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Y 3.N 88:10/1723
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Safety evaluation report related to the license renewal of Oconee Nuclear Station, units 1, 2, and 3 : docket nos. 50-269, 50-270, and 50-287 |
1 |
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Y 3.N 88:10/1724/DRAFT
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Standard review plan for the review of DOE plans for achieving regulatory compliance at sites with contaminated ground water under title I of the Uranium Mill Tailings Radiation Control Act : draft report for comment |
1 |
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Y 3.N 88:10/1737
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Software quality assurance procedures for NRC thermal hydraulic codes |
1 |
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Y 3.N 88:10/1740
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Voltage-based alternative repair criteria : a report to the Advisory Committee on Reactor Safeguards by the Ad Hoc Subcommittee on a Differing Professional Opinion |
1 |
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Y 3.N 88:10/1742/FINAL/V.1-2
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Perspectives gained from the Individual Plant Examination of External Events (IPEEE) program, final report |
1 |
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Y 3.N 88:10/1744
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Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data |
1 |
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Y 3.N 88:10/1745
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Standard format and content for technical specifications for 10 CFR 72 cask certificates of compliance |
1 |
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Y 3.N 88:10/1746
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System-level repository sensitivity analyses, using TPA version 3.2 code |
1 |
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Y 3.N 88:10/1747/FINAL
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Overview and summary of NRC involvement with DOE in the Tank Waste Remediation System-Privatization (TWRS-P) Program |
1 |
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Y 3.N 88:10/1749
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Implications from the phenomenon identification and ranking tables (PIRTs) and suggested research activities for high burnup fuel |
1 |
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Y 3.N 88:10/1750
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Assessment of soil amplification of earthquake ground motion using the "CARES" code version 1.2 |
1 |
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Y 3.N 88:10/1752
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Assessment of modernization and integration of BWR components and spatial kinetics in the TRAC-M, version 3690, code |
1 |
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Y 3.N 88:10/1753
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Risk-based performance indicators : results of phase 1 development |
1 |
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Y 3.N 88:10/1754
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A new comparative analysis of LWR fuel designs |
1 |
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Y 3.N 88:10/1755
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Some observations on risk-informing appendices A and B to 10 CFR part 50 : prepared for the Advisory Committee on Reactor Safeguards |
1 |
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Y 3.N 88:10/1756
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Safety culture : a survey of the state-of-the-art, prepared for the Advisory Committee on Reactor Safeguards |
1 |
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Y 3.N 88:10/1762
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Integrated issue resolution status report |
1 |
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Y 3.N 88:10/1764/DRAFT
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Guidance for the review of changes to human actions : draft report for comment |
1 |
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Y 3.N 88:10/1764/FINAL
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Guidance for the review of changes to human actions, final report |
1 |
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Y 3.N 88:10/1766
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Safety evaluation report related to the license renewal of North Anna Power Station, units 1 and 2, and Surry Power Station, units 1 and 2 : docket nos. 50-388, 50-389, 50-280, and 50-281, Virginia Electric and Power Company |
1 |