Nos. 1234, 1324, Dockets 83-4003, 83-4037. Argued April 14, 1983. Decided May 27, 1983. Eric Ole Thorsen, Asst. County Atty., County of Rockland, New City, N.Y. (Marc L. Parris, County Atty., County of Rockland, New City, N.Y., of counsel), for petitioner. Michael B. Blume, U.S. Nuclear Regulatory Com'n, Washington, D.C. (Herzel H.E. Plaine, Gen. Counsel, Peter G. Crane, Acting Asst. Gen. Counsel, E. Leo Slaggie, Acting Sol., U.S. Nuclear Regulatory Com'n, Washington, D.C., Carol E. Dinkins, Asst

Atomic energy is capable of application for peaceful as well as military purposes. It is therefore declared to be the policy of the United States that- (a) the development, use, and control of atomic energy shall be directed so as to make the maximum contribution to the general welfare, subject at all times to the paramount objective of making the maximum contribution to the common defense and security; and (b) the development, use, and control of atomic energy shall be directed so as to promote

(a) Conditions The Commission is authorized to issue licenses to persons applying therefor to transfer or receive in interstate commerce, manufacture, produce, transfer, acquire, possess, use, import, or export under the terms of an agreement for cooperation arranged pursuant to section 2153 of this title, utilization or production facilities for industrial or commercial purposes. Such licenses shall be issued in accordance with the provisions of subchapter XV and subject to such conditions as the

The following paragraphs of this section, with the exception of paragraphs (r) and (gg), and the applicable requirements of 10 CFR 50.55a , are conditions in every nuclear power reactor operating license issued under this part. The following paragraphs with the exception of paragraph (r), (s), and (u) of this section are conditions in every combined license issued under part 52 of this chapter, provided, however, that paragraphs (i) introductory text, (i)(1), (j), (k), (l), (m), (n), (w), (x), (y)

i. purpose General Design Criterion 2 of Appendix A to part 50 of this chapter requires that nuclear power plant structures, systems, and components important to safety be designed to withstand the effects of natural phenomena such as earthquakes, tornadoes, hurricanes, floods, tsunami, and seiches without loss of capability to perform their safety functions. It is the purpose of these criteria to set forth the principal seismic and geologic considerations which guide the Commission in its evaluation

(a) The criteria in this subpart apply to the decommissioning of facilities licensed under parts 30, 40, 50, 52, 60, 61, 63, 70, and 72 of this chapter, and release of part of a facility or site for unrestricted use in accordance with § 50.83 of this chapter, as well as other facilities subject to the Commission's jurisdiction under the Atomic Energy Act of 1954, as amended, and the Energy Reorganization Act of 1974, as amended. For high-level and low-level waste disposal facilities (10 CFR parts

Each application must contain the following information: (a)An integrated plant assessment (IPA). The IPA must- (1) For those systems, structures, and components within the scope of this part, as delineated in § 54.4 , identify and list those structures and components subject to an aging management review. Structures and components subject to an aging management review shall encompass those structures and components- (i) That perform an intended function, as described in § 54.4 , without moving parts

(a) Each licensee shall make or cause to be made, surveys of areas, including the subsurface, that- (1) May be necessary for the licensee to comply with the regulations in this part; and (2) Are reasonable under the circumstances to evaluate- (i) The magnitude and extent of radiation levels; and (ii) Concentrations or quantities of residual radioactivity; and (iii) The potential radiological hazards of the radiation levels and residual radioactivity detected. (b) Notwithstanding § 20.2103(a) of this

(a) Applicants for licenses, other than early site permits and manufacturing licenses under part 52 of this chapter and renewals, whose applications are submitted after August 20, 1997, shall describe in the application how facility design and procedures for operation will minimize, to the extent practicable, contamination of the facility and the environment, facilitate eventual decommissioning, and minimize, to the extent practicable, the generation of radioactive waste. (b) Applicants for standard

(a)Definitions. Risk-Informed Safety Class (RISC)-1 structures, systems, and components (SSCs) means safety-related SSCs that perform safety significant functions. Risk-Informed Safety Class (RISC)-2 structures, systems and components (SSCs) means nonsafety-related SSCs that perform safety significant functions. Risk-Informed Safety Class (RISC)-3 structures, systems and components (SSCs) means safety-related SSCs that perform low safety significant functions. Risk-Informed Safety Class (RISC)-4

(a) (1) Each applicant for a license authorizing operation of a production or utilization facility shall include in his application proposed technical specifications in accordance with the requirements of this section. A summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the technical specifications. (2) Each applicant for a design certification or manufacturing