Section I References

DOE-HDBK-6004-99

SECTION I REFERENCES

10CFR50 (A)

10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear

Power Plants," specifically: GDC 1, 13, 19, 20, 22, 23, 24, and 64.

10CFR50 (I)

10 CFR Part 50, Appendix I.

10CFR50 (J)

10 CFR Part 50, Appendix J, "Primary Reactor Containment Leakage

Testing for Water-cooled Reactors."

ASME 93

ASME Boiler and Pressure Vessel Code, 1992 Edition with 1993

Addenda.

Caldwell 89

Design Features of the JET Vacuum Enclosure for Safe Operation

with Tritium, C. J. Caldwell-Nichols, E. Usselmann; IEEE Thirteenth

Symposium on Fusion Engineering, October 1989, Knoxville, TN,

p.716.

DOE-STD-1020-94

DOE-STD-1020-94 DOE Standard, "Natural Phenomena Hazards

Design and Evaluation Criteria for Department of Energy Facilities,"

April, 1994.

DOE 6430.1A (a)

Division 13 of DOE Order 6430.1A, "General Design Criteria," 1989.

DOE 6430.1A (b)

DOE 6430.1A, Section 1550.99, "Special Facilities," 1989.

DOE 6430.1A (c)

DOE Order 6430.1A Section 1328-7.1, "Fusion Test Facilities,"

1989.

IEEE 308

IEEE Std 308 "Standard Criteria for Class 1E Power Systems for

Nuclear Power Generating Equipment," 1991.

IEEE 603

IEEE-603, "Criteria for Safety Systems for Nuclear Power Generating

Stations," 1991.

NET 93

Next European Torus Predesign Report, Fusion Engr. and Design 21,

pp. 335-338 (1993).

NUREG-0800

Chapter 7.1 of NUREG-0800, "Standard Review Plan for the Review

of Safety Analysis Reports for Nuclear Power Plants," July 1981.

NUREG/CR-4961

Summary of Hydrogen-Air Detonation Experiments, NUREG/CR-

4961, May 1989.

RG 1.140

USNRC Regulatory Guide (Reg. Guide): 1.140.

RG 1.47

USNRC Regulatory Guides (Reg. Guides): 1.47, "Bypassed and

Inoperable Status Indication for Nuclear Power Plant Safety

Systems," May 1973 .