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MimmeurstwsarmiimeLwmws&M4MEFM]LyXh['171WJr2fFpi | |||
: NRC FORM 818 Us NUCLEAR REGULATOR 4Y COMMISSION d | |||
** CERTIFICATE OF COMPLIANCE I | |||
' ''C'"" FOR RADIOACTIVE MATERIALS PACKAGES | |||
- . acvem MMR c PAC 8MGE MMDCArm MBER d PAGEidUuBEn iactamcare5gn 4 USA /5580/B( )F 1 e f ot2 At asuM8 | |||
) | |||
2 Fet.Austs 1 a Th.s cartificate is issued to certify that the packaging and contents descnbed en iteen $ below, meets the apphcable safety standards set forth in Title 10. Code '' | |||
of Federal Regulatsons. Part 11. | |||
* Packaging and Tranphon of Radioactive Matenal." | |||
b This certsftcate does not reiseve the consagr'or from Comphance with any requirement of the regulations of the U S. Dep rtrnent of Transportation or other appbcab4e regulatory agencies encludeng the government of any country through or anto which the package will be transported l' q | |||
l '. | |||
317sgi,c4ys issyoc 1m 84so or a s4rm am vsis,aegtgT,ggeggegr a,c,,, | |||
U.c. Department of Energy Safety Analysis Report 'or SSW Power Unit L Division of Naval Reactors shipping container dated August 9, 1968, ? | |||
Washington, DC 20585 as amended. | |||
c cxacT,um 71-5580 ;. | |||
a co,orious . L This certificate is cond,tionai upon tutvishng in eqwrements of io crn Part 7i, as asp:.cabie. and tne cmdinons specified beio. l s. | |||
(a) Packaging (1) Hodel No.: S5W Power Unit | |||
?, | |||
(2) Description ' s | |||
~ | |||
The SSW Power Un'it shipping container (PUSC) is a container and support assembly designed to shipiand. store new naval reactor power units. The,FUSC is comprised 1 essentially ofithree major assemblies: (ITthe outeriframe,' (2) th'e + inner frame, and (3) the shipping container. . Duding sbjpment, the shipping' container is bolted - to 4the ' inner-frasei "nj a' horizontal, position. Two trunnions welded lower end;of'theto-the middle 'sictiorr ofithe.provide cont'afn'eVaiidiaiso, shipping' theepeans whereby thecod s h' container ~ can b'e rotated-fiom totthe vertical'(loading-unloa'dihp thet))orizontal(shipping) | |||
Attitudesjn' the inner frame. attitude i dre bolted to the inner Thei,rprinions frame.VThp innerturn frame in and trundio'n shipping bases" con *4which[fner are supported by the outerf/areandpedestalthrough80elahtheshockmounts,eachof which is secured.to both the j,nneJQrame and outer frame. | |||
D '**r --!r % 1 Approximate dimensfo:hs of'the' three major assemblies of the PUSC 3 are: shioping container: 95 inches diameter by 234 inches; Inner i Frame: 109 inches width by 52 inches height by 269 inches length; ( | |||
Outer Frame: 121 inches width by 56 inches height by 236 inches ! | |||
length. Maximum weight of the loaded PUSC is approximately 127,900 l lbs. | |||
e | |||
'J. ; | |||
i 8806210437 880610 ADOCK07Og0 i | |||
PDR C | |||
, _ ........... .....-.............-... = | |||
y- | |||
_MNIMO_ NMMEOMEOW)W ; ! | |||
CONDITIONS (contenuM) l> j 5 % ! | |||
ihL Page 2 - Certificate No. 5580 - Revision No. 4 - Docket No. 71-5580 $ l 6 l (3) Drawings k The packaging is constructed in accordance with Westinghouse Electric >M Corporation Drawing Nos. 936F963, Rev. 3 and 936F964, Rev. 2. f (b) Contents (1) Type and form of material N P. | |||
Unirradiated fuel aassemblies of the following type, f (i) SSW Core 4 power unit with control rods insta?. led and secured in place by holddown mechanism. l (ii) ,53G Core 3 power unit with control rods installed and secured in place by holddown mechanism, f (iii) DMC Power Unit with control rods installed and secured in h place by holddown mechanism. > | |||
h (2) Maximum quantity of material per package f l | |||
~ | |||
One fuel assembly as described in 5(b)(1)(i), S(b)(1)(ii), or 5(b)(1)(iii). . | |||
k 5 | |||
(c) Fissile Class ; s III | |||
( | |||
l Maximum number of packages | |||
[' | |||
l per shipment: One (1) g I | |||
I i i 6. Expiration date: ' December 31, 1992. ' | |||
l 8 | |||
y ,.. , REFERENCE l | |||
B Safety Analysis Report for S5W Power Unit Shipping Container, WAPD-0P(R)SA-820 dated b b | |||
q August 9, 1968; Addendum to WAPD-0P(R)SA-820 dated September 28, 1987. | |||
FOR THE U.S. NUCLEAR REGULATORY COMMISSION l 4 a< | |||
l Charles E. MacDonald, Chief h I Transportation Branch gj I Division of Safeguards and [ | |||
Transportation, NMSS l | |||
k Octe: JUN 101988 f i i N ) | |||
I I I k I , , , , ,m , s m . - - y rp - - w . m -r= w w .r- - - - m m w c r +~*- Y | |||
t jf 4 UNITED STATES 4 | |||
f" }, NUCLEAR REGULATORY COMMISSION | |||
. 1 WASHINGTON, D. C. 20555 | |||
+.... | |||
Transportation Branch Approval Record Model No. 55W Power Fawer Unit Docket No. 71-5580 Revision No. 4 i | |||
The applicant has established the suberiticality of the $5W shipping container with a DMC power unit as conter ',s, under accident flooded conditions using the Monte Carlo RCP01 computer program. The neutron cross sections used have successfully calculated relevant naval reactu criticals with the RCP01 program. | |||
The applicant performed a structural analysis to evaluate the response of the contents under the hypothetical accident conditions in 10 CFR 71. The structural analysis indicated that possible movement of the control rods would be limited to a small displacement. The criticality analysis was conservatively based upon an assumption that the control rods would move a larger distance than indicated by the structural analysis. The structural analysis also evaluated the possible rearrangement of the contents under the accident tests specified in 10 CFR 71. | |||
The criticality analysis was conservatively based upon an assumed greater rearrangement of contents than was indicated by the structural analysis. The staff agrces with the structural analyses included in the application. | |||
The staff has verified (through geometry specifications and nuclide number densities) the fissile, poison, moderator and structural mass loadings and locations of the masses used in the computer modeling as stated in the SAR r dated September 28, 1987, Addendum to WAPD-0P(R)SA-820. | |||
The RCP01 program with the neutron cross section set has compared favorably NRC's KENO-IV-123 group neutron cross section set for estimating K,ff for the same naval reactor benchmarks. | |||
The UMC power as contents in the SSW shipping container has been demonstrated to satisfy the requirements of 10 CFR 71. | |||
Charles E. MacDonald, Chief Transportation Branch Division of Safeguards and Transportation, NMSS Date: Jlm 101988 | |||
. - _ .}} |
Latest revision as of 00:25, 17 December 2020
ML20195B503 | |
Person / Time | |
---|---|
Site: | 07105580 |
Issue date: | 06/10/1988 |
From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
To: | |
Shared Package | |
ML20195B497 | List: |
References | |
NUDOCS 8806210437 | |
Download: ML20195B503 (3) | |
Text
MimmeurstwsarmiimeLwmws&M4MEFM]LyXh['171WJr2fFpi
- NRC FORM 818 Us NUCLEAR REGULATOR 4Y COMMISSION d
- CERTIFICATE OF COMPLIANCE I
' C'"" FOR RADIOACTIVE MATERIALS PACKAGES
- . acvem MMR c PAC 8MGE MMDCArm MBER d PAGEidUuBEn iactamcare5gn 4 USA /5580/B( )F 1 e f ot2 At asuM8
)
2 Fet.Austs 1 a Th.s cartificate is issued to certify that the packaging and contents descnbed en iteen $ below, meets the apphcable safety standards set forth in Title 10. Code
of Federal Regulatsons. Part 11.
- Packaging and Tranphon of Radioactive Matenal."
b This certsftcate does not reiseve the consagr'or from Comphance with any requirement of the regulations of the U S. Dep rtrnent of Transportation or other appbcab4e regulatory agencies encludeng the government of any country through or anto which the package will be transported l' q
l '.
317sgi,c4ys issyoc 1m 84so or a s4rm am vsis,aegtgT,ggeggegr a,c,,,
U.c. Department of Energy Safety Analysis Report 'or SSW Power Unit L Division of Naval Reactors shipping container dated August 9, 1968, ?
Washington, DC 20585 as amended.
c cxacT,um 71-5580 ;.
a co,orious . L This certificate is cond,tionai upon tutvishng in eqwrements of io crn Part 7i, as asp:.cabie. and tne cmdinons specified beio. l s.
(a) Packaging (1) Hodel No.: S5W Power Unit
?,
(2) Description ' s
~
The SSW Power Un'it shipping container (PUSC) is a container and support assembly designed to shipiand. store new naval reactor power units. The,FUSC is comprised 1 essentially ofithree major assemblies: (ITthe outeriframe,' (2) th'e + inner frame, and (3) the shipping container. . Duding sbjpment, the shipping' container is bolted - to 4the ' inner-frasei "nj a' horizontal, position. Two trunnions welded lower end;of'theto-the middle 'sictiorr ofithe.provide cont'afn'eVaiidiaiso, shipping' theepeans whereby thecod s h' container ~ can b'e rotated-fiom totthe vertical'(loading-unloa'dihp thet))orizontal(shipping)
Attitudesjn' the inner frame. attitude i dre bolted to the inner Thei,rprinions frame.VThp innerturn frame in and trundio'n shipping bases" con *4which[fner are supported by the outerf/areandpedestalthrough80elahtheshockmounts,eachof which is secured.to both the j,nneJQrame and outer frame.
D '**r --!r % 1 Approximate dimensfo:hs of'the' three major assemblies of the PUSC 3 are: shioping container: 95 inches diameter by 234 inches; Inner i Frame: 109 inches width by 52 inches height by 269 inches length; (
Outer Frame: 121 inches width by 56 inches height by 236 inches !
length. Maximum weight of the loaded PUSC is approximately 127,900 l lbs.
e
'J. ;
i 8806210437 880610 ADOCK07Og0 i
PDR C
, _ ........... .....-.............-... =
y-
_MNIMO_ NMMEOMEOW)W ; !
CONDITIONS (contenuM) l> j 5 % !
ihL Page 2 - Certificate No. 5580 - Revision No. 4 - Docket No. 71-5580 $ l 6 l (3) Drawings k The packaging is constructed in accordance with Westinghouse Electric >M Corporation Drawing Nos. 936F963, Rev. 3 and 936F964, Rev. 2. f (b) Contents (1) Type and form of material N P.
Unirradiated fuel aassemblies of the following type, f (i) SSW Core 4 power unit with control rods insta?. led and secured in place by holddown mechanism. l (ii) ,53G Core 3 power unit with control rods installed and secured in place by holddown mechanism, f (iii) DMC Power Unit with control rods installed and secured in h place by holddown mechanism. >
h (2) Maximum quantity of material per package f l
~
One fuel assembly as described in 5(b)(1)(i), S(b)(1)(ii), or 5(b)(1)(iii). .
k 5
(c) Fissile Class ; s III
(
l Maximum number of packages
['
l per shipment: One (1) g I
I i i 6. Expiration date: ' December 31, 1992. '
l 8
y ,.. , REFERENCE l
B Safety Analysis Report for S5W Power Unit Shipping Container, WAPD-0P(R)SA-820 dated b b
q August 9, 1968; Addendum to WAPD-0P(R)SA-820 dated September 28, 1987.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION l 4 a<
l Charles E. MacDonald, Chief h I Transportation Branch gj I Division of Safeguards and [
Transportation, NMSS l
k Octe: JUN 101988 f i i N )
I I I k I , , , , ,m , s m . - - y rp - - w . m -r= w w .r- - - - m m w c r +~*- Y
t jf 4 UNITED STATES 4
f" }, NUCLEAR REGULATORY COMMISSION
. 1 WASHINGTON, D. C. 20555
+....
Transportation Branch Approval Record Model No. 55W Power Fawer Unit Docket No. 71-5580 Revision No. 4 i
The applicant has established the suberiticality of the $5W shipping container with a DMC power unit as conter ',s, under accident flooded conditions using the Monte Carlo RCP01 computer program. The neutron cross sections used have successfully calculated relevant naval reactu criticals with the RCP01 program.
The applicant performed a structural analysis to evaluate the response of the contents under the hypothetical accident conditions in 10 CFR 71. The structural analysis indicated that possible movement of the control rods would be limited to a small displacement. The criticality analysis was conservatively based upon an assumption that the control rods would move a larger distance than indicated by the structural analysis. The structural analysis also evaluated the possible rearrangement of the contents under the accident tests specified in 10 CFR 71.
The criticality analysis was conservatively based upon an assumed greater rearrangement of contents than was indicated by the structural analysis. The staff agrces with the structural analyses included in the application.
The staff has verified (through geometry specifications and nuclide number densities) the fissile, poison, moderator and structural mass loadings and locations of the masses used in the computer modeling as stated in the SAR r dated September 28, 1987, Addendum to WAPD-0P(R)SA-820.
The RCP01 program with the neutron cross section set has compared favorably NRC's KENO-IV-123 group neutron cross section set for estimating K,ff for the same naval reactor benchmarks.
The UMC power as contents in the SSW shipping container has been demonstrated to satisfy the requirements of 10 CFR 71.
Charles E. MacDonald, Chief Transportation Branch Division of Safeguards and Transportation, NMSS Date: Jlm 101988
. - _ .