10 C.F.R. § 100.11

Determination of exclusion area, low population zone, and population center distance

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(a) As an aid in evaluating a proposed site, an applicant should assume a fission produce release 1 from the core, the expected demonstrable leak rate from the containment and the meteorological conditions pertinent to his site to derive an exclusion area, a low population zone and population center distance. For the purpose of this analysis, which shall set forth the basis for the numerical values used, the applicant should determine the following:

1 The fission product release assumed for these calculations should be based upon a major accident, hypothesized for purposes of site analysis or postulated from considerations of possible accidental events, that would result in potential hazards not exceeded by those from any accident considered credible. Such accidents have generally been assumed to result in substantial meltdown of the core with subsequent release of appreciable quantities of fission products.

(1) An exclusion area of such size that an individual located at any point on its boundary for two hours immediately following onset of the postulated fission product release would not receive a total radiation dose to the whole body in excess of 25 rem 2 or a total radiation dose in excess of 300 rem 2 to the thyroid from iodine exposure.

2 The whole body dose of 25 rem referred to above corresponds numerically to the once in a lifetime accidental or emergency dose for radiation workers which, according to NCRP recommendations may be disregarded in the determination of their radiation exposure status (see NBS Handbook 69 dated June 5, 1959). However, neither its use nor that of the 300 rem value for thyroid exposure as set forth in these site criteria guides are intended to imply that these numbers constitute acceptable limits for emergency doses to the public under accident conditions. Rather, this 25 rem whole body value and the 300 rem thyroid value have been set forth in these guides as reference values, which can be used in the evaluation of reactor sites with respect to potential reactor accidents of exceedingly low probability of occurrence, and low risk of public exposure to radiation.

(2) A low population zone of such size that an individual located at any point on its outer boundary 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 total radiation dose to the whole body in excess of 25 rem or a total radiation dose in excess of 300 rem to the thyroid from iodine exposure.

(3) A population center distance of at least one and one-third times the distance from the reactor to the outer boundary of the low population zone. In applying this guide, the boundary of the population center shall be determined upon consideration of population distribution. Political boundaries are not controlling in the application of this guide. Where very large cities are involved, a greater distance may be necessary because of total integrated population dose consideration.

(b) For sites for multiple reactor facilities consideration should be given to the following:

(1) If the reactors are independent to the extent that an accident in one reactor would not initiate an accident in another, the size of the exclusion area, low population zone and population center distance shall be fulfilled with respect to each reactor individually. The envelopes of the plan overlay of the areas so calculated shall then be taken as their respective boundaries.

(2) If the reactors are interconnected to the extent that an accident in one reactor could affect the safety of operation of any other, the size of the exclusion area, low population zone and population center distance shall be based upon the assumption that all interconnected reactors emit their postulated fission product releases simultaneously. This requirement may be reduced in relation to the degree of coupling between reactors, the probability of concomitant accidents and the probability that an individual would not be exposed to the radiation effects from simultaneous releases. The applicant would be expected to justify to the satisfaction of the Commission the basis for such a reduction in the source term.

(3) The applicant is expected to show that the simultaneous operation of multiple reactors at a site will not result in total radioactive effluent releases beyond the allowable limits of applicable regulations.

Note:

For further guidance in developing the exclusion area, the low population zone, and the population center distance, reference is made to Technical Information Document 14844, dated March 23, 1962, which contains a procedural method and a sample calculation that result in distances roughly reflecting current siting practices of the Commission. The calculations described in Technical Information Document 14844 may be used as a point of departure for consideration of particular site requirements which may result from evaluation of the characteristics of a particular reactor, its purpose and method of operation.

[27 FR 3509, Apr. 12, 1962, as amended at 31 FR 4670, Mar. 19, 1966; 38 FR 1273, Jan. 11, 1973; 40 FR 8793, Mar. 3, 1975; 40 FR 26527, June 24, 1975; 53 FR 43422, Oct. 27, 1988; 64 FR 48955, Sept. 9, 1999; 67 FR 67101, Nov. 4, 2002]
Notes of Decisions
New England Coalition on Nuclear Pollution v. United States Nuclear Regulatory Comm'n, Pub. Serv. Co. of New Hampshire, Intervenors, 582 F.2d 87 (1st Cir. 1978). · cites it 4× “” 10 C.F.R. § 100.11 (a)(1) & n.2. Immediately surrounding the circular exclusion area there must be a concentric band, labelled a “low population zone”, with a sufficiently small number of residents so “that there is a reasonable probability that appropriate protective measures…”
N. Indiana Pub. Serv. Co. v. Porter Cnty. Chapter of Izaak Walton League of Am., Inc., 423 U.S. 12 (1975). · cites it 4× “" At the time of NIPSCO's application and also at the time of the Court of Appeals' decision, 10 CFR § 100.11 (a) (3) (1975) further provided, in pertinent part, that "[a]s an aid in evaluating a proposed site" for a nuclear power plant a permit applicant should determine for…”
Nat. Resources Def. Council v. Nuclear Regulatory Comm'n & United States of Am., 666 F.2d 595 (D.C. Cir. 1981). “t structure, system, component or part thereof necessary to assure (1) the integrity of the reactor coolant pressure boundary, (2) the capability to shut down the reactor and maintain it in a safe shut down condition, or (3) the capability to prevent or mitigate the consequences…”
Union of Concerned Scientists v. Atomic Energy Comm'n & United States of Am., Boston Edison Co., Intervenor, 499 F.2d 1069 (D.C. Cir. 1974). “Petitioner points to the AEC’s Reactor Site Criteria, 10 C.F.R. 100.11(a), in support of its view.”
Carstens v. California Coastal Comm'n, 182 Cal. App. 3d 277 (Cal. Ct. App. 1986). “( 10 C.F.R. § 100.11 (a)(1).) On April 25, 1975, the Atomic Safety and Licensing Appeals Board ruled that SCE’s original exclusion-area plan was unacceptable because SCE could not exercise the degree of control required by 10 Code of Federal Regulations, section 100.”
Porter Cnty. Chapter of the Izaak Walton League of Am., Inc. v. Atomic Energy Comm'n, 515 F.2d 513 (7th Cir. 1975). · cites it 5× “Population density and use characteristics are further defined in 10 C.F.R. § 100.11 . A license applicant is directed to assume (a) a fission product release from the core, (b) the expected demonstrable leak rate from the containment and (c) the meteorological conditions…”
Massachusetts v. United States Nuclear Regulatory Comm'n, 924 F.2d 311 (D.C. Cir. 1991). “See 10 C.F.R. § 100.11 (a)(l)-(2). The siting regulations also require the determination of a “population center distance,” measuring the distance to the nearest area of dense population, which must be at least one and one-third times the radius of the LPZ.”
— 10 C.F.R. § 100.11(a) — 1 case
Union of Concerned Scientists v. Atomic Energy Comm'n & United States of Am., Boston Edison Co., Intervenor, 499 F.2d 1069 (D.C. Cir. 1974). “Petitioner points to the AEC’s Reactor Site Criteria, 10 C.F.R. 100.11(a), in support of its view.”
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