ML20024D324
| ML20024D324 | |
| Person / Time | |
|---|---|
| Site: | 07109183 |
| Issue date: | 06/30/1983 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20024D322 | List: |
| References | |
| NUDOCS 8308040538 | |
| Download: ML20024D324 (5) | |
Text
N U.S. NUCLEAR RE~ ULATORY C MMISSloN I
.NRQ FORM 61a CERTIFICATE OF COMPLIANCE l
i le ni to CFR 7' FO RADlIACTIVE MATERIALS PACKA7ES
!E 1 a CERTIFICATE NUMBER b REVISION NUMBER
- c. PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES !
9183 0
USA /9183/B( )
1 4
ls 2 P?EAMBLE This certificate is issued to certify that the packaging and contents desenbed initem 5 below. meets the applicable safety standards set forth in Title 10. Code of j
a Federal Regulations. Part 71. " Packaging of Radioactive Matenals for Transport and Transportation of Radioactive Matenal Under Certain Conditions "
l, b This Certificate does not relieve the Consignor from Compliance with any requirement of the regulations of the U.S. Department of Transportation or other appiscable regulatory agencies, including the government of any Country through or into which the package will be transported.
j
!N 3 THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION a PREPARED BY (Name and Addresst 0 TITLE AND IDENTIFICATION OF REPORT OR APPLICATION f
Duke Power Company Nuclear Fuel Services, Inc. application dated
)
422 South Church Street October 6, 1972, as supplemented.
i Charlotte, NC 28242 i
!g c DOCxET NUMBER 71-9183
!N 4 CONOITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and tne conditions specified below.
(a)
Packaging H
1 T
(1) Model Nc.:
9183
!N iN IN (2)
Description
- g N
A steel, lead and water shielded shipping cask.
The cask is a right i
circular cylinder with upper and lower steel encased balsa impact limiters.
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The overall dimensisns are 214 inches in length and 50 inches in diameter.
L The gross weight of.the cask is approximately 50,000 pounds.
The inner p
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cavity is 178 inches long and 13.5 ir.ches in diameter. The thickness of
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the inner shell is 5/16 inch and 1-1/4 inches for the outer shetl.
The two stainless steel shells are welded to a 2-inch thick stainless steel shield disc at the bottom. The annulus between the inner and outer shells is filled with lead (max. lead thickness 6-5/8 incnes, minimum 5 inches).
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h The lid is stainless steel frustum of cone 7.5 inches thick. The lid is secured to the cavity flange by six, ASTM-A320, Grade L43,1-1/4 inch L
l diameter bol.ts. The seal is provided by two polytetrafluoroethylene l
0-rings.
Four neutron shield tanks, each with surge tank and rupture disc, l
provide a 4-1/2-inch thick (borated) water-ethylene glycol mixture around the outer shell.
Four trunnions, two located on either side of the upper l
i l
or lower impact limiter, are provided.
Other cask features include two e
drain valves located in the bottom shield disc, vent valve, head closure f
gasket leak check valve, and rupture disc-pressure relief valve system h
4 l
located in the cavity flange, For transport the cask may be enclosed in an l
expanded metal cage.
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H 9300040538 830722 PDR ADOCK 07109 q
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mmmzzaxmmm.sammenws' = = mmxv mm2sumsw.amm
U.S. NUCLEAR REGULATORY COMMISSION NRC FORO elsA lI I4 83',-
CONIITIONS (continued)
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Page 2 - Certificate No. 9183 - Revision No. 0 - Docket No. 71-9183 6
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5.
(a)
Packaging (continued) g it i
N (3) Drawings g
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,t lI The Model No. 9183 shipping cask is constructed in accordance with jg II Nuclear Fuel Services, Inc., Drawing No. E 10080, Sheets 1 through 4, E
Rev. 19.
Y (b) Contents E
(1) Type and form of material g
,E Solid nonfissile irradiated hardward.
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(2) Maximum quantity of material per package i[<
Not te exceed a cavity content weight of 3,700 lbs and as needed,
- g apprcgriate compcnent spacers shall be used in the cask cavity to
'y limit movement of contents durina occi@nt conditions of trar sport.
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6.
The cask cavity must be cry (no free water) when delivered to a carrier for fi trans port. If the p>.ckage is leaded or unloaded under water or water is introduced
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into the cavity, residual moisture must b6 removed from the cas< cavity by tlj positioning the cask vertical and with both drain lines opea.
Air pressure must be applied through the open vent line in such a manner to. insure no liquid E
remains in the cask cavity and drain lines.
Alternatively, the cavity must be
- R i
evacuated until pressure falls below 1" of Hg (0.5 psi) at 60 F and remains E
there for 15 minutes. Valve off the vacuum line and re. wye vacuum suur:e.
Cavity must maintain a vacuum of at least 1" of Hg for an additional 15 ainutes f
before returning to atmospheric pressure.
g 7.
The vent and drain valves must be 1/2" FG 466TSW fliser ball valves (Worchester Valve Company, Inc.).
The ball of the valve may have a bleed hole to equalize the pressure between the cask cavity and the ball passage in a closed position.
)
8.
In addition to the requirements of Subpart D of 10 CFR Part 71, each package g
i prior to first use must meet the acceptance tests and criteria specified on g;
pages A-21 thru A-34 of the Nuclear Fuel Services, Inc. application dated October 6, g
1972, as amended, March 1,1973 and Nuclear Assurance Corporation letter dated lR' November 1,1974. The results of these tests must be documented and retained 4
$I for the life of the cask.
9.
The rupture discs for the neutron shield tanks must be type "B" or "DV" (BS&B l
Safety Systems, Inc.) or equivalent.
'g; E-i E
10.
The water-ethylene glycol mixture in the neutron shield tanks may contain up to i
1.0 weight percent boron.
This mixture must not freeze or precipitate in a A,
I temperature range from -40 F to 330 F.
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mamausc-xacmenw--mm.-em-w,-,.c.e.c w c,w
I U.S. NUCLEAR REGULATCY COMMISSION NRC. FORM S1SA sen, ' '
CONDSTIONS (continuedi il
.g ll Page 3 - Certificate No. 9183 - Revision No. 0 - Docket No. 71-9183 jg i
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11.
In addition to the requirements of Subpart D to 10 CFR Part 71, each package i
prior to first use must meet the acceptance tests and criteria specified on
- E
's pages A-21 through A-34 of the Nuclear Fuel Services, Inc. application dated j
I October 6,1972, as amended, March 1,1973 and Nuclear Assurance Corporation ig I
letter dated November 1,1974.
The results of these tests must be documented
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and retained for the life of the cask.
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12.
In lieu of the requirements of 10 CFR 971.54(h), the licensee must perform
's periodic maintenance and testing of 0-rings, drain and vent ball valves, relief i
valves, and ruoture discs of the cask as indicated in the table given below.
ig l
i During inactive periods, the maintenance and testing frequency may be disregarded lg N
provided that the package is brought into full compliance prior to the next use p
II of the package.
I t
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Cask Component Period Test / Action
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Ball Valve Each shipment Hydro test to 80 psig*
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Ball Valve Annually Replace seats and seals
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!E If 0-rings Each shipment Test to 80 psig*
(lR 0-rings Quarterly Test te 167 psig*
0-rings Annually Test to 1006 psig*
Inner Contaiomer.t Vessel Quarterly Test to 250 psig*
j IE Cavity Relief Valve Annually Test at set point
!F-
?E Cavity Rupture Disc Annually Replace iJ i
Neutron Shield Tank
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- l Rupture Disc Annually Replace
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Impact Limiters Annually Test for leakage il
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- There must be no visual (pressure gauge) indications of pressure drop i
N for the component under test during a 10-minute test period.
Otherwise, ly lN corrective action must be taken and the test repeated until such time g
ll as the component meets the specified test.
(Test to pressures equal to
,R 4
or greater than those indicated.)
{
f 13.
The package authorized by this certificate is hereby approved for use under the j
jij general license provisions of 10 CFR 571.12.
lg lN
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14.
Expiration date:
July 31, 1984.
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U.S. NUCLEAR REGULATOIY CSMMISSisN NRG FOR;1818A A 338 CONDmoNS (continued) y
!g N '
a Page 4 - Certificate No. 9183 - Revision No. 0 - Docket No. 71-9183 g
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REFERENCES 1
N
.1 Nuclear Fuel Services, Inc. application dated October 6,1972.
!g 1
- g 3
Supplements dated:
November 9, 1972; January 10 and 22, February 1 and 28, March 1,
'E j
14, and 21, May 4, June 4, and July 26,1973; July 17,1974; May 4,1976; and November 9,!k ll 1977.
y 1
- p
- g Nuclear Assurance Corporation supplements dated
November 1,1974; August 13 and
!y
'I December 24, 1975; September 13, 1976; October 20, 1977; May 25, July 18, and September 25g 1
1978; June 8, July 26, and October 31, 1979; and March 3, July 3, 1980 and December
!g 1
1, 1980.
lE 1
- p l
Duke Power Company Supplement dated: June 30, 1983.
- 1l in
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FOR THE V.S. NUCLEAR REGULATORY COMMISSION 4
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Charles E. MacDonald, Chief g
i iransportatlott Certification Branch
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Divisio:t o7 Ft el Cjcie and
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- 4 Material Safety, NMSS j
1 81 2 Date-s 4
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U.S. Nuclear Regulatory Commission Transportation Certification Branch Approval Record Model No. 9183 Package Docket No. 71-9183 By letter dated June 30, 1983, Duke Power Company requested an interpretation whether the current Certificate of Compliance for the Model No. NFS-4 package requires cask cavity measurements for the shipment of irradiated hardwa re.
The NRC staff has elected to issue a new Certificate of Compliance for the liodel No. NFS-4 cask to separate the shipment of irradiated fuel and irradiated hardware. The new certificate (No. 9183) is restricted to irradiated hardware and clearly indicates what conditions apply to the shipment of the irradiated hardware and does not require cavity measurements.
The certificate has been issued for a period of one (1) year to permit the applicant time to submit a consolidated application to replace the approximately 30 applications referenced in the current Certificate of Comp!iance for the Model No. NFS-4 ra3k.
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C [rles E, fiacDonald, Chie 4
Transportation Certification Branch Division of Fuel Cycle and flaterial Safety, NMSS
'I Date:
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