§ 52.17 Contents of applications; technical information.
(a)For applications submitted before
September 27, 2007, the rule provisions
in effect at the date of docketing apply
unless otherwise requested by the applicant in writing. The application must contain:
(1) A site safety analysis report. The site safety analysis report shall include the following:
(i) The specific number, type, and thermal power level of the facilities, or range of possible facilities, for which the site may be used;
(ii) The anticipated maximum levels of radiological and thermal effluents each facility will produce;
(iii) The type of cooling systems, intakes, and outflows that may be associated with each facility;
(iv) The boundaries of the site;
(v) The proposed general location of each facility on the site;
(vi) The seismic, meteorological,
hydrologic, and geologic characteristics
of the proposed site with appropriate
consideration of the most severe of the natural phenomena that have been historically reported for the site and
surrounding area and with sufficient margin for the limited accuracy, quantity, and period of time in which the historical data have been accumulated;
(vii) The location and description of any nearby industrial, military, or transportation facilities and routes;
(viii) The existing and projected future population profile of the area surrounding the site;
(ix) A description and safety
assessment of the site on which a
facility is to be located. The assessment
must contain an analysis and evaluation
of the major structures, systems, and
components of the facility that bear
significantly on the acceptability of the
site under the radiological consequence
evaluation factors identified in
paragraphs (a)(1)(ix)(A) and (a)(1)(ix)(B)
of this section. In performing this
assessment, an applicant shall assume a
fission product release 1 from the core
into the containment assuming that the
facility is operated at the ultimate power
level contemplated. The applicant shall
perform an evaluation and analysis of
the postulated fission product release,
using the expected demonstrable containment leak rate and any fission
product cleanup systems intended to
mitigate the consequences of the
accidents, together with applicable site
characteristics, including site
meteorology, to evaluate the offsite
radiological consequences. Site characteristics must comply with part 100 of this chapter. The evaluation must
(A) An individual located at any point on the boundary of the exclusion area for any 2 hour period following the onset of the postulated fission product release, would not receive a radiation dose in excess of 25 rem 2 total effective dose equivalent (TEDE).
(B) An individual located at any point
on the outer boundary of the low
population zone, who is exposed to the
radioactive cloud resulting from the postulated fission product release (during the entire period of its passage) would not receive a radiation dose in excess of 25 rem TEDE;
(x) Information demonstrating that site characteristics are such that adequate security plans and measures can be developed;
(xi) For applications submitted after
September 27, 2007, a description of the
quality assurance program applied to
site-related activities for the future design, fabrication, construction, and testing of the structures, systems, and
components of a facility or facilities that may be constructed on the site. Appendix B to 10 CFR part 50 sets forth the requirements for quality assurance programs for nuclear power plants. The description of the quality assurance
program for a nuclear power plant site shall include a discussion of how the applicable requirements of appendix B to part 50 of this chapter will be satisfied; and
(xii) An evaluation of the site against applicable sections of the Standard Review Plan (SRP) revision in effect 6 months before the docket date of the application. The evaluation required by this section shall include an identification and description of all differences in analytical techniques and procedural measures proposed for a site and those corresponding techniques and measures given in the SRP acceptance criteria. Where such a difference exists, the evaluation shall discuss how the proposed alternative provides an acceptable method of complying with the Commission's regulations, or portions thereof, that underlie the corresponding SRP acceptance criteria. The SRP is not a substitute for the regulations, and compliance is not a requirement.
(2) A complete environmental report as required by 10 CFR 51.50(b).
(b)(1) The site safety analysis report
must identify physical characteristics of
the proposed site, such as egress
limitations from the area surrounding the site, that could pose a significant impediment to the development of emergency plans. If physical characteristics are identified that could pose a significant impediment to the development of emergency plans, the application must identify measures that would, when implemented, mitigate or eliminate the significant impediment.
(2) The site safety analysis report may also:
(i) Propose major features of the emergency plans, in accordance with the pertinent standards of 10 CFR 50.47, and the requirements of appendix E to 10 CFR part 50, such as the exact size and configuration of the emergency planning zones, for review and approval by NRC, in consultation with the Department of Homeland Security (DHS) in the absence of complete and integrated emergency plans; or
(ii) Propose complete and integrated
emergency plans for review and
approval by the NRC, in consultation
with DHS, in accordance with the
applicable standards of 10 CFR 50.47,
and the requirements of appendix E to
10 CFR part 50. To the extent approval
of emergency plans is sought, the
application must contain the
information required by
§§ 50.33(g) and (j) of this chapter.
(3) Emergency plans submitted under
paragraph (b)(2)(ii) of this section must
include the proposed inspections, tests,
and analyses that the holder of a combined license referencing the early site permit shall perform, and the acceptance criteria that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, the facility has been constructed and will be operated in conformity with the emergency plans, the provisions of the Act, and the Commission’s rules and regulations. Major features of an emergency plan submitted under paragraph (b)(2)(i) of this section may include proposed inspections, tests, analyses, and acceptance criteria.
(4) Under paragraphs (b)(1) and
(b)(2)(i) of this section, the site safety
analysis report must include a
description of contacts and
arrangements made with Federal, State,
and local governmental agencies with
emergency planning responsibilities.
The site safety analysis report must
contain any certifications that have been
obtained. If these certifications cannot
be obtained, the site safety analysis
report must contain information,
including a utility plan, sufficient to
show that the proposed plans provide
reasonable assurance that adequate
protective measures can and will be
taken in the event of a radiological
emergency at the site. Under the option
set forth in paragraph (b)(2)(ii) of this
section, the applicant shall make good
faith efforts to obtain from the same
governmental agencies certifications
(i) The proposed emergency plans are practicable;
(ii) These agencies are committed to participating in any further development of the plans, including any required field demonstrations, and
(iii) That these agencies are committed to executing their responsibilities under the plans in the event of an emergency.
(c) An applicant may request that a limited work authorization under 10 CFR 50.10 be issued in conjunction with the early site permit. The application must include the information otherwise required by 10 CFR 50.10(d)(3). Applications submitted before, and pending as of November 8, 2007, must include the information required by § 52.17(c) effective on the date of docketing.
(d) Each applicant for an early site permit under this part shall protect Safeguards Information against unauthorized disclosure in accordance with the requirements in §§ 73.21 and 73.22 of this chapter, as applicable.
[54 FR 15386, Sept. 18, 1989, as amended at 61 FR 65175, Dec. 11, 1996; 72 FR 49522, Aug. 28, 2007; 72 FR 57447, Oct. 9, 2007; 73 FR 63571, Oct. 24, 2008]
1 The fission product release assumed for this evaluation should be based upon a major accident, hypothesized for purposes of site analysis or postulated from considerations of possible accidental events. Such accidents have generally been assumed to result in substantial meltdown of the core with subsequent release into the containment of appreciable quantities of fission products.
2 A whole body dose of 25 rem has been stated to correspond numerically to the once in a lifetime accidental or emergency dose for radiation workers which, according to NCRP recommendations at the time could be disregarded in the determination of their radiation exposure status (see NBS Handbook 69 dated June 5, 1959). However, its use is not intended to imply that this number constitutes an acceptable limit for an emergency dose to the public under accident conditions. Rather, this dose value has been set forth in this section as a reference value, which can be used in the evaluation of plant design features with respect to postulated reactor accidents, to assure that these designs provide assurance of low risk of public exposure to radiation, in the event of an accidents.