ML20236X039
| ML20236X039 | |
| Person / Time | |
|---|---|
| Site: | 07106003 |
| Issue date: | 12/07/1987 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20236X031 | List: |
| References | |
| NUDOCS 8712080384 | |
| Download: ML20236X039 (9) | |
Text
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.senC Pomelets U.S. NUCLEAR CETULATORY C1MMISSl!N I
- u CERTIFICATE CF COMPLIANCE w cFR n FOR RADl! ACTIVE MATERIAt.S PACKACES MBER b RE SiON NUMBER c. A G O NT C Tl NUMBER d. P E NUMBER 3. tot L NUMBER f AGES 1_c, CERTIF
- 2. PREAMJLE
- c. This certificate is issued to certify that the packaging and contents desenbed in item 5 below, meets the appucable safety standards set forth in Title 10. Code of Federal Regulations. Part 71. " Packaging and Transportation of Radioactive Material?
- b. Th3 certificate does not reheve the consignor from comphance with any requirement of the regulations of the U S. Department of Transportation or other apphCable regulatory agenCles, including the government of any country through or into which the package will be transported.
& THIS T FICA 5 THE BASIS OF A SAFETY ANALYSIS RE RT OF THE A GO T ON i
U.S. Department of Energy Safety' Analysis Report for M-73v sni)FHig
,: Division of Naval Reactors container dated December 30, 1958, as i
Washington, DC 20585 supplemented.
c-T NuuBER - 71-6003 4 CONDITIONS .
Th3 certificate as conditional upon fulfilhng the requirements of 10 CFR Part 71. as apphcable, and the conditions specified below.
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[ (a) Packaging (1) Mode 1INo.: " M-l'30 - ;
(2) Description .,
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The fodel No. Mil 30' shipping container is an upright cylinder 84 inches in diameter,by 158 inches overall height. . The container walls consist of;a finned 1-inch thick, outer shell~(fabricated from either carbon steel, carbontsteeltwith stainless' steel' clad, or solid. stainless steel),10 iriches.of lead shielding,'and a 1-inch thick; inner pressure vessel.(fabricated from carbon" steel. clad with stainless steel). The ;
top of the con.tainer isicovered'witha shielded closure head which is boltedsto the' container and seals the-pressure vessel. An access opening.with a b'olted shield' plug is provided in the closure head for li loading and unloading spent fuel.
The pressure vessel has an inside diameter of 55 inches. The central region contains a secondary heat exchanger (not used during shipment) surrounded by a 1/2-inch thick carbon steel backup cylinder 29 inches in diameter. The annulus <which remains between the backup cylinder l and the pressure vessel provides a space 13 inches wide and 130 inches high for spent fuel. The spent fuel is contained in the annulus by module holders designed for the particular core to be shipped.
The container has external penetrations to the pressure vessel for steam and water relief lines and a fill and drain line (which are capped during shipment) and a pressure sensing line which remains open to a pressure gage during shipment. The container also has penetrations which do not open to the pressure vessel for secondary heat exchanger lines (which are capped during shipment) and a temperature sensing '
line. ;
87120GO384 871207 l PDR ADOCK 07106003 C PDR l
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_ CONDMONS (c:ntinued)l L WW " MGW kW ??' NkdH JPage 2 Certificate No. 6003 -! Revision No. 8 . Docket No.'71-6003' u
l.
I5' . . (a)L; Packaging (cont'd)
(2) Description (cont'd)
For LWBR spent: fuel' shipments, the heat exchanger and' associated Jstructures have'been removed..externalipenetrations. plugged'and seal welded,:and'an externalishield and. energy absorber added during modifications... '
i its transport. vehicle by an "A"1 frame-Thecontainer.is,supportedon,hfl,adedcontainerwithoutits.
structure., Gross .weightifof. th o support-structureisapproximat'el/228',0004ohnds.
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.(3) . Drawings-
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The packaging-is constructed in accordance'with! General Electric 6
, Drawing ,Nos; 247E209, Sheet 1, Rev.- R; Sheet 3'2, Re~v. K; Sheet 3, Rev..
1T; Sheete'4', Re'vl U;'; Sheet 5 of 5, Rev.;Fjand 247E228L Rev. F.
AG- pjys gg For LWBR, spent fuelYshipmentsi the container has.been modified in.
accordance with Westinghouse Electrici. Drawing ll76J481; Sheet 1. Rev.! G, Sheet '2iRev. E and anfexternaleener with.. Westinghouse. Elec'tric . Drawing!gyfabsorber 15.25E32,,Res.A.S addedsin accordance .
'(b) Contents hhh ['
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(1) Typeand<formof[maleri51[AgM;Jny[#' @
. . ,# 4 Irradiated fuel assemblies', activated /corrosionjpoducts and structural
_ parts containing up to 40 gallons of. residual (contaminated water. The fuelassembliesfandsructuralpartsareof{the.followingtypes:
(1)- S3W/S4W fuel ^subassembl.ies.of core type 2.
s (ii) S5W fuel modules of core types 2 or 3.
(iii) S5W corner fuel modules of core types 2 or 3.
u j
l (iv)- .DlG fuel modules of core types 1 or 2. )
(v) DlG removable fuel assemblies of core types 1 or 2.
(vi) SIC /S2C fuel modules with control rods.
(vii) SlC/S2C peripheral fuel' modules.
(viii) S3G-3/3A fuel module with or without control rods.
(ix) SAD cell. 1 1[
. . . . . ...c .,......o . , .. . . . . . . . . , , , , . ... . 1,. ...:w,,v,,,,,,,,. ,, ,
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. CONORTIONS (continued) i llN
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. Page 3 - Certificate'No. 6003 - Revision No. 8 - Docket No. 71-6003 !
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l 5.- (b). Contents (cont'd) l (1) Type and form of material'(cont'd) !
l (x) .S3G-3/3A irradiated thermocouple and thermocouple cases. I I
(xi). LWBR blanket fuel modules.
l (xii) LWBR' reflector fuel modules. l 1
-(xiii) LWBR. seed fuelfmodufes* A (,jj I
4}At* *-Q i (xiv) S8G l
s vfulldize fuel' cell with cr w)thout control rod.
e
.4 (xv) S8G?partialsizefuelcellwithor/s without control rod. g vi .
L,.6 g (xvi) s S5W-4A_ recoverable irradiated fuel modules with control- l 1 frod.,jey Ag - l l
sq vy . gx I f,
(2) Maximumquantityof[*pmaterialipeFl package 3 s
- x j-l y
- 52 fuel ads $mbliesia.sjescribed in 5(b)(1)ii).
.(1) p X.- %
4
_o _, , 1 (ii) L .12 'fu'el assemblies ~ asidescribed in' 5(b)(1)(ii) or 9 fuel I
I
. assemblies.as=describedin'5(b)(1)(ji)and;4fuelassemblies i m asdescribedinj5(b)(1)(iii).
, - s. .
l1 (iii) 16 fuel!asssmbl Ns~asi d escribed in 5(b)(l')(iv) and I
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4" fuel assemblies as described in 5(b)(1)(v). I '
I (iv) 9 fuel assemblies'as described inL5(b)(1)(vi) and I 8 fuel 1 assemblies as described in'5(b)(1)(vii). lj
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(v) 10 fuel assemb' lies"a's' described in 5(b)(1)(viii). I J l 1 (vi) 9 fuel assemblies as described in 5(b)(1)(viii) and one fuel I assembly as described in 5(b)(1)(ix).
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(vii) 9 fuel. assemblies as described in 5(b)(1)(viii) and one structure as described in 5(b)(1)(x). lll p
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(viii) 3 fuel assemblies as described in 5(b)(1)(xi). I 1
(ix) 4 or less fuel assemblies as described in 5(b)(1)(xii). lj f
(x) 6 fuel assemblies as described in 5(b)(1)(xiii). I N
(xi) 4 fuel cells as described in 5(b)(1)(xiv); or i l 8
2 fuel cells as described in 5(b)(1)(xiv) ano !
2 fuel cells as described in 5(b)(1)(xv). l (xii) 6 fuel assemblies as described in 5(b)(1)(xvi). l1ll ,
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I LPageL-4CertificateNo.6003-RevisionNo.8-DocketNo. 71-6003
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. 5.; l(b) Contents (cont'd) l l
(3) Shipments shall be further limited by thermal requirements i as follows:' I I
(1) Shipment of contents specified in 5(b)(1)(iv)' a'nd 5(b)(1)(v) and I limited.in 5(b)(2)(iii)lshall have a decay heat' load not to exceed- I 33,500 Btu /hr per shipment. l'!
l (ii)- Shipment of contents?specified in.5(b)(1)(vi).andl5(b)(1)(vii) and- I limited in 5(b)(2)(iv)Jshi11 be made in a stainless steel M-130' I container,and7 sh'all' have'a 'd;eca[ heat load net to exceed 18,960; I Btu /hr pe nshipment. 'N<f . >. , l
%v (iii) Shipm' erit of contents specified in. 5(bf(3 ')'(viii) ,5(b)(1)(1x)and !
5(b)(1)(x) and. limited in'5(b)(2)(v), 5 b)(2)(vi) and 5(b)(2)(vii) I shall be-made at a time after shutdownJas/dytermined from: Bettis l Atomic Powerplaboratory report WAPD-0P(PP)S-4401 dated June 29,11979 I
'ahd shall%have'aidecay.. heat loadMot to exceed 28,620 Btu /hr for. the
!shipboardcore;and30,0,00; Btu /hrifortheprototypecore. l
~ g T , .q w , g (iv). U$hipment of-Q contents:specified!in 5(b)(1)(1)Q,r5(b)(1)(ii) I b and 5(b)(1)(iii) and limite'd in15(b)(2)(1) and 5(b)(2)(ii) I
- shall'be made'no earliertthanE72-daysJafter sh'tdown u and shall I
'have aqdecay, heat' load not';to exceed;33,500@te/hr per shipment. l
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(v) Sh) nEofcontentsIsp fiskiirii(b)(1)(xi[ and limited in !
5(b )(viii).shall have asheatiload nottto" exceed 48,000 Btu /hr. I and a residual water quantity not to exceed 4.6 gallons.
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(vi) Shipmentlof contents specified in 5(b)(1)(x11) and limited in I
-5(b)(2)(ix) shall have a heat load not to exceed 3,672 Btu /hr.. l
,m y (vii) Shipment of contents s'pe'cified in 5(b)(1)(xiii), and limited in I 5(b)(2)(x) shall have a heat load not to exceed 27.600 Btu /hr and I a residual water quantity not to exceed 7.5 gallons. j (viii) Shipment of cantents specified in 5(b)(1)(xiv) or 5(b)(1)(xv) l as limited by 5(b)(2)(xi) shall have a-fully loaded container i heat load not to exceed 15,400 Btu /hr per shipment. I I
(fx) Shipment of contents specified in 5(b)(1)(xvi) and limited in I 5(b)(2)(xii) shall have a heat load not to exceed 23,800 Btu /hr and shall be made no earlier than 92 days after shutdown. l g
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s & CONDtTlONS (continued)
Page: 5 - Certificate No. 6003 - Pevision No. 8 - Docket No. 71-6003 L 5. (cont'd) ,
(c) . Fissile Class- III Maximum. number of packages per shipment: cne'
- 6. For shipments involving the contents specified in 5(b)(1)(ii) or 5(b)(1)(iii) the Model-No. M-130 package shall be inspected to. verify that' boron poisen plates are-in the module holders.
71 :ForshipmentsinvolvingthecontentiisdAHiedin,5(b)(1)(viii),5(b)(1)(1x)or 5(b)(1)(x)~ the thermocouple 'and"thermocodiil'e# cases if included or the' vacant
. module holder shall be located'in the.mid-positiorP:offeither. cage and module-hsider assembly.: W * /r\
v sQ .
Le 8; Shipments shall be made in the' dry condition,' except for res,idual water as
' limited;in5(b)(1),,5(b)(2)(5),and5(b)(2)(7).
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0 Container number four (M-130-4)'has' been modified by adding a-2-inch thick 5 by 4-inch wide steel plate welded between+ fins 32/and 49 at approximately
.18.4 inches from the bottom of:the' container.% The cooling finslin this-
' localized area removed 'to permit. attachment ;of the- plate.directly:to the ,
outer; shell of the containerk " . '
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110. ' Containers M-130' ~4'.and M-130-10 may;be 'ussd for the contents.Jpecified in il 5(b)(1)(viii)'and 5(b)(1)(x) only. '>; ,
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- 11. .. Expiration date: December'31, 1992..
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' CONDITIONS (c:ntinued) I!
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[ Page'6 . Certificate No. 6003 - Revision No. 8 - Docket No. 71-6003 l L 1.
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! I REFERENCES l
LSafaty analysis report for M-130 shipping' container, MAO-E8-703 dated December 30, 1968. I I
Supplements: - Naval Reactor letters A#2256 dated February 24, 1969 and G#1931 dated- I March 3, 1969; General Electric Company letter ONP-74520-526 dated April 3,.1972; j Naval Reactors letter G#3207 dated April 27, 1972; General: Electric Company letter g ONP-74520-528 dated-April 28, 1972; Naval Reactors letter G#3250 dated. June 6, 1972; I
'. General Electric Company letters ONP-745,70-635[ dated,0ctober. 25,1972; ONP-74570-654~ l dat::d December 4,1972; ONP-74570-666? dated "Dbcemberil241972; ONP-74570-682 dated- I I
^
-January 12, 1973; ONP-74570-698' dated January 31,1973;LONP-74570-687 dated February 6,.
'1973;.ONP-74390-65 dated March 4 26, 1973; DLGN-85570-854 datedsSeptember 24, 1973;-
l
' DLGN-85570-901 dated January;le,1974; Naval Reactors 'lettef GT4061 dated January 29,-
- 1974; General Electric Company letters DLGN-85570-924 dated Feb'ruary 15, 1974;.DLGN-g
{h I
' 85570-923 dated March 6, 1974;sDLGN-85570-969 dated May 24 61974T Naval Reactors I
lett:r G#4991 dated November 25,1975;: General: Electric 7 Company letters ONP-74340- 1 JTT-73 dated December lT,1975; CGN-85570-ll45 dated' September 9,1976; CGN-85570 . I
'1146 dated-3eptember 10, 1976; CGN-85570-1148 dated September 14,[=1976; Bettis Atomic P wer Laboratory letter.WAPD-R(K)-1378 dated ' August 30. 1976; WAPD20P(PP)S-4401 dated l y
June 29, 1979; Naval . Reactor letters G#6197 dated July 13, 1979; G#7136 dated I i March 17, 1982; and WAPD-LD(CES)SE-181 dathd September, 1981;;WAPD-LP(CES)SE-96 1 dat:d February, 1982,1WAPD-LP(CES)SE-170idatedrJulyT1981;, Naval.Re s tors letter i G#7160 dated May 18, 1982; Naval Reactorsiletter Gf7582 dated September 7, I 4 1983;-. Naval Reactors letter GfC87.-5692 datedSeptl ember 2,1987;andNavalReactors l letter G#C87-5689 dated Septemberf23, 1987.; , i I
FOR THE U.S.. NUCLEAR REGULATORY COMMISSION I
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Charles E.. MacDonald, Chief I Transportation Branch I Division of Safeguards and I Transportation, NMSS l 1
-Date:_ DEC 0 7 987 l I
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UNITED STATES ;
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. ~ L NUCLEAR REGULATORY. COMMISSION N (ii jg / WASHINGTON lD. C.20555 Hi V 36 1. .
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l a s Transportation Branch 3, ..Ap)roval Record'.
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Model to. M-130 Package-EL A ,, Docket No.-71-6003 >
Revision 8 w<ak cin f ,
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M y' JByLapplication'datedSeptember2.'1987/(G#C87-5692); Naval" Reactors'..U.S. ,
m K Department _ of; Energy, requested;that Certificate No. -6003;be revised to . ,
~L ' incorporate restrictions on.two Model No.1M-130 containers?:These containers, '
u e m ; ? identified.as M-130-4 and M-130-10i were found toihave~ localized shieldingc
,'* defects when first used forks 3G recoverable irradiated fuel shipments. ' Thel .
4" " F , defectsLwere not previously detected because; previous f1 uel typesfshipped in
> 1these two containers were located in the container,such that external-f .radiationnievels'were'not affected by the presence of the' defects.; The M-130-4:1
, container has-been modified'and both containers were re-evaluated,per 10.CFR.
- Part 71 for S3G shipments. LNo. modifications totthe M-130-10 container were' <
needed for S3G shipments. ~As a. result, containers M-130-4 and M-130-10:have 'a '
tbeen; limited.to!S3G shipments (see conditions 9 and:10). -
By.applicatiorJdated September 23,1987(G#C87-5689), Naval: Reactors,U.S.
LDepartment cf; Energy, requested that CertificateiNo. 6003:be1 amended to permit f< '
shipment of S5W-4A recoverable irradiated fuel -(RIF) modules' in the:Modelz No.
? M-130 shipping containe"r.
LBy" application' dated November 10, 1987 (G#87-3254), Naval: Reactors, U.S.
Department of Energy,' request the Certificate No. -6003 be renewed., There. have.
theenlno container modifications.or operationaliexperience'which would preclude continued use of these containers. , ,
- t. .
'The Model No. M-130 container has been previously analyzed and scale-modelt testedi to show compliance with-the structural. requirements-_of.10-CFR Part 71. Since the3 a ..
> weight of the 55W-4A RIF modules is less than.the weight.of currentlyJauth_orized d 1 contents, the: previous structural analysis was deemed sufficient.to show compliance s with 10 CFR Part 71. :The applicant presented additional analyses to s'how that there will be no unacceptable rearrangement of:the' fuel or rupture of the fuel cladding under hypothetical accident conditions. :)
J The applicant-has. demonstrated that the requested contentsi(six'SSW-4A RIF c
- modules) satisfy the criticality requirements of 10 CFR.Part 71. The
- Westinghouse-RCP01 Monte Carlo- computer program was used to establish the. q h
s Wsubcriticality?of a' single damaged and~ flooded Model No.: M-130 container under "the mostireactive accident conditiens specified in,10.CFR 71. The,maximumfK (W : calculated by. the RCP01' program was 0.923. - The results of the RCP01 program,ff compare favorably with K values calculated for NR casks with similar contents using;the KENO computer k gram and the 123-group GAM-Thermos cross sections set.
.The applicant also incorporated several conservative assumptions into the
.RCP01 criticality analysis. They are: .
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P < were used giving maximum. reactivity as a function':of reactor life.-
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- 2) ; Preferential.' voiding of: regions surrounding:the. flooded fuel-modules
.was; assumed to-yield a' maximum K Land increasing; coupling 1between lesL- N u.byLreducing1 neutron absorp
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f3)! The controllrodlin each' assembly: module was? assumed to'be'. withdrawn- '
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' 0 from thel active- fuel! region'by 7.5' inches', whereas the' structural . ,
? ,, , analyses indicate the rod movement to beicloser to'2.5 inches.;
Inhadditiont the, staff verified' material atomic number densities and volumes-o , + usedLin.modeling thelfuel modules,lcontro11 rods and waters (used to model .
1 iflooding). The masses calculated show that the: input'to.the.RCP01 program' correctly. represented the1 cases intended.
<n TheIapplicant's:shiEliling, analysis.is. based.cna.gammaand.neutronsource'
": strengths derived from actualfreactor power history. These sources'were used.
6
! int the SPAN shielding computer program.to calculate dose rates for nonnalcand
. accident conditions.
The!following Lt!ableTis a sumary of the SPAN program results.
Dose Rates.in Mrem /hr.-
, Cask Surface 1 Me'ter from Surface
~ Side-Midplane- Side-Midplane:
Normal.. Neutron- -11.7- .4.8*
Conditions- Gamma' 1.1 0.45*
L 2Acchient Neutron - 45 7 Conditions Gamma - 80
- Calculated by NRC using a R-1.3'),,
fall-off for both neutron and gama flux
- These calculations.show that the dose rate requirements of Part 71 for both inormalland accident con'ditions.of transport are met.
- Because the internal heat: load ~~and pressures are within the: limits for which the m g' Model No..M-130 package has'previously been evaluated, the,NRC staff concludes the f . package is~ adequate for-the thermal conditions.in 10'CFR Part 71. The internal, heat load is limited to 23,800 Btu /hr which requires that shipment not be made 4
Learlier thanL92 days after shutdown.
The! maximum pressure calculated for the package under accident conditions is 350; psi - a:value which conservatively assumes the presence of the 40 gallons of' residual water. The package has been tested to 525 psi.
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- The:NRC staff agrees with the applicant's conclusion that'the fuel cladding will not.be ruptured under accident conditions and-that no radioactive materials will be' released.
The changes requested.in the~ September.2 and September 23, 1987 applications. 'j will not affect the ability of the Model No. M-130 shipping package ~to meet- l the requirements of 10 CFR Part 71. .i
.The certificate of compliance has been renewed for a five-year- period which. l expires December 31, 1992.
4 i
Char es E. MacDonald, Chief i Transportation: Branch -
Division of Safeguards and Transportation, NMSS !
Date: INEC 0 7 N87 a
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