ML19256E058

Requests 6-month Extension for Certificate of Compliance in Order to Prepare Revised Sar.Forwards Oversize Drawing C001-5-9200,Revision 1,drawings of Cask Lid Lifting Device & Analysis of Shipping Cask Tie Downs

ML19256E058
Person / Time
Site:	07106475
Issue date:	10/10/1979
From:	Koh B HITTMAN NUCLEAR & DEVELOPMENT CORP. (SUBS. OF HITTMAN
To:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
14350, NUDOCS 7910250579
Download: ML19256E058 (24)

Text

.--

"O lb Nuc ar &

Cevaiopment Corporation 9150 Red Branch Road Columbia, Maryland 21045 Refer to:

301/730-7800 HN-S7042 October 10, 1979 Mr. Charles E. MacDonald Transportation Branch p

to Division of Fuel Cycle and Material Safety cc p

U.S. Nuclear Regulatory Commission n[(7(( Q %

Washington, D.C.

20555

%)

b " 8 g,.., %UU11 o

Subject:

Renewal of Certificate of Compliance Radioactive Materials Package D

g**"**

Identification No. USA /6574/B( )

Hittman Nuclear & Development Corp.

'[9 4

Model No. HN-200 a;

Reference:

Docket No. 71-6475 Safety Analysis Report HN-200, Rev. 1 (8 copies)

HNDC Dwg. #C001-5-9200 Rev. I(6 sheets, 8 copies)

Dear Mr. MacDonald:

Reference is made to our letters of September 11, 1979, and September 24, 1979, which requested the extension of the current Certificate of Compliance for the subject radioactive materials package.

As discussed in our letter of September 24, 1979, it is requested that extension of the certification be based on the Safety Analysis currently on file and the new drawings which reflect the current "as built" configuration of the cask.

The proprietary Safety Analysis Report submitted with our September 11, 1979 letter, will be revised to include the items discussed in this and previous letters.

The revised Safety Analysis Report will be submitted with an application to grant a full term revision or ex-tension of the Certificate of Compliance.

It is requested that the current certificate be extended for a minimum period of six months to allow time for the revision and review of the revised Safety Analysis Report.

Enclosed are eight copies of Drawing Number C001-5-9200, Rev.

I.,

Sheets 1 through 6.

These drawings were previously submitted with our letter of September 11, 1979, as proprietary drawings.

As re-quested in the October 1, 1979 meeting in your office (Dick Ode-gaarden, NRC; Ross Chappell, NRC; and C. W.

Mallory, HNDC), the September 11, 1979 request that these drawings be treated as pro-prietary and withheld from the public document room, is hereby

.i."

$)h@d 1210 070 g.gg 02 1

mosnosy c

]b Mr. Charles E. MacDonald October 10, 1979 rescinded.

The " Notice" on the attached drawings is an attempt to protect our commercial rights and does not restrict the use of this information for licensing purposes by the Nuclear Regu-latory Commission.

The following new drawings replace those cited in the current certification.

New Old C001-5-9200 Sheet 3 (Rev. I)

HN4301-E-200D Sheet 3 C001-5-9200 Sheet 4 (Rav. I)

HN4301-E-200D Sheet 4

.C001-5-9200 Sheet 6 (Rev. I)

HN4301-E-200D Sheet 6 Drawings Number C001-5-9200, Sheets 1, 2 and 5, are new drawings containing information not included in the original submittal.

Drawings HN4301-C-202, HN4301-C-203, and HN4301-C-204, listed in the current certification show details on the alternate internal packaging configurations not required as part of the Safety Analysis.

Other information requested in the October 1, 1979 meeting and supporting information relative to the current "as built" condi-tion of tho cask and the original design is contained in the following paragraphs.

1.

Fabrication Detnils and Materials of Construction The attached drawings contain the same degree of detail as the drawings now referenced in the current certificate of compli-ance.

In addition, Sheets l and 2 are a parts list which con-tains the details relative to the individual components and materials of construction.

2.

Removal of the Lower Z-Ring and Installation of Stainless Steel Canning over the Lower Impact Skirt A Z-ring (Part 36 on Drawing HN4301-E-200) was originally used to hold the lower impact ring in position.

Br ackets (Part 50) were used to hold the Z-ring in position.

With this design, the impact ring was exposed and contaminated liquid would enter the annulus between the ring and the cask.

During the decontamination of the cask, the cask was modified to prevent future contamination in this area.

As shown on the new drawings (C001-5-9200 Rev.

I, Cheets 3 and 6), the lower impact ring is now canned with stainless steel.

The lower portion of the canning is welded to the beams under the cask, and the conical section is secured by bolted rings (See Sheet 3).

In order to install the canning, it was neces-sary to remove.the lower Z-ring and brackets.

1210 071

-~..

b Mr. Charles E. MacDonald October 10, 1979 The lower Z-ring was not a part of the original Safety Analysis of the HN-200 cask.

The cask sits upon eight 10BJ10 steel beams (See View D-D on Sheet 4).

Th; lower impact ring consists of pie-shaped segments which are inserted between the beams and which also extend up the side of the cask.

Steel plates welded on the ends of the beams and the stainless steel canning hold the lower impact ring segment in place.

During an accident, the foam rings would be in place to withstand impact as required.

3.

Canning of Upper Impact Ring, Covering of Center Section and Relocation of Insulation In the original design, the upper impact skirt was unprotected and formed a cavity which would collect water on the lid of the cask (Dwg. HN4301-E-200).

To eliminate this undesirable condition, the entire ring was canned, and the center of the ring was covered (Dwg. C001-5-9300, Sheet 1).

The fixture used to connect the upper impact ring to the upper Z-ring was modified with the addition of canning.

In the original design, a block of foam 23 inches in diameter was attached to the shield plug insulation assembly.

With the addition of the cover over the impact ring, the foam block was attached to the underside of the impact ring cover (Dwg. C001-5-9200, Sheet 3, Rev. I).

In addition, the insu-lation cap was eliminated.

The removal of the insulation cap is discussed in paragraph 5 below, and a reanalysis of the top impact is discussed in paragraph 7 and Attachment C.

4.

Reduction of Foam in Impact Rings The upper impact ring (part 54) on Dwg. COO 1-5-9200, Rev. H, Sheet 3, shows the configuration of the ring as it currently exists.

The amount of impact material is less than that shown in the prior drawings.

As 1ndicated, the inner portion of the lower edge of the upper impact ring is about one and one-half inches larger in diameter than originally indicated.

This re-duces to about one-half inch at the top of the cask.

Based on an average inner diameter of 67.75 inches, and an average re-fuction of foam of one inch, the reduction in the amount of foam

- less than four percent.

The reduced amount of foam (less than four percent) and the reduced thickness at the inner corner (approximately one-half inch) will not significantly affect the original analyses of the crushing of the foam during corner drop, side impact or top impact.

The amount of foam in the lower impact skirt is also reduced from that shown on Dwg. C001-5-9200, Sheet 3.

The original 1210 972

. Mr. Charles E. MacDonald October 10, 1979 dimension of the foam allowed clearance for removal.

After the cask became contaminated before the canning was added to the lower impact ring (See 2 above), it was necessary to remove the fomn to decontaminate the cask.

Slices of foam were taken from the foam blocks in order to remove contam-ination.

Estimates of the amount of material which may have been removed were obtained by surveying people who participated in this work.

The estimates of the maximum amount of material removed from individual foam segments range from one to two inches.

This reduction in the amount of material in this area is not considered to significantly affect the impact analysis of the cask. The cask is supported on the bottom by an array of 10-inch wide flange beams, shown on View D-D on Dwg. C001-5-9200, Sheet 4.

These beams plus the foam were considered in the energy absorption of the cask support structure (Pages 48 through 50 of the original Safety Analysis), and the amount of deflection on a bottom drop was less than 2.5 inches with a significant portion of the energy absorbed by the deformation of the steel beams (20 percent).

The analysis of the corner drop and the side drop considered only foam, typical of the top impact ring.

The beams in the bottom support structure extend 10 inches beyond the bottom of the cask in all directions and would contribute to the absorption of energy in both the corner drop and side drop cases.

The contribution of the beams would be greater than the reduction of the foam material.

This case will be anal-yzed further in the revision of the Safety Analysis Report.

5.

Modification of Cask Lid Lifting Method The lid of the HN-200 is constructed with 36 steel stiffeners which are one inch thick and 3.5 inches deep (Dwg. HN4301-E-200 and Dwg. C001-5-9200, Sheet 2).

In the operation of the cask, it was found that the spaces between these stiffeners would collect liquid and contamination.

For this reason, canning was added to cover the top and sides of the stiffeners.

In the original design, the cask lid was lifted by three shackles attached by bolts through holes in three of the stiffener bars (Part 19 on Dwg. HN4301-E-200).

With the canning of the stiff-eners. it was necessary to provide another means of lifting.

New lifting brackets (See C001-5-9200, Sheets 3 and 5) were welded to three of the stiffener bars which extend through the canning and provide strength equivalent to the original lifting method.

Attachment A contains the analysis of the new lift lugs and connectors.

Insulation has been added between the stiffeners to decrease the heat input during a hypothetical fire accident.

1210 073

OtEM Mr. Charles E. MacDonald October 1Q 1979 6.

Adequacy of the Tie-Down Structures on the HN-200 Cask and Maximum Weight of Contents The structural members on the HN-200 cask are designed to meet the requirements of paragraph (d) of Section 10CFR71.31.

These structural members are designed to withstand static loads of "2x, 10x, and 5x" in the vertical, horizontal and transverse horizontal directions, respectively, without generating stresses in excess of the yield strengths of the material.

In order to make this analysis, it is necessary to assume a system of tie-downs capable of withstanding the static forces specified.

The system of tie-downs used for this analysis are shown in the original Safety Analysis Report (page 14) and are based on the HTS pipe with turnbuckles having a tensile strength of 250,000 pounds or greater.

The adequacy of the structural members on the cask to withstand the tie-down forces on the cask is shown in the original Safety Analysis Report (pages 13 through 28).

This analysis is based on a cask v:eight of 47,000 pounds, versus 48,000 pounds used in the analysis of the lifting eyes, impact resis-tance and other parameters.

The 47,000 pounds corresponds to a payload of 9,675 pounds and is limited by the stresses in the cask shell under the combined "2x, 10x and 5x" condition specified for the tie-down members.

The weight of the contents also enters into the analysis of the bending of the cask lid assembly under impact conditions (pages 66 and 67).

The original analysis was based on weight of contents of 10,000 pounds.

Accordingly, it is requested that the maximum loaded weight for a single disposable inner container be increased to 9,675 pounds rather than the 7,400 pounds now specified.

The tie-downs used on the HN-200 cask are designed in accor-dance with D.O.T.

regulations in 49CFR177.834(a) and 177.842(d).

These regulations require packages to be blocked and braced to not change positions and to be secured against movement under conditions normally incident to transport.

Attachment B con-tains the analysis of the requirements for tie-downs based on the combined loads resulting f rom maximum braking and turning on a radius and at a speed where the inner wheels are at the point of leaving the road.

A quarter-inch steel cable would provide the combined required cable tension of 4,862 pounds.

Accordingly, the three-quarter inch cables used as tie-downs on the HN-200 cask provide a factor of safety of approximately nine, but would still not allow the tie-down structures or the cask to be overstressed or damaged.

1210 074

n.

+..

...~

b Mr. Charles E. MacDonald October 10, 1979 7.

Top Impact Foot Drop The original analysis of the top impact from a 30-foot drop assumed that the impact ring would shear at a 450 angle (Page 63) and that the amount of foam available to absorb energy would extend beyond the perimeter of the cask.

It also assumed that the Z-ring would support the foam beyond the cask perimeter.

The top impact of the cask has been re-evaluated on a more conservative basis.

This analysis, which is included as Attachment-C, assumes that only the portion of the foam inside the perimeter of the cask, plus the inner disk of foam, will be effective in resisting inpact.

As indicated, the calculation shows a margin of 11.4 percent.

The actual margin will be greater since the outer foam and Z-ring will make some contribution.

8.

Cask Penetrations The only cask penetration is the drain plug shown in Section G-G on Dwg. C001-5-9200, Rev.

I, Sheet 3.

This drain is not used except during decontamination.

Water which may enter the cask while the cover is off is removed by pumping rather than the drain plug.

To our knowledge, the attached drawings and the items noted above represent the current "as built" condition of the HN-200 shipping package.

It is requested that the proprietary information submitted with our September 11, 1979 letter be returned.

The Safety Analysis Report will be revised and resubmitted in approximately 60 days.

In addition, reduced size drawings will be provided to facilitate handling and filing.

An early issuance of the extension of the Certificate of Compliance based on the attached drawings and the revised minimum weight of a single container would be greatly appreciated.

Additional informa-tion or answers to any further questions you may have will be pro-vided upon request.

Very truly yours,

)

1w[C3-C__,

Barry Koh, Ph.D.

Vice President and General Manager cmw blUf)i)

Attachments

ATTACIDIENT A CASK LID LIFTING DEVICE I

I'E'C3 i

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"^f r37i r, " p r N cr ' tit:r p q Carh " : lev in" pi n conn ct or hi, a ret or! 1 i f f cap.,ci t y of cr,'10 pounr:n safe workinrj loar! (n e Fig. V ')

i.nr! an ul t irnate s t r eivj t.'i of %,000 poun9'.

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(t il l' (!"?,I' T tC r:T':r.: ;,

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l l)t (0.75in)(1.00in)

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= 3.69 S,130 psi i

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4'"'" ponne!/ inch luvlt h is th safe loi." por linrar inch of 1/2" welel Ilib <cfr l onri (4800#/in)(15.0 in)(2 welds) = l1-1,000"

=

1210 077 114,000# n 6,100tt

'1 h e safe working load is much greater than the actual load (cask tid wt.), hence the rib weld length is adequate

.s ATTACIDIENT B llN-200 SIIIPPING CASK ANALYSIS OF TIE DO'#NS

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ATTACllMENT c 1210 085

?00R OR GINAL F.4 Top Impact - 30 Foot Drop a. Ener g _ Absorption by Protective Foam 11.5 in 11 = 7 113 = 32.125 fn 11 = 26.35 in 3 Il2 .0" I l 113-I l l l a h a o o o o a n T Impact Area There are basically two volumes where the foam crushes, (1) tlie foam under the cask lid, and (2) the foam under the cask inside the cask perimeter. The kinetic energy of the drop is as follows: K.E = WX W = 47,000 lbs X= 30 ft (17,000#)(30 ft)(12in/ft) K.E. = 16,920,000 in-lbs K.E. = The volumes ol' loam displaced are claculated as follows; \\*y =n(It2 - Il3 )X (outer ring) 2 V. = v lii X (inncr cylinder) 1210 086

The compressive strength of the foam is equal to 2350 psi therefore: K.E. (71+

2) 350

= ,n ( R,,2 _ yt,2)X + nR X 2350 2 K.E. = J 1 K.E. = 2350 n X(Il ~ It3+ 1 ) 2 2 X = K.E./(2350)(n)(Il _ gz + ) g 3 1 2 2 X = 16,920,000/(2350)(n)(32.125 - 26.55 + 11.52) X 1.99 in = Based on the foam compaction graph at 70% compaction, the foam compressive strength begins to drastically increase. 1.99/8.00 0.62 < .7 = h!argin of safety = (0.62/0.70 - 1) 0.111 = i 1210 087}}