ML19209A673
| ML19209A673 | |
| Person / Time | |
|---|---|
| Site: | 07109853 |
| Issue date: | 09/14/1979 |
| From: | Harris R, Pryor W OAK RIDGE NATIONAL LABORATORY |
| To: | |
| Shared Package | |
| ML19209A674 | List: |
| References | |
| 14101, NUDOCS 7910050166 | |
| Download: ML19209A673 (4) | |
Text
.
OR0 Review of Report ORNL/ENG/TM-15 Safety Analysis Report for Packaging:
The Unirradiated Fuel Element Shipping Container Raymond E. Harris William A. Pryor This review is made under the requirements of DOEM-0529 and 5201.
It covers the containers used for transport of unirradiated fuel elements for the following reactors:
ORR (0ak Ridge Research Reactor)*
BSR (Bulk Shielding Reactor.*
PCA (Pool Critical Assembly)*
HFBR (BNL High-Flux Beam Reactor)**
NBSRR (National Bureau of Standards Research Reactor)***
There are three types of containers which are similar in design. The differences are due to the differences in the fuel elements they are designed to accommodate. Table I summarizes the dimensions of the con-tainers and the fuel elements. Each container is designed to transport seven fuel elements as Fissile Class I.
A.
General Standards for all Packaging:
1.
The material and construction are such that there will be no significant chemical, galvanic or other reaction among con-tainer components or between the package components and the package contents.
2.
The container is equipped with positive closure as required.
3.
Lifting devices for packagings.
The container (s) are designed to be lifted by use of a fork-lift truck. Thus, they are not equipped with container lifting devices per se. The Oak Ridge and Brookhaven containers 7910050 /6 /0
- 0ak Ridge, TN
- Upton, New York O
110y. 29 V
- Near Washington, D.C.
7%E g g$,_
j gg( 1
2 will be lifted from underneath.
Due to the height of the NBL containers, they will be placed on an external skid with the longitudinal center line horizontal and shipped in this manner.
4.
Tie-down devices.
The package (s) is designed to be shored and blocked into place during shipment.
It has no tie-down devices.
B.
Structural Standards for Type B and Large Quantity Packaging Well recognized theory is used in the SARP to demonstrate the capability of the packages relative to requirements in the structural standards for Type B and large quantity packaging.
OR review indicates that ORNL has adequately covered and ade-quately demonstrated in the SARP the ability of the packages to meet these requirements.
C.
Normal Conditions of Transport Standard calculational techniques and test results are used in the SARP to demonstrate compliance of the container with all requirements for normal conditions of transport. The OR review substantiates the ORNL conclusion that the container meets those requirements. Since the outer container is fabricated of stain-less steel,which is ductile over the range of -40 to 1300F, brittle fracture is not a concern.
D.
Hypothetical Accident Conditions Standard calculational techniques and test results are used in the SARP to also demonstrate compliance of the container with all re-quirements under hypothetical accident conditions. The OR review of the calculations and test results substantiates the ORNL con-clusion that the container meets those requirements.
E.
Nuclear Criticality Safety Nuclear criticality safety calculations were made using the KENO IV Code and the Hansen-Roach neutron cross-section sets. The combina-tion has been validated experimently.
1i09 330
3 The calculations provide conservative answers, since the evaluations are based on nine elements per container rather than seven elements per container. Approval was given to 370g 2350 per element. The calculations assumed 350g 23sU 10%. The higher approved loading at this time pemits small increases without revising the Certificate of Compliance.
It can be concluded that these containers meet the requirements for Fissile Class I.
F.
Quality Assurance The quality assurance requirem'ents for fabrication and main-tenance were reviewed by the OR Quality Assurance Branch and were found to be generally acceptable.
G.
Distribution The SARP was distributed under TID-4500, UC-71.
H.
Conclusion The requirements of DOEM-0529 and 5201 have been met. Therefore, it is recomended that the Unirradiated Fuel Element Shipping Containers be certified.
1i09 331
TABLE I SUIDIARY DESIGN DATA CONTAINERS A!;D FUEL El.CIE!iTS Container Fuel Elements Gross outside Inner Basket Na:ninal
!!a x in.uta Llei ht 1.ength Diameter Base Length Cavities
- Dimensions 235g per t
_ In.)
(In.)
(In.)
Fuel l'l e men t (g),
(
Type
( I t). ),
(In.)
(In.) _
(In.)
1.
A.
ORR 580 56 5/8 24 1/2 29 x 29 38 3/4 4x4 A. 38 3/8 x 3.033 x 3.397 370 15. liSR II. 34 3/8 x 2.996 x 3.397 370 PCA 11.
liFilR 70d 75 1/2 24 1/2 29 x 29 57 1/2 4x4 57 1/4 x 2.878 x 3.218 370 1I1.
!;bSRR 850 87 1/8 26 30 1/2 69 3/16 4 1/2 68 51/64 x 3.125 x 3.8125 370 x
x 30 1/2 4 1/2 a.
Oak Ridge Researt.h Reactor b.
ilulk Shielding Reactor c.
Pool Crit ical Asserd21y d.
liigh-Flux 11eam Reactor c.
Nat lonal liureau of Standards Research Reactor
- 7 Cavities per basket; 1 fuci elen.ent per cavity Na c
W r
uu N
,