordance with it may not exhibit stress-strain properties as shown in Figure 1 of Section 1.3 above. Some samples of foam taken during fabrication activ-ities indicate that the upper bound of the stress-strain curve in Figure 1 should be raised. The revised limits of the stress-strain curve are shown in Figure 1.10.2-1. An analysis of the effect of this revised upper bound on the package margins of safety is presented below. 1.10.2.2 End. Imnact The end impact drop orientation is the drop orientation most seriously affected by the revised foam properties. NuPac's EYDROP program is used to evaluate the force s generated from a 31 foot drop onto an unyielding surface. EYDROP, like its sister programs CYDROP and SYDROP, has been used to demonstrate compliance of several other packages (such as the T-3 Spent Fuel Shipping Cask, Certificate of Compliance No. 9132, and the NuPac PAS-1 package, Certificate of Compliance No. 9184) to the 10 CFR 71 drop events. Table 1.10.2-1 presents output f rom EYDROP for the OH-142 using the revised upper bound of the stress-strain curve as shown in Figure 1.10.2-1. The table was generated using the equivalent outside diameter of the package. This equivalent diameter is calculated by determining the actual end area of the overpack and finding that diameter of a circle which has the same end area as the actual overpack. Also, the analysis assumes the entire overpack area is effective, corresponding to both the most conservative assumption presented in the body of this report as well as the results of numerous test programs. 1-147

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HnFas 08-142 SAR Rev. 11, 6/85 TABLE 1.10.2-1 EYDROP(ENO3 PACKAGE HE!OMT e 64000. (LBS) PACKAGE O!AMETER e 100.34 (!N) Nott DIAMETER e 55.00 (1N) OVERPACK DEPTN e 14.00 (!N) DROP MEIOM7 a 31.00 (FT) ++++ INPACY ++++ ++++++ ENEROY ++++++ CRUSN DEPTN STRAIN FORCE 4CCEL. KINETIC STRAIN RAf10 (1N) (LBS) (0) (IN-L S ) (1N-LSI (SE/KE) .25 .014 1490224. 24.4 23824000. 211278. .009 .50 .028 3340453. S2.8 23440000. 445113. .035 .75 ,042 3070679. 79.2 23856000. 1901505. .080 1.00 .056 6197042. 94.8 23472000. 3309970. .139 1.25 .049 445S697. 100.9 23884000. 4491542. .20S 1.50 .003 6633053. 104.4 23904000. 4533904. .273 3.75 .097 6479108. 107.5 23920000. 4229176. .344 11 7018933. 109.7 23934000. 9944431. 416 .[25 2.03 .s 7119234 111.2 23952000. 11733702. 490 2.25 2.50 .139 7192218. 112.4 23944000. 13522633. .544 2.75 .153

7244524, 113.2 23944000.

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7811504, 125.0 24112000.

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~ Nhrmo 05-142 SAR Rev. 11, 6/85 The table predicts that for the revised stress-strain limits, the acceleration experienced by the package womid be 117 s's, slightly higher than previous analysis had predicted. The predicted deflection, 3.94 inches, is slightly less than previously predicted. As a result of this analysis, the margins of safety predicted for the secondary lid closure bolts are affected slightly. For the 24 inch opening, the bolt force would be: P = (3098 lbs.)(117 g)/ 8 bolts = 45308 lbs./ bolt i The associated margin of safety is then: M. S. = (56000/45308) - 1 = +0.24 For the optional 29 inch opening, the force in the bolts may be calculated as follows: P = (4186 lbs.)(117 g)/ 8 bolts = 61220 lbs./ bolt The margin of safety for the 29 inch opening wonid be: M. S. = (75750/61220) - 1 = +0.24 Therefore, the revised stress-strain limits do not affect the ability of the package to resist the effects of a 31 foot end impact onto an anyielding surface. 1 1-150

1 Nuana 08-142 SAR Rev. 11, 6/85 1.10.2.3 Corner Innact The change in the 1,typer bound of the stress-strain curve causes Cases 3 and 4 discussed in the body of this report to be obsolete. Tab l e s 1.10.2-2 and 1.10.2-3 present the same drop orientation (approximately 40 degrees from vertical) as previously analyzed. From the tables, it can be seen that the maximum acceleration experienced by the package is 77.2 s's, slightly higher than previously used for design. This slight increase in the package acceler-ation (77.2 3's versus 76.4 s's used previously) will have an affect on the package primary closure device design loads. Using the method shown in the Safety Analysis Report to be very conservative, the loads in the ratchet binders can be calculated: (19900)(77.2)(38.125)eoa 400= (1011660)(15.83) coa 40 + 0 + 2(38.125)P (3.5) b t Pb = 122,195 lbs. per binder The margin of Safety for the binder is then: 1 M. S. = (160,000/122,195) - 1 = +0.31 f 1 { { 1-151

MmPao OH-142 SAR Rev. IL 6/85 TABLE 1.10.2-2 CYDROP(CORNER) NUCLEA4 PACEA0tNO PROPRIEfARY 07.19.11 S S/ 04/ 04 OH-142 PULL SS INCN NOLE PACKAGE NETONT e 44800. (L83) PACKAGE EXf ERNAL LENGTN e 120.30 (!N) PACIA0E EXTERNAL DIAMETE9e 101.00 (!N) PACKAGE EXfERNAL NOLE DIAe SS.88 (INI PAYLOAD ENVELOPE LENGTN e 44.30 (IN) PAYLOAD ENVELOPE DIAMETERe 74.00 (!N) DVERPACE LEHOTN e 40.08 (IN) De0P NE!ONY e 31.e4 (FT) ORIENTATION ANGLE 40.090 (DEGREE 3 WRT TO VERf!CAi) a PLATEAU CRU$N STRESS e .00 (PSI) (DEFAULT TAEEN Af 10 PCT STRAIN) $fRE13/ STRAIN EVAtuATED IN 1/2 CRU$N PLANE ELLIPSE Afe NX e 25 POTNi$ PARALLEL 70 $EMI-MtNOR ELLIPtE AKl3 NT e 23 POINTS PARALLEL TO SEMiaMAJ04 ELLIPSE A113 EXPERIMENTAL STRAIN VS. STRE33 VALUES PT STRAIN sfREss 1 0.as 0.0e 2 .09 1100.00 3 .10 1230.00 4 .20 1330.88 5 .30 1490.00 4 40 1730.00 7 .30 2220.00 4 .60 3470.00 9 .70 7000.00 le .40 !!000.48 CYDROP(CORNER) NUCLEA4 PACEA0tNO P40PRIEfARY 07.19.11 85/04/05 e. ON-142 FULL 33 INCN N0LE ++ CRUSH PLANE ++ ++++ IMP ACT ++++ ++++++ ENERGY ++++++ Ot3fRISutt0N OP STRAIN RAf!OS SY CRUSN PERCENT QP CONTACT AREA DEPTM AREA V0 TUNE FORCE ACCEL. KINEf!C sfRAIN RAf!0 Lt.70 07.70 07.30 of.te of.SS (!N) (IN2) (IN3) (L83) (0) (IN*L8) (IN-LO) (S E/ KE) LE.40 LE.90 Lt.95 .50 11.9 3. 2281. .0 23:4eets. 170. . css os.0e s.00 0.00 e.00 e.se ).00 33.6 14 12940 .2 23472000 4375. .000 04.06 0.00 0.00 0.00 0.00 a.30 61.5 34. 35004 .S 25904000 14361. 00L 00.00 0.00 0.80 0.00 0.00 2.00 94.4 77 44309. 1.0 21934400. 41649 ,002 00.00 0.0e 0.00 0.00 0.00 2.30 131.4 134 }09174. .4 23944000. 44941. .604 00.00 e.80 8.00 e.00 0.06 1 00 172.0

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~1 itemme OE-142 SAR Rev. 11, 6/85 TABLE 1.10.2-3 CYDROP(CORNER) NUCLEAR PACEA0INO PR0PRIE7ARY 07.14.39 85/e4/04 DN-142 CENTRAL NOLE PILLED PACKAGE WEIGNT e 44800. (LBS) PACKAGE EXTERNAL LENSTN e 120.8e (IN) PACKAGE EXTERNAL DI AMETERe 101.00 (IN) PACKAGE EXTERNAL NOLE DIAS .04 (IM) PAYLOAO ENVELOPE LEN0fM e 84.38 (!NI PAYLOAD ENVELOPE DIAMETERe 76.08 (IN) DVERP4CK LENGTN e 40.00 (gN) DROP MEf0NT e 31.te (PT) ORIENTATION ANGLE e 40.090 (DEGREES WRf TO VERf! CAL) PLATEAU CRUSN STRESS e ,gg (p3g) (DEPAULT TAKEN Af te PCT STRAIN) STRESS / STRAIN EVALUATED IN 1/2 stUSN PLANE ELLIPSE Afe NX e 23 POINTS PARALLEL TO SENt*NINOR ELLIPSE AXf3 NY e 25 POINTS PARALLEL TO SEMI-NAJOR ELLIPSE AXIS EXPERIMENTAL STRAIN VS. STRESS VALUES PT STRA!N STRESS 1 0.0e 0.00 2 .0S Itse.00 3 .10 ' 250.00 4 .2e .330.00 30 ,498.0e 6 40 .738.00 7 .30 2228.00 8 .40 3478.0e

  • 9

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NErhe0E-142SAR Rev. 11, 6/85 The effect of losing the capability of one of the ratchet binders prior to the drop event is analyzed la a more realistic manner, which results in a ratchet binder load approximately one third of that used for design. It is incomoelvable that the slight change in the foam stress-strain curve would affect that analysis such that the resulting margia of safety would be less than that onioslated oomservatively above. The binder retaining pins are calculated to have a capacity of 261,316 lb s. The resulting margia of safety is therefore: N. S. = (261,316/122,195) - 1 = +1.14 The Mark I overpack retainer pins have a capacity of 32,800 lbs. In double shear. The body of the report demonstrates that shear of the pin is the controlling conditica rather than shear out. The pin load is calculated as below: P, = (122195 lbs.)(3000 lbs.)/(19900 lbs.) = 18421 lbs. The margin of safety is then: N. S. = 32,800 lbs./18,421 lbs. - 1 = +0.78 The load carried by the closure bolts in the Mark I bolt-on lid design can be omiculated as below: (16900)(77.2)(38.125)oos 40' = 12267878 + (266.7)(P )(71.25/76.25) b Pb = 103,670 lbs./ bolt Since the capacity of each stad is eslaulated to be 120750 lbs./ stad, the margin of safety is as belows N. S. = (120,750/103670) - 1 = +0.16 1-154

. ~... 15mrneON-142SAR Rev. 11, 6/s5 The especity of the cask body closure ring is calculated to be 210,000 lbs. at each stad location. The margin of safety for the closure ring is them: N. S. = (210,000/103,670) - 1 = +1.03 i Bearing stresses in the overpack attachment lugs osa be calculated as follows: I fbrs = 122,195/((1.50)(1.625)) = 50,131 yei The margin of safety is them: 1 M. S. = (90,000/50,131) - 1 = +0.30 i The weld capability of the Mark I hold-down lag weld is 157,500 lbs. The margin of safety is them l N. S. = (157,500/122,195) - 1 = +0.29 i The shear-out capaalty of the binder attachment lugs is calculated to be l 197,350 lbs. Therefore, the margin of safety is: N. S. = (197,350/122,195) - 1 = +0.62 All of the margins of safety calculated la Section 1.7.1.2 of the report that 4 are affected by the revised stress-strain limit on the foam have been presented above. Nome of the margias have been affected sisalfloastly, and j all remain positive, even with very sosservative analysis tookalques. 1here-fore, the revised stress-strain limits do not af fect the ability of the j package to resist the ef fects of a 31 foot oorser drop onto an smyloiding sarface. j l l i i 1-155 j l

karse05-142SAR Rev. 11, 6/35 1.10.2.4 jigg Immant. NsPao's SYDROP program was used to evaluate the effects of a 31 foot drop onto the package side. Analyses were performed assuming the the entire length of the overpack is effective la resisting the impact and assuming that only that portion of the overpack between the cask shield and the impact surface is offective in resisting the impact. The latter assumption was made to develop a very acaservative prediction of acceleration. Tests have shown that this assumption does not accurately model the actual response of an overpack to impact loads. The ro ssi ts of the smalyse s are pre sented in Tables 1.10.2-4 and 1.10.2-5. The tables show that the more rigorous lategration techniques employed by the SYDROP program result in prodloted socelerations less than those used for design. As a rosmit, the margins of safety presented in the body of this report under predict the actus1 margias of safety, even with the revised fosa data. Therefore, the revised stress-strala limits do not affect the ability of the package to resist the effects of 31 foot side drop onto na asyloiding surface. 1-156

7-MmPas 05-142 SAR Rev. 11, 6/85 TABLE 1.10.2-4 $Y0a0PtstDt1 NUCLEAE P4CEA0140 PR0PRIEfAAY 10.14.12 85/64/04 ON-842 UNIACRED PGAM EPPECTIVE PActAct Wf!CNT e 44000. (L95) PACKAGE EXTERNAL LENG7N e 40.80 ilND PACKAGE (XTENNAL DIAMtitR. 168.83 (INI P4YLOA0 OSANttgt e 14.00 (tNI DACP Nt!GMT e 34.88 (PT) STRAIN V1 Stat 33 TASLE PT STRAIN STRt11 0.00 0.04 .0$ 100.00 .40 .250.00 4 .40 .338.00 .30 490.80 4 40 .710.90 7 .50 ,!220.00 0 .40 left.se 9 .78 1000.40 SYOROP(S!08) NUCL8A4 P4CEA01NO PA0P4ItfA4? 14.14.12 49/94/04 ON*l42 UNIACLES POAN (PPtCTIVt ++ CausN PLANT **

  • * *
  • IMPACT ****

++++++ ENERGY

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mapine 05-142 SAR Rev. lio 6/85 l TABLE 1.10.2-5 I i SY000P(S!$tt NUCLtA4 PACaA01NO PR0PRIEfARY 17.90.29 $$/04/11 0M 142 ONLY 4ACatt PGAM EFFECf!VE PACKA06 tefl0NT e 44000. (10$1 PACKA0s EltitRNAL $$N0fM e 44.00 (lN D P4CEAet EXftRNAL DIANETRA e 101.00 ( N) PAYLOAS StANtitR e 14.00 (i N) 31.00 fl OROP Nt!ONT e sinAIN Vs statss fa$le Pf sinal # sferss 0.00 0.00 .09 '100.00 .0 .sl0.00 2 l 4 .e e.ee .4 490.00 l l 40 750.00 .50 i'2{0.00 I .40 4r0.00 i 9 .T0 '000.00 6 I STOOOP(littl NUCLEA0 PACaA01NO P40P018?AeY 17.90.29 09/04/11 On*142 DNLY $4Ctte 70AM EFFICf!Vt 9+ CAUSN PLANE ++ ++++ INPACT ++++ ++ m + ENSA6Y ++++++ $$$fel4Ufl04 OP Sf4AIN GAftet Of (8014 Pt# CONT OP CONTACT AttA 00Pt4 40th Vet tlNE F0ect ACCtt. P0ffNflAL Sf0AIN 84fl0 48.10 Of.70 Of.00 Of te Of.99 l (INp (INA) (1488 (L6%) (0) (!N*L 9) (IN+441 ($E/Pil 68.00 Lt.90 Lt.99 l 't 44.4 74 189444. .'.0 , 5024000. 1410 .001 00.00 .00 0.00 0,00 0.00

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8980000, left i..

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Ilamae 05-142 SAR Rev. 11, 6/85 1.10.2.5 Conslaaloma The analyses presented above demonstrate that the revised upper bound on the stress-strain properties of the fose has no effect on the package's ability to meet the requirements of 10 CFR 71. 8 e 1-159

Iberne 05-142 SAR Rev. 11, 6/g3 7.2.5.1 The paskase should be leak tested stilizing a halogen deteetor type test stallar to the one presented la Appen-dia 7.3.2. The halogen gases shall be introdseed to the fully assembled package through appropriate fittings la j the drala port area or a vent port, if so equipped. (See Des Y-20-201D, Deta11 FA Y-20-202D, Deta11 Na Des. AL-2% 202, Detail Ig or AL-20-203, Detail E). a 1.2.5.2 The leak test described la Section 7.2.3.1 shall be per-formed at the Primary and Secondary lid seals and at all ports as appropriate for the partientar OE-142 eask son-figuration. The required elements of this leak test are as l follows: 1. A halogen ses leak deteetor espable of deteettas a j leak rate o f 0.3 on./ yr. shall be used. Its estibration, adjustment, and use shall be la assordance with the manufsetsrer's requirements. ) l 2. Dieh1orodifluoromethane (Freon R-12) shall be seed as the halogen and pressurising gas. 3. The paskastag or package (as appropriate) shall be assembled for the test la assordance with Sostion 6.0. The ensk shall be pressurised through the drain or vest port, as applicable. 4. The temperature of the eask shall be measured before the test. The pressurination of the sank shall be I based on this temperature as follows: 1 1 7-3 4 r+~ --ee.. -.---,-. --. _, n,m,,,__ 7--,.7,mm--,_,m,

~ Nhhme05-142 EAR Rev. 11, 6/85 Cask Body Temperstare Cask Pressarisation Range (*F) (hominal PSIG) 10-40 3.3 41-70 3.4 71-100 3.5 101-120 3.6 5. The sensitivity of the test shall be approsisately 5 1 10-6 std. ee/ses/ The asseptance criterion shall be no leak in eseess of 10-5 std. ee/see. 6. Each seal area shall be tested. 7. If aseeptance eriterion is not met, a retest shall be sondnoted followins an assembly recheek, maintenance, and/ or reassembly. 4 e 7-3-a

a e, 30mPas 0E-142 SAR Rev. 11, 5/85 N U [ L E / I R u li T e PIl[K/1GING A Pacific Nuclear Company APPENDIX 7.3. 2 PROCEDURE FOR SEAL INTEGRITY LEAK TEST OF THE 011-142 TYPE B SilIPPING CONTAINER LT-23 REV. O MAY 31, 1985 [4 ( Dato (By lo y hY $$< hl'V .) M Datd Enijinc~ ring - 4C( hee, h - b[l[8S-- Dato Quality Annurancu

  • *Mb.,

he, A Y Dato anuf acturing/l/roduction j Vh ^ Date other / 6

  • W'85 7-16 onto Document Contfol/itoloano

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