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E 1.99:nureg--1556-vol.1
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Consolidated guidance about materials licenses Program-specific guidance about portable gauge licenses. Final report; Volume 1. |
1 |
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E 1.99:nureg--1557
|
Summary of technical information and agreements from Nuclear Management and Resources Council industry reports addressing license renewal |
1 |
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E 1.99:NUREG--1560-Vol.1
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Individual plant examination program Perspectives on reactor safety and plant performance. Part 1: Final summary report; Volume 1. |
1 |
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E 1.99:NUREG--1560-Vol.2
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Individual plant examination program Perspectives on reactor safety and plant performance. Parts 2--5: Final report; Volume 2. |
1 |
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E 1.99:nureg--1560-vol.3
|
Individual plant examination program Perspectives on reactor safety and plant performance. Part 6, appendices A, B, and C. |
1 |
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E 1.99:NUREG--1561
|
Standard Review Plan Maintenance Program implementing procedures document |
1 |
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E 1.99:NUREG--1563
|
Branch technical position on the use of expert elicitation in the high-level radioactive waste program |
1 |
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E 1.99:nureg--1564
|
Long-term kinetic effects and colloid formations in dissolution of LWR spent fuels |
1 |
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E 1.99:NUREG--1565
|
Dry oxidation and fracture of LWR spent fuels |
1 |
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E 1.99:NUREG--1568
|
License renewal demonstration program NRC observations and lessons learned. |
1 |
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E 1.99:nureg--1570
|
Risk assessment of severe accident-induced steam generator tube rupture |
1 |
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E 1.99:NUREG--1571
|
Information handbook on independent spent fuel storage installations |
1 |
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E 1.99:NUREG--1572
|
Safety evaluation report related to the renewal of the operating license for the research reactor at North Carolina State University |
1 |
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E 1.99:NUREG--1574
|
Standard review plan on antitrust reviews. Final report |
1 |
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E 1.99:NUREG--1575
|
Multi-agency radiation survey and site investigation manual (MARSIM). Final report |
1 |
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E 1.99:NUREG--1600-Rev.1
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General statement of policy and procedures for NRC enforcement actions Enforcement policy. Revision 1. |
1 |
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E 1.99:NUREG--1601
|
Chemical process safety at fuel cycle facilities |
1 |
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E 1.99:nureg--1604
|
Circumferential cracking of steam generator tubes |
1 |
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E 1.99:NUREG--1607
|
Safety evaluation report related to the Department of Energỳs proposal for the irradiation of lead test assemblies containing tritium-producing burnable absorber rods in commercial light-water reactors. Project Number 697 |
1 |
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E 1.99:nureg--1610
|
Controlling the atom. The beginnings of nuclear regulation 1946--1962 |
1 |
