Safety Evaluation Report of Barakah Units 1 and

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SER Summary-CLA Barakah Units 1&2
The regulation specifies the minimum requirements for an operations personnel training
program, including technical knowledge of the nuclear facility, management competencies
and communications skills, and familiarity with accident symptoms and accident response.
Requirements for training program resources such as classroom facilities, training material,
and training simulator are also described.
4.3 Summary of Applicable Regulatory Guidance
FANR regulatory guides (RGs) are issued to describe acceptable methods for complying
with FANR regulations. The following paragraphs summarize the regulatory guides
applicable to the Barakah Units 1 and 2 CLA. Regulatory Guides are not substitutes for
regulations, and compliance with them is not required. Methods of complying with the
requirements in regulations different from the guidance set forth by the regulatory guide can
be acceptable, if the alternatives provide assurance that the requirements are met.
FANR-RG-001, “Content of Nuclear Facility Construction and Operating Licence
Applications”
FANR-RG-001 provides guidance for the content of the detailed information required to be
submitted in support of a licence application per FANR-REG-06. The guidance provided in
FANR-RG-001 is based in part on IAEA Safety Guide GS-G-4.1, “Format and Content of the
Safety Analysis Report for Nuclear Power Plants,” U.S. NRC Regulatory Guide 1.206,
“Combined License Applications for Nuclear Power Plants,” and U.S. NRC Regulatory
Guide 1.70, “Standard Format and Content of Safety Analysis Reports for Nuclear Power
Plants.”
The regulatory guide states that safety analysis reports (SARs) are important documents
that FANR assesses in determining the adequacy of the plant design and suitability as a
licensing basis. Content of the SARs is delineated by section, with reference to the
applicable IAEA Safety Guide or U.S. NRC Regulatory Guide.
For a construction licence application, FANR-RG-001 provides that the application should
provide sufficient information about the proposed approach to allow a complete safety review
of the construction activities.
FANR-RG-002, “Application of Management Systems for Nuclear Facilities”
FANR-RG-002 describes acceptable methods for complying with FANR-REG-01. The
regulatory guide refers to several international standards for specific guidance, including
IAEA Safety Guide GS-G-3.1, “Application of the Management System for Facilities and
Activities,” IAEA Safety Guide GS-G-3.5, “The Management System for Nuclear
Installations,” and American National Standards Institute (ANSI)/ American Society of
Mechanical Engineers (ASME) NQA-1, “Quality Assurance Requirements for Nuclear Facility
Applications.”
FANR-RG-003, “Probabilistic Risk Assessment: Scope, Quality and Applications”
FANR-RG-003 provides guidance for implementing the requirements of FANR-REG-05. The
guidance states that the PRA should represent the design and site-specific features of the
facility, and address all initiating events that challenge the facility, including internally and
externally initiated events, and cover all modes of plant operation. Also, the PRA should
provide a Level 1 analysis of core damage frequency and a Level 2 analysis of large release
frequency.