|
The company's staff are familiar with and apply industry
standards and practices as appropriate for clients' projects. This
includes the following common requirements, standards and guides.
Canadian Nuclear Safety Commission
- Nuclear Safety Control Act
- Regulations for Nuclear Power Plants
- C-006R1, Draft Regulatory Guide -- Requirements for the Safety
Analysis of CANDU NPP
- R-7, Requirements for Containment Systems for CANDU NPP
- R-8, Requirements for Shutdown Systems for CANDU NPP
- R-9, Requirements for Emergency Core Cooling Systems for CANDU
NPP
- R-10, The Use of Two Shutdown Systems in Reactors
- R-77, Overpressure Protection Requirements for Primary Heat
Transport Systems in CANDU Powered Reactors Fitted with Two Shutdowns
Systems
- R-85, Radiation Protection Requisites for the Exemption of
Certain Radioactive Materials from Further Licensing Upon
Transferral or Disposal
- S-98, Reliability Program for Nuclear Power Plants
- S-99, Reporting Requirements for Operating Nuclear Power
Plants
- S-294, Probabilistic Safety Assessment (PSA) for Nuclear
Power Plants
- G-129, Keeping Radiation Exposures "As Low as Reasonably
Achievable (ALARA)"
- G-149, Computer Programs Used in Design and Safety Analyses
of Nuclear Power Plants and Research Reactors
Canadian Standards Association
- N286-05, Management System Requirements for Nuclear Power
Plants
- N286.0-92(R1998), Overall Quality Assurance Program for Nuclear
Power Plants
- N286.2-00, Design Quality Assurance for Nuclear Power Plants
- N286.5-95(R2000), Operations Quality Assurance for Nuclear Power
Plants
- N286.7-99(R2003), Quality Assurance of Analytical, Scientific
and Design Computer Programs for Nuclear Power Plants
- CAN3-N290.6-M82, Requirements for the Monitoring and Display of
CANDU Nuclear Power Plant Status in the Event of an Accident
- N290.13, Requirements for Environmental Qualification of
Equipment for CANDU Nuclear Power Plants
- N293-95, Fire Protection in CANDU Nuclear Power Plants
ANSI Standards and Guides
- ANSI/ANS-5.1, Decay Heat Power in Light Water Reactors
- ANSI/ANS-6.4-1997, Nuclear Analysis and Design of Concrete
Radiation Shielding for Nuclear Power Plants
- ANSI/ANS-58.2, Design Basis for Protection of Light Water
Nuclear Power Plants Against the Effects of Postulated Pipe
Rupture
- ANSI/ANS-58.4, Criteria for Technical Specifications for Nuclear
Power Plants
- ANSI/ANS-10.3, Documentation of Computer Software
- ANSI/ANS-10.4, Guidelines for the Verification and Validation
of Scientific and Engineering Computer Programs for the Nuclear
Industry
- ANSI/ISA-67.04.01-2000, Setpoints for Nuclear Safety-Related
Instrumentation
IAEA Standards and Guides
- NS-R-1, Safety of Nuclear Power Plants: Design Safety
Requirements
- NS-R-2, Safety of Nuclear Power Plants: Operation Safety
Requirements
- NS-R-3, Site Evaluation of Nuclear Power Plants
- TS-R-1, Regulations for the Safe Transport of Nuclear
Materials
- INSAG-12, Basic Safety Principles for NPP
- INSAG-14, Safe Management of the Operating Lifetimes of NPP
- INSAG-10, Defence in Depth in Nuclear Safety
- Safety Report Series No. 29, Accident Analysis for Nuclear Power
Plants with Pressurized Heavy Water Reactors
- INSAG-19, Maintaining the Design Integrity of Nuclear
Installations Throughout Their Operating Life
IEEE Standards and Guides
- IEEE 323-1983, Standard for Qualifying Class IE Equipment
for Nuclear Power Generating Stations
|
