ML20024D381

From kanterella
Jump to navigation Jump to search
Forwards Request for Addl Info Re 830331 Application for Approval of Model PAS-2 Packaging.Response Requested within 30 Days of Ltr Receipt
ML20024D381
Person / Time
Site: 07109181
Issue date: 07/27/1983
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: Hansen L
NUCLEAR PACKAGING, INC.
References
NUDOCS 8308040691
Download: ML20024D381 (3)


Text

s 9 /

'7 m i

L FCTC: RHO 71-9181 Jyt y 1993 g q (, _ c,5 Nuclear Packaging, Inc.

ATTil: fir. Larry Hansen 815 South 28th Street Tacoma, WA 98409 Gentlenen:

This refers to your application dated March 31, 1983, requesting approval of the Model No. PAS-2 packaging.

In connection with our review, we need the information identified in the enclosure to this letter.

Please advise us within thirty (30) days from the date of this letter when this information will be provided. The additional information requested by this letter should be submitted in the form of revised pages.

If you have any questions regarding this matter, we would be pleased to nect with you and your staff.

Sincerely, I

Charles E. HacDonald, Chief l

Transportation Certification Branch l

Division of Fuel Cycle and

!!aterial Safety, ?#!SS i

Enclosure:

As stated Distribution: w/ enc 1 e

y$g RH0degaarden (2) 8 0-CEWilliams l

@S WHLake mN EPEaston CRMarotta D's Docket File o

00 NRC PDR o@

IE HQ 8e Region V no NMSS R/F FCTC R/F G

-d-

! su =4W0degaard n:al...

.. :....CIC...

.......FCIC.

...5(1ECTC.

. ECTC........... dQCTC_....

.... FCTC.

a CEWilliams HLake EPEaston CRMarotta CEPfacEnald 07/>I/83 07/((83

' 07/[83 07/d/,83 07/2983 078t1/83

==>

! nney.one ns p_o;sogncu ano OF FICIAL RECORD COPY

i liuclear Packaaina, Inc.

!!odel No. PAS-2 Packacina Docket fto. 71-9131

/

Encl to ltr dtd: M 271983 Drawings

~'

l.

Drawing fio. X-20-2200, Sheet 1 of 4:

a.

flote 5 should be nodified to require dryness of the absorbent and its grinding in accordance with Section G.2 of the application.

b.

Outer overpack should be narked with I)SA/9181/B( ), not USA /9070/B.

2.

Drawing No. X-20-220D, Sheet 3 of 4:

a.

Show the weld joint requirenent for the longitudinal joint in the outer shell of the shielded sanple cask.

b.

It is not clear in Detail "C," if the lead shield block isolates the valve opening from the verniculite absorbing naterial.

The drawing should be clarified to show that there is corrunication between the valve opening and the absorbing naterial and also between the valve sten and the absorbing naterial.

c.

Detail C is referenced for only one of the two Whitey ball valves.

Indicate the detail applies to both valves.

d.

Specify the bolt circle for the 1/2" lid bolts.

c.

Provide a drawing of the fill tubes.

3.

Provide nanufacturer's data sheet on the Whitey ball valve showing valve operational features and data.

Containnent 1.

Provide rational for not requiring all scaling surfaces scaled with 0-rings to be fabricated fron stainless steel with a surface finish specified. The secondary containnent vessel is fabricated fron carbon steel and because the package is for emergency use, it should have a high degree of reliability.

2.

Because of the possibility of freezing of the liquid contents and subsequent breakage of the primary containnent vessel, the sanple shield should be provided with an internal leak tight and testable Cover.

^">

NR F RM 318 (1 8 ) NRCM 0240 OFFICIAL RECORD COPY L

. e Operating Procedure Section 7.0 1.

Provide flow diagrams in support of Figure 7.1.4-1 (p 7-2).

2.

Revise Iten 7.2.4.9 of the application to clearly indicate that at assembly verification, any leak rate exceeding the design criteria (i.e., leaktight per ANSI N14.5 definition) is grounds for rejecjion.

f less sensitivity than the design leak rate, up to lx10 Tests g/sec, are penaitted but nust be used as a go/no-go test.

atn-cm Acceptance Tests and liaintenance Progran, Section 8.0 1.

Provide acceptance and maintenance program for the outer overpack.

2.

In the discussion of the maintenance progran (Section 8.2), the 0-rings are routinely inspected on an annual basis and replaced every 5 years.

t a.

Revise the annual inspection to include leak testing to denonstrate that the design containment criteria continues to be satisfied by each package used.

b.

Elastemer seals should be replaced annually to avoid aging or wear-out degradation.

3.

Provide the grid dimensions to be used in the gamma scan inspection j

of the sample shield.

4.

Revise the procedures to provide leak testing of the Whitey ball valves.

J

'"c">

RNWAME )

^">

NRC FORM 318 (1080) NRCM O24

___ - _-O F F. IC I A L R EC.O R D_ CO P_ _Y, _ _ _. _ - _ _ _ _._

-