ML19322E656
| ML19322E656 | |
| Person / Time | |
|---|---|
| Site: | 07106387 |
| Issue date: | 05/07/1979 |
| From: | Tiernan M ENERGY, DEPT. OF |
| To: | |
| Shared Package | |
| ML19322E651 | List: |
| References | |
| 15295, NUDOCS 8004020059 | |
| Download: ML19322E656 (7) | |
Text
-. - _
9-U.s. DEPARTMENT oF ENERGY cis 771 CERTIFICATE OF COMPLIANCE 10 C 71 For Radoactive Materials Packages Ia. Cert 8 cate Numcer 1b. Revision No.
Ic. Pac = age toentification No.
Id. Page No.
t e. Total No. Pages.
USA /6387/BLF (00E-RL) 2 USA /6387/BLF (00E-RL) 1 5
- 2. PREAMBLE 2a.
This certificate is issued to satisfy Sections 173.393a,173.394.173.395, and 173.396 of the Department of Transportation Ha.'
Materials Regulations (49 CFR 170-189).
Ob.
The packaging and contents described in item 5 below, meets the safety standards set forth in Subpart C of Titre 10. Ccde of Fede as Regulations, Part 71,"Pacttaging of Radioactive Materias for Transoort and Transportation of Radioactive Material Under Certain Conditions.
2c.
This certificate does not reheve the consignor from comphance with any requirement of the regulations of the U S. Department of Transportation or other appheaule regulatory agencies, including the government of any country through or into wn.ch the package wdl be transported.
- 3. Th.s certificate is issued on the basis of a safety analysis report of the package design or acotication-(1) Prepared by (Name and address):
(2) Title and ident.f. cation ot report or application:
(3) Date:
Westinghouse Hanford Company TC-138, Rev.1 "HEDL Model-60 January 1978 Hanford Engineering Development Unirradiated Fissionable Material La boratory Shipping Container Safety Analysis P.O. Box 1970 Report for Packaging (SARP)" by F. M. Smith, Richland, Washington 99352 C. A. Rogers, and L. B. Colton i
- 4. CONDITIONS This certificate is conditional upon the fulf dhng of the requirements of sutpart D of 10 CF R 71,as appkcable,and the cond.tions specified in item 5 below.
5.. Descript.on of Packaging and Authorized Contents, Model Numoer, Fissile Class.Otner Conditions, ar d References; a.
The package is identified as the HEDL Model-60 container and is described on Hanford Engineering Development Laboratory drawing number H-3-3?t29, seven sheets, revisions as identified in TC-138, Revision 1.
b.
The authorized packaging consists of a rectangular metal " birdcage" with a centrally positioned inner containment vessel, which is a Schedule 40, 304-L a
stainless steel pipe,101 1/4" long X 6" I.D.
The containment vessel, which has a one-inch welded end plate on one end and a welded flange with gasket and bolted blind plate closure at the other end, is rigidly supported within an outer welded framework (cage) of steel angle iron by means of welded steel support plates and pipe spokes. The containment vessel is fitted with a rupture disc which is designed for up to 300 psi. See H-3-32429 (Sheet 6) for details.
The outer framework, with dimensions of 18" X 112-1/2", is covered with expanded metal mesh (si/2" openings), which is welded to the outer surface of the framework. The tare weight of the package is a nominal 825 pounds, with weight of contents not to exceed 175 pounds. A complete description is found in Document TC-138, Revision 1.
6a. cate of issuance.
May 7, 1979 l sb. e piration cate-FOR THE U.S. DEPARTMENT OF ENERGY la. #ddress tof ooElssaing 0ffacel 7b. n ga Nanw and Tsts 'I'of 00&corowng 0fficall Richland Operations Office
, g[rA g g,y P.O. Box 550
- g. nael W. Tiernan, Director c
Richland, Washington 99352 Safety & Environmental Protection Division hW N
$$# Wsiss
. ~ _.,_. -... -..
.e 5.
Continued c.
The contents of each package authorized by this certificate consist of large quantities of fissile and up to or including Type B quantities of other radioactive materials as noted below packaged as Special Form Material [ meeting the requirements of 49-CFR-173.398(a)]
and as further limited in paragraphs d-f; transport indices for these limits 4
are listed in Paragraph d. below.
(1) Not more than Type B quantities of nonfissile radioactive material, not otherwise specified, in dry, solid form.
(2) FFTF Type Pins Not more than 120 FFTF-type fuel pins, as described in Document TC-138, Revision 1, Appendix A, provided the pins are constrained to the insert described on Drawing H-3-32429, sheets 2 and 3.
(3) Other Pins Containing Plutonium and Uranium Pins containing Pu(310)0 -U(fl00)02 may be shipped under limits 2
given in Table 1.
Carbide and nitride fuel pins are allowed if the Pin Limit Number of Table 1 is multiplied by 0.8 to compensate for the higher densities of carbides and nitrides.
Natural Th02 may be substituted for natural or depleted U02 without changing any limits specified in this certificate.
All pins shall be constrained to Pin Holder Inserts described in Drawings H-3-32429 sheets 2 and 3, H-3-42514. H-3-39691 sheets 1 and 2, or H-3-44280 of TC-138, Revision 1.
The 2gdasrestrictedinAppendixA Pucontegoftheplutonium shall not be less than 10 w}' and the Pu content shall not exceed one half of the NPu content.
(4)
Fissile Material in Undefined Geometry For modgrated gPu (non-isolated form), and 235erial (i.e., moder Pu, 239 u, 440 P
Pu, U in any solid physical or chemical form may be shipped under one of gPu content of the plutonium does net exceed 50% of the following batch limits (or equivalent *), provided the 240Pu content. Paragraph d. below identifies the allowable transport index for these limits.
i i
I l
l
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. (a) 150 g (max) fissile
]
(b) 500 g (max) fissile (c) 900 g (max) fissile For moderated material (i.e., moderation not controlled) in any solid physical or chemical form, the following material may be shipped as a single batch (or equivalent *).
(d) 280 g (max) of U233 ither 237 241Am (e) 15 kg (max) o{4gPu f1p and/or (f) 3 g4{ max)gCf and gp isolated form), 242 m, 243Cm, 244Cm, A
Cm, Cf.
d.
The packaging authorized by this certificate with the contents as limited in paragraph c. above meets the requirements for shipment as either a Type B package with an assigned transport index based solely on radiation levels, or a Fissile Class II package with minimum transport indices (T.I.) as follows:
Type B Fissile Class II Contents Package Minimum T.I.
Item c.(1) x Item c.(2) 0.4 Item c.(3) 7.0 Item c.(4)a 0.1 Item c.(4)(b) 1.3 Item c.(4)(c) 7.0 Item c.(4)(d) 1.3 Item c.(4)(e) 0.2 Item c.(4)(f) 0.6 In addition to the restrictions described above, the decay heat from the e.
contents must ccmply with either of the following conditions:
(1) total heat load not to exceed 37.00 watts, or
(?) heat load not to exceed 12.3 watts per foot of fuel length, f.
Each user of the Model-60 must possess or have access to quality assurance records which substantiate that containers under its control (procurement) meet the design parameters as specified in document TC-138, Revision 1; and the user must have an established quality assurance program that meets the requirements as specified in MC 0529, " Safety Standards for the Packaging of Fissile and Other Radioactive Materials",
and 10 CFR 71 Appendix E, " Quality Assurance Criteria for Shipping Packages for Radioactive itaterial.
- Combinations of fuel types may be shipped within a single package as long as the sum of the masses for each fuel type divided by its batch limit does not exceed unity.
4-1 g.
Prior to each shioment, each container is required to be inspected and packaged according to written operating procedures equivalent to i
those required in Document TC-138, Revision 1.
h.
All details concerning the package and associated hardware not specifically described in this certificate shall be as indicated in Document TC-138, Revision 1.
- i. Each user of packages approved under this certificate shall register his name and address with the Richland Operations Office, U. S. Depart-ment of Energy, P.O. Box 550, Richland, Washington 99352, and have a copy of Document TC-138, Re/ision 1 within his company.
l 1
I I
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LIMITS FOR PltiS C0fiTAltiltiG PLUT0NIUM Aft 0 UFANIUM MODEL 60 Fuel Column Fael Column Diameter Pu+235U Content Limit flumber*
Diameter Pu+23sU Content Limit flumbe (in. max)
Wt.% Max.
(Pins Max)
(in. max)
Wt.% Max.
(Pins Max) 0.205 100 30 0.350 100 10 75 40 75 13 50 60 50 20 35 85 40 25 33 90 35 28 30 100 30 33 28 107 25 40 25 120 0.400 100 7
0.230 100 24 75 10 75 32 50 15 50 48 40 19 35 68 30 26 30 80 25 31 28 85 20 39 26 92 24 100 0.500 100 5
22 109 75 6
20-120 50 10 40 12 0.250 100 20 30 16 75 26 25 20 50 40 20 25 35 57 15 33 30 66 28 71 0.550 100 4
25 80 75 6
23 86 50 8
20 100 40 10 18 111 30 13 16 120 25 16 20 20 0.270 100 17 15 26 50 34 45 37 0.600 100 3
40 42 75 4
35 48 50 7
30 56 40 8
28 60 30 11 25 14 0.290 100 15 20 17 75 20 15 23 50 30 40 37 35 42 30 50 15235 25 60
- Combinatiens of fuel types may be shipped within a single package as long asl%
i sum of the masses for each fuel type divided by its batch limit does not exceed unity.
SAFETY EVALVATION BY THE RICHLAND OPERATIONS OFFICE FOR REVISION 2 TO THE HEDL MODEL 60 SHIPPING CONTAINER - USA /6387/BLF (DOE /RL)
SUMMARY
The HEDL ltodel 60 shipping container is currently certified for transport of unirradiated fissionable material under DOE-RL and NRC certificates.
It has been requested by HEDL in a letter dated liarch 7,1979 that this certificate be revised to increase the container versatility and practicability. A i
similar revision has been requested of the NRC Certificate 6387, which has been transmitted to 00E-HQ.
The following evaluation of the requested changes will establish that adequate bases exist for their approval.
1 DISCUSSION The first change request that Table I of the certificate be revised to include higher enrichment and pin limit number combinations. The current l.
certificate does not allow interpolation of pin limits with varing enrichment (Pu + 2350 contents) range. The new table uses smaller incremental enrichment ranges, therefore, 37 additional pin combinations limits have been added.
The criticality analysis bases the total fissile density at 2 Kg fissile material per foot within the containment vessel (not to exceed 37 inches total fuel length).
Withe the 2,000 gm. of fissile material as the controlling limit the maximum pins limit is derived as follows:
The volume (per foot) of a pin in each " Fuel Column Diameter" section is calculated. The amount of plutonium in that one foot section is calcualted using the theoretical density of the Pu per gm/cmfcm3 and the Pu being 88% of Pu0.
Pu02 as 11.46 gm 2
This gives then multiplied by the volume of one foot of the pin give the total Pu in the one foot section. When the amount of Pu in that pin is divided into the 2,000 gm limit, the maximum pins limit number is determined.
15235
2-The following ratio can also be used to calculate the maximum pins limit number.
100%
0.205 30 X wt%
X dia.
where:
30 is the maximum pin limit for 100 wt% contents of a 0.205" dia, fuel column (could use from any group).
X wt% = wt% of pin where maximum pins limit is not known.
X dia. = dia. of pin where maximum pin limit is now known.
Therefore, the maximum pin limit relates to the 2,000 gm of fissile material per foot within the containment vessel.
Change 2 requests that the drawing number for the 36 tube pin holder insert be referenced. The published Model 60 SARP, TC-138, Revision 1 lists the 36 tube pin holder insert, however, it had not been built. Since then, it was designed on drawing H-3-44280 and fabricated.
Change 3 requests that the density differences of plutonium and uranium carbides (PuC2) and nitrides (pun ) be addressed.
The shipmcnt of plutonium 2
and uranium carbides and nitrides are still limited to a total fissile density of 2.0Kg, fissile. However, the carbides and nitrides have higher densities than the oxides. To compensate for these greater densitites the maximum number of fuel pins per fuel column diameter is determined by multiplying the pins limit number from the Table 1 by 0.8.
Change 3 request allowing substitution of natural Th02 for either natural or 2
re all nonfissionable and have depleted UO. Natural Th02 and depleted UO2 2 for natural or depleted similar nuclear characteristics. The substitution of Th0 U02 will not change any limits specified in the certificate.
This request for revision to the DOE-RL certificate was reviewed by RL-SAF staff and discussed with HEDL staff; it is concluded that a revised DOE-RL Certificate of Compliance for the Model 60 should be initiated.
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M N$r 7/999 Date
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15295
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