ML21244A483
| 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 NUCLEAR SECURITYADMINISTRATION
"'w2@i'N"o'T"O"N'"Mo^s^s's"fdo**
%Ess NR:RR:ASHunt G#C21-04011 August 26,2021 CONFIDENTIAL Unclassified upon removal ofEnclosures (1) and(2).
John Lubinski Office Director, ofNuclear Material Safety andSafeguards NuclearRegulatory Commission Washington, DC20555 M-140 SPENT FUELSHIPPING CONTAINER -
SAFETY ANALYSIS REPORT FOR PACKAGING S3G-3 SPENT NUCLEARFUEL; REQUEST FORNUCLEAR REGULATORY COMMISSION REVIEW AND CONCURRENCE (U)
Background:
a.M-140 shipping containers areused toship the Navy's submarine spent nuclear fuel,includingS3G-3 from fuel, servicing totheNaval Reactors Facility facilities atthe IdahoNationalLaboratory. TheM-140 shipping containeris certified asaType B package forshipment offissileandhighly radioactive material.
b.TheS3G-3 reactorcore isinstalled inboth Moored TrainingShip (MTS) DANIEL WEBSTER (MTS 626) MTSSAMRAYBURN and (MTS 635). Thereare minor modifications tothe upper fuel module structure ofsomemodules ineach MTS that differ fromstandard S3G-3 modules. MTS626and635are scheduled forinactivation, with theMTS635inactivation beginning inlate 2022.
Discussion:
a.Naval Reactors revised the S3G-3 spent fuel intheM-140 shippingcontainer safetyanalysisreport forpackaging (SARP) andincluded anaddendum tosupport shipmentofspent fuelfrom MTS626and635. Theaddendum supplements analyses intheSARP toaccount forthe minor differences inthe MTScargo whencompared to thepreviouslyevaluated S3G-3 cargo.
b.Enclosure (1)provides asummary oftheSARP changes andEnclosure (2) providestheSARP.Enclosure (3) providesdraft revision17ofthe DOE-NR Certificate ofCompliance. Naval Reactors considers that the Enclosure (2) SARP demonstrates package compliance withthe requirements of10CFR71. Naval Reactors notes that a separaterequest toamend andrenew the NRCcertificate ofcompliance for theM-140 shippingcontainer wasprovided inNRletter G#C21-00922 dated March 23,2021 Document transmitted herewith contains RESTRICTED DATA
2 NR:RR:ASHunt G#C21-04011 Request for Action: NRCreview andconcurrence isrequested forchangestothe S3G-3 spent fuel in the M-140 container shipping SARP, provided (2).
inEnclosure Finalconcurrence isrequested byAugust 2022 tosupport submarineinactivation schedules.
youhave If anyquestions, please donothesitate tocall meat(202) oremail 781-6034 ornicholas.plate@navy.mil.
N. S.Plate Naval Reactors
Enclosure:
SUMMARY
(1) OFCHANGES TO S3G-3 SPENTFUEL INTHEM-140 SAFETY ANALYSIS REPORT FOR PACKAGING S3G-3 (2) SPENTFUELINTHEM-140 SAFETY ANALYSIS REPORT FOR PACKAGING DOE-NR (3) CERTIFICATE OFCOMPLIANCE FOR THEM-140 SPENT FUELSHIPPING CONTAINER, USA/9793/B(U)F-85 REVISION 17 (DRAFT)
Copy to(Prime Contractor):
KAPLADSARS NRLFO NRLFO-Transportation [M.
Division Salamon)
Director, Division ofFuel Management, NMSS,NRC,[A. Kock)
Chief, Storage andTransportation LicensingBranch, 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 SC,RSS,RS,NNL[C.
Analysis, Haslett)
(3)
ENCLOSURE FORTHEM140 SPENT FUELSHIPPING OFCOMPLIANCE DOENRCERTIFICATE CONTAINER, REVISION17 (DRAFT)
USA/9793/B(U)F85 (3)
Enclosure to Ser0 8G#C21-04011
U.S.DEPARTMENT OFENERGY DOE F 5822.1 (585) CERTIFICATE OFCOMPLIANCE OMBApproval (FormerlyEV-618) ForRadioactive MaterialsPackages No.1910-2000 1a.CertificateNumber 1b.Revision No. 1c.Package IdentificationNo. id.Page No. ie.Total No.Pages l USA/9793/B(U)F-85 (DOE-NR)
- 2. PREAMBLE x USA/9793/B(U)F-85 (DOE-NR) 1 4 2a.This isissued certificate under the authority of49CFRPart 173.7(d).
2b.Thepackaging andcontents described initem 5below meetsthesafetystandards setforth insubpart E,"Package Approval and Standards,"
subpart F,"Package, SpecialForm, andLSA-Ill Tests," Title 10,CodeofFederal Part Regulations, 71.
2c.This certificate does not relievetheconsignor from compliance anyrequirement with oftheregulationsoftheU.S. Department of Transportation orother applicableregulatory agencies, the including government ofanycountry through orintowhich the package will be
- 3. This certificate isissued onthebasis ofasafetyanalysis ofthe report package design orapplication (1) P reparedby (Name address):
and (2) Title andidentification ofreportorapplication: (3) Date Naval Nuclear Laboratory (See Contents List) February 1991 P.O.Box79 Spent Fuel inthe M-140 Shipping WestMifflin, PA15122-0079 Container Safety Analysis Report for Packaging
- 4. CONDITIONS This certificate isconditional upon thefulfillingofthe applicable Operational and Quality Assurance requirements of49CFRParts 100-199 and 10CFR Part 71,andthe conditionsspecified initem 5 below.
- 5. Description ofPackaging andAuthorized Contents, Model Number,Criticality Safety index, Other Conditions, and
References:
a.M TheM-140 Spent Fuel shipping container isaright circular cylinder with an overall height of194inches anda 126-inch maximum outer diameter. Thecontainer body c onsists of a 304 stainless steel forging with 14-inch-thick finned side walls anda 12-inch-thick bottom plate onwhich a 5-inch-high setof covered concentric cylinders (which act asanenergy absorber) are welded. The 13-inch-thick (minimum) closure head isheld inplace byawedge closure system consisting of36 wedge assemblies andis sealed via concentric O-rings. Thebody hasaninside diameter of70inchesand aninsideheight of146inches. Anaccess opening, closed bya bolted shield plug, isprovided inthe closure head for loading andunloading ofspent fuel. During transport, a stainless steel protective dome,which fits intoa groove inthe upper body flange, covers the closure head. This domeisbolted tothe container body.
Spent fuel ispositioned within theM-140 shipping container byuseofanintemals assembly. The internals assembly iscomposed ofstacked spacer plates, which have openings for the spent fuel modules. Theintemals assembly hasatopplate ortopplate subassembly which ispreloaded by springs against a retaining ring fitted inagroove inthecask wall. Various intemals assemblies areused toship different types ofspent fuel intheM-140 shipping container.
FORTHEU.S. DEPARTMENT OFENERGY 7a.Address (ofDOEIssuing Omce) 7b. NameandTitle Signature, (ofDOEApproving Otticial)
Naval Reactors U.S.Department ofEnergy C.W.Taylor Washington, DC 20585 Deputy Director, Naval Reactors
Certificate ofCompliance 2 - USA/9793/B(U)F-85 (DOE-NR)
Revision 16(draft) 5.(Continued)
TheM-140 vessel haspenetrations for cooling water circulation,venting, andthermocouples. These penetrations areused only during loading andunloading operations andare sealed during shipment.
Thecontainer issupported bya support ring mounted tothe outside ofthe cooling fins. Thesupport ring isbolted toa specially-designed well-type railcar. Theshipping weight ofa loaded M-140 container is about 375,000 pounds.
b.Authorized Contents Thecontents ofthe container consist of fissile material, fission products, activatedcorrosion products, structural parts,andsomeresidual water (about 6gallons except asnoted below) be assumed to contaminated with activated corrosion products. Maximum quantitiesper c ontainerfor particular cores are asfollows:
(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 than afull container worth of modules mustbeevaluated on acase basis.
(2) S8G: Seeapplicable safety analysis report formaximum allowable quantity offuel modules andcontrol rods.
(3) D2W: Seeapplicable safety analysis report formaximum allowable quantity offuel modules andcontrol rods. Shipments maycontain up to 11gallons of residual water.
(4) S6W: Seeapplicable safety analysis report formaximum allowable quantity offuel modules andcontrol rods.
(5) S9G: Seeapplicable safety analysis report formaximum allowable quantity offuel modules andcontrol rods.
c.M Theminimum CSIfor criticality control ofanM-140 shipping container loaded witheach 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-140 shipment issubject toshielding, thermal, andcontainment limits. TheM-140 container shall notbeshipped until the container isdrained andthe shieldingholdtime issatisfied. Container draining isgoverned bythe thermal limits specified below. Based oncontainment assumptions, shipments shall bemadenoearlier than 150days aftershutdown. Other corespecific restrictions are also listed.
(2) Shipments shall bemadeinadry condition, except forresidual water.
CertificateofCompliance 3 USA/9793/B(U)F-85 (DOE-NR)
Revision 16(draft) 5.(Continued)
(3)Transport byair offissilematerial isnotauthorized.
(4) S3G-3 a) S.hjg!djnng Shipment shall bemadenoearlier than 120days aftershutdown.
b)Thermal: Container draining shalloccur noearlier than 130days aftershutdown oratatime after shutdown asdetermined from applicable safety analyses. Thedecay heat level shall notexceed 62,300 BTU/hr perM-140 container atthe time ofcontainer draining.
c) Control rods.
rod holddown devices mustbeinstalled ondefueling shipment cells which have control d)Thecore agemustben M x A::A-. 4 A-A-- ALLEEyAt222t25 M M m-mem--++ ssn (5) .S8G a) SII.ieldjng Shipment shall bemadenoearlier than 89days after shutdown.
b)Thermal: Container draining shall occur noearlierthan 105days aftershutdown oratatime after shutdown asdetermined fromapplicable safety analyses. Thedecay heat levelshallnotexceed 47,050 BTU/hr perM-140 container atthe time ofcontainer draining.
c) Full with andpartial control fuel rods.
modules maybeshipped inany combination, butall modules must beshipped d)Control rod holddown devices mustbeinstalled onthe cells. Module grapple adapters serve as control rod holddown devices.
(6) D22.W a) Silieldjng Shipment shall bemadenoearlier than 150days aftershutdown.
b)Thermal: Container draining occur shall noearlier than 148days aftershutdown formiddle-of-life shipboard cores oratatime after shutdown asdetermined from applicable safetyanalyses. For all other shipboard cores, container draining should occur noearlier than 163days after shutdown oratatime after shutdownasdetermined from applicable safety analyses. Thedecay heat level shall notexceed 45,000BTU/hr per M-140 container atthe time ofcontainer draining.
c) Control adapters rodholddown serve asthe devices rod mustbeinstalled holddowndevices.
onrodded modules. Theuniversal grapple (7) gW a) Sj1jelfii!1g Shipment shall bemadenoearlier than 50days after shutdown.
b)Thermal: Container draining occur shall noearlier than 340days after shutdown orata time after shutdown asdetermined fromapplicable safety analyses. Thedecay heat levelshall not exceed 41,712 BTU/hr per M-140container atthe time ofcontainer draining.
Certificate ofCompliance 4 . USA/9793/B(U)F-85 (DOE-NR)
Revision 16(draft) 5.(Continued) c)All S6W spentfuel modules must have control rods, control rod restraints,andgrapple adapters installed. A lower pedestal mustbeinstalled ineach module holderport.
(8)E a) Bjeldjng, Shipment shall bemadenoearlier than 100days aftershutdown.
b)Thermal: Container draining shall occur noearlierthan 164days after shutdown oratatime after shutdown asdetermined from applicable safety analyses. Thedecay heatlevelshallnotexceed 55,002 BTU/hr per M-140 container at the time ofcontainer draining.
c) All S9Gspent adapters fuel installed.
modules must have control rods, rod control holddown devices,andgrapple e.References None.
f.Additional Information Nuclear Regulatory Commission review ofthe SARPfor shipment ofS3G-3spent fuelintheM-140 shipping container iscontained intheir memorandum SGTB:NLO 71-9793 dated October 2,1991 Nuclear Regulatory Commission review oftheSARPfor shipment ofS8G spent fuel (bothshipboardand prototype) iscontained intheir memorandum SGTB:NLO 71-9793 dated April 30,1992, andDocket No.
71-9793 dated November 4,2014.
Nuclear Regulatory Commission review ofthe SARPfor shipment ofD2Wspent fuel inthe M-140 shipping container iscontained intheir memorandum No.
Docket 71-9793 datedSeptember 3,1995 and Docket No.71-9793 dated February2010.
22, Nuclear Regulatory Commission review ofthe SARPfor shipment ofS6Wspent fuelinthe 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 ofthe SARPfor shipment ofS9Gspent fuelintheM-140 shipping container iscontained intheir memorandum Docket No.71-9793 dated June 25,2003.