ML21244A483

Request for Amendment No 21 for the M-140 Package, Docket No. 71-9793

ML21244A483
Person / Time
Site:	07109793
Issue date:	07/26/2021
From:	Plate N US Dept of Energy (DOE)
To:	John Lubinski Office of Nuclear Material Safety and Safeguards
Bernie White NMSS/DFM/STLB 301-415-6577
References
NR:RR:ASHunt G#C21-04011
Download: ML21244A483 (7)

Text

%

DEPARTMENTOF ENERGY NATIONAL NUCLEARSECURITY ADMINISTRATION

"'w2@i'N"o'T"O"N'"Mo^s^s's"fdo**

%Ess NR:RR:ASHunt G#C21-04011 August 26,2021 CONFIDENTIAL Unclassified uponremoval ofEnclosures (1) and(2).

JohnLubinski

Director, Office ofNuclear Material SafetyandSafeguards Nuclear Regulatory Commission Washington, DC20555 M-140SPENTFUELSHIPPING CONTAINER

- SAFETYANALYSIS REPORT FOR PACKAGING S3G-3SPENTNUCLEARFUEL; REQUEST FORNUCLEAR REGULATORY COMMISSION REVIEW AND CONCURRENCE (U)

Background:

a.M-140shipping containers areusedtoship the Navy's submarine spent nuclear

fuel, including S3G-3

fuel, fromservicing facilities totheNaval Reactors Facility atthe Idaho National Laboratory.

TheM-140shipping containeris certified asaTypeB package forshipment offissile andhighly radioactive material.

b.TheS3G-3reactor core isinstalled inbothMoored TrainingShip (MTS) DANIEL WEBSTER(MTS 626) andMTSSAMRAYBURN(MTS 635).

Thereare minor modifications totheupper fuel module structure ofsomemodules ineach MTS that differ fromstandard S3G-3modules.

MTS626and635arescheduled forinactivation, with theMTS635inactivation beginning inlate 2022.

Discussion:

a.Naval Reactors revised theS3G-3 spent fuel intheM-140shipping container safety analysis report forpackaging (SARP) andincluded anaddendum tosupport shipment ofspent fuel fromMTS626and635.Theaddendum supplements analyses intheSARPtoaccount fortheminor differences intheMTScargo whencompared to thepreviously evaluated S3G-3 cargo.

b.Enclosure (1) provides asummary oftheSARPchanges andEnclosure (2) provides theSARP.Enclosure (3) provides draft revision 17oftheDOE-NRCertificate ofCompliance.

Naval Reactors considers that theEnclosure (2)

SARPdemonstrates package compliance with therequirements of10CFR71.

Naval Reactors notes that a

separate request toamendandrenew theNRCcertificate ofcompliance fortheM-140 shipping container wasprovided inNRletter G#C21-00922 dated March23,2021 Document transmitted herewith contains RESTRICTED DATA

2 NR:RR:ASHunt G#C21-04011 Request for Action:

NRCreview andconcurrence isrequested forchanges tothe S3G-3 spent fuel intheM-140 shipping container SARP,provided inEnclosure (2).

Final concurrence isrequested byAugust 2022tosupport submarine inactivation schedules.

Ifyouhaveanyquestions, please donothesitate tocall oremail meat(202) 781-6034 ornicholas.plate@navy.mil.

N. S.Plate Naval Reactors

Enclosure:

(1)

SUMMARY

OFCHANGES TO S3G-3 SPENTFUELINTHEM-140 SAFETYANALYSIS REPORT FOR PACKAGING (2)

S3G-3SPENTFUELINTHEM-140 SAFETY ANALYSIS REPORT FOR PACKAGING (3)

DOE-NRCERTIFICATE OFCOMPLIANCE FOR THEM-140 SPENT FUELSHIPPING CONTAINER, USA/9793/B(U)F-85 REVISION 17 (DRAFT)

Copyto(Prime Contractor):

KAPLADSARS NRLFO NRLFO-Transportation Division

[M.Salamon)

Director, Division ofFuelManagement, NMSS,NRC,[A.

Kock)

Chief, Storage andTransportation Licensing

Branch, DFM,NMSS,NRC[J.

McKirgan)

Senior Project

Manager, STLB,DFM,NMSS,NRC[B.

White)

General

Manager, NNL[G.

Lubinsky)

Manager, Reactor Servicing, NNL[V.

Pantioni)

Manager, Reactor Servicing

Systems, RS,NNL[M.Drewen)

Manager, Shipping Containers, RSS,RS,NNL[S.

Fiscus)

Manager, Shipping Container

Analysis, SC,RSS,RS,NNL[C.

Haslett)

ENCLOSURE (3)

DOENRCERTIFICATE OFCOMPLIANCE FORTHEM140 SPENT FUELSHIPPING CONTAINER, USA/9793/B(U)F85 REVISION17 (DRAFT)

Enclosure (3) to Ser08G#C21-04011

U.S.DEPARTMENT OFENERGY DOEF 5822.1 (585)

CERTIFICATE OFCOMPLIANCE OMBApproval (Formerly EV-618)

ForRadioactive Materials Packages No.1910-2000 1a.Certificate Number 1b.Revision No.

1c.Package Identification No.

id.PageNo.

ie.Total No.Pages l

USA/9793/B(U)F-85 (DOE-NR) x USA/9793/B(U)F-85 (DOE-NR)1 4

2. PREAMBLE 2a.This certificate is issued under theauthority of49CFRPart173.7(d).

2b.Thepackaging andcontents described initem 5below meetsthesafety standards setforth insubpart E,"Package Approval Standards,"

and subpart F,"Package, SpecialForm, andLSA-Ill Tests,"

Title 10,CodeofFederal Regulations, Part 71.

2c.Thiscertificate doesnotrelieve theconsignor from compliance withanyrequirement oftheregulations oftheU.S.Department of Transportation orother applicable regulatory

agencies, including thegovernment ofanycountry through orinto which thepackage will be 3.This certificate isissued onthebasis ofasafetyanalysis reportofthepackage design orapplication (1)

Prepared by(Name andaddress):

(2)Title andidentification ofreport orapplication: (3)Date Naval Nuclear Laboratory (See Contents List)

February 1991 P.O.Box79 Spent Fuel intheM-140Shipping WestMifflin, PA15122-0079 Container Safety Analysis Report for Packaging

4. CONDITIONS This certificate isconditional uponthefulfilling oftheapplicable Operational and Quality Assurance requirements of49CFRParts 100-199 and 10CFRPart 71,andtheconditions specified initem5below.

5. Description ofPackaging andAuthorized

Contents, ModelNumber, Criticality Safetyindex, Other Conditions,and

References:

a.M TheM-140Spent Fuelshipping container isaright circular cylinder with an overall height of194inches anda126-inch maximum outer diameter.

Thecontainer bodyconsists ofa 304 stainless steel forging with14-inch-thick finned side walls anda12-inch-thick bottom plate onwhich a 5-inch-high setof covered concentric cylinders (which actasanenergy absorber) arewelded.

The 13-inch-thick (minimum) closure headisheld inplace byawedgeclosure system consisting of36 wedge assemblies andissealed viaconcentric O-rings.

Thebodyhasaninside diameter of70inchesand aninsideheight of146inches.

Anaccess

opening, closed byabolted shield

plug, isprovided inthe closure head for loading andunloading ofspent fuel.

During transport, astainless steel protective dome,which fitsinto a

groove intheupper bodyflange, covers theclosure head.Thisdomeisbolted tothe container body.

Spent fuel ispositioned within theM-140shipping container byuseofanintemals assembly.

The internals assembly iscomposed ofstacked spacer

plates, which haveopenings forthespent fuel modules.

Theintemals assembly hasatopplate ortopplate subassembly which ispreloaded by springs against aretaining ring fitted inagroove inthecaskwall.

Various intemals assemblies areused toship different types ofspent fuel intheM-140shipping container.

FORTHEU.S.DEPARTMENT OFENERGY 7a.Address (of DOEIssuing Omce) 7b.Signature, NameandTitle (of DOEApproving Otticial)

Naval Reactors U.S.Department ofEnergy C.W.Taylor Washington, DC20585 Deputy

Director, Naval Reactors

Certificate ofCompliance USA/9793/B(U)F-85 (DOE-NR)

Revision 16(draft) 5.(Continued)

TheM-140 vessel haspenetrations forcooling watercirculation,

venting, andthermocouples.

These penetrations areusedonly during loading andunloading operations andaresealed during shipment.

Thecontainer issupported byasupport ring mounted totheoutside ofthecooling fins.

Thesupport ring isbolted toaspecially-designed well-type railcar.

Theshipping weight ofaloaded M-140container is about 375,000pounds.

b.Authorized Contents Thecontents ofthe container consist offissile

material, fission

products, activated corrosion

products, structural

parts, andsomeresidual water (about 6gallons except asnotedbelow) assumed tobe contaminated with activated corrosion products.

Maximum quantities percontainer forparticular cores areasfollows:

(1)

S3G-3:

Seeapplicable safety analysis report formaximum allowable quantity offuel

modules, control rods,and core structurals.

Shipments ofadifferent configuration other than that assumedin the SARP orofless thanafull container worth of modules mustbeevaluatedon acase basis.

(2)S8G:

Seeapplicable safety analysis report formaximum allowable quantity offuel modules andcontrol rods.

(3)

D2W:

Seeapplicable safety analysis report formaximum allowablequantity offuel modules andcontrol rods.

Shipments maycontain up to 11gallons ofresidual water.

(4)S6W:

Seeapplicable safety analysis report for maximum allowable quantity offuel modules andcontrol rods.

(5)

S9G:

Seeapplicable safety analysis report formaximum allowable quantity offuel modules andcontrol rods.

c.M Theminimum CSIforcriticality control ofanM-140shipping container loaded with each authorized cargo isasfollows:

(1)

S3G-3:

CSI= 100 (2)S8G:

CSI= 0 (3)D2W:

CSI= 0 (4)S6W:

CSI= 0 (5)

S9G:

CSI= 0 d.Restrictions (1)

M-140shipment issubject toshielding,

thermal, andcontainment limits.

TheM-140container shall notbeshipped until thecontainer isdrained andtheshielding holdtimeissatisfied.

Container draining isgoverned bythethermal limits specified below.

Basedoncontainment assumptions, shipments shall bemadenoearlier than150daysafter shutdown.

Other corespecific restrictions arealsolisted.

(2)

Shipments shall bemadeinadrycondition, except forresidual water.

Certificate ofCompliance

- 3 USA/9793/B(U)F-85 (DOE-NR)

Revision 16(draft) 5.(Continued)

(3)

Transport byairoffissile material isnotauthorized.

(4)

S3G-3 a)

S.hjg!djnng Shipment shall bemadenoearlier than120daysafter shutdown.

b)Thermal:

Container draining shall occur noearlier than130daysafter shutdown oratatimeafter shutdown asdetermined from applicable safety analyses.

Thedecay heatlevel shall notexceed 62,300 BTU/hr perM-140 container atthetimeofcontainer draining.

c)

Control rodholddown devices mustbeinstalled ondefueling shipment cells which havecontrol rods.

d)Thecore agemustben M x

A::A-.

4A-A--ALLEEyAt222t25 M

M m-mem--++ssn (5).S8G a)

SII.ieldjng Shipment shall bemadenoearlierthan 89daysafter shutdown.

b)Thermal:

Container draining shall occur noearlierthan 105daysafter shutdown oratatimeafter shutdown asdetermined fromapplicable safety analyses.

Thedecay heatlevel shall notexceed 47,050 BTU/hr perM-140container atthetimeofcontainer draining.

c)

Full andpartial fuel modules maybeshipped inanycombination, butall modulesmustbeshipped with control rods.

d)Control rodholddown devices mustbeinstalled onthecells.

Module grapple adapters serve as control rodholddown devices.

(6)D22.W a)

Silieldjng Shipment shall bemadenoearlier than150daysafter shutdown.

b)Thermal:

Container draining shall occur noearlier than148daysafter shutdown for middle-of-life shipboard cores oratatimeafter shutdown asdetermined fromapplicable safety analyses.

For allother shipboard

cores, container draining should occur noearlier than163daysafter shutdown oratatimeafter shutdown asdetermined fromapplicable safety analyses.

Thedecay heatlevel shall notexceed 45,000 BTU/hr perM-140container atthetimeofcontainer draining.

c)

Control rodholddown devices mustbeinstalled onrodded modules.

Theuniversal grapple adapters serve astherodholddown devices.

(7)gW a)

Sj1jelfii!1g Shipment shall bemadenoearlier than50daysafter shutdown.

b)Thermal:

Container draining shall occur noearlier than340daysafter shutdown oratatime after shutdown asdetermined fromapplicable safety analyses.

Thedecayheatlevel shall not exceed 41,712BTU/hr perM-140container atthetimeofcontainer draining.

Certificate ofCompliance

. 4.

USA/9793/B(U)F-85 (DOE-NR)

Revision 16(draft) 5.(Continued) c)

All S6W spentfuel modules musthavecontrol

rods, control rodrestraints, andgrapple adapters installed.

A lowerpedestal mustbeinstalled ineachmodule holder port.

(8)

E a)

Bjeldjng, Shipment shallbemadenoearlier than100daysafter shutdown.

b)Thermal:

Container draining shall occur noearlier than164daysafter shutdown oratatimeafter shutdown asdetermined from applicable safety analyses.

Thedecay heatlevel shall notexceed 55,002 BTU/hr per M-140 container atthetimeofcontainer draining.

c)

AllS9Gspentfuel modules must have controlrods, control rodholddown

devices, andgrapple adapters installed.

e.References None.

f.Additional Information Nuclear Regulatory Commission review oftheSARPfor shipment ofS3G-3spent fuel intheM-140 shipping container iscontained intheir memorandum SGTB:NLO 71-9793 dated October 2,1991 Nuclear Regulatory Commission review oftheSARPfor shipment ofS8G spent fuel(both shipboard and prototype) iscontained intheir memorandum SGTB:NLO 71-9793 dated April 30,1992, andDocket No.

71-9793 dated November 4,2014.

Nuclear Regulatory Commission review oftheSARPforshipment ofD2Wspent fuel intheM-140 shipping container iscontained intheir memorandum Docket No.71-9793 datedSeptember 3,1995and Docket No.71-9793 dated February 22,2010.

Nuclear Regulatory Commission review oftheSARPforshipment ofS6Wspent fuel inthe M-140 shipping container iscontained intheir memorandum Docket No.71-9793 dated August 10,1998 and Docket No.71-9793 dated September 26,2017.

Nuclear Regulatory Commission review oftheSARPforshipment ofS9Gspent fuel intheM-140 shipping container iscontained intheir memorandum Docket No.71-9793 dated June25,2003.