Source: https://www.law.cornell.edu/cfr/text/10/72.24
Timestamp: 2015-04-21 13:32:34
Document Index: 728613926

Matched Legal Cases: ['art 72', '§ 72', '§ 72', 'art 20', '§ 72', '§ 72', '§ 72', '§ 72', 'art 72', 'art 72', 'art 72', 'art 72', 'art 72', 'art 72', 'art 72', 'art 72', 'art 72', 'art 72']

10 CFR 72.24 - Contents of application: Technical information. | LII / Legal Information Institute
CFR › Title 10 › Chapter I › Part 72 › Subpart B › Section 72.24 10 CFR 72.24 - Contents of application: Technical information.
There are 16 Updates appearing in the Federal Register for 10 CFR 72. View below or at eCFR (GPOAccess)
§ 72.24
Contents of application: Technical information.
Each application for a license under this part must include a Safety Analysis Report describing the proposed ISFSI or MRS for the receipt, handling, packaging, and storage of spent fuel, high-level radioactive waste, and/or reactor-related GTCC waste as appropriate, including how the ISFSI or MRS will be operated. The minimum information to be included in this report must consist of the following:
A description and safety assessment of the site on which the ISFSI or MRS is to be located, with appropriate attention to the design bases for external events. Such assessment must contain an analysis and evaluation of the major structures, systems, and components of the ISFSI or MRS that bear on the suitability of the site when the ISFSI or MRS is operated at its design capacity. If the proposed ISFSI or MRS is to be located on the site of a nuclear power plant or other licensed facility, the potential interactions between the ISFSI or MRS and such other facility—including shared common utilities and services—must be evaluated.
A description and discussion of the ISFSI or MRS structures with special attention to design and operating characteristics, unusual or novel design features, and principal safety considerations.
The design of the ISFSI or MRS in sufficient detail to support the findings in § 72.40 for the term requested in the application, including:
The design criteria for the ISFSI or MRS pursuant to subpart F of this part, with identification and justification for any additions to or departures from the general design criteria;
the design bases and the relation of the design bases to the design criteria;
Information relative to materials of construction, general arrangement, dimensions of principal structures, and descriptions of all structures, systems, and components important to safety, in sufficient detail to support a finding that the ISFSI or MRS will satisfy the design bases with an adequate margin for safety; and
Applicable codes and standards.
An analysis and evaluation of the design and performance of structures, systems, and components important to safety, with the objective of assessing the impact on public health and safety resulting from operation of the ISFSI or MRS and including determination of:
The margins of safety during normal operations and expected operational occurrences during the life of the ISFSI or MRS; and
The adequacy of structures, systems, and components provided for the prevention of accidents and the mitigation of the consequences of accidents, including natural and manmade phenomena and events.
The means for controlling and limiting occupational radiation exposures within the limits given in part 20 of this chapter, and for meeting the objective of maintaining exposures as low as is reasonably achievable.
The features of ISFSI or MRS design and operating modes to reduce to the extent practicable radioactive waste volumes generated at the installation.
An identification and justification for the selection of those subjects that will be probable license conditions and technical specifications. These subjects must cover the design, construction, preoperational testing, operation, and decommissioning of the ISFSI or MRS.
A plan for the conduct of operations, including the planned managerial and administrative controls system, and the applicant's organization, and program for training of personnel pursuant to subpart I.
If the proposed ISFSI or MRS incorporates structures, systems, or components important to safety whose functional adequacy or reliability have not been demonstrated by prior use for that purpose or cannot be demonstrated by reference to performance data in related applications or to widely accepted engineering principles, an identification of these structures, systems, or components along with a schedule showing how safety questions will be resolved prior to the initial receipt of spent fuel, high-level radioactive waste, and/or reactor-related GTCC waste as appropriate for storage at the ISFSI or MRS.
The technical qualifications of the applicant to engage in the proposed activities, as required by § 72.28.
A description of the applicant's plans for coping with emergencies, as required by § 72.32.
A description of the equipment to be installed to maintain control over radioactive materials in gaseous and liquid effluents produced during normal operations and expected operational occurrences. The description must identify the design objectives and the means to be used for keeping levels of radioactive material in effluents to the environment as low as is reasonably achievable and within the exposure limits stated in § 72.104. The description must include:
An estimate of the quantity of each of the principal radionuclides expected to be released annually to the environment in liquid and gaseous effluents produced during normal ISFSI or MRS operations;
A description of the equipment and processes used in radioactive waste systems; and
A general description of the provisions for packaging, storage, and disposal of solid wastes containing radioactive materials resulting from treatment of gaseous and liquid effluents and from other sources.
An analysis of the potential dose equivalent or committed dose equivalent to an individual outside the controlled area from accidents or natural phenomena events that result in the release of radioactive material to the environment or direct radiation from the ISFSI or MRS. The calculations of individual dose equivalent or committed dose equivalent must be performed for direct exposure, inhalation, and ingestion occurring as a result of the postulated design basis event.
A description of the quality assurance program that satisfies the requirements of subpart G to be applied to the design, fabrication, construction, testing, operation, modification, and decommissioning of the structures, systems, and components of the ISFSI or MRS important to safety. The description must identify the structures, systems, and components important to safety. The program must also apply to managerial and administrative controls used to ensure safe operation of the ISFSI or MRS.
A description of the detailed security measures for physical protection, including design features and the plans required by subpart H. For an application from DOE for an ISFSI or MRS, DOE will provide a description of the physical protection plan for protection against radiological sabotage as required by subpart H.
A description of the program covering preoperational testing and initial operations.
A description of the decommissioning plan required under § 72.30.
[53 FR 31658, Aug. 19, 1988, as amended at 63 FR 26961, May 15, 1998; 64 FR 53615, Oct. 4, 1999; 66 FR 51839, Oct. 11, 2001; 76 FR 8890, Feb. 16, 2011]
Title 10 published on 2014-01-01The following are only the Rules published in the Federal Register after the published date of Title 10.For a complete list of all Rules, Proposed Rules, and Notices view the Rulemaking tab.2015-02-05; vol. 80 # 24 - Thursday, February 5, 201580 FR 6430 - List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask System, Certificate of Compliance No. 1014, Amendment No. 8, Revision No. 1
typeregulations.gov FR Doc.2015-02310 RIN3150-AJ47 NRC-2014-0233 NUCLEAR REGULATORY COMMISSION Direct final rule. The direct final rule is effective April 21, 2015, unless significant adverse comments are received by March 9, 2015. If the direct final rule is withdrawn as a result of such comments, timely notice of the withdrawal will be published in the Federal Register . Comments received after this date will be considered if it is practical to do so, but the NRC staff is able to ensure consideration only for comments received on or before this date. Comments received on this direct final rule will also be considered to be comments on a companion proposed rule published in the Proposed Rules section of this issue of the Federal Register . 10 CFR Part 72 SummaryThe U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the Holtec International HI-STORM 100 Cask System listing within the “List of approved spent fuel storage casks” to add Revision No. 1 to Amendment No. 8 (effective May 2, 2012, and corrected on November 16, 2012), to the Certificate of Compliance (CoC) No. 1014. Amendment No. 8, Revision No. 1, changes burnup/cooling time limits for thimble plug devices; changes Metamic-HT material testing requirements; changes Metamic-HT material minimum guaranteed values; and updates fuel definitions to allow boiling water reactor fuel affected by certain corrosion mechanisms with specific guidelines to be classified as undamaged fuel.
2015-01-29; vol. 80 # 19 - Thursday, January 29, 201580 FR 4757 - List of Approved Spent Fuel Storage Casks: NAC International MAGNASTOR® System; Certificate of Compliance No. 1031, Amendment No. 4
typeregulations.gov FR Doc.2015-01693 RIN-3150-AJ39 NRC-2014-0058 NUCLEAR REGULATORY COMMISSION Direct final rule. The direct final rule is effective April 14, 2015, unless significant adverse comments are received by March 2, 2015. If the direct final rule is withdrawn as a result of such comments, timely notice of the withdrawal will be published in the Federal Register . Comments received after this date will be considered if it is practical to do so, but the NRC staff is able to ensure consideration only for comments received on or before this date. 10 CFR Part 72 SummaryThe U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations to add Amendment No. 4 to the Certificate of Compliance (CoC) No. 1031 for the NAC International MAGNASTOR® System. Amendment No. 4 changes a limiting condition for operation (LCO) in the technical specifications for transportable storage canister (TSC) vacuum drying and helium backfill times, and corrects a typographical error. The NRC approval of this Amendment would not authorize transportation.
2015-01-22; vol. 80 # 14 - Thursday, January 22, 201580 FR 3147 - List of Approved Spent Fuel Storage Casks: Transnuclear, Inc. Standardized Advanced NUHOMS® Horizontal Modular Storage System; Certificate of Compliance No. 1029, Amendment No. 3
typeregulations.gov FR Doc.2015-01031 RIN3150-AJ31 NRC-2013-0271 NUCLEAR REGULATORY COMMISSION Final rule. This final rule is effective on February 23, 2015. 10 CFR Part 72 SummaryThe U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the Transnuclear, Inc. (TN) Standardized Advanced NUHOMS® Horizontal Modular Storage System (NUHOMS® Storage System) listing within the “List of Approved Spent Fuel Storage Casks” to include Amendment No. 3 to Certificate of Compliance (CoC) No. 1029. The NRC published a direct final rule on this amendment in the Federal Register on April 15, 2014. The NRC also concurrently published an identical proposed rule on April 15, 2014. The NRC received significant adverse comments on the direct final rule; therefore, the NRC withdrew the direct final rule on June 25, 2014, and is proceeding, in this Federal Register notice, to address the comments on the companion proposed rule.
2014-12-16; vol. 79 # 241 - Tuesday, December 16, 201479 FR 74594 - List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM FLOOD/WIND System; Certificate of Compliance No. 1032, Amendment No. 1
typeregulations.gov FR Doc.2014-29427 RIN3150-AJ40 NRC-2014-0102 NUCLEAR REGULATORY COMMISSION Direct final rule; confirmation of effective date. The effective date of December 17, 2014, for the direct final rule published October 3, 2014 (79 FR 59623), is confirmed. 10 CFR Part 72 SummaryThe U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of December 17, 2014, for the direct final rule that was published in the Federal Register on October 3, 2014. This direct final rule amended the NRC&apos;s spent fuel storage regulations by revising the Holtec International HI-STORM FLOOD/WIND (FW) System listing within the “List of approved spent fuel storage casks” to include Amendment No. 1 to Certificate of Compliance (CoC) No. 1032.
2014-11-19; vol. 79 # 223 - Wednesday, November 19, 201479 FR 68763 - List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM Underground Maximum Capacity Canister Storage System, Certificate of Compliance No. 1040
typeregulations.gov FR Doc.2014-27398 RIN3150-AJ42 NRC-2014-0120 NUCLEAR REGULATORY COMMISSION Direct final rule; withdrawal. Effective November 19, 2014, the NRC withdraws the direct final rule published at 79 FR 53281 on September 9, 2014. 10 CFR Part 72 SummaryThe U.S. Nuclear Regulatory Commission (NRC) is withdrawing a direct final rule that would have added the Holtec International HI-STORM Underground Maximum Capacity (UMAX) Canister Storage System, Certificate of Compliance (CoC) No. 1040, to the “List of approved spent fuel storage casks.” The NRC is taking this action because it has received at least one significant adverse comment in response to a companion proposed rule that was concurrently published with the direct final rule.
2014-10-03; vol. 79 # 192 - Friday, October 3, 201479 FR 59623 - List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM FLOOD/WIND System; Certificate of Compliance No. 1032, Amendment No. 1
typeregulations.gov FR Doc.2014-23633 RIN3150-AJ40 NRC-2014-0102 NUCLEAR REGULATORY COMMISSION Direct final rule. The direct final rule is effective December 17, 2014, unless significant adverse comments are received by November 3, 2014. If the direct final rule is withdrawn as a result of such comments, timely notice of the withdrawal will be published in the Federal Register . Comments received after this date will be considered if it is practical to do so, but the NRC staff is able to ensure consideration only for comments received on or before this date. 10 CFR Part 72 SummaryThe U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the Holtec International HI-STORM FLOOD/WIND (FW) System listing within the “List of approved spent fuel storage casks” to include Amendment No. 1 to Certificate of Compliance (CoC) No. 1032. Amendment No. 1 adds a new heat load pattern for the multipurpose canister (MPC)-37, broadens the back pressure range for MPC-37 and MPC-89, and updates certain definitions related to fuel classification. Also, the amendment makes a correction to the expiration date of CoC No. 1032.
2014-09-30; vol. 79 # 189 - Tuesday, September 30, 201479 FR 58672 - List of Approved Spent Fuel Storage Casks: Transnuclear, Inc. NUHOMS® HD Cask System, Certificate of Compliance No. 1030, Amendment No. 2
typeregulations.gov FR Doc.2014-23220 RIN3150-AJ30 NRC-2013-0269 NUCLEAR REGULATORY COMMISSION Direct final rule; confirmation of effective date. Effective date: The effective date of October 14, 2014, for the direct final rule published July 31, 2014 (79 FR 44264), is confirmed. 10 CFR Part 72 SummaryThe U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of October 14, 2014, for the direct final rule that was published in the Federal Register on July 31, 2014. This direct final rule amended the NRC&apos;s spent fuel storage regulations by revising the Transnuclear, Inc. NUHOMS® HD Cask System listing within the “List of Approved Spent Fuel Storage Casks” to include Amendment No. 2 to Certificate of Compliance (CoC) No. 1030.
2014-07-31; vol. 79 # 147 - Thursday, July 31, 201479 FR 44264 - List of Approved Spent Fuel Storage Casks: Transnuclear, Inc. NUHOMS® HD Cask System, Certificate of Compliance No. 1030, Amendment No. 2
Title 10 published on 2014-01-01The following are ALL rules, proposed rules, and notices (chronologically) published in the Federal Register relating to 10 CFR 72 after this date.2015-02-05; vol. 80 # 24 - Thursday, February 5, 201580 FR 6430 - List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask System, Certificate of Compliance No. 1014, Amendment No. 8, Revision No. 1
80 FR 6466 - List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask System, Certificate of Compliance No. 1014, Amendment No. 8, Revision No. 1
typeregulations.gov FR Doc.2015-02309 RIN3150-AJ47 NRC-2014-0233 NUCLEAR REGULATORY COMMISSION Proposed rule. Submit comments by March 9, 2015. Comments received after this date will be considered if it is practical to do so, but the NRC staff is able to ensure consideration only for comments received on or before this date. 10 CFR Part 72 SummaryThe U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage regulations by revising the Holtec International HI-STORM 100 Cask System listing within the “List of approved spent fuel storage casks” to add Amendment No. 8, Revision No. 1, to the Certificate of Compliance (CoC) No. 1014. Amendment No. 8, Revision No. 1, changes burnup/cooling time limits for thimble plug devices; changes Metamic-HT material testing requirements; changes Metamic-HT material minimum guaranteed values; and updates fuel definitions to allow boiling water reactor fuel affected by certain corrosion mechanisms with specific guidelines to be classified as undamaged fuel.
80 FR 4808 - List of Approved Spent Fuel Storage Casks: NAC International MAGNASTOR® System, Certificate of Compliance No. 1031, Amendment No. 4
typeregulations.gov FR Doc.2015-01691 RIN3150-AJ39 NRC-2014-0058 NUCLEAR REGULATORY COMMISSION Proposed rule. Submit comments by March 2, 2015. Comments received after this date will be considered if it is practical to do so, but the NRC staff is able to ensure consideration only for comments received on or before this date. 10 CFR Part 72 SummaryThe U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage regulations to add Amendment No. 4 to the Certificate of Compliance (CoC) No. 1031 for the NAC International MAGNASTOR® System. Amendment No. 4 changes a limiting condition for operation in the technical specifications for transportable storage canister vacuum drying and helium backfill times, and corrects a typographical error. The NRC approval of this Amendment would not authorize transportation.
79 FR 59693 - List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM FLOOD/WIND System; Certificate of Compliance No. 1032, Amendment No. 1
typeregulations.gov FR Doc.2014-23631 RIN3150-AJ40 NRC-2014-0102 NUCLEAR REGULATORY COMMISSION Proposed rule. Submit comments by November 3, 2014. Comments received after this date will be considered if it is practical to do so, but the NRC staff is able to ensure consideration only for comments received on or before this date. 10 CFR Part 72 SummaryThe U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage regulations by revising the Holtec International HI-STORM FLOOD/WIND (FW) System listing within the “List of approved spent fuel storage casks” to include Amendment No. 1 to Certificate of Compliance (CoC) No. 1032. Amendment No. 1 adds a new heat load pattern for the multipurpose canister (MPC)-37, broadens the back pressure range for MPC-37 and MPC-89, and updates certain definitions related to fuel classification. Also, the amendment makes a correction to the expiration date of CoC No. 1032.