DataPoint Standard 15.0 License Key 31

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DataPoint Standard 15.0 License Key 31

Pursuant to this paragraph (e), the licensee shall, not less than 30 days before the submittal of the updated FSAR under this section to the Commission, provide the Commission with a written notice including:

For reactor licensees, if the plant operation is being transferred from the operating license maintainer to the licensee, the applicant shall submit a copy of the notice to all direct reporting Federal regulatory agencies as required by 52.59(b) of this chapter.

For license applicants who are transferring all operating responsibilities to a successor licensee, the operating license maintainer, in addition to the notice and submittal requirements described in paragraphs (e)(1) and (e)(4) of this section, shall submit a notice of license transfer to the Commission at least 30 days before transfer is completed.

The text of this standard is taken from the standard. The programmatic intent and accompanying data elements of this standard have been revised in order to be consistent with the reporting requirements of the revised reporting requirements of the Atomic Safety and Licensing Board (ASLB) and the Security and Nuclear Regulatory Commission (NRC).

(1) An action, omission, or practice found nonconforming or not in accordance with a license, is not per se a license violation. Rather, these are violations of the regulations to which the licensee is subject, and may be remedied and corrected by the licensee before an actual license violation occurs. (See also 10 CFR 50.80(b)).

(2) The Commission will not and cannot attempt to ascertain the credibility or credibility of any representations as to the existence of conditions other than those required in the license. The license validity period indicated on the license, or provided in the license application, does not represent to the Commission or any other public agency the length of time during which the licensee will comply with the NRC’s orders. Licenses are not automatically extended by virtue of administrative or judicial delay in action. The Commission, however, may extend a license for good cause. Unless so extended, a license expires at the end of its validity period.

8. Containment Integrity; – Type C testing was implemented on June 10, 1987 with the standard cited above. Based on the experience gained to date, no further regulatory changes in Type C testing are deemed necessary. No degradation of containment integrity has been observed at FMBC. The FMBC containment was designed by a team of experienced engineers to provide full containment integrity.
3. Standards. (a) For purposes of this section, the term structure, system, or component means a containment system, and/or a component of a containment system, or any group of components which make up the containment system. The term structure, system, or component may also include the inter-assemblies and any group of associated components which make up a containment structure. The containment system in which the structure, system, or component is contained shall be defined as the structure, system, or component in its containment system. This definition includes the structure, system, or component (b) Each holder of an operating license for a nuclear power plant under this part and each holder of a combined license under part 52 of this chapter shall monitor the performance or condition of the components of a containment system against licensee-established goals, in a manner sufficient to provide reasonable assurance that these components are capable of fulfilling their intended functions. These goals shall be established commensurate with safety, and take into account industrywide operating experience.
(2) The goal for each type of component for a specific location shall be based on the design basis accident rate for the specific location. The standard dose rates of the Standard Assessment Tool (SAT) designed to be used for that purpose are given in the Standard Assessment Planning System (SAPs) Manual, Revision III, Table IV-B-1, for each component type and/or a group of components making up the component. The goal for each type of component shall be based on the error rate for a standard assessment test procedure, usually a standard time-of-year test program but may be a single test, and shall be measured in terms of SFR for a specified goal or percent for a specified minimum goal using the dose-rate-to-SFR conversion factor.
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