Deviations From Standard Format (RG 1.70)

It includes appropriate sec-

groups of nuclear safety criteria.

tions from the SRP, NRC Information Notices and Bulletins,

NUREGs, and other documents specified in the NRC criteria.

Although these sources do not always specify requirements, they

provide interpretations of the criteria, as well as methods

specified by the NRC or considered acceptable to the NRC for

implementing and satisfying the pertinent NRC criteria.

1.3

Recognizing the unique features and characteristics

associated with many DOE reactors, Chapter 10 was expanded to

include experimental facilities as well as the steam- and power-

conversion systems that are specified in Regulatory Guide 1.70.

As a result of the TMI-2 accident, human factors criteria were

added to the SRP.

Although Regulatory Guide 1.70 has not been

revised to include such criteria, Chapter 18 of this document

identifies human factors criteria specified in the SRP.

1.4

This section compiles the criteria that address the

need, preparation, and revision of a safety analysis report

(SAR); such criteria are not included in the areas of nuclear

Criteria are also identified whose

safety addressed in a SAR.

methods of implementation may affect the preparation of various

sections of a SAR, particularly for new reactors.

1.4.1

Code of Federal Regulations

Commission Interim Policy Statement, "Nuclear Power

Plant Accident Considerations Under the National Environmental

Policy Act of 1969," 45 FR 40101, June 13, 1980.

Commission Policy Statements.

"Systematic Safety Evaluation of Operating

Nuclear Power Reactors, " 49 FR 45112, November 15, 1984.

"Severe Reactor Accidents Regarding Future

Designs and Existing Plants," 50 FR 32138, August 8, 1985.

"Safety Goals for the Operation of Nuclear

Power Plants," 51 FR 30028, August 21, 1986.

"Maintenance of Nuclear Power Plants," 53 FR

9430, March 23, 1988

"Maintenance of Nuclear Power Plants," 53 FR

50611, December 8, 1989.

1-3