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CFR 10(PTS0-199) : JAN 87

Withdrawn

Withdrawn

ENERGY - NUCLEAR REGULATORY COMMISSION

Published date

01-12-2013

Withdrawn date

03-14-2024

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DocumentType
Standard
PublisherName
Code of Federal Regulations
Status
Withdrawn

ASTM D 5608 : 2016 : REDLINE Standard Practices for Decontamination of Sampling and Non Sample Contacting Equipment Used at Low Level Radioactive Waste Sites
ASTM D 5411 : 2010 : R2015 Standard Practice for Calculation of Average Energy Per Disintegration (¯E) for a Mixture of Radionuclides in Reactor Coolant
ASTM D 5144 : 2008 Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants
BS ISO 16966:2013 Nuclear energy. Nuclear fuel technology. Theoretical activation calculation method to evaluate the radioactivity of activated waste generated at nuclear reactors
ACI 349 : 2013 CODE REQUIREMENTS FOR NUCLEAR SAFETY-RELATED CONCRETE STRUCTURES AND COMMENTARY
ASTM E 1281 : 2015 : REDLINE Standard Guide for Nuclear Facility Decommissioning Plans
I.S. EN 1473:2016 INSTALLATION AND EQUIPMENT FOR LIQUEFIED NATURAL GAS - DESIGN OF ONSHORE INSTALLATIONS
IEEE 933-2013 REDLINE IEEE Guide for the Definition of Reliability Program Plans for Nuclear Generating Stations and Other Nuclear Facilities
EN 1473:2016 Installation and equipment for liquefied natural gas - Design of onshore installations
ASCE 1 88 : 1988 N-725 GUIDELINE FOR DESIGN AND ANALYSIS OF NUCLEAR SAFETY RELATED EARTH STRUCTURES
IEEE 603-2009 REDLINE IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
ACI 349M : 2013 CODE REQUIREMENTS FOR NUCLEAR SAFETY-RELATED CONCRETE STRUCTURES AND COMMENTARY
ASTM C 1571 : 2003 Standard Guide for Characterization of Radioactive and/or Hazardous Wastes for Thermal Treatment
ASTM E 1760 : 2016 : REDLINE Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
ASTM D 5411 : 2010 Standard Practice for Calculation of Average Energy Per Disintegration (E) for a Mixture of Radionuclides in Reactor Coolant
ASTM D 5144 : 2008 : EDT 1 Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants
BS EN 1473:2016 Installation and equipment for liquefied natural gas. Design of onshore installations
IEEE 7-4.3.2-2016 IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations
PD IEC/TR 63084:2017 Nuclear power plants. Instrumentation and control important to safety. Platform qualification for systems important to safety
IEEE 692-2013 REDLINE IEEE Standard for Criteria for Security Systems for Nuclear Power Generating Stations
IEEE 577-2012 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations
ASTM D 5144 : 2008 : R2016 Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants
ASTM E 2421 : 2015 : REDLINE Standard Guide for Preparing Waste Management Plans for Decommissioning Nuclear Facilities
IEC TR 63084:2017 Nuclear power plants - Instrumentation and control important to safety - Platform qualification for systems important to safety
IEEE 627-2010 IEEE Standard for Qualification of Equipment Used in Nuclear Facilities
ASTM C 1571 : 2003 : R2012 Standard Guide for Characterization of Radioactive and/or Hazardous Wastes for Thermal Treatment (Withdrawn 2018)
IEEE 308-2012 REDLINE IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
IEEE 338-2012 IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety
14/30297213 DC : 0 BS EN 1473 - INSTALLATION AND EQUIPMENT FOR LIQUEFIED NATURAL GAS - DESIGN OF ONSHORE INSTALLATIONS
ISO 16966:2013 Nuclear energy — Nuclear fuel technology — Theoretical activation calculation method to evaluate the radioactivity of activated waste generated at nuclear reactors
IEEE 379-2014 IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
ASTM C 1682 : 2017 : REDLINE Standard Guide for Characterization of Spent Nuclear Fuel in Support of Interim Storage, Transportation and Geologic Repository Disposal
ASME STP-NU-001 : 2005 RISK INITIATIVES IN ASME NUCLEAR CODES AND STANDARDS
ASME ANDE 1 : 2015 ASME NONDESTRUCTIVE EXAMINATION AND QUALITY CONTROL CENTRAL QUALIFICATION AND CERTIFICATION PROGRAM

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