ML20204H828

Rev 3 to Procedure RDW 5.9, Documentation of Radioactive Matl Shipping Package Insp,Certification & Safety Analysis (49CFR173.24)

ML20204H828
Person / Time
Site:	Point Beach
Issue date:	05/11/1984
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20204H448	List: ML20204H444 ML20204H451 ML20204H456 ML20204H461 ML20204H469 ML20204H477 ML20204H484 ML20204H489 ML20204H507 ML20204H519 ML20204H533 ML20204H547 ML20204H571 ML20204H578 ML20204H589 ML20204H596 ML20204H606 ML20204H616 ML20204H622 ML20204H638 ML20204H650 ML20204H661 ML20204H677 ML20204H697 ML20204H711 ML20204H724 ML20204H728 ML20204H748 ML20204H754 ML20204H760 ML20204H764 ML20204H776 ML20204H807 ML20204H818 ML20204H828 ML20204H837
References
RDW-5.9, NUDOCS 8411120394
Download: ML20204H828 (4)

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RDW 5.9 MINOR Revision 3 05-11-84

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DOCUMENTATION OF RADIOACTIVE MATERIAL SHIPPING PACKAGE INSPECTION, CERTIFICATION & SAFETY ANALYSIS (49 CFR 173.24) 1.0 GENERAL' This procedure outlines the documentation requirements for packages used to transport radioactive materials. These documents are in addition to the shipping papers required. Files must be maintained for the documents.

2.0 REFERENCES

2.1 10 CFR Part 71, Packaging Radioactive Material for Transport 2.2 49 CFR Part 173, Shippers - General Requirements for Shipments and Packagings 2.3 File HP 2.6, Package QA Documents 2.4 Mound Facility Report MLM-2228, Packaging Compliance with DOT Spec. 7A. See file HP 2.6.7 3.0 FILE ENTRIES 3.1 File HP 2.6 will be used to maintain a copy of the certificate of Compliance or other approval authorizing use of a package. All documents referred to in the license, or other aporoval, will also be maintained in file HP 2.6.

3.2 User registration letters to NRC, when requiren, will be filed in HP 2.6.

3.3 Package inspection documents will be maintained with the shipping papers pertaining to the shipment for which the package was used.

These are filed in HP 2.1.1 or 2.1.4, as appropriate.

4.0 REQUIRED DOCUMENTS 4.1 Preliminary determinations of quality assurance and quality control l should be performed by the package vendor. An NRC Certificate of Compliance maintained in file HP 2.6 will be sufficient evidence that the preliminary determinations required prior to the first use of the package have been performed by the package manufacturer.

4.2 The table below lists all the possible radioactive waste hantities authorized for shipment. Beside each quantity is a notation showing i that documentation is required ("yes") or is not required ("no"). A series of nusabers indicates which documents are required. The key is at the bottom of the table.

8411120394 841105 PDR ADOCK 05000 P

f RDW 5.9 Page 2 Package

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Quantity Packaged Documentation Required Limited quantity No Radioactive instrument or article No LSA, not greater than Type "A" quantity, transported in a sole use vehicle No LSA. not transported in a sole use vehicle Yes (1)

LSA, > Type "A" quantity Yes (1, 2, 4, 5)

Type "A" Quantity in a shipping cask Yes (1, 2, 4, 5)

Type "A" Quantity in a drum or liner Yes (1, 3, 4)

Type "B" Quantity Yes (1, 2, 4, 5)

Highway Route Controlled Quantity Yes (1, 2, 4, 5)

KEY:

(1) Routine inspection (2) NRC Certificate of Compliance (3) Vendor certification (4) Safety Analysis j (5) User registration letter to the NRC NOTE: FISSILE MATERIALS ARE NOT LISTED. NO FISSILE MATERIAL MAY BE SHIPPED WITHOUT SPECIFIC AUTHORIZATION FROM THE SUPERINTENDENT - CHP.

4.3 Foreign-made packages and packages intended for international shipment require additional documents. Such packages and shipments are not expected to be used at PBNP. Contact the Nuclear Plant specialist or engineer assigned to radwaste for details if necessary.

5.0 DESCRIPTION

OF DOCUMENTS ,

5.1 Routine Inspections 5.1.1 Routine inspections of cask packages are performed with the use of cask checkoff forms, the CHP-131 series. These forms are unique in that they are part of the shipping papers and a copy is sent with the shipment.

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RDW 5.9 Page 3 5.1.2 Routine inspections of other packages are performed, if necessary, using form CHP-78. They are filed with the shipping paper, but no copy is sent with the shipment.

5.1.3 The routine inspection is normally performed by personnel authorized by a CHP Supervisor. Cask inspections will be done by operations in the normal course of loading.

5.2 Certificate of Compliance 5.2.1 This document is required for a cask shipment unless exempted by Section 4.2 above. It is 1. sued by the NRC. It contains the package identification number, a physical description of the package, authorized contents, and other special instructions. The Certificate of Compliance normally contains references to other documents. All such references must be filed with the certificate.

5.2.2 The Certificate of Compliance should always be consulted before shipment to verify compliance with its conditions.

5.3 vendor certification 1

5.3.1 This is required for Type "A" quantities (DOT Specification

.7A). Typically, it is a certification for a 55-gallon drum.

It states that the containers meet the requirements of DOT Spec. 7A. The manufacturer of the package must supply this.

5.3.2 In the special case of 55-gallon drums, this requirement is satisfied if the drums are certified as meeting DOT Spec. 17H.

A 17H steel drum, 55-gallon size, ce-tified as a DOT Specification 7A, Type "A" package, may weigh no more than

[ 840 pounds when loaded.

5.3.3 If the manufacturer has marked the container with a U.S. DOT specification marking, this is acceptable as a certification.

l (49 CFR 173.22) 5.4 Safety Analysis 5.4.1 A Type A package must be provided with a safety analysis by its manufacturer. It must demonstrate that the package complies with the specification set forth in 49 CFR 178.350 (DOT Specification 7A). It must also demonstrate that the package will pass the tests specified in 49 CFR 173.465 &

173.466. The manufacturer is exempted from this requirement if a generic safety analysis for the packaging is already on file at PBNP. Refer to reference 2.4 above for generic safety analyses which are applicable to 55 gallon drums.

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~ . o RDW 5.9 Page 4 49 CFR 173.415 provides a list of Type "A" packages which are acceptable to the DOT.

5.4.2 Packages to be used for shipping greater than Type "A" quantities must be provided with a safety analysis by the manufacturer. This also applies to packages transporting LSA material if the package contains greater than Type A quantities. The nalysis is more extensive than for a Type "A" package. It must show compliance with the following regulations:

10 CFR 71.85-91 10 CFR 71 Subpart E 10 CFR 71 Subpart H 49 CFR 173.465 & 173.471 If the package is used for LSA material and is shipped via a sole use vehicle, the safety analysis ooes not need to comply with 10 CFR 71.51. [10 CFR 71.52(a))

49 CFR 173.416 provides a list of Type "B" packages acceptable to the DOT.

i 5.5 User Registration Letter A package used to transport greater than Type "A" quantities, even if the material meets LSA requirements, needs a user registration letter.

The letter informs the Director of Nuclear Material Safety and Safeguards of the intent to use a particular package. See 10 CFR 71.12 for details to be contained in the letter.

5.6 Reports (10 CFR 71.95) 5.6.1 Notification must be made to the NRC within 30 days to report the following:

a. Any incident in which there is significant reduction in the effectiveness of any authorized package during use.

b. Details of any defects with safety significance in the packaging after first use and the steps taken to repair the defects and prevent their recurrence.

5.6.2 The notification must be made to the Director, Nuclear Material Safety & Safeguards, U.S. Nuclear Regul'atory Commission, Washington, DC 20555.

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