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- Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents in Westinghouse-Designed Operating Plants. Část 4 (Appendix 10-2.část) . Washington : U.S. Nuclear Regulatory Commission, 1980 . s 175-350 . [1, currently available 1]
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- Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents in Westinghouse-Designed Operating Plants. Část 2 (Appendix 4-9) . Washington : U.S. Nuclear Regulatory Commission, 1980 . Přerušstr . [1, currently available 1]
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- Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents in GE-Designed Operating Plants and Near-Term Operating License Applications . Washington : U.S. Nuclear Regulatory Commission, 1980 . Přerušstr . [1, currently available 1]
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- Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents in Westinghouse-Designed Operating Plants. Část 3 (Appendix 10-1.část) . Washington : U.S. Nuclear Regulatory Commission, 1980 . 174 s . [1, currently available 1]
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- Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents in Westinghouse-Designed Operating Plants. Část 1 . Washington : U.S. Nuclear Regulatory Commission, 1980 . Přerušstr . [1, currently available 1]
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- Followup Actions Resulting from the NRC Staff Reviews Regarding the Three Mile Island Unit 2 Accident : (To All Operating Nuclear Power Plants) / Darrell G. EISENHUT . Washington : U.S. Nuclear Regulatory Commission, 1979 . Přerušstr . [1, currently available 1]
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- Followup Actions Resulting from the NRC Staff Reviews Regarding the Three Mile Island Unit 2 Accident : (To All Pending Operating License Applicants) / Domenic B. VASSALLO . Washington : U.S. Nuclear Regulatory Commission, 1979 . Přerušstr . [1, currently available 1]
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- An Aging Failure Survey of Light Water Reactor Safety Systems and Components / P.E. MAC DONALD . B.m.n.r. . sl29-45 . [1, currently available 1]
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