Applicability - std301120020008

DOE-STD-3011-2002

compliant Safety Analysis Report. It was not expected to be fully compliant with

the Order. However, a BIO under 10 CFR 830 must fully satisfy the requirements

of 10 CFR 830 parts .202 and .204.

Specifically, the DSA (BIO) must include:

Facility categorization according to DOE-STD-1027

A description of the facility (including the work to be performed)

A systematic identification of hazards associated with the facility

Evaluation of normal, abnormal, and accident conditions (including potential

natural phenomenon hazards that might be associated with long term status) that

might be associated with the generation or release of radioactive or other

hazardous materials, including consideration of the need for analysis of beyond

design basis accidents

Derivation and classification of hazard controls necessary to protect workers, the

public, and the environment

Definition of the characteristics of safety management programs necessary to

ensure safe operation, including criticality safety, when criticality hazards exist

Applicability. DSAs are required for Hazard Category 1, 2, or 3 nuclear facilities as

1.2

defined in 10 CFR 830 and formalized in DOE-STD-1027, Hazard Categorization

and Accident Analysis Techniques for Compliance with DOE 5480.23. Facilities and

operations that fall below the Hazard Category 3 threshold are considered outside the

scope of 10 CFR 830 requirements for a DOE-approved DSA. The methodology in

this Standard has been determined to be acceptable for the following types of DOE-

owned or DOE-leased (including National Nuclear Security Administration [NNSA])

Hazard Category 1, 2, and 3 nuclear facilities and activities:

a. A nuclear facility with a limited operational life;

b. The deactivation of a nuclear facility; and

c. The transition surveillance and maintenance of a nuclear facility.

The terms "nuclear facility with a limited operational life", "deactivation", and

"transition surveillance and maintenance activities" are defined in Table 3 of

Appendix A of 10 CFR 830 Subpart B and are further expanded upon in Section

V.2.4, Basis for Interim Operations for Deactivation, Surveillance and Maintenance,

and Limited Operational Life Facilities, of DOE Guide 421.1-2. In the context of this

Standard, these activities are interpreted to be interim operations, since the expected

normal lifetime for these activities is ideally anticipated to be the short (i.e., less than

5 years for limited operational life) interim transitional periods immediately prior to,

during, or after deactivation. While this standard allows for an abbreviated and

graded approach to development of a safety basis, the expectation exists that the

completeness of the analysis will be sufficient so that even though a limited

operational life is envisioned, significant hazards will be identified and appropriate

controls implemented accordingly. It is also important to recognize and anticipate

that the ideal may not be realized. That is, especially in the case of transition

surveillance and maintenance, the time interval that a facility may be in that mode

may extend many years beyond "short." When this may be the case, special attention