10 CFR 71.95, Reports

Reports

a

(a) The licensee, after requesting the certificate holder's input, shall submit a written report to the Commission of--

(1) Instances in which there is a significant reduction in the effectiveness of any NRC-approved Type B or Type AF packaging during use; or

(2) Details of any defects with safety significance in any NRC-approved Type B or fissile material packaging, after first use.

(3) Instances in which the conditions of approval in the Certificate of Compliance were not observed in making a shipment.

b

(b) The licensee shall submit a written report to the Commission of instances in which the conditions in the certificate of compliance were not followed during a shipment.

c

(c) Each licensee shall submit, in accordance with § 71.1, a written report required by paragraph (a) or (b) of this section within 60 days of the event or discovery of the event. The licensee shall also provide a copy of each report submitted to the NRC to the applicable certificate holder. Written reports prepared under other regulations may be submitted to fulfill this requirement if the reports contain all the necessary information, and the appropriate distribution is made. Using an appropriate method listed in § 71.1(a), the licensee shall report to: ATTN: Document Control Desk, Director, Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguards. These written reports must include the following:

(1) A brief abstract describing the major occurrences during the event, including all component or system failures that contributed to the event and significant corrective action taken or planned to prevent recurrence.

(2) A clear, specific, narrative description of the event that occurred so that knowledgeable readers conversant with the requirements of part 71, but not familiar with the design of the packaging, can understand the complete event. The narrative description must include the following specific information as appropriate for the particular event.

(i) Status of components or systems that were inoperable at the start of the event and that contributed to the event;

(ii) Dates and approximate times of occurrences;

(iii) The cause of each component or system failure or personnel error, if known;

(iv) The failure mode, mechanism, and effect of each failed component, if known;

(v) A list of systems or secondary functions that were also affected for failures of components with multiple functions;

(vi) The method of discovery of each component or system failure or procedural error;

(vii) For each human performance-related root cause, a discussion of the cause(s) and circumstances;

(viii) The manufacturer and model number (or other identification) of each component that failed during the event; and

(ix) For events occurring during use of a packaging, the quantities and chemical and physical form(s) of the package contents.

(3) An assessment of the safety consequences and implications of the event. This assessment must include the availability of other systems or components that could have performed the same function as the components and systems that failed during the event.

(4) A description of any corrective actions planned as a result of the event, including the means employed to repair any defects, and actions taken to reduce the probability of similar events occurring in the future.

(5) Reference to any previous similar events involving the same packaging that are known to the licensee or certificate holder.

(6) The name and telephone number of a person within the licensee's organization who is knowledgeable about the event and can provide additional information.

(7) The extent of exposure of individuals to radiation or to radioactive materials without identification of individuals by name.

d

(d) Report legibility. The reports submitted by licensees and/or certificate holders under this section must be of sufficient quality to permit reproduction and micrographic processing.

Federal Register

, as amended at 67 FR 3585, Jan. 25, 2002; 68 FR 58818, Oct. 10, 2003; 69 FR 3796, Jan. 26, 2004; 75 FR 73945, Nov. 30, 2010]

External Links

NRC website 10 CFR 71.95

v t e Code of Federal Regulations
Title 10 Part 71 - PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL
10 CFR: 1 2 4 5 7 9 10 11 12 13 14 15 16 19 20 21 25 26 30 31 32 33 34 35 36 37 39 40 50 51 52 54 55 60 61 62 63 70 71 72 73 74 75 76 81 95 100 140 150 160 170 171
0, General Provisions, Purpose and scope 1, Communications and records 2, Interpretations 3, Requirement for license 4, Definitions 5, Transportation of licensed material 6, Information collection requirements: OMB approval 7, Completeness and accuracy of information 8, Deliberate misconduct 9, Employee protection 10, Public inspection of application 11, Protection of Safeguards Information 12, Exemptions, Specific exemptions 13, Exemption of physicians 14, Exemption for low-level materials 15, Exemption from classification as fissile material 16, 17, General Licenses, General license: NRC-approved package 18, 19, Previously approved package 21, General license: Use of foreign approved package 22, General license: Fissile material 23, General license: Plutonium-beryllium special form material 24, 25, 31, Application for Package Approval, Contents of application 33, Package description 35, Package evaluation 37, Quality assurance 38, Renewal of a certificate of compliance or quality assurance program approval 39, Requirement for additional information 41, Package Approval Standards, Demonstration of compliance 43, General standards for all packages 45, Lifting and tie-down standards for all packages 47, External radiation standards for all packages 51, Additional requirements for Type B packages 53, 55, General requirements for fissile material packages 57, 59, Standards for arrays of fissile material packages 61, Special requirements for Type B packages containing more than 105A2 63, Special requirement for plutonium shipments 64, Special requirements for plutonium air shipments 65, Additional requirements 71, Package, Special Form, and LSA-III Tests^{<a href="#N_2_7171">2</a>}, Normal conditions of transport 73, Hypothetical accident conditions 74, Accident conditions for air transport of plutonium 75, Qualification of special form radioactive material 77, Qualification of LSA-III Material 81, Operating Controls and Procedures, Applicability of operating controls and procedures 83, Assumptions as to unknown properties 85, Preliminary determinations 87, Routine determinations 88, Air transport of plutonium 89, Opening instructions 91, Records 93, Inspection and tests 95, Reports 97, Advance notification of shipment of irradiated reactor fuel and nuclear waste 99, Violations 100, Criminal penalties 101, Quality Assurance, Quality assurance requirements 103, Quality assurance organization 105, Quality assurance program 107, Package design control 109, Procurement document control 111, Instructions, procedures, and drawings 113, Document control 115, Control of purchased material, equipment, and services 117, Identification and control of materials, parts, and components 119, Control of special processes 121, Internal inspection 123, Test control 125, Control of measuring and test equipment 127, Handling, storage, and shipping control 129, Inspection, test, and operating status 131, Nonconforming materials, parts, or components 133, Corrective action 135, Quality assurance records 137, Audits Appendices: 10 CFR 71 Appendix A

10 CFR 71.95, Reports

a

b

c

d

Federal Register

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