Corrections made to annual cost burden calculations. Additional clarification regarding burden hour calculation assumptions added to supporting statement.
table that charts list comparision
Inventory as of this Action
Requested
Previously Approved
06/30/2012
06/30/2010
06/30/2010
45,520
0
45,517
5,218,227
0
5,211,667
1,816,726
0
255,446
Final Rule entitled: 10 CFR Parts 50 and 52, Consideration of Aircraft Impacts for New Nuclear Power Reactors." The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to require applicants for new standard design certifications that do not reference a standard design approval; new standard design approvals; combined licenses that do not reference a standard design certification, standard design approval, or manufactured reactor; and new manufacturing licenses that do not reference a standard design certification or standard design approval to assess the effects of the impact of a large, commercial aircraft on the nuclear power plant. Based on the insights gained from this assessment, the applicant shall include in its application a description and evaluation of design features, functional capabilities, and strategies to avoid or mitigate the effects of the aircraft impact. The evaluation of such design features, functional capabilities and strategies must include core cooling capability, containment integrity, and spent fuel pool integrity. The impact of a large, commercial aircraft is a beyond-design-basis event, and the NRCÂs requirements applicable to the design, construction, testing, operation, and maintenance of design features, functional capabilities, and strategies for design basis events would not be applicable to design features, functional capabilities, or strategies selected by the applicant solely to meet the requirements of this rule. The objective of this rule is to require nuclear power plant designers to perform a rigorous assessment of design features that could provide additional inherent protection to avoid or mitigate, to the extent practicable, the effects of an aircraft impact, with reduced reliance on operator actions.
The U.S. Nuclear Regulatory Commission (NRC or the Commission) is amending its regulations to require applicants for new nuclear power reactors to perform a design-specific assessment of the effects of the impact of a large, commercial aircraft. The applicant is required to use realistic analyses to identify and incorporate design features and functional capabilities to show, with reduced use of operator actions, that either the reactor core remains cooled or the containment remains intact, and either spent fuel cooling or spent fuel pool integrity is maintained. In addition, these amendments contain requirements for control of changes to any design features or functional capabilities credited to show that the facility can withstand the effects of an aircraft impact.
Because the final rule is applicable to applicants under both 10 CFR parts 50 and 52, the NRC is relocating the aircraft impact assessment requirements that were contained in proposed 10 CFR 52.500 to a new section, 10 CFR 50.150. This change is also consistent with the recent revision to 10 CFR part 52, where the NRC took a comprehensive approach to reorganizing 10 CFR part 52 and making conforming changes throughout 10 CFR Chapter I, "Nuclear Regulatory Commission," to reflect the licensing and approval processes in 10 CFR part 52. In making conforming changes involving 10 CFR part 50 provisions in that rulemaking, the NRC adopted the general principle of keeping technical requirements in 10 CFR part 50 and maintaining applicable procedural requirements in 10 CFR part 52. For these reasons, the NRC is relocating the proposed aircraft impact requirements from proposed 10 CFR 52.500 to 10 CFR 50.150.
The NRC is also expanding the class of applicants that are required to comply with this rule based on consideration of public comments and implementation issues. In one change, the NRC is applying the final rule to 10 CFR part 50 license applicants as well as applicants under 10 CFR part 52. The final rule requires both new power reactor construction permit applicants and operating license applicants to perform the required assessment and include the description of the identified design features and functional capabilities in their applications. The NRC is applying the final rule to applicants at both the construction permit and operating license stages because it is not until the operating license stage that the applicant is required to provide the NRC with its final design. The NRC can issue a construction permit based on preliminary design information. Therefore, the NRC believes it is necessary to require applicants to perform the aircraft impact assessment at both stages and to include the required information in both applications based on the level of design information available at the time of each application. These changes are reflected in the addition of new paragraphs (a)(13) and (b)(12) in 10 CFR 50.34, ÂContents of construction permit and operating license applications; technical information, requiring all applicants for a construction permit or operating license which are subject to 10 CFR 50.150(a) (proposed 10 CFR 52.500) to submit the information required by 10 CFR 50.150(b) as a part of their application. Paragraph (a) of 10 CFR 50.150 has similarly been revised.
The NRC is seeking clearance with respect to the final changes to 10 CFR Parts 50 and 52 regarding the requirements under the new 10 CFR 50.150 for applicants for new nuclear power reactors to perform a design-specific assessment of the effects of the impact of a large, commercial aircraft.
On behalf of this Federal agency, I certify that the collection of information encompassed by this request complies with 5 CFR 1320.9 and the related provisions of 5 CFR 1320.8(b)(3).
The following is a summary of the topics, regarding the proposed collection of information, that the certification covers:
(i) Why the information is being collected;
(ii) Use of information;
(iii) Burden estimate;
(iv) Nature of response (voluntary, required for a benefit, or mandatory);
(v) Nature and extent of confidentiality; and
(vi) Need to display currently valid OMB control number;
If you are unable to certify compliance with any of these provisions, identify the item by leaving the box unchecked and explain the reason in the Supporting Statement.
10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities