Atlantic Nuclear Services Inc.

Licensing and Safety Concepts

Development of benefit-cost analysis (BCA) methodology used in evaluating the safety case for proposed design changes under Point Lepreau Refurbishment.
Production of plant Safety Reports -- ANS staff have produced the 1997, 2000 and 2003 versions of the Point Lepreau Safety Report.
Participation in a working group on risk informed decision making in licensing of CANDU reactors.
Participation in the Safety & Licensing Steering Committee for the refurbishment of Point Lepreau.
Work in design and licensing basis for Point Lepreau.
Performance of Periodic Safety Review report for PLGS Refurbishment.

Development of the Impairments Manual for the Point Lepreau GS which implements the Safe Operating Envelope (SOE) for the special safety systems.
Technical support to Point Lepreau DOA program, which is a review to ensure alignment of safety analysis, design and operating procedures for safety systems.
Training of station staff on the requirements and implementation of the SOE.

Analysis support for safe operating envelope, design changes, outage management and safety analysis.
ANS staff have developed most of the primary and secondary side idealizations of the Point Lepreau GS for the CATHENA two-phase thermalhydraulic code.
CANDU-6 systems and CANDU test facilities have been modelled with RELAP.
The PHOENICS 3D code has been used for detailed modelling of circuit features and containment.
Experience with the full reactor physics range codes from ENDF data manipulation to lattice codes, diffusion codes, Monte Carlo analysis (MCNP), shielding assessments, decay heat calculations, criticality analysis, etc.
There has been on-going work in verification, validation and maintenance of the RFSP code.

Technical support for Level 1 and 2 PSA’s at Point Lepreau and Embalse.
Development of fault tree models for various safety related systems using the CAFTA code suite.
Training of Point Lepreau staff on PSA methodology Level 1 and 2, including Human Reliability Assessment.
Incorporating Common Cause Failure (CCF) into the fault trees for SDS1 and SDS2 at Point Lepreau.
Plant walkdowns for Fire/Flood PSA at Point Lepreau.
Determination of plant cable routing using combination of database analysis of DICON data and elementary drawings at Point Lepreau.

Developed a methodology for assessing the safety significance of fires for nuclear safety in the Fire Hazard Assessment for Point Lepreau.
Analysis of cable routing and plant walkdowns to determine need for improved protection to ensure Group I/II separation of safety functions in the event of a fire.

Assessment of the safety significance of events for input to the Corrective Action program at Point Lepreau.
Assessment of system performance or operating margins against analysis assumptions regarding impact on safety and licence limits.

Experienced in the operation and application of fuel and reactor physics industry standard simulation codes.
Development and maintenance of procedures for calibrating the ROP system detectors.
Developed methods for core monitoring of channel flow, time averaged flux shape, flux tilts and related core parameters.

Certified staff for power plant operations and qualified power plant operators.
Preparation and review of operating procedures for both normal and abnormal conditions.