Source: https://www.law.cornell.edu/cfr/text/10/appendix-C_to_part_52
Timestamp: 2017-05-24 10:17:53
Document Index: 550531409

Matched Legal Cases: ['art 52', 'art 52', 'art_52', 'art 52', 'art 52', 'art 51', 'arts 20', 'art 50', 'art 50', 'art 52', 'art 52', 'art 52']

10 CFR Appendix C to Part 52, Design Certification Rule for the AP600 Design | US Law | LII / Legal Information Institute
CFR › Title 10 › Chapter I › Part 52 › Subpart H › Appendix C_to_part_52 10 CFR Appendix C to Part 52, Design Certification Rule for the AP600 Design
Appendix C constitutes the standard design certification for the AP600 1 design, in accordance with 10 CFR part 52, subpart B. The applicant for certification of the AP600 design is Westinghouse Electric Company LLC.
1 AP600 is a trademark of Westinghouse Electric Company LLC.
4. The investment protection short-term availability controls in Section 16.3 of the DCD.
A. Tier 1, Tier 2 (including the investment protection short-term availability controls in Section 16.3), and the generic technical specifications in the AP600 DCD (12/99 revision) are approved for incorporation by reference by the Director of the Office of the Federal Register on January 24, 2000, in accordance with 5 U.S.C. 552(a) and 1 1 CFR part 51. Copies of the generic DCD may be obtained from Ronald P. Vijuk, Manager, Passive Plant Engineering, Westinghouse Electric Company, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355. A copy of the generic DCD is available for examination and copying at the NRC Public Document Room located at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. Copies are also available for examination at the NRC Library located at Two White Flint North, 11545 Rockville Pike, Rockville, Maryland 20852; and the Office of the Federal Register, 800 North Capitol Street, NW., Suite 700, Washington, DC.
B. An applicant or licensee referencing this appendix, in accordance with Section IV of this appendix, shall incorporate by reference and comply with the requirements of this appendix, including Tier 1, Tier 2 (including the investment protection short-term availability controls in Section 16.3), and the generic technical specifications except as otherwise provided in this appendix. Conceptual design information in the generic DCD and the evaluation of severe accident mitigation design alternatives in Appendix 1B of the generic DCD are not part of this appendix.
D. If there is a conflict between the generic DCD and either the application for design certification of the AP600 design or NUREG-1512, “Final Safety Evaluation Report Related to Certification of the AP600 Standard Design,” (FSER), then the generic DCD controls.
a. A plant-specific DCD containing the same type of information and utilizing the same organization and numbering as the generic DCD for the AP600 design, as modified and supplemented by the applicant's exemptions and departures;
3. Include, in the plant-specific DCD, the proprietary information and safeguards information referenced in the AP600 DCD.
A. Except as indicated in paragraph B of this section, the regulations that apply to the AP600 design are in 10 CFR parts 20, 50, 73, and 100, codified as of December 16, 1999, that are applicable and technically relevant, as described in the FSER (NUREG-1512) and the supplementary information for this section.
B. The AP600 design is exempt from portions of the following regulations:
1. Paragraph (a)(1) of 10 CFR 50.34 - whole body dose criterion;
2. Paragraph (f)(2)(iv) of 10 CFR 50.34 - Plant Safety Parameter Display Console;
3. Paragraphs (f)(2)(vii), (viii), (xxvi), and (xxviii) of 10 CFR 50.34 - Accident Source Term in TID 14844;
4. Paragraph (a)(2) of 10 CFR 50.55a - ASME Boiler and Pressure Vessel Code;
5. Paragraph (c)(1) of 10 CFR 50.62 - Auxiliary (or emergency) feedwater system;
6. Appendix A to 10 CFR part 50, GDC 17 - Offsite Power Sources; and
7. Appendix A to 10 CFR part 50, GDC 19 - whole body dose criterion.
A. The Commission has determined that the structures, systems, components, and design features of the AP600 design comply with the provisions of the Atomic Energy Act of 1954, as amended, and the applicable regulations identified in Section V of this appendix; and therefore, provide adequate protection to the health and safety of the public. A conclusion that a matter is resolved includes the finding that additional or alternative structures, systems, components, design features, design criteria, testing, analyses, acceptance criteria, or justifications are not necessary for the AP600 design.
1. All nuclear safety issues, except for the generic technical specifications and other operational requirements, associated with the information in the FSER and Supplement No. 1, Tier 1, Tier 2 (including referenced information which the context indicates is intended as requirements and the investment protection short-term availability controls in Section 16.3), and the rulemaking record for certification of the AP600 design;
2. All nuclear safety and safeguards issues associated with the information in proprietary and safeguards documents, referenced and in context, are intended as requirements in the generic DCD for the AP600 design;
7. All environmental issues concerning severe accident mitigation design alternatives associated with the information in the NRC's environmental assessment for the AP600 design and appendix 1B of the generic DCD, for plants referencing this appendix whose site parameters are within those specified in the severe accident mitigation design alternatives evaluation.
E.1. Persons who wish to review proprietary and safeguards information or other secondary references in the AP600 DCD, in order to request or participate in the hearing required by 10 CFR 52.85 or the hearing provided under 10 CFR 52.103, or to request or participate in any other hearing relating to this appendix in which interested persons have adjudicatory hearing rights, shall first request access to such information from Westinghouse. The request must state with particularity:
2. If a person claims that the information is necessary to prepare a request for hearing, the request must be filed no later than 15 days after publication in the Federal Register of the notice required either by 10 CFR 52.85 or 10 CFR 52.103. If Westinghouse declines to provide the information sought, Westinghouse shall send a written response within 10 days of receiving the request to the requesting person setting forth with particularity the reasons for its refusal. The person may then request the Commission (or presiding officer, if a proceeding has been established) to order disclosure. The person shall include copies of the original request (and any subsequent clarifying information provided by the requesting party to the applicant) and the applicant's response. The Commission and presiding officer shall base their decisions solely on the person's original request (including any clarifying information provided by the requesting person to Westinghouse), and Westinghouse's response. The Commission and presiding officer may order Westinghouse to provide access to some or all of the requested information, subject to an appropriate non-disclosure agreement.
This appendix may be referenced for a period of 15 years from January 24, 2000, except as provided for in 10 CFR 52.55(b) and 52.57(b). This appendix remains valid for an applicant or licensee who references this appendix until the application is withdrawn or the license expires, including any period of extended operation under a renewed license.
b. A proposed departure from Tier 2, other than one affecting resolution of a severe accident issue identified in the plant-specific DCD, requires a license amendment if it would:
d. If a departure requires a license amendment under paragraphs B.5.b or B.5.c of this section, it is governed by 10 CFR 50.90.
6a. An applicant who references this appendix may not depart from Tier 2* information, which is designated with italicized text or brackets and an asterisk in the generic DCD, without NRC approval. The departure will not be considered a resolved issue, within the meaning of Section VI of this appendix and 10 CFR 52.63(a)(5).
(1) Maximum fuel rod average burn-up.
(2) Fuel principal design requirements.
(3) Fuel criteria evaluation process.
(4) Fire areas.
(5) Human factors engineering.
(1) Nuclear Island structural dimensions.
(2) ASME Boiler and Pressure Vessel Code, Section III, and Code Case - 284.
(3) Design Summary of Critical Sections.
(4) ACI 318, ACI 349, and ANSI/AISC - 690.
(5) Definition of critical locations and thicknesses.
(6) Seismic qualification methods and standards.
(7) Nuclear design of fuel and reactivity control system, except burn-up limit.
(8) Motor-operated and power-operated valves.
(9) Instrumentation and control system design processes, methods, and standards.
(10) PRHR natural circulation test (first plant only).
(11) ADS and CMT verification tests (first three plants only).
1. The applicant for this appendix shall maintain a copy of the generic DCD that includes all generic changes to Tier 1, Tier 2, and the generic TS and other operational requirements. The applicant shall maintain the proprietary and safeguards information referenced in the generic DCD for the period that this appendix may be referenced, as specified in Section VII of this appendix.
c. After the Commission makes the finding required by 10 CFR 52.103(g), the reports and updates to the plant-specific DCD must be submitted, along with updates to the site-specific portion of the final safety analysis report for the facility, at the intervals required by 10 CFR 50.59(d)(2) and 50.71(e), respectively, or at shorter intervals as specified in the license.
[ 72 FR 49517, Aug. 28, 2007, as amended at 76 FR 72085, Nov. 22, 2011]
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typeregulations.gov FR Doc.2014-28238 RIN3150-AI85 NRC-2010-0135 Docket No.52-0010 NUCLEAR REGULATORY COMMISSION NUREG; issuance. December 2, 2014. 10 CFR Part 52 SummaryThe U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG-1966, Supplement 1, “Final Safety Evaluation Report Related to the Certification of the Economic Simplified Boiling-Water Reactor Standard Design, Supplement 1.”
2014-10-15; vol. 79 # 199 - Wednesday, October 15, 201479 FR 61944 - Economic Simplified Boiling-Water Reactor Design Certification
typeregulations.gov FR Doc.2014-24362 RIN3150-AI85 NRC-2010-0135 Nuclear Regulatory Commission Final rule. This final rule is effective on November 14, 2014. The incorporation by reference of certain publications listed in this regulation is approved by the Director of the Office of the Federal Register (OFR) as of November 14, 2014. 10 CFR Part 52 SummaryThe U.S. Nuclear Regulatory Commission (NRC) is adopting a new rule certifying the Economic Simplified Boiling-Water Reactor (ESBWR) standard plant design. This action is necessary so that applicants or licensees intending to construct and operate an ESBWR design may do so by referencing this design certification rule (DCR). The applicant for certification of the ESBWR design is GE-Hitachi Nuclear Energy (GEH).
2013-07-23; vol. 78 # 141 - Tuesday, July 23, 201378 FR 44036 - Station Blackout Mitigation Strategies