ML20003H392

From kanterella
Jump to navigation Jump to search
Certificate of Compliance 9144,Revision 0,for Model SGC-1
ML20003H392
Person / Time
Site: 07109144
Issue date: 04/27/1981
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20003H383 List:
References
NUDOCS 8105050740
Download: ML20003H392 (2)


Text

Form NRC 618 U.S. NUCLEAR REGULATORY COMMISSION D

CERTIFICATE OF COMPLIANCE

,g CFR 71 For Radioactive Materials Packages 1.la) Certificate Number 1.(b) Revision No.

1.(c) Package identification No.

1.(d) Pages No. 1.(e) Tota! No. Pages Ql dd O

HE A / 9144 / A I

2

2. PREAMBLE 2.(a)

This certificate is issued to satisfy Sections 173.393a.173.334,173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170-189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Cangerous Cargoes Regulations (46 CFR 146--1491. as amended.

2.(b)

The packaging and contents described in item 5 below, meets the safety staricards set forth in Subpart C of Titte 10. Code of Federal Regulations. Part 71, " Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditeons.**

2.(c)

This certificate does no. relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Tt msportation or otrar applicable regulatory agencies. induding the government of any country through or into which the package wi.I be transporter *.

3. This certificate is issued r n the basis of a safety analysis report of the package design or application-3.(a)

Prepared bv (Name and address):

3.(b)

Title and identification of report or applicz* ion:

Chem-Nuclear Si stems, Inc.

Chem-Nuclear Systems, Inc. application dated P. O. Box 1865.

January 19, 1981, as supplemented.

Bellevue, WA 98009 3.(c)

Docket No. 7l-9l44

4. CONDITICNS This certificate is conditional upon the fulfilling of the reau;rements of Subpart 0 of 10 CFR 71, as applicable, and the conditions specified in item 5 below.
5. Description of Packaging and Authorized Contents, k si Nummer, Fissile Class, Other Conditions, and

References:

(a) Packaging (1) Model No. : SGC-1 (2) Description A steel shipping container for shipment of the lower assembly of a steam generator. The external dimensions of the packaging are 42'6" length and ranging in diameter from 13'5" to 15'7".

The packaging consists of a cylindrical section rolled from 2.5" thick steel plate with 2.75" thick end plates. The packaging is flanged down the center of the cylinder and sealed with a Neoprene gasket and 112, two-incti bolts on 12-inch centers.

The lower shell assembly has two external saddle base support assemblies.

The packaging is provided with two drain plugs. The packaging weight is 276,000 pounds and the gross weight is 722,000 pounds.

The top and bottom openings are sealed with 3 to 5-inch thick steel plate welded to the steam generator. All other openings are, sealed with 2" thick (minimum) plate or bar steel and welded closed.

(3) Drawings The packaging is constructed in accordance with Chem-Nuclear Systems, Inc.

Drawing Nos. Il0-2700-E01, Revision A; 110-2700-E02, Sheet Nos. I thru 3 Revision A; 110-2700-E03, Revision A; ll2-2700-E01, Revision A; and 115-0127-D01, Revision A.

810 5 0 50 F/O'

,,-i

.-m_

Pag 2 2 - Certificate N2. 9144 - Revision No. 0 - Docket Ns. 71-9144 (b) Contents (1) Type and ' form of caterial Steam generator lower assembly containing radioactive material adhering to the inside of the tube surfaces.

(2) Maximum quantity of material per package 750 Ci of principally corrosion products, mainly Co-60.

6.

The steam generator lower assembly must be sealed in accordance with Figures 1.2-3, Rev. 2 and 1.2-5, Rev.1 (pp 1-10 and 1-11). The exterior surface of the steam generator lower assembly must be decontaminated to no more than 220 dpm/100cm2 7.

In lieu of meeting the requirements of 10 CFR 5571.31(d) and 71.36 and Appendix A, Free Drop,10 CFR 71:

a.

An escort must be provided during land transport which is know-ledgeable in the use of radiation survey instrument, be equipped with an appropriate survey instrument, supplies to permit the es-tablishment of a radiation exclusion area, and be provided with written procedures to be followed in an emergency situation.

b.

Appropriate scans must be taken to control the maximum land speed to 10 mr"..

On curves and grades, the maximum land speed must be lim'ced to 5 mph.

8.

The lifting devices-must be securely covered during transport to prevent their use during transport as a tie-down device or for lifting the loaded package.

9.

The package authorized by this certificate must be transported on a vehicle, inland water craft, or barge assigned for sole use of the licensee.

l

10. The package authorized for use by this certificate is hereby approved for use under license provision of 10 CFR 571.12(b).

I 11.

Expiration date: April 30,1986.

l

~

REFERENCES Chem-Nuclear Systems, Inc. application dated January 19, 1981.

Supplements dated: March 31, and April 21, 1981.

i FOR THE U.S. NUCLEAR REGULATORY COMMISSION

&A $M

^W CharTes ~E. MacDonald, Chief i

Transportation Certification Branch Division of Fuel Cycle and 70 Date:

o..