ML20129B894

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Forwards Revised Pages to OH-142, Sar. Revs Concern Leakage Requirements,Thermal Shield Tolerance,Gamma Scan Calibr Procedure & QA Program
ML20129B894
Person / Time
Site: 07109073
Issue date: 06/03/1985
From: Temus C
NUCLEAR PACKAGING, INC.
To: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
25334, 4024, NUDOCS 8507150615
Download: ML20129B894 (40)
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Text

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u;n,, paurew g y y g gf.m,..g g a g, ig s,4 x m O June 3, 1985 Ng File: 011-142 y e Ref: 4024 Mr. Charles E. MacDonald, Chief Nhh Transportation Certification Branch U. S. Nuclear Regulatory Commission qf Washington, DC 20555

Reference:

OH-142 Safety Analysis Report, Docket No. 71-9073 -(J 3g{

Dear Mr. MacDonald:

After some discussion with your staff, we have prepared the enclosed revised pages to the 011-142 Saf ety Analysis Report to adequately address leak testing requirements as well as to adjust the drawings and QA section of the report to reflect current practice. We have also included copies of page 1-90 which apparently was not included in our May 6 submittal. The changes we have made include: o The Operating Procedures (Section 6.0) have been re-vised to require all Type B quantity shipments which r-are not classified as LSA to be leak tight to at least cc 10-5 acc/sec. The leak test used to demonstrate this .[ c3 has been included as an appendix to Section 6. g< s en [;$/

  • h 0 changed The thermal shield tolerance on the drawings has been

~ i e.,; o, g 1 to reficct a more realistic fabrication g //?'c .5- ~ tolerance. Calculations demonstrating that the new j i,y g i ff tolerance has no ef fect on the package's ability to 4 ay meet the requirements of 10 CPR 71 is included as Attachment I to this letter. p o The discussion of our Gamma Scan calibration has been updated to reficct our current practice. o The Quality Assurance Section has been updated to reflect current Regulatory Guide information regarding the existence of our QA system. All outdated information has been deleted. As you can see, all changes are very minor. Only the leak test change has any impact on safety, and this change is to make shipments demonstrably more safe than has been current practice. N O h g#0&3 )b o603 r,,~.~.-- ?, a3 i

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I June 3, 1985 Mr. Charles E. MacDonald, Chief Transportation cettification Branch Page 2 This revision, including revised drawings, has been copyrighted. This entire submittal contains proprietar y information per the notice included on the fly leaf 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 perrninnion should not be construed as a waiver of or in any way prejudicial to our lawful proprietary rights to this material. It is is done only to f acilitate the issuance of a Certificate of Compliance. 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 materia 3 in exprennly 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 call either myself or Stephen Goetsch. Thank you very much for your help in this matter. Very truly yours, NUCLEAR PACKAGING, INC. e% Charles J. mus Technical Director ed. Enclosed: As stated U3 b~ A

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  • PLATE & SHAPES CONFORM TO ASTM-A516, GR70 SHEETS CONFORM TO ASTM-A36 OR 304 SST PER ASTM-A240 WHERE NOTED.

si;,... v. m ... +. - ,o" E 2. MATERIAL : ASTM-A514 OR A517 l . ?,- 3. FOAM: 1,000 PS! CRUSH STRENGTH RIGID POLYURETHANE. PER NUPAC FOAM SPECIFICATION NPI-F6. h Wh 4. LEAD: PER FEDERAL SPECIFICATION QQ-L-17tE, GRADE A OR C. a h Ol 5. REMOVED g,,N 6. REFERENCE DATA: CASK WT: 54,000Las, e PAY LOAD: 10,000tss, GROSS WT: 64,000Las, g 7. REMOVED otfAIL K 8. ALL WELDING PROCEDURES AND PERSONNEL SHALL BE QUALIFIED IN ACCORDANCE WITH ASME CODE, SECTION IX. ion c C 9. ALL WELDS SHALL BE INSPECTED VIA NDT METHODS AS FOLLOWS: TOP VIEW SHOWING OPTIONAl LIFTING LUG AND CIRCUMFERENTIAL CONTINUOUS WELDS: MAGNETIC PARTICLE PER ASME CODE SECTION !!!, DIVISION I, SUBSECTION NB, ARTICLE NB-5000 AND SECTION V, ARTICLE 7. LONGITUDINAL SHELL WELD: RADIOGRAPHIC PER ASME CODE SECTION !!!, DIVISION 1, SUBSECTION NB, ARTICLE NB-5000 AND SECTION V, ARTICLE 2.

10. AS AN'0PTION, 12 GA. NO. 304 STAINLESS STEEL CLADDING MAY BE INSTALLED ON THE INTERIOR & EXTERIOR SURFACES OF THE FLASK BODY a INTERIOR SURFACES OFotfAiL-S )

[otimL THE UPPER LID, & SEAL WELDED ALONG ALL EDGES & SEAMS.

11. PAINT ALL EXPOSED CARBON STEEL SURFACES WITH ONE COAT CARER 0 ZINC !!

( a ONE COAT PHENGLINE 305, OR ONE PRIMER COAT (5 NILS) ,< g,. 4 MOBIL CHEM EP0XY N0. 80W9 & ONE FINISH COAT (5 MILS) MOBIL CHEM E?0XY n ei ~" NO. 89W9. kl6 -

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BETWEEN THE OVERPACKS.

13. FLASKS FABRICATED PRIOR TO 3/84 MAY BE MADE USING ASTM-A36 MATERIAL.

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g d ~ ~~~ Pf!CN A 10 GA. l50. 304 STA!1E13 STEEL THERML SHIE'J. f BE 0( V = TALLID SETWEEN THE QVERPACK3. ~-~ ~k 9 S( IT ALL EXPOSED CAAACM $ TEEL SURFACES WITHONECOAT CAR 50Z!flC 1.1 g ~d" ~ j E CDAT PuEle0LinE 305. COLOR 727 M. GRAY. OR CNE PRI.1R CCAT OPT. / \\ d itLS) 1"3BIL DEM EP1XY NO.19W9 4 CNE FIRISM CCAT (5 MIL 3) Mc3!L FILLET 50 9 EPQXY No. *l9W9. COLCR WHtIE. 7 l All CPT10N.12 6A NO. 304 STAINLESS STEEL CLK. DING MY BE INSTALLD THE lETERIOR & EXTERICR SURFACES OF THE Ft.ASK BCDY a 12TER10R g FACES OF THE UPPER LID, & $EAL wet. ED ALCM ALL CGES & $EAMS. "~~ 1 . So y,'/x c. s1. ~~ }V O#I 881I SIT m con-n nusu ROTATED 90* BOTH INDEXING MEMBERS 5H0wN VIEW P. - it 7 ~ Also Avanable On 4 Aperture Card,, y,m ,,,,w m,,,_ -.- s 1 1 Aaser 7xe waw raar, sa owe. xs. /; ~% I C+erNTYP Y-to -toto, per?ta c. I' T1 s M @D z RA0ius Q s (,,,,,,L, _JM M{,utu n DETAIL-d '2. 9 SCALE: l/4 \\ / Fm" th PLT. C t LD 2 g f TYP, 2 g g g I X 45 CHAMFER IX IX f ANGLE l { Y////////74 3 '=- / ~ f - [' ** mLc } z h\\\\\\- 4 r i }~ ,, t F -g g TYP),p 1 _ LIFTING L 5 CCVEAED _DURING _I DETAll f-SC^W2 DETAIL L-L $~_ 0 $, _.. "'W* u.,o....... u.. m. _@E.YnT"*Y NUCLEAR PACKAGING, INC. Q( rAcoNA WASNfNSTON 1:,g,.,.%.a n? p BULK RESIN SHIPPING FLASK 1 ri H p'", *. c',On MODEL OH142 MK-l 8

  • is
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BOLT ON LID _CONElGURATION*. -= =" al-N if= I N / ETuM 'st tt 11 ma-2 \\/

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8 l 7 l 6 l 5 ~ PACKACE SH"ALL BE leAMKED A DENTFED N ACCORDANC REOUMDdDeTS OF to CFR 71JB5(c) S CONOW W 4 M N DE EM WM e COAT ALL DJEED iXTERIOR SURFACES CF FLASK RETWEE3 UPPER AND LCER h, w-A3 OkUPACK3 WITN ONE (1) COAT (MIN 3/16 THK) *AL3!-CLAD

  • NO. 89.

AN QPTION, A 10 GA. 20. % STA!llC33 STEEL THEPflAL SHIEL) MY BE M, thakMed MridesressvedudsaxWitour. U" I# PAINT ALL DPOSED CARBON STEEL SURFACE 3 WITNONECCAT CAR 30 ZIAC 11 11. a ONE COAT PMDOLinE 305, COLOR 727 M. GRAY,02 ONE PRItEA COAT - i-L O (5 RILS) MOBIL CHEM EPCIT NO. 39W9 8 QNE FIE!$N COAT (5 MILS) M081L l g .29 y OiEM IJWY lug. Eini9, COLO24 Wi!!TE. d ?.s.. -. : - -- - 4'.-D. A3 AN OPTION,12 GA NO. 304 STAINLESS STEEL CLALOING MAY BE INSTALLD[ ' ON THE INTDICA E DTU!OR SURFACES OF THE FLASK BODY s IXTERIOR la SURFACES T THE UPPD LID, 4 SEAL WEL E3 ALONG ALL CGES & SE#tS. ?, l g I ',j. i ,g' s,' s

  • C zR

,J-5'_ 4_ A{_ y D Z f.9 i p

  • go (

C '9., ALL WELDS SHALL BE INSPECTED VIA NDT DETAIL-K METHODS AS FOLLOWS: . S0 ) 6 - 101 OlA LIFTING LUG AND CIRCUMFERENTIAL CONTINUOUS ' WELDS: MAGNETIC PARTICLE PER ASME CODE SECTION !!!, OlVISION 1, SUBSECTION NB, ARTICLE

  • NB-5000 AND SECTION V, ARTICLE 7.

LONGITUDINAL SHELL WELDS: RADIOGRAPHIC PER ASME CODE SECTION lit, DIVISION I, SUBSECTION NB, ARTICLE NB-5000 AND SECTION V, ARTICLE 2. "~ ~~ ~ 'OETAIL-DETAIL-8 IOGA DETAIL C __-.- --..-_____.___- - - - -____ _r l .. / t a -4 e'7%s 1 -' ' N ' ' K y IO GA. ALL WELDING PROCEDURES AND PERSONNEL g 8 SHALL BE QUALIFIED IN ACCORDANCE WITH, t tO GA 7 . ASME CODE, SECTION IX. I ~ h DETAIL-M + 24 0lA - = O %1 '087/tMW/ " -l oc E /s ao 19 '% / DMMBTECC W Rotorfo = M 50 r 8 2 66 OIA oEmt-D k REFERENCE DATA: OETAIL-H /. CASM wT: 54,000LBS. P-72 q. i m PAY LOAO: lo.OOO LBS. GROSS WT: 64,000 LBS. OETAIL-G l g

5. MMO li i

_ y s t. ,,, J e" t-e f ns f ~^ DETAIL-f f 3 % LEAO: PER FEDERAL SPECIFICATION r - -- - -- m - n --- r QQ L-t7le. GRADE A OR C. t J l l 3 n R SS DIA - 10,00 PSI CRUSH STRENGTH 4 680 POLYURETHANE. PER NUPAC FOAM h F0AM: A = SPECIFfCATION NPI-F6. -- 7 6 OIA 2 hMATERIAL* AS7"A(-ASr4 tW AS/7 -tOI O(A d NOMINAL AIR GAP (I MATERIAL: LOW CAR 80N HOT ROLLED STEEL: PL. ATE & SH APES CONFORM To ASTM-A546. di " SECTION A-A i3 l.

SHEETS ~ CONFORM TO ASTM-A415, A3/. on 3od SST NOTES: UNLESS OTHERWISE SPECIFIED 1

l 6 i 5

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~* y 3/4 M CIA 94Apot e TY s /O .g q _ _t250 W. OPTION - 1 [' f$ - 't. -4 *.SC b.SO y-1.1g - N PLASTIC PIPE PU.lG m 4,o0. g,gg R; TYh y z COUPLING N 10 GA. H/2 PIPE SIZE N RATCHET BINGER (TORCUE BINDER TO 80 FT/LBS-PRELOAO) PATTERSON 13/4 XIO TYPE J OR EQJAL s!\\ ' p~m (164000 L8. MIN. BREAKING STRENGTH) ~~ ,'4 ' l YP OPTION - 2 K g Y DETAIL -H N -- -225 SCALE 1/2 COTTER PIN-f DIA HEX SLOTTED Nut ij-SjuNC 42*FOR REAR LU6S g \\ 2.50 24'FOR FRONT LU65 f h I \\j\\ HEX. HO BOLT lh-SfLNC GRADE 6 g N [ i If PLT. s ~ i*\\ ' _ _, 'c \\L court 79-80 s Joeyt ortT-4 _ DETAll - E _ SD soo-s,a ~~ -u rom fry ~scas tasamu. sanato coursaamanon aport matenrr szwona toman J- ~ VIEW P-P m m,,, y a o Loo, saa ses. po. v-se-noso, estazL a a vzza n m SCALE i/4. pacg7* 776 Down L At>. Y' 20 -202 O, 69eo f NPT PIPE PLUG 150 G DRAIN PORT-l.13 DIA HOLE g

  • I.25 x 3 coop 7 PLI

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  • THREADED ONE 3 PLT N

d' END ONLY Q .'i / m 3 PLT. 77 ,g U \\ DIA HOLE OETAll-G v C SCALE: t/4 y VIEFLATION DAMPENING WASHER 8 Fl.AsK BCDY OUTER SELL WELCEO TO 7/L6 HEX ROD QPita'A' n u m m !E DETAIL-F Mr a w acx A 5 " g g-cenom. to a m rxEwL satEu .12 V L Lm u, B> MOTES: UNLESS OTHERWISE SPECIFIED critenAL THEmAL sattu IETAIL_ i .s I 7 1 6 - I 5

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  • - l.13 i PLT.

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  • NO. 49. A3 9

g All WT105. A 10 GA. no. 304 STAT::LESS STEEL THERMAL SHIELD MY BE __.j4 ge e 6 e PLCETORQUE ' .lASTALLS KTWEDI THE O.YAPACK3

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  • *e '2 4

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  • .+

ogTAit.J} iocA. .'.,ALL WELDING PROCEDURE AND PERSONNEL otmL,C SHALL BE QUALIFIED IN ACCORDANCE WITH l 3 ME. CODE, SECTION IX. r ..- -; --. ;f 9 gg D j tw/n %,'AMW a/ e i ~ I t m 1-n - 1 1 s17 1 y lu GA. j. 1;:: Lsu NIJ F# ^ Ahh ei l $':>hATEmAs. CONFORM 5 TO k O GA 5 B IleTM-ASHo GRD.1"TO.'T oEmt-K [' i

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MmPao OH-142 SAR Rev. 10, 6/85 MODEL OH-142 SHIPPING CONTAINER REVISION 10 DELETION AND INSERTION INSTRUCTIONS Delete Insert 6-3 6-3 7-1 7-1 7-3 thru 7-5 7-3 thru 7-20 8-1 8-1 Dws. AL-20-202 Dwg. AL-20-202 Sheets 1 thru 3 Sheets 1 thru 3 Dwg. AL-20-203 Dwg. AL-20-203 Sheets 1 thru 2 Sheets 1 thru 2 Dwg. Y-20-201D Dwg. Y-20-201D Sheets 1 thru 2 Sheets 1 thru 2 Dwg. Y-20-202D Dwg. Y-20-202D Sheets 1 thru 2 Sheets 1 thru 2 l' Page 1-90 was inadvertently omitted from Revision 8 p19ase find attached. l l l l l

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I NmPa] OH-142 SAR Rev.10, 6/85 6.1.7 The lug in the conter of the secondary lid may be used to remove the secondary lid from the cask. Care should be taken to avoid damage to the gasket in the Iip of the secondary lid. 6.1.8 Inspect secondary lid studs, bolts and nuts for signs of wear. Damaged threads and excessive corrosion shall be cause for replacement of these items. 6.1.9 Load cask through secondary lid. Replace secondary lid and torque bolts to 200 1 10 ft-lbs. i 6.1.10 Survey the loaded cask to assure compliance with 10 CFR 71.47. Inspect for surf ace contamination per the requirements of 10 CFR 71.81(i). 6.1.11 If the shipment is not classified as Low Specific Activity material, a leak-test per section 7.2.5 shall be performed. 6.1.12 Inspect the package for proper labeling necessary to meet all applicable regulations. i l 6-3

MnPao OH-142 SAR Rev. 10, 6/85 LO ACCEPTANCE TESTS Ap_ MAI!EENANCE EBOGJ&)l LJ, Accentance Tests The Model OH-142 packaging shall be inspected and released for use by respon-i sible operation personnel prior to loading. The following items will be included in such inspection: 7.1.1 Before first use, all OH-142 package configurations shall be subjected to the leak test as described below in section 7.2.5. 7.1.2 All configuration checks described in section 6.2.8 above. 7.1.3 l The cask shall be pressure tested to 1.5 times the normal operating pressure of the cask. This may be taken conservatively as the pressure given for the Hypothetical Accident Condition in Section 1.7.3.3. In that section, the pressure is given as 11.59 psig, so this test shall be carried out at 17.4 l psig. 7.1.4 The integrity of the shield shall be demonstrated by means of a gamma scan performed on the lead-filled cylinder during the f abrication process. See Appendix 7.3.1 for a description of this procedure. l l 7-1 1

,~ / NmPao OH-142 SAR Rev. 10, 6/85 7.2.5.12 The p'aekage should be leak tested utilizing a halogen detector type test in accordance with Appendix 7.3.2. The halogen gases shall be introduced to the fully asisembled r r package through appropriate fittings in the drain ~ port s'rea or a vent port, if so equipped. (See Dws Y-20-201D, Detail F; Y-20-202D, Deta11 N; Dwg. AL--20-202, Deta11 E; or AL-20-203, Detail E). 7.2.5.2 The leak test describe [In Section 7.2.5.1 shall be per-j formed at the Primary and Secondary lid seals and at all ports as appropriate for the particular OH-142 cask con-figuration. The acceptance criterion will be 10-5 std cm /s. Test sensitivity will be approximately 5210-6 sta 3 3 cm /s. ,/ Y f / e r .r / r Y f v W 7-3

NmPas 08-142 SAR Ray. 8, 5/85 7.3 APPENDIX APPENDIX 7.3.1 DISCUSSION QF GAMMA M PROCF, DURE Lead shielding integrity shall be confirmed via gamma scanning. There are two gamma scan techniques utilized. The main difference is in the method utilized to determine acceptance criteria. Both Gamma Scan Techniques sre exactly the same in all other respects and are conducted as follows. An Eberline E120 probe or equivalent is used to scan the outer surface of the cask while an Iridium 192 or Cobalt 60 source of sufficient strength is present in the center of the cask. The source is first placed on the bottom of the cask while the surface is scanned around its circumference parallel to the source. The source is then moved up a pre-determined distance and the circumference scanned again. This sequence is repeated until the entire cask surface is scanned. For these tests, the cask surface is gridded (in this case the grid con-i l sists of 4 inch squares) and a chart is made to reflect the gridded cask surface. Readings are taken from each grid square by scanning every point I in the grid and recording the maximum reading in the corresponding grid on the chart. This data then serves as the raw gamma scan results. All readings are in Milliroentgens (MR). The readings are evaluated by comparing them to predetermined MR values for nominal, or as designed, lead thickness and nominal -10% lead thickness. The two different methods utilized to determine acceptance criteria are discussed below. The Laboratory Calibration Method (NuPac Procedure GS-001) utilizes test blocks of the cask wall made up of lead and steel sheets. The test blocks simulate nominal or as designed and -10% lead thicknesses. The source is placed behind the test block at a distance equal to the inside radius of 7-4

MnPas OH-142 SAR Rev. 10, 6/85 the cask. The probe is then placed on the outside of the test block and readings are taken. This sequence is repeated on the nominal and -10% test blocks and the data is recorded. The resultant values are then averaged. A ratio of the values is also de-veloped. Then the average value is multiplied by the ratio. The value so derived is the maximum acceptable value for the shielding to be inspected. An optional Laboratory Calibration Method can be utilized in lieu of the lead / steel calibration mockup method. In that case, calculations are run to establish acceptance criteria. To do this, complied source power data and attenuation characteristics data for steel, lead and distance through air are utilized to calculate the ex-pected readings at the cask surface. The calculations allow for different source powers and are corrected for nominal and -10% shielding configurations. h The following excerpt from NuPac Gamma Scan Procedure No. GS-001 is provided to illustrate the calculation Method of Laboratory Calibration: 1.1 The nominal and -10% shielding calibration MR readings may be obtained via calculation as an option. These calculations shall be performed as follows: 1.1.1 Data and transmission charts found in the Tech / Ops Gamma Radiography Radiation Handbook shall be utilized. Copies of the handbook can be obtained from: Tech / Ops, Inc. Radiation Products Division 40 North Avenue Burlington, Mass. 01803 7-5 __ O

MaFao OH-142 SAR Rev. 10, 6/85 1.2.2 Attachment A, Table 2, ' Selected Radioisotope Data' from the handbook shall be utilized to obtain source power data. (Copy of Table 2 included as Attachment A.) 1.2.3 Attachment B figures of the handbook shall be utilized to determine the attenuation of Gamma Rays in the shielding ma-terials utilized in the cask to be inspected. (Copy of typical figures included as Attachment B.) 1.2.4 The following is an example of the calculated calibration method using Cobalt 60: EXAMPLE Cask O.D. 48 in. Cask I.D. 36 in. I.D. Wall 0.50 in. 0.D. Wall 0.50 in. FE Lead Shielding = 5.0 in. Less 10% lead shielding = 4.5 in. Total FE shielding = 1.0 in. Source Cobalt 60 strength 15 curies x 14.0 = 210 R/Hr at 12 in. (using Attachment A). 210 R/Hr at 12 in. = 52.5 R/Hr at 24 in. This would be the outer surf ace of the cask. 52.5 R/hr at 24 in. x reduction f actor for 1.0 in. FE 0.58 = 30.45 R/Hr. 30.45 R/Hr at 24 in. x reduction factor for 5.0 Pb 0.0009 = 27.4 Mr/Hr. 30.45 R/Hr at 24 in. x reduction f actor for 4.5 in Pb 0.000185 = 56.3 Mr/Hr (using Attachment B). 7-6 )

MaFas OH-142 SAR Rev. 10, 6/85 Design thickness reading at cask surface = 27.4 Mr/Hr. Design thickness reading less 10% Pb = 56.3 Mr/Hr. The following is an example of the calculated calibratica method using Iridium 192: 1 EXAMPLE Cask O.D. 48 in. Cask I.D. 46 in. I.D. Wall 0.25 in. FE 0.D. Wall 0.25 in. FE Lead Shielding = 1.5 in less 10% lead = 1.35 in. Total FE Shielding 0.50 in. Source Iridium 192 50 curies x 5.9 = 295 R/hr at 12 in. (using Attachment A). l 295 R/Hr. at 12 in. = 73.75 R/Hr at 24 in. This would be the outer surf ace of the cask. J 73.75 R/Hr at 24 in. x Reduction Factor for 0.50 in. FE 0.55 = 40.5625 R/Br. 40.5625 R/Hr. x Reduction Factor for 1.50 Pb. 0.0024 = 0.09735 R/hr. 40.5625 R/Hr. x Reduction Factor for 1.35 in. Pb. 0.004 = 0.16225 R/Hr. (using Attachment B.) Design thickness reading at cask surf ace = 97.35 Mr/Hr. Design thickness reading less 10% of Pb = 162.2 Mr/Hr. The calculation values and methods are based on data developed during approximately 300 actual calibrations utilizing the lead sheet / steel plate sandwich technique described in Rev. 4 of the referenced procedure. 7-7

i NmPas (EH-142 SAR Rev. 10, 6/85 Additional correlation has been provided by the use of established attenuation 1 values obtained from the various figures found in the Tech / Ops Radiation Safety Handbook. This reference source is a recognized standard document utilized throughout the NDE industry. This information, together with NuPa c 's, extensive laboratory data enabled NuPac to develop the current optional calculation method of laboratory calibration for gamma scan. The calculation method provides a greater degree of accuracy and correlation to the actual gamma scan conditions present in a typical cask than the lead and steel plate setup used in the past. It also reduces operator exposure during the calibration phase. The resultant calibration values for acceptance of the lead shield are, in f act, slightly more conservative and therefore assure a greater margin of safety for the shield. The resultant improvement in the calibration of gamma scan acceptance criteria provides greatly improved accuracy and repeatability. To illustrate this accuracy, correlation and conservativeness, the calibration data for a typical OH-142 gamma scan was rerun using the calculation method of Laboratory Calibration. The original calibration technique for this cask had been the lead and steel setup method. The correlation between the two Laboratory Calibration methods is essentially identical. The variance in the acceptance criteria between the two methods is f rom.3 MR in the nominal to.1 MR in the -10% value s. This equals to more than 2% variance between the Pb/FE and calculation methods of Laboratory Calibration. The difference in percentage (DIFF, %) between the nominal and - 1-% values for the two calibrations is also very close with the Pb/FE at 64% and the Calc at 63%. The calibration results follow: 7-8

MmPao OH-142 SAR Rev. 10, 6/85 SUIGIARY OF GAMMA SCAN ACCEPTANCE VALUES - OH-142 Source Type Source Strength Calib Type Nominal Value -10% Value Diff (curies) (1) (MR) (2) (MR) (3) (%)(4) Co 60 11 Pb/FE 21.5 33.5 64% Co 60 11 Calc 21.2 33.4 63% NOTES: 1. Pb/FE = Laboratory Calibration using lead and steel sheets to simulate the cask wall. Calc = Laboratory Calibration using the calculation method. 2. Nominal Values is the calibrated acceptance value expected if the lead and steel thickness meet the design requirements. 3. The -10% value is the calibrated gamma reading expected if the lead thickness is 10% less than that required by the design. The steel thickness is assumed to be at the nominal. This reading will be large r than the nominal reading. No reading above this value during actual i gamma scan inspection is acceptable. 4. DIFF (%) refers to the percentage of difference between the Nominal and -10% values. A variance of approximately 5 to 6% between the nominal and l -10% values of separate calibrations is normal. This is attributable to differences in lead density (cast vs. rolled sheet), accuracy of meters and related equipment, as rolled steel thickness variables, etc. l l 7-9

NmPao CH-142 SAR Rev. 10, 6/85 The Field Calibration Method (NuPac Procedure GS-002) utilizes a specially f abricated test lid which incorporates a holder for various lead and steel sheet thicknesses. This fixture is installed onto the cask to be scanned. The test lid is then set up to simulate the nominal lead thickness, the source is placed below the test lid in the cask at a distance equal to the inside radius of the cask. Readings are then takin. The test lid is then set up to recreate the -10% lead thickness configuration, and readings are again taken. Other readings are then taken in 1/8 inch lead thickness increments between and beyond the two base readings until four to eight readings are obtained. The data is then plotted on a chart of readings versus lead thickness. The value for nominal lead -10% is then utilized as the maximum accepttble reading during the actual gamma scan. 7-10

NmPas OH-142 SAR Rev. 10, 6/85 I GS - 001 - ATTACIDENT A TABLE 2 SELECTED RADIOISOTOPE DATA s Radioisotope Halflife Pnncipal Photon Specific Gamma Ray Constant Energies (kev) R!hr per curie at t foot at 1 meter Cesium"7 30 662 3.4 0.32 y Cobalta 5.3 1173,1332 14.0 p 1.30 y C Iridium'a 74d 311,468.60 .9 p 0.55' C Thulium"' 34d 4 - ys 0.015 0.0014 Ytt (13i'a 63.110,131 1.35 0.125 C 177,198,308 Tm x-rays

  • Ame.9can National Standards institute Standard N432 bas crocosed a v arus of a48Reistr Ci for the scocific gamma ray constant for inosur9192.

7-11

Rsv. 10, 6/85 NuPac OH-142 SAR GS - 000 - ATTACHMENT B 1 d i t-? ' I i - i 1.._. s LN.. 5 '1 t- + . p'.__r

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  • - b -

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==_=1_'" " ;'- _-6 42= - =.v -- -s:-- _==_ _b m m-w -- 4 _ e-- x----+-- ATTENUATION OF GAMMA RAYS ' F ROM Co6c. Csl37. frM3 y bv LEAD @*11.34) '1 ' '\\ s'x= F i I I l 0.1, . v' : i i _a. ' - -_ r 4 2 m, __ - r. 3 2- ._.; t +. e g3 - s i_4 - tr g 1.'.--'~y 7 1 - _ a- -2x. e-l _ ;:s .r,._-_j ._i.= 7

== - =*=a 4 1 -+ += \\ j ='i= # -Q -' I'= u M- - .A m -. -w -'= = = _ + vi- &t = c -u =_w2 =, = =t==-; =125-i-(=_ =_';F i :' '\\i'=~-~='--' 2'i ' t'~ ~

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-_g=-+=t y-.;=g M=. - iE-_. ; _ _ 4-+ =-_=

- - = - - - g, _ + oi t.r - i1 = 1:_ a. _ t in.1:.ra--Y-- - ".,=- r % "pg. Map = { -. ;____ _._ _. _ 4_1 1__ _ _5i- = t = m 2 w -s3 + t_v + 1 a- =- %c _ g, , n: - - = 1 , r. 1 -. w n-, wy

- w y.+c

+. +v-,- - w_.v n e w -E i :r~ - -N i -h.61. =d._ ? i-r- T i'% hh i8--- i rz =- C= Lei. _ ?b- - W - 'ru g, =._i 1 = =p _'--_-T_-i- :-Lq \\ t:i _t--+ r -- ' - . p - --- _h=Er Et-ib- '= a.- t p i= = h3 ___ m caso ,u:_w =L-M g= = =-y r.-2=E=;=-

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NuPas OH-142 SAR Rev. 10, 6/85 NU[ LEI 1R9e \\ PII[KIIGING A Pacific Nuclear Company APPENDIX 7.3.1 PROCEDURE FOR l SEAL INTEGRITY LEAK TEST OF THE OH-142 TYPE B SHIPPING CONTAINER LT-23 REV. O MAY 31, 1985 f e . d By Date /- A / Engins rin g ' Ddtd w AD L/4/ar ( Quality A3surance Date Lwh j anufactpring/ Production Date Other Date 6 * $'85 Document Control / Release 7-16 Date

NmPas 0E-142 SAR Rev. 10, 6/85 LT-23, Rav. O May 31, 1985 1.d SCOPE 1.1 This procedure provides methods and requirements for the verification of seal integrity on the OH-142 Type B Shipping Container. 1.2 The tests in this procedure are to be performed prior to first use as part of the cask acceptance inspection with the test described in reference 2.8. Thereafter, a seal integrity test will only be performed as part of in-service and/or maintenance testing 1.3 The tests shall be performed as required by 10 CFR 71.87 (c) and the specific sections of USNRC Certifi-cate of Compliance No. 71-9073. M REFERENCE DOCUMENTS 2.1 ANSI N14.5 Leakage Tests on Packages for Shipment of Radioactive Materials. 2.2 RDT Standard, F5-lT, Cleaning and Cleanliness Require-ments for Nuclear Components. 2.3 Code of Federal Regulations No. 10, Part 71. 2.4 NUPAC Quality Procedure No. QP-5, Quality Planning 2.5 NUPAC Quality Procedure No. QP-6, Inspection and Veri-fication 2.6 NUPAC Quality Procedure No. QP-7, Discrepancy Reporting and Control 2.7 NUPAC OH-142 Operation and Maintenance Manual OM-12 2.8 NUPAC Procedure No. LT-22, OH-142 Structural Pressure Test. M REOUIREMENTS l 3.1 The cask assembly shall have been inspected and tested in accordance with the reference 2.8 pressure test procedure and written inspection instructions prepared and completed in accordance with reference 2.4 and 2.5. These acceptance activities shall have been performed prior to first use. l 7-17

Maras 05-142 SAR Rev. 10, 6/85 l LT-23, Rav. O May 31, 1985 3.2 Prior to each seal integrity test, the cleanliness of j the internal and external surfaces shall be in accord-I ance with reference 2.2 sections as directed by Quality Planning per reference 2.4. 3.3 The seal integrity test described in this procedure I shall be performed prior to first use. It shall then be performed prior to each shipment and after each seal replacement or annual maintenance activity. 3.4 The following test equipment shall be required for the seal integrity test. 3.4.1 LEAK DETECTOR: A General Electric Model H-10, TIF Model 5500 or equivalent halogen gas leak detector capable of detecting a leak rate'of 1/2 ounce / year. 3.4.2 HALOGEN GAS SOURCE: Dichlorodifluoromethane (Freon R-12 refrigerant) shall be utilized to provide the halogen gas and pressurization for the seal integrity test. The Freon R-12 container shall be pressurized with appropriate shut off valves and fittings to interface with the cask vent or drain port.

3.4.3 GAUGE

A gauge capable of indicating pres-sure up to 10 psig to an accuracy of +/ .50 % of the indicated reading shall be utilized.

3.4.4 THERMOMETER

A thermometer with a range of - 0 0 20 to +120 F, accurate to +/- 2 F, shall be utilized to obtain cask temperatures. 3.5 Cask seal integrity shall be tested with the cask fully assembled in the shipping configuration as specified in the applicable requirements of reference 2.7. 1 Q PROCEDURE 4.1 Verify that all cask configuration, cleanliness and test equipment requirements of Section 3.0 of this procedure have been met. 7-18

Nahe 0E-142 SAR Rev. 10, 6/85 LT-23, Rav. O May"31, 1985 4.2 Adjust the sensitivity of the leak tester to 1/2 ounce / year as required in the applicable manufactur-e r's instruction manual. 4.3 Install the appropriate fittings and gauge on the cask vent or drain port for injecting the Freon R-12 into the cask containment cavity. NOTE: ASSURE THAT THE GAUGE IS PLACED TO INDICATE CONTAINMENT CAVITY PRESSURE. 4.4 Measure cask body temperature to an accuracy of +/- 20 F. Record the temperature for use in Step 4.5. 4.5 Pressurize the cask containment cavity with Freon R-12 through the provided pressurization port to the pres-sure required for the cask temperature obtained in Step 4.4 as shown in table 1 below. TABLE 1 REQUIRED CHARGE PRESSURE (PSIG) AT GIVEN TEMPERATURE (O F) CASK BODY TEMPERATURE CHARGE PRESSURE RANGE (O F) (PSIG) 30 - 40 3.3 41 - 70 3.4 71 - 100 3.5 101 - 120 3.6 USE OF THE CHARGE PRESSURES SHOWN IN THIS TABLE WITH THE HALOGEN DETECTOR SET AT 1/2 OZ/ YEAR WILL DETECT LEAKAGE TO A NORMAL LEAK RATE OF 1.0 x 10-5 atm - cm /sec 3 l l l 7-19 l

Marine 05-142 SAR Rev. 10, 6/85 LT-23, Rev. O May 31, 1985 NOTE: THE FREON CONTAINERS MUST NORMALLY BE IN AN UPRIGHT POSI-TION TO ASSURE THAT THE FREON IS IN A GASEOUS STATE.

HOWEVER, SOME SUPPLIED PRESSURIZED FREON CONTAINERS MAY REQUIRE A DIFF-ERENT ORIENTATION.

BE SURE TO REFER TO THE CONTAINER LABELING FOR SPECIAL INSTRUCTIONS. THE RATE OF FREON INJECTION CAN BE IN-CREASED BY PLACING THE CONTAINER IN A PAN OF LUKEWARM WATER. THIS MAY BE PARTICULARLY HELPFUL WHEN THE AMBIENT TEMPERATURE IS BELOW 45 DEGREES F. 4.6 Af ter the Freon R-12 has been injected per Step 4.5, close off-the injection valve so that the gas cannot escape from the cask containment cavity. 4.7 Hold the probe of the adjusted leak detector 1/16 to 1/8 inches from the interface areas of the primary and secondary lids and/or the overpack to cask body area. 4.8 Move the probe along the area being inspected at a rate not exceeding 21/2 feet / minute. Probe all areas de-scribed in Step 4.7. 4.9 If the probe passes over a leak, there will be a visual and audible signal from the detector corresponding to the one obtained during the detector adjustment and calibration check discussed in paragraph 4.2. id ACCEPTANCE CRITERIA 5.1 No leak rate greater than 1/2 ounce / year shall be acceptable. With the detector adjusted and calibrated per paragraph 4.2, an audible signal or signal light will be emitted by the detector. This will indicate that the cask is rejectable as exceeding the specified-leak rate. 5.2 If a greater leak rate than that stated in 5.1 is observed, seal condition, fastener and ratchet binder torque and seal interfaces shall be checked and the test rerun. 5.3 If the test is failed three (3) consecutive times, a Quality Discrepancy Report (QDR) shall be prepared and dispositioned in accordance with reference 2.7 before proceeding further. 7-20 4

MnPao OH-142 SAR Rev. 10, 6/85 J.d QUALITY ASSURANCE NnPac's quality assurance program used for the design, f abric a tion, a s semb ly, testing, use and maintenance of the NuPac OH-142 cask is designed and admin-istered to meet the 18 critoria of 10 CFR 71, Subpart H. A description of the program has been submitted to the NRC under NuPac letter QA-78-1, Re v. 4, dated January 28, 1985, and has received Quality Assurance Program Approval No. 0192. I 8-1 ....}}

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