1. 10 CFR Part 830 -- Nuclear Safety Management - eCFR
10 CFR Part 830; Agency: Department of Energy. Part 830. Authority: 42 U.S.C. ... The Code of Federal Regulations (CFR) is the official legal print ...
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2. 10 CFR Part 830 -- Nuclear Safety Management - eCFR
Part 830 defines nuclear facility broadly to include a reactor or a nonreactor nuclear facility where an activity is conducted for or on behalf of DOE and ...
(a) The following definitions apply to this part:
3. 10 CFR Part 830 - Law.Cornell.Edu - Cornell University
10 CFR Part 830 - PART 830—NUCLEAR SAFETY MANAGEMENT · § 830.1 Scope. · § 830.2 Exclusions. · § 830.3 Definitions. · § 830.4 General requirements. · § 830.5 ...
Source:
4. 10 CFR 830, Nuclear Safety Requirements
Federal Register publication of DNFSB Recommendation 2020-1, Nuclear Safety Requirements.
Home > Board Activities > Recommendations > 10 CFR 830, Nuclear Safety Requirements
5. [PDF] DOE Order Self Study Modules - 10 CFR 830 Safety Basis Documentation
This guide describes suggested non-mandatory approaches for meeting requirements in. 10 CFR 830 related to developing DSAs. Accelerators and their operations ...
6. 10 CFR Part 830 Nuclear Safety Technical Positions
Technical Positions to directives issued by Nuclear and Facility Safety Policy provide clarification for specific applications of the requirements in DOE orders ...
Technical Positions to directives provide clarification for specific applications of the requirements in DOE orders, rules and other directives.
7. 10 CFR § None - § 830.3 Definitions. - Law.Cornell.Edu
§ 830.3 Definitions. (a) The following definitions apply to this part: Administrative controls means the provisions relating to organization and management, ...
§ 830.3 Definitions.
8. [PDF] Recommendation 2020-1, 10 CFR 830, Nuclear Safety Requirements ...
21 feb 2020 · 10 CFR 830 captures the fundamental requirements for nuclear safety management to ensure contractors perform work “with the hazard controls that ...
9. Nuclear Safety Management - Federal Register
19 okt 2020 · Title 10 CFR part 830 was proposed to establish safety management requirements for DOE nuclear facilities. DOE issued, as final, the sections of ...
The Department of Energy (DOE or the Department) is amending its regulations concerning nuclear safety management. These regulations govern the conduct of DOE contractors, DOE personnel, and other persons conducting activities (including providing items and services) that affect, or may affect,...
10. [PDF] Regulatory Summary for 10 CFR 830 Part B
Brief Description of Best Practice: The Price Anderson Amendment Act (PAAA) involves several CFRs (e.g., 10 CFR 830, 10 CFR 835, 10 CFR 851, etc.).
11. DOE G 414.1-4, Safety Software Guide for Use with 10 CFR 830 ...
This Guide provides acceptable methods for implementing the safety software quality assurance requirements of DOE O 414.1C, Quality Assurance.
This Guide provides acceptable methods for implementing the safety software quality assurance requirements of DOE O 414.1C, Quality Assurance. Certified 11-3-10. No cancellation.
12. [PDF] 10 CFR 830 Major Modification Determination for Advanced Test ...
ensure proper implementation of the requirements established by 10 CFR 830 (10 CFR 830). Safety basis. The documented safety analysis and hazard controls ...
13. 10 CFR §830 Nuclear Safety Management
Title 10, part 830 of the Electronic Code of Federal Regulations.
14. Implementing 10 CFR Part 830 Subpart B at WIPP
28 jun 2024 · Implementation of Title 10 Code of Federal Regulations Part 830, Subpart B Nuclear Safety Management (1) was accomplished at the Waste ...
Implementation of Title 10 Code of Federal Regulations Part 830, Subpart B Nuclear Safety Management (1) was accomplished at the Waste Isolation Pilot Plant (WIPP) in a timely and efficient manner. The primary reason the transition went smoothly was that the existing safety analysis was relatively new, initially developed in 1995, and written in accordance with the safe harbor document DOE-STD-3009 (2). The WIPP Safety Analysis Report (SAR) (3) is kept up-to-date with the unreviewed safety question (USQ) process and thorough oversight and input provided by DOE-Carlsbad Field Office (CBFO) documented in the annual safety evaluation report (SER) process.
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15. [PDF] 10 CFR 830 Major Modification Determination for Emergency ...
ensure proper implementation of the requirements established by 10 CFR 830. (10 CFR 830). Safety basis - The documented safety analysis and hazard controls ...
16. DOE G 421.1-2A, Implementation Guide for Use in Developing ...
19 dec 2011 · Title 10 Code of Federal Regulations (CFR) Part 830, Subpart B, Safety Basis Requirements, requires the contractor responsible for a ...
Title 10 Code of Federal Regulations (CFR) Part 830, Subpart B, Safety Basis Requirements, requires the contractor responsible for a Department of Energy (DOE) nuclear facility to analyze the facility, the work to be performed, and the associated hazards and to identify the conditions, safe boundaries, and hazard controls necessary to protect workers, the public, and the environment from adverse consequences. Supersedes DOE G 421.1-2.
17. 830.310 - CFR - Code of Federal Regulations Title 21 - FDA
CHAPTER I--FOOD AND DRUG ADMINISTRATION DEPARTMENT OF HEALTH AND HUMAN SERVICES. SUBCHAPTER H - MEDICAL DEVICES. PART 830 -- UNIQUE DEVICE IDENTIFICATION.
The contact for device identification designated under § 830.320(a) shall provide FDA with the following information concerning each version or model of a device required to bear a unique device identifier (UDI) on its label:
18. Ruling Concerning 10 CFR Parts 830 (Nuclear Safety Management) and ...
5 feb 1996 · The Department of Energy (DOE) has issued Ruling 1995-1 which interprets certain regulatory provisions relating to DOE's nuclear safety ...
The Department of Energy (DOE) has issued Ruling 1995-1 which interprets certain regulatory provisions relating to DOE's nuclear safety requirements. This Ruling is intended to be a generally applicable clarification that addresses questions concerning the applicability and effect of these...
19. CFR - Code of Federal Regulations Title 21 - FDA
(10) The type of production identifiers that appear on the label of the device;. (11) The FDA premarket submission number of a cleared or approved device, or ...
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20. Quality Assurance Management System Guide for Use with 10 CFR ...
No. relatedhistoryexemptionsstandards. Show All. Superseded By: DOE G 414.1-2A, Quality Assurance Management System Guide for Use with 10 CFR 830 Subpart A ...
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21. [PDF] 10 CFR 830 Major Modification Determination for Advanced Test ...
ensure proper implementation of the requirements established by 10 CFR 830. (10 ... 10 CFR 830, Subpart B, “Nuclear Safety Management,” Code of Federal ...
22. Avaliação da adequação das regulamentações do 10 CFR parte ...
10 CFR parte 830. Áreas de conhecimento da DGPM: Engenharia naval. Data do documento: 2023. Editor: Centro de Instrução Almirante Alexandrino (CIAA). Descrição ...
O Complexo de Manutenção Especializada (CME) é uma instalação nuclear fundamental que proporcionará suporte em terra para a operação e manutenção do primeiro Submarino Convencionalmente Armado com Propulsão Nuclear (SCPN). A importância do CME reside na sua capacidade de garantir a eficácia operacional e de segurança do SCPN, além de cumprir as exigências de manutenção e assegurar a integridade do submarino e dos trabalhadores envolvidos. Dada a natureza nuclear das operações e funções do CME, é necessário submeter a instalação a um processo de licenciamento nuclear em conformidade com as regulamentações do órgão fiscalizador responsável. No entanto, atualmente, não existe uma normativa específica que aborde a análise de segurança e o licenciamento de instalações de suporte em terra para submarinos com propulsão nuclear. Nesse contexto, surge a necessidade de explorar a aplicabilidade do 10 CFR Parte 830 - Gestão da segurança nuclear, como uma orientação inicial para o licenciamento do CME. Este estudo visa investigar se o 10 CFR Parte 830 é de fato adequado para ser usado como guia preliminar no licenciamento do CME, analisando sua congruência com os princípios estabelecidos pela Comissão Nacional de Energia Nuclear (CNEN) para este tipo de operação. Escolheu-se o 10 CFR Parte 830, pois ele estabelece requisitos para a gestão de segurança nuclear em instalações do Departamento de Energia dos Estados Unidos e atividades associadas. Esses requisitos abrangem di...
23. [PDF] Best Practice #199 - Energy Facility Contractors Group
several CFRs (e.g., 10 CFR 830, 10 CFR 835, 10 CFR 851, etc.). PAAA Enforcement. Coordinators are expected to understand the PAAA regulations and determine ...
24. DOE G 414.1-1B, Management and Independent Assessments Guide ...
Management and Independent Assessments Guide for Use with 10 CFR Part 830, Subpart A, and DOE O 414.1C, Quality Assurance; DOE M 450.4 -1, Integrated Safety ...
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25. [PDF] FEMP-2604 IMPLEMENTING 10 CFR 830 AT THE FEMP SILOS - OSTI.GOV
the requirements of 10 CFR 830 and 29 CFR 1910.120. The format of this document is well- suited to addressing worker safety issues seen in environmental ...
26. [PDF] PD711 ASME NQA-1 and DOE Quality Assurance Rule 10 CFR 830 Day 1
Day 1. • Module 1: Overview of the ASME NQA-1 Standard and 10 CFR 450.2 Integrated. Safety Management. • Module 2: - ASME NQA-1 Part 1 Requirements 1-2.
27. 10 CFR 830 Major Modification Determination for Advanced Test ...
The replacement of the ATR Control Complex's obsolete computer based Reactor Data Acquisition System (RDAS) and its safety-related Lobe Power Calculation ...
The replacement of the ATR Control Complex's obsolete computer based Reactor Data Acquisition System (RDAS) and its safety-related Lobe Power Calculation and Indication System (LPCIS) software application is vitally important to ensure the ATR remains available to support this national mission. The RDAS supports safe operation of the reactor by providing 'real-time' plant status information (indications and alarms) for use by the reactor operators via the Console Display System (CDS). The RDAS is a computer support system that acquires analog and digital information from various reactor and reactor support systems. The RDAS information is used to display quadrant and lobe powers via a display interface more user friendly than that provided by the recorders and the Control Room upright panels. RDAS provides input to the Nuclear Engineering ATR Surveillance Data System (ASUDAS) for fuel burn-up analysis and the production of cycle data for experiment sponsors and the generation of the Core Safety Assurance Package (CSAP). RDAS also archives and provides for retrieval of historical plant data which may be used for event reconstruction, data analysis, training and safety analysis. The RDAS, LPCIS and ASUDAS need to be replaced with state-of-the-art technology in order to eliminate problems of aged computer systems, and difficulty in obtaining software upgrades, spare parts, and technical support. The major modification criteria evaluation of the project design did not lead to the...
