ML20041F509
| ML20041F509 | |
| Person / Time | |
|---|---|
| Site: | 07109103 |
| Issue date: | 02/17/1982 |
| From: | Clay Johnson NAC INTERNATIONAL INC. (FORMERLY NUCLEAR ASSURANCE |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 20334, NUDOCS 8203170042 | |
| Download: ML20041F509 (10) | |
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Nuclear Assurince Corporation 52 24 Executive Park West Q
Atlanta, Georgia 30329 gCDgg (404) 325-4200 N
Telex: 549567,542703 9
DOCKETED Yp USNRC Q
715 Horizon Drive 51982 > -~.18cq 2].
Grand Junction. Colorado 81501
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February 17, 1982
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h Mr. Charles E. MacDonald, Chief u en" N'Q3 p'/
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Transportation Certification Branch f; /
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Washington, D. C.
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Dear Mr. MacDonald:
NLI-6502 Spent Fuel Shipping Cask ( AECL Cask)
Docket No. 71-9103 The Nuclear Assurance Corporation (NAC) hereby requests Revision 2 to Certificate of Compliance No. 9103, dated May 3,1978.
This revision is to permit shipment of four irradiated Big Rock Point Nuclear Power Station fuel rods having a new fuel enrichment in the isotope U-235 of not more than 4.6 w/o, for a tetal of 203 grams U-235.
This shipment would be dry, with no coolant in the cask cavity, as is normal for this cask.
Specifically, it is requested that:
a)
Item 5(b)(1)(ii) be added, to read as follows:
(ii)
Big Rock Point Nuclear Power Station zirconium-clad fuel rods enriched in the U-235 isotope with the following specifica-tions:
Maximum U-235 content per rod prior to irradiation, g 51 Maximum average burnup, MWD /MTU 40,000 Minimum decay time, days 365 u) tem 5(b)(2)(ii) be added, to read as follows:
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Four Big Rock Point Nuclear Power Station fuel rods and a maximum decay heat load of 200 BTU /hr.
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Mr. Charles E. MacDonald Page 2 February 17, 1982
- provides the analyses to substantiate the nuclear criti-cality safety of the Big Rock Point fuel rods, and that dry shipment of these fuel rods can be accomplished in the NLI-6502 (AECL) cask in full compliance with the appropriate federal regulations. The analyses are summarized in Table 1.
Plans are currently being made to ship four fuel rods from Big Rock Point to Argonne National Laboratory by March 26, 1982.
Your expeditious review of this request will be greatly appreciated.
In accordance with the requirements of 10CFR170, a check for $150.00 is enclosed.
If you have any questions regarding this matter, please contact me at your earliest convenience.
Very truly yours, NUCLEAR ASSURANCE CORPORATION e
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Charl
. Johnson f
Vice President Engineering and Transportation Services CRJ:bam Attachments h
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ATTACHMENT 1
SUBJECT:
DRY SHIPMENT OF BIG ROCK POINT NUCLEAR POWER STATION FUEL RODS ENRICHED IN THE U-235 ISOTOPE TO NOT MORE THAN 4.6 WEIGHT PERCENT I.
NUCLEAR CRITICALIY SAFETY ANALYSIS 1.0 Summary This section presents an analysis of the AECL cask loaded with 4 BWR fuel rods enrichea to 4.6 w/o U-235. The results of the calcu-lation indicate that the keff of the cask / fuel assembly configura-tion is less than 0.269 at the 99% confidence level.
This value is well below that obtained for fuel presently approved for shipment in the AECL cask.
A calculation to obtain the optimal spacing of the fuel rods was performed using the NULIF code, part of the Fuel Utilization and Performance Analysis Code System maintained by the Babcock and Wilcox Company, Nuclear Power Generation Division.
The resulting optimal pitch was used to develop a homogenized fuel region via the AMPX code preprocessors, and keff was calculated using the KENO-IV code version also maintained by Babcock and Wilcox and the GAM-THERMOS 126-group nuclear data library.
2.0 Data Parameters Fuel Rod Parameters:
4 Pellet Radius: 0.4737 cm Clad Inner Radius: 0.4838 cm Clad Outer Radius: 0.5702 cm Optimum Pitch:
1.73 cm Cell Effective Radius: 0.976 cm Dancoff Correction Factor:
0.1125 Effective Moderator Cross Section per Absorber Atom: 60.91 barns
N-U235:
1.081 X 10-3 atoms / barn-cm N-238: 2.213 X 10-2 atoms / barn-cm N-Zr: 4.227 X 10-2 atoms / barn-cm N-H in H 0: 6.692 X 10-2 atoms / barn-cm 2
N-0 in H 0:
3.346 X 10-2 atoms / barn-cm 2
Homogenized Fuel Parameters:
i N-U235: 2.546 X 10-4 atoms / barn-cm l
N-U238:
5.212 X 10-3 atoms / barn-cn N-Zr: 4.041 X 10-3 atoms / barn-cm N-H: 4.409 X 10-2 atoms / barn-cm N-0: 3.298 X 10-2 atoms / barn-cm Cuboid: 3.46 cm on a side, infinite length approximation Cask Parameters:
No credit was taken for the resonance absorption properties of the depleted uranium angles in the cask; they were conservatively treated as lead.
1 The fuel region was centered in the cask to obtain the full bene-fit of the surrounding water reflector, as shown in Figure 1.
Cask Material Densities (obtained from the SAR):
4 l
Lead: 3.302 X 10-2 atoms / barn-cm Steel :
Iron:
5.994 X 10-2 atoms / barn-cm l
Chromium:
1.839~X 10-2 atoms / barn-cm l
Nickel:
1.815 X 10-3 atoms / barn-cm 2
1 II.
STRUCiURAL 4
1.0 Summary e
i 1
The four rods to be shipped weigh considerably less then the 20 NRU j
or 28 NRX fuel assemblies presently approved for shipment in the
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AECL cask.
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2.0 Fuel Weight Data j
28 NRX Assemblies 4 Big Rock Point Fuel Rods I
l kg U235:
0.550/asbl X 28 asbl = 15.4 0.203 t
Enrichment w/o:
0.93 0.046 kg U:
16.6 4.4 l-l Fuel Weight, 176.4 kg 4.5 kg l
including clad t
and structure
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III. THERMAL I
1.0 Summary The ORIGEN (0ak Ridge Isotopic Generation) code as supported by.
j Babcock and Wilcox was used to calculate the decay heat after 365 days cool-time for the four fuel rods, which is much less than the rated heat load of the AECL cask.
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i Detailed fuel rod temperature calculations were not performed
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because of the very low heat load and the much higher fuel tempera-(
ture tolerance of the Zircaloy-clad oxide fuel.
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Previous analyses of LWR fuel with similar burnups and cool-time f
indicate that the temperature of-the fuel pellets will' be 15 F higher than the temperature of the air filling the cask cavity.
r This indicates that fuel temperatures on 100'F days will be signif-i icantly less than 200 F.
3 I
-. ~. - - - -
P IV. SHIELDING 1.0 Summary The ORIGEN code also provides 6, y, and neutron source terms, as well as thermal generation rates. A calculation was performed for 28 NRX assemblies to allow comparison to the four Big Rock Point fuel rods. A detailed shielding analysis was not performed because l
the source terms for four BWR rods were much less than those for l
the fuel the AECL cask is currently permitted to carry, resulting l
in much lower cask surface dose rates.
l 2.0 Discussion Spectral differences between radiation produced by NRX and BWR fuel will cause a small differenc? in the effectiveness of the AECL cask shielding, however, an estimate of cask surface doses may be ob-tained by ratioing the source terms:
m 4 Rod Source Term Dose
= Dose 4 rods HRX 28 NRX Asbl Source Term fuel 28 NRX Asbl 4 BWR Rods Source Teros:
s 870,000 Curie 11,000 Curie Y
272,000 Curie 500 Curie 7.6 X 105 n/sec 2.2 X 106 n/sec Surface Dose Rates:
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<138 mR/hr
<1.39 mR/hr e
n 0.001 mR/hr 0.003 'mR/hr 4
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Total Surface Dose Rates:
28 NRX Asbl:
138 mR/hr 4 BWR Rods:
1.4 mR/hr V.
GASE0US FISSION PRODUCT INVENTORIES 1.0 Summary The ORIGEN calculations performed for the shielding analysis also provide nuclide inventories.
Inspection of the caiculation results shows that the four Big Rock Point fuel rods contain considerably less gaseous fission product material than the NRX fuel currently
. shipped in the AECL cask.
2.0 Resul ts The gaseous fission products with significant amounts are tabulated below:
28 NRX Asb1 4 BWR Rods 4BWR/28 NRX (Curies)
Iodine 131 8.37 9 X 10-11 10-11 Tritium 71.12 2.36 3.3%
Xenon 131M, 133 4.05 7 X 10-8 2 X 10-8 j
Krypton 85 2054 48.13 2.3%
Other gaseous fission products have concentrations below the recommended cutoff, 10-25 Curies, for ORIGEN.
i 5
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TABLE 1 COMPARIS0N OF 4 BWR FUEL RODS TO 28 NRX FUEL ASSEMBLIES i
l 1
28 NRX 4 BWR Fuel Rods Assemblies (cool-time 365 days)
A.
Structural Fuel Weight 176.4 kg 4.5 kg B.
Criticality Keff
< 0.75 (measured) 0.269 (calculated)
Initial U-235 15.4 kg 0.203 kg l
C.
Thermal Heat Load 11,855 BTU /hr 184 BTU /hr
}
0.
Shielding Total S and y Activity 1,142,000 Curies 11,523 Curies 1
Cask Surface Dose 138 mR/hr 1.39 mR/hr Neutron Source 7.6 X 10 n/sec 2.2 X 106 n/sec 5
Cask Surface Dose 0.001 mR/hr 0.003 mR/hr E.
Gaseous Fission Product Inventory Iodine 8.37 Curies (SAR) 9 X 10-11 Curies j
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a 2/-N/03 Docket No.
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William O. Miller License Fee Management Branch Office of Administration MATERIALS TPAi!SPORTATI0tl APPROVAL CLASSIFICATI0!!
Applicant:
-/7 M Approval l'o:
7/b 3 Fee Category
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0 /kqf 8 Application Dated:
d // 7 /8 2 --
Received:
2 Applicant's Classification:
The above application for amendment has been reviewed by the WSS Transportation Branch, in accordance with Section 170.31, and is classified as follows:
- 1. ~ Amendments to Accrovals in Fee Catecories 11A throuch 11E (a)
Major (b)
Minor (c)
Lddministrative 2
Justification for reclassification:
l 3.
The application was filed (a) nursuant to written NRC request and the amendment is being issued for the conynnience of the Com:aission, or (b)
Other (State reason):
FBb V
3ig nature:
Branch [!!!SS Transportatj'on,Th Date:
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