ML20059G858

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Certificate of Compliance 9788,Rev 4,for Model S5W Reactor Compartment Shipping Package.Approval Record Encl
ML20059G858
Person / Time
Site: 07109788
Issue date: 09/07/1990
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20059G851 List:
References
NUDOCS 9009130208
Download: ML20059G858 (4)
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i u.S. NUCLEAR REGULATORY COtsestSSION I fe., **

CERTIFICATE CF CEMPuANCE l. o cra 71 FOR RADIOACTIVE RAATERIALS PACKAGES i nuusen a PA e muuoEn a to1AL NuuofR PAGs4

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E 6fecate is leaued to certify that the packaging and contents doecribed in item $ below, rneets the applicable safety standards set forth in Title 10 Co i

of Federal Regulateons, Part 71," Packaging and Transportation of Radioactive Material" I

b. Tnis cornficais oo.s not reitove the coneionor from compience with any requiremer3t of the reoutstions of ine u.s o.partment of Transpo>tation or other l

appiieao.e rees.aiory sooncies, inciuding the covernment of any country through or intc which tne packa0e will be transported r

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A a twisgegisygomE BASIS OF A SAFETY AWSIS,nf 9,H fCA a F EI' lCADON i

U.S. Department'of Energy.

' Deactivated S5W Reactor Compartment Safety I

Division of Naval Reactors-Analysis Report for packaging dated July 1981, y

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- 1 Washington DC. 20585 as supplemented.

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oocustauuesa 71-9788 l

ficate la conditional upon fulfillan0 the requirements of ' 0 CFR Part 71,' as applicable, and the conditions tpectfied below.

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I (a) Packaging I

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- (1). Model Wo.: S5W Reactor Compartment l

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The package consists.of'a deactivated;and ~defueled 'S5W. Reactor I

l Compartment which has -been. separated,froin the? remainder of the submarine

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hull and prepared for shipmentLby, sealing'allropenings and attaching I

I structural. pads 'for. handling and tiedown. LThe package is between 35 and

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l 45 featxiong and'approximately?cylindr,1callwith a-maximum diameter of 33 g

I feet. The reactor compartment itself,is'between two containment g.

l bulkheads which are added to the package-before shipping. TheLship's.

t hull and the containment; bulkheads define the. package cantainment i

i boundary The forward containment bulkhead may include' existing ship I

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structurt, ich'has been sealed to form a watertight bulkhead. There is I

an overhans of.the hull structure beyond the containment bulkheads' at I

both ends of the package. The hull is' constructed of HY-80 steel and g

l the' containment bulkheads are HT or HS steel. The maximum weight of the t

p' Jage is 2,160,000 pounds. The deactivated reactor niant remains in.-

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i place within the compartment during shipment. - The plant is-defueled and E

I drained except for small inaccessible pockets of water. -Potentially l

l radioactively contaminated components and piping from other locat ins'in 5

l the ship may be placed within the package and secured.-

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I 71-9788.

Page'2L-Certificate No. 9788 - Revision ~No. 4 - Docket No..

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'(a) (3) Drawings o

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' The package is constructed in accordance with the. drawings, figures, and-

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l sketches included in the application'(see Reference, below).

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I (b)

Contents I

I Activated. structural. components associatod with>the reactor and plant i

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i piping, ion exchange resin, and!other miscellaneous components.

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I 230 gallons of contamihate'dswate,rpsjon products'(crud J

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contaminated with radioac$ive fo I

ramatelso he present-in the. package.

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'lon exchange resipsVwith,up to 3.1 curids'of C9-60 may be shipped in the l l

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The af t containmentdulkheads-and stiffeners, horizontal-QTder plate, and any i

l I. 6.o between th.e~ pressure hull.and the outer non-pressdihull must be!

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I structure recessed at least 7 051nches f,7m the aft end of the package.')The forward I

containment'bulkkfad and,.;sttffeners, nitting stiffener'sptieck ptvucture,: and l

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horizontal girditjmust begracessed at least 15.0 JrshesTfrom the, forward end!of l

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the package. g py<. 4']

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The Lowest Service Temperatur'e;(LST) must bt etermined for each tpackage.

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l The package shall not be shipped uni.essnits:LST/issless than or equal to-the I,

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l normal daily minimum temperature % expected dur[ngjthe[shi,pment of :the package.

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I t The minimum waiting time.from finalJreactor :siutdown until shipmsnt shall be in l

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accordance with. Table 5:3 <of. the applicat' ion,tand shall. not be less than 185 i

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i Additiona'l shielding may be provided 'on-the~ exterior ~ of the package by steel' l 9..

plates securely welded to the package: surface -so'as _to remainj'in place under I

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the hypothetical accidant conditionslin 10:CFR Part 71.-,(,

i In addition to the requirements of Subpart G of-10 CFR'Part 71:

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(a) Each package must be preparedifor shipme'nt anda wrated ir decordance w.

i, Procedures", of the-the procedures described in Chapter'7.0," "Operat application.

l (b) Each package'must be tested and maintained in accordance with the procedures-I I

des fibed-in Chapter 8.0, " Acceptance Tests and Maintenance Program", of. the I

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application, l

i Expiration date:' December 31, 1992

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l,Phge'3) Certificate No. 97887-Revision.No,f4'- Docket'No. 71-9788-

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,c REFERENCESi l

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l Deactivated S5W Reactor Compartment Safety AnalysiscReport for Packaging, i

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WARD-RE0(c)-250, dated Juiy 1951.

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>d Supplement: Naval Reactors Memorandum Z#C90-14, 416 dated March 29. 1990 and I

I supplement dated: July 6,.1990. Naval. Reactors Memorandum Z i C90-14456 dated l

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T.0R T 4E U.S NUCLEAR REGULATORY COMMISSIONi l

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Charles E. MacDonald,-

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,,N > Kao UNITED STATES:

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~ APPROVAL RECORD f

Model S5W Reactor Compartment Shipping Package Certificate of. Compliance No.L9788-Revision.4

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By application dated August. 30L ~1990,. the: Division' of Naval Reactors, U.S.: Department _of~ Energy requested an_' amendment to Certificate'of Compliance-No. 9788 to allow as much as 230 gallons-of contaminated waterJ to be1 retained

'in the package.

The water, which is retained in plant components and piping systems,: contains onl crud associated with the plant components.' The ' total: amount of 3 radioactivity.in this water is-less than 0.1% of the crud sources in the. package and thus, will:

not have any significant effects-on the radioactive source assumed for shielding-

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calculations.

The application performed an analysis to show that even' if all 230.ga11ons of' water in the package vaporized as.a result of the hypothetical-fire accident, the total internal pressure woald'not, exceed the structural. limits of the.

package.

t water in The staff agrees with the applicant's conclusion that the addit'or,

-the package will not affect significantly the capability _ of the sackage to meet the requirements of 10-CFR Part 71.-

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e Charles E. MacDonald, Chief Transportation Branch Division ofiSafeguards and Transportation, HMSS SEP 01 1990 Date:

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