ML20023C162
| ML20023C162 | |
| Person / Time | |
|---|---|
| Site: | 07109788 |
| Issue date: | 05/06/1983 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20023C161 | List: |
| References | |
| NUDOCS 8305110614 | |
| Download: ML20023C162 (4) | |
Text
.
I b.
f a
t Form NRC418 U.S. NUCLEAR REGULATORY COMMISSION i
CERTIFICATE OF COMPLIANCE 10 C R 71 For Radioactive Materials Packages f.hh*
1.(el.Tgtal No. Pages...
..., l N
.q No.
1.(d)
No.
,s
- 2. PREAMBLE
, 2.f al This certificate is inued to satisf'y Sections 173.393a,173.394,17.3.395,'and 173.396 of the Department'of Transportation. Hazardous
' Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10a and '146-19-100 o_f me Department'of Transportation. Dangerous Cargoes Regulations (46 CFR 146-f 49), as amended.
The packa6ing and metents described in item 5-below, meets the safety" standards set-fotth.in'Subpert'C o'f'T1tte 10,' Code of i
J.(b).
Federal Regulations, Part 7t, Packaging of Radioactive Meterials for Transport and. Transportation of Radioactive Material Uader Certain Conditions."
2.(c)
This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory. agencies, including the government of any country through or into which the package will be transported.
- 3. This certificate is issued on the basis of a safety analysis report of the package design or application-3.(a)
Prepared by (Name and addre.ts):
3.(b)
Title and identification of report or application:
U.S. Department of Energy Deactivated SSW Reactor Compartment Safety Division of Naval Reactors Analysis Report for packaging dated July 1981 Washington, DC 20545 71-9788 3.(ci Dockei No.
- 4. CONDITIONS This certificate is c nditional upon the fulfilling of the requirements of Subpart D of '10 CFR 71, as applicable, and the conditions specified in itsm 5 Lelow.
- c. 5. 'Doecription of Pactreging and AuthorireB Contents /Model Number'; Fietilt Class, Other Conditions, and
References:
(a) Packaging l
(1) Model No.:
S5W Reactor Compartment (2) Description The package consists of the deactivated and defuled S5W Reactor Compartment which has been separated from the remainder of the, submarine hull and '
prepared for shipment by sealing all openings and attaching structural pads for handling and tiedown. The package is approximately 37 feet c
long and approximately cylindrical with a maximum diameter of 33 feet.
The reactor compartment itself is between bulkheads. There is an overhang of the hull structure beyond the bulkheads at'both ends of the package.
Various potentially radioactive components attached to the after bulkhead are enclosed within a sealed cover during shipment.
All other radioactive material in the package is within the reactor compartment. All penetrations to. the compartment are sealed.
The hull is constructed of HY-80 steel and.the bulkheads are HY-80 or HT J
- e ' teel t sMaxiinum weight of. thegackage -is approxilnately 2,016',000 l
s-s pounds. The deactivated, reactor plant remains in pl. ace within.the compartment during.shipnient.
7,p giriaicBessible pockets of" wit'teF.is. defueled and drained exceptt.. T Tjie, plant
~
w pm-e&.4 removed.
Potentially-contaminated components.and piping from other locations in the ship may be placed within the compartment and secured.
P305110614 830506 PDR ADDCK 071*****
C PDR n
4 s'
Page 2 - Certificate No. 9788 - Revision No. 0 - Docket No. 71-9788 5.
(a)
(3)
Drawings The package is constructed in accordance with the drawings, figures, and sketches included in the application document (see Reference,..
~ *'
.4
- .below).2
- ' ~ ' ' ' '
^
(b) Contents
~
. Activated structural cpmpon'ents assoc'f ated with thi r'eactor and plant
piping, and other miscellaneous ~ components contaminated with radioactive-.
- i'
. ' ' corrosion' produ~ cts -(crud). ' Approximately 50' gallons of' contaminated' water';
may also be present in the package..
~
6.
The package may not be shipped until at least 365 days after final reactor shutdown.
7.
Expiration date: May 1, 1988.
REFERENCE Deactivated S5W Reactor Compartment Safety Analysis Report for Packaging, WAPD-RE0(c)-250, dated July 1981.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION s
m.
e Charles'E.'MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, if4SS Date:
c.
p a. L* r d. t '}:.. Us ?s,'
p.if e.".~fs';e.'.
l$ :, t*. A } *....m :.~ 7 i. <4 ;.,.,. :ti.
- S-
> : ~ i. '-C
.Q 4
.a.,;. 's s
0
.x 8
g 4
e
+
3 l
U.S. Nuclear Regulatory Commission i
Transportation Certification Branch Approval Record Model S5W Reactor Compartment Shipping Container Docket No. 71-9788 l
. By application-dateduJune 30r1982, the Divisiont of Naval Reactdrs, UeS.^ '
4 e
Department of Energy requested a Certificate of Compliance for the SSW Reactor Compartment Shipping Container.
Package 'Descripdon.
The'pa'ckaha' bas'ically' consists of'a S5W1Reactior'C6mpartment'which has' -
f io 1
been separated from the remainder of.the submarine. hull. All openings and penetrations to the compartment are sealed before shipment.
The reactor plant remains in place within the compartment during shipment.
The reactor plant is defueled and drained, except for small inaccessible pockets of water.
The container is cylindrical in shape and is approximately 37 feet long by 33 feet in diameter. The maximum weight of the package is approximately 2,016,000 pounds. The package may not be shipped until at least 365 days after final reactor shutdown.
Structural Evaluation There are no lifting or tie-down devices that are considered to be a structural par.t, of,the packa.ge..
The application shows that the reactor compartment shell is adequate to meet the load resistance requirements of 10 CFR $71.32(a) and the external pressure requirements of 10 CFR 971.32(b).
The application used simple equations and reasoned argument to evaluate 4
the package for the normal and accident tests specified in 10 CFR Part 71.
The application adequately demonstrates that the package will remain intact and perform its intended safaty function under Normal Conditions of Transport.
The package was _ evaluated for a 30-foot drop test in the end,- side, corner and oblique orientations. The results indicate that the package would not experience a reduction in shielding effectiveness and there would be no loss of radioactive material.
The package was also evaluated for the 40-inch puncture test. The-results indicate the 6-inch diameter pin could. puncture through the hul1 ~
of.the reactor compartment (i.e., the package containment vessel)~and,
' assuming the pin is' sufficiently long,'other comporients siich as the-i steam generator could also be punctured. The significance of puncture.
..uhd6r'*Contiisment Evalu&'tfon!""lielows "ioactive material is' discuss wjth, respect. to potential rele~ase_of, rad
^ ' #..
'.@. W.
"" " # " ~ ' " *
~
~
9
4, I
~,
Containment Evaluation The containment provided by the package has been reviewed for normal and accident conditions and has been found to satisfy the requirements of 10..CFR. Pa r.t 71...
,. 4
.4..
The contents which must be contained during shipment are irradiated corrosion products (crud). The application c'onservatively assumed that 33% of all. surface crud is' loose; 50% of all loose i:rdd. from the steam
. generators and 20%. of all loose crud from other components.is assumed to
~
escape to the. reactor compartmenti For normal conditions', the applicatf or$ shows there would be no breac'h of the reactor compartment. Therefore, there would be no release of radioactive material. The application also demonstrated that the concentration of contamination in the water within the reactor compartment would be within the limits specified in 10 CFR Part 71.
Under accident conditions, the application indicates the reactor compartment could be breached as a result of the puncture test. However, the maximum expected release is within the limits specified in 10 CFR Part 71. This conclusion is conservatively based upon the assumption that loose crud from the steam generators, main coolant piping system, reactor vessel, and purification system may be present in the reactor compartment.
Shielding Evaluation The external radiation levels for the package were evaluated in the application and found to be within acceptable limits under both normal and accident conditions.
M!
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS MAY 0 61983 Date:
l
'.v..
.e.. >.. u. -.. n.:. ;..
,....;. a :.,,.. r.. n..
... :.,c...~
l l