Corrections made
to annual cost burden calculations. Additional clarification
regarding burden hour calculation assumptions added to supporting
statement.
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 NRCs 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, Contents 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