ML20148A920

Forwards Certificate of Compliance 9080 for Model HN-600. Certificate Supercedes Rev 1

ML20148A920
Person / Time
Site:	07109080
Issue date:	10/23/1978
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Barrin J, Kinkade K, Lundvall A BALTIMORE GAS & ELECTRIC CO., CHEM-NUCLEAR SYSTEMS, INC., HITTMAN NUCLEAR & DEVELOPMENT CORP. (SUBS. OF HITTMAN
References
NUDOCS 7810300371
Download: ML20148A920 (7)

Text

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$8 RE0g o

UNITED STATES E

o NUCLEAR REGULATORY COMMisslON g

W ASHINGTON, D, C.

20555 007 2 3 MB FCTR:RH0 71-9080 Those on Attached List Gentlemen:

x Enclosed is Certificate of Compliance No. 9080, Revision No. 2, for the Model No. HN-600 shipping package. This certificate supersedes, in its entirety, Certificate of Compliance No. 9080, Revision No.1, dated June 15,1978.

Changes made to the enclosed certificate are indicated by vertical lines in the margin.

Those on attached list have been registered as users of this package under general license provisions of 10 CFR 571.12(b) or 49 CFR 5173.393a.

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This approval constitutes authority to use this Jackage for shipment of radioactive material and for the package to be slipped in accordance with the provisions of 49 CFR 5173.393a.

Sincerely, 0 *j&

Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety

Enclosures:

1.

Certificate of Compliance No. 9080, Revision No. 2 2.

Addendum No. 1 to NRC SER for the Model No. HN-600 packaging cc:

w/ encl Mr. Richard R. Rawl Department of Transportation 92lo36032/

MODEL NO. HN-600 PACKAGING USA /9080/A OCT 2 3 m Addressees (w/ encl)

Ltr dtd:

Hittman Nuclear & Development Corporation Indiana and Michigan Power Company ATTN: Mr. John C. Darrin ATTN: Mr. John Tillinghast 9190 Red Branch Road P.O. Box 18 Columbia, MD 21045 New York, NY 10004 Baltimore Gas & Electric Co.

Iowa Electric Light and Power Company

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ATTN: Mr. A. E. Lundvall ATTN: Mr. Keith Young,

P.O. Box 1475 P.O. Box 351 Baltimore, MD 21203 Cedar Rapids, IA 52406 Chem-Nuclear Systems, Inc.

Metropolitan Edison Company ATTN: Mr. Karl H. Kinkade ATTN: Mr. M. R. Buring P.O. Box 1856 P.O. Box 542 Bellevue, WA 98009 Reading, PA 19603 Commonwealth Edison Philadelphia Electric Company ATTN: Mr. B. B. Stephenson ATTN: Mr. V. S. Boyer Dresden Nuclear Power Station P.O. Box 8699 R.R. #1 Philadelphia, PA 19101 Morris, IL 60450 Nebraska Public Power District Conmonwealth Edison ATTN: Mr. Jerry V. Sayer ATTN: Mr. N. J. Kalivianakis P.O. Box 98 Quad Cities Nuclear Power Station Brownville, NE 68321 22710 - 206 Avenue North Cordova, IL 61242 Conmonwealth Edison ATTN: Mr. N. E. Wandke Zion Generating Station Shiloh Blvd. and Michigan Zion, :L 60099 Consolidated Edison Company of New York, Inc.

ATTN: Mr. Stanley Wisla Indian Point Station Broadway and Bleakley Ave.

Buchanan, NY 10511

f~orm NfjC.018 U.S. NUCLE AR REGULATORY CO AMISSION 10 CFR (1 CERTIFICATE OF COMPLI ANCE U

For Radioactive Materials Packages s

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1(a) Ce t f te Number 1 (b) R vision No.

1.(c) a de t fication No.

1.(d) ages No. 1.(e) T tal No. Pages

2. PRE AMBLE 2.(a)

This certificate is issued to satisfy Sections 173.393a,173.394,173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.

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2.(b)

The packaging and contents riescribed in item 5 below, meets the safety standards set forth in Subpart C of Title 10, Code of l

Federal Regulations, Part 71, " Packaging of Rahoactive Materials for Transport and Transportation of Radioactive Material Under l

Certain Conditions."

l 2.(c)

This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country through or into which the package will be transported.

3.

This certificate is issued on the brSis of a safety analysis report of *he package design or appl l cation ~

3.(a)

Prepared by (Name and address):

3.(b)

Title and identification of report or application:

Hittman Nuclear & Development littman Nuclear & Development Corporation application Corporation lated January 12, 1977, as supplemented.

9190 Red Branch Road Columbia, Maryland 21045 3.(c)

Docket No.

71-9080

4. CONDITIONS g

This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specified in item 5 below.

b.

Description of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and

References:

a)

Packaging (1) Model No.:

HN-600 (2) Description A steel encased, lead shielded cask for low specific activity material. The cask is a right circular cylinder 54-1/2 inches high by 84 inches in diameter. The cask cavity is 40-1/4 inches high by 75-1/2 inches in diameter. The cask side wall consists of a 3/8-inch thick inner steel shell, a 3-inch lead shell, and a 3/4-inch thick outer steel shell. The base is comprised of fj I

two steel plates welded together to form a 5-1/2-inch thick base 1

which is integrally welded to the inner and outer steel shells of i.

the side wall. A steel flange is welded to the inner and outer

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shells of the side wall at the top. The 5-1/2-inch thick lid is

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comprised of two steel plates welded together, which are stepped to mate with the steel flange.

The cask closure is sealed by a neoprene gasket located between the lid and steel flange.

Positive closure is accomplished by eight ratchet binders.

The lid contains a 6-1/2-inch thick centrally located shield plug, comprised of g

three steel plates stepped and welded.

The shield plug is sealed by a gasket, and eight 3/4-inch studs and nuts are used to provide

> 1 positive closure.

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Page 2 - Certificate No. 9080 - Revision No. 2 - Docket No. 71-9080 5.

a)

Packaging (cont'd)

(2) Description (cont'd)

Tie-down is accomplished by four tie-down 'ugs welded to the cask body.

There are four cask lifting lugs, three lid lifting lugs, and one shield plug lifting lug.

The package i

gross weight is approximately 48,000 pounds.

l (3) Drawings The packaging is fabricated in accordance with Hittman Nuclear

& Development Corporation Drawings Nos. : C001-4-9600, Sheet 1, Rev. C; C001-4-9601, Sheet 1, Rev. B and Sheet 2, Rev. 0; C001-4-9602, Eheet 1, Rev. B and Sheet 2, Rev. 0; C001-4-9603, Sheet 1, Rev. A.

(b) Contents (1) Type and form of material (i) Solids and solidified waste, meeting the requirements for low specific activity radioactive material as defined in 10 CFR 571.4(g), in secondary containers.

(ii) Activated solid components meeting the requirements for low specific activity radioactive material as defined in 10 CFR 571.4(g).

(2) Maximum quantity of material per package Greater than Type A quantities of radioactive material with the weight of the contents, secondary containers and shoring not exceeding 13,000 pounds.

6.

Shoring shall be placed between secondary containers (or activated components) and the cask cavity to prevent movement during normal conditions of transport.

7.

The lid and shield plug lifting lugs shall not be used for lifting the cask, and shall be covered in transit.

8.

The package authorized by chis certificate shall be transported on a motor vehicle, railroad car, aircraft, inland water craft, or hold or deck of a seagoing vessel assigned for the sole use of the licensee.

Page 3 - Certificate No. 9080 - Revision No. 2 - Docket No. 71-9080 9.

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

10.

Expiration date: August 31, 1982.

REFERENCES l

Hittman Nuclear & Development Corporation application dated January 12, 1977 (includingSARdated1/13/77).

Supplements dated:

June 6 and 21,1977; and August 18, 1978.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION fh fc w

Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety Date:

23m

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ADDENDUM NO. 1 FOR U.S. NUCLEAR REGULATORY COMMISSION TRANSPORTATION BRANCH SAFETY EVALUATION OF THE HITTMAN NUCLEAR & DEVELOPMENT CORPORATION MODEL HN-600 PACKAGING USA /9080/A

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Encl to Ltr dtd Sumnary

)

By application dated August 18, 1978, Hittman Nuclear & Development Corporation requested revision to the approval for shipment of low specific activity radioactive material in the Model No. HN-600 packaging.

It was requested that the weight limit of the contents, secondary con-tainers and shoring be increased to 13,000 pounds and the total package weight be increased correspondingly to about 48,000 pounds and that the Type A secondary container limitation be deleted.

The applicant has submitted packaging drawing revisions and structural evaluations to show that the effects of the one-foot free fall test u,

required under normal conditions of transport will not significantly

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reduce the package containment ability and that the lifting and tie-down requirements are met.

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Based on the statements and representations contained in the application, the staff has concluded that the Model No. HN-600 packaging and contents, as described, satisfy the requirements of 10 CFR Part 71.

Reference Hittman Nuclear & Development Corporation application dated August 18, 1978.

Drawings The packaging is fabricated in accordance with Hittman Nuclear & Develop-ment Corporation Drawings Nos. :

C001-4-9600, Sheet 1, Rev. C; C001-4-9601, Sheet 1, Rev. B and Sheet 2, Rev. 0; C001-4-9602, Sheet 1, Rev. B and Sheet 2, Rev. 0; C001-4-9603, Sheet 1, Rev. A.

()

Structural / Thermal Evaluation The applicant has shown that the general standards of 10 CFR Part 71 have been met.

The lifting and tie-down devices, if overloaded to failure, would not impair the ability of the packaging to meet other requirements in the regulations nor significantly decrease the shielding properties of the packaging.

B

_2_

The applicant has demonstrated by analysis that the packaging satisfies the performance requirements for normal conditions of transport when subjected to the free drop tests described in Appendix A of 10 CFR Part 71. The secondary containers or activated solid components are positioned within the cask to minimize secondary impacts. While there may be localized damage as a result of the one-foot free drop, containment for normal conditions of transport is assured by the cask seals.

fC j" 4

-Charles E. MacDonald, Chief Transportation Branch I

Division of Fuel Cycle and Material Safety OCT 2 3 m Date:

7 u crmrra. I e i l t, w

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A THIS DOCUMENT CONTAINS OCT 2 31978 POOR QUAUTY PAGES

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1-7 MEMORANDUM FOR:

JamesH.Conran,LicensingProjectiM'anager, j

Standardization Branch, DPM i

FROM:

Walter P. Haass Chief, Quality Assurance Branch,

. Division of Project Management

SUBJECT:

REVIEW SCHEDULE FOR GAISSAR 6

As requested in your memorandum of October 18, 1978 to C. Long, et al, we have reviewed the acceptability of your proposed Level D schedule i

for the review of the GAISSAR application and find the datas assigned 1

to QAB hr important milestones to be acceptable.

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Originalsigned by

. Walter P. Haass

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Walter P. Haass, Chief Quality Assurance Branch Division of Project Management cc:

D. Skovholt J. Gilray R. McDennott DJ8fbBUTION:

g kCentral File QAB Projects QAB Chron. File 4

Dross, OPH

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W(sNt 10/23/78 NRC IOR.M 318 (9 76) NRCM 0240 W u, s. oovsawusar emiurine orrics, este - essas4 78103003D-