An STSM shall have a working level knowledge of the content of the safety basis requirements

DOE-STD-1175-2006

DOE-STD-1027-92, Hazard Categorization and Accident Analysis

Techniques for Compliance with DOE Order 5480.23, Nuclear Safety

Analysis Reports [SAR];

DOE-STD-1083-95, Requesting and Granting Exemptions to Nuclear

Safety Rules;

DOE-STD-1104-96, Review and Approval of Nonreactor Nuclear Facility

Safety Analysis Reports;

DOE-STD-1120-2005, Integration of Environment, Safety, and Health into

Facility Disposition Activities, Volumes 1 and 2;

DOE-STD-1186-2004, Specific Administrative Controls;

DOE-STD-3009-94, Preparation Guide for U.S. Department of Energy

Nonreactor Nuclear Safety Analysis Reports;

DOE-HDBK-3010-94, Airborne Release Fractions/Rates and Respirable

Fractions for Nonreactor Nuclear Facilities;

DOE-STD-3011-2002, Guidance For Preparation Of Basis For Interim

Operation (BIO) Documents;

DOE-EM-STD-5502-94, Hazard Baseline Documentation;

10 CFR 820, Procedural Rules for DOE Nuclear Activities; and

10 CFR 830, Subpart B, Safety Basis Requirements.

Discuss the development and maintenance of the requirements described in

10 CFR 830, Subpart B, Safety Basis Requirements," for DOE and contractors

authorized to operate nuclear facilities.

Discuss the following items in the context of safe operation of a nuclear facility:

Authorization Agreements;

Authorization Basis;

Documented Safety Analysis;

Fire Hazard Analysis;

Graded approach;

Limiting conditions for operation;

Limiting control setting;

Operational Readiness Review;

Preliminary Documented Safety Analysis;

Potential Inadequacies of the Safety Analysis (PISA);

Readiness Assessment;

Safety Significant Components (SSCs);

Safe Harbor Methodologies;

Safety Analysis Report for Packaging;

Safety Basis;

Safety Class SSCs;

Safety Evaluation Report;

Safety limit;

Safety significant SSCs;

Shipper Receiver Agreements;