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Spotlight
Publications Available in the Agencywide Documents Access and Management System (ADAMS) – 2019
| Documents added in 2019 | |||
|---|---|---|---|
| V = Volume | N = Number | R =Revision | P = Part | S = Supplement | Ch = Chapter | Add = Addendum | Sec = Section | DFC = Draft For Comment | |||
| PUBLICATION NUMBER |
TITLE | DATE OF PUBLICATION |
ADAMS ACCESSION NUMBER |
| NUREG-0654, R2 | Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants: Final Report | December 2019 | ML19347D139 |
| NUREG-1908, V4 | Information Technology/Information Management Strategic Plan: Fiscal Years 2020 – 2024 | November 2019 | ML19323D858 |
| NUREG/CR-2907, V23 | Radioactive Effluents from Nuclear Power Plants: Annual Report 2017 | November 2019 | ML19317E480 |
| NUREG-2223, V2 | Safety Evaluation Report: Related to the License Renewal of South Texas Project Units 1 and 2, Docket Nos. 50-498 and 50-499, South Texas Project Nuclear Operating Company | November 2019 | ML19316C155 |
| NUREG-2223, V1 | Safety Evaluation Report: Related to the License Renewal of South Texas Project Units 1 and 2, Docket Nos. 50-498 and 50-499, South Texas Project Nuclear Operating Company | November 2019 | ML19316C085 |
| NUREG-1415, V33, N2 | Office of the Inspector General Semiannual Report to Congress: April 1, 2019 – September 30, 2019 | October 2019 | ML19331A150 |
| NUREG/CR-7258 | Technical Manual and User’s Guide for MILDOS, Version 4.1 | November 2019 | ML19325C903 |
| NUREG/CR-7259 | MILDOS Version 4.1 Computational Verification Report | November 2019 | ML19325C464 |
| NUREG-2155, R2, DFC | Implementation Guidance for 10 CFR Part 37, "Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material" – Draft Report for Comment | October 2019 | ML19298A303 |
| NUREG-2220, V3 | Fiscal Year 2019 – Agency Financial Report | November 2019 | ML19322A345 |
| NUREG/CR-7245 | State-of-the-Art Reactor Consequence Analyses (SOARCA) Project: Sequoyah Integrated Deterministic and Uncertainty Analyses | October 2019 | ML19296B786 |
| NUREG-1437, S6, Second Renewal | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Subsequent License Renewal for Surry Power Station, Units 1 and 2 - Draft Report for Comment | October 2019 | ML19274C676 |
| NUREG-1650, R7 | The United States of America National Report for the Convention on Nuclear Safety: Eighth National Report, October 2019 | October 2019 | ML19289D687 |
| NUREG-1437, S5, Second Renewal | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Subsequent License Renewal for Turkey Point Nuclear Generating Unit Nos. 3 and 4 – Final Report | October 2019 | ML19290H346 |
| NUREG/CR-2907, V22 | Radioactive Effluents from Nuclear Power Plants: Annual Report 2016 | April 2019 | ML19275J127 |
| NUREG/CR-7263 | NDE Reliability Issues for the Examination of CASS Components | September 2019 | ML19255J814 |
| NUREG/BR-0514, R1 | Internal Control | September 2019 | ML19254C119 |
| NUREG-1885, R12 | Report to Congress on the Security Inspection Program for Commercial Nuclear Power Reactors and Category I Fuel Cycle Facilities: Results and Status Update (Annual Report for Calendar Year 2018) | September 2019 | ML19254C759 |
| NUREG/IA-0515 | Analyses of an Unmitigated Station Blackout Transient in a Generic PWR–900 with ASTEC, MAAP and MELCOR Codes | March 2019 | ML19248C697 |
| NUREG-1556, V9, R3 | Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Medical Use Licenses, Final Report | September 2019 | ML19256C219 |
| NUREG/IA-0514 | Customization of XTV Graphics Output in TRACE v5.0 Patches 5, 4 & 3 | February 2019 | ML19238A130 |
| NNUREG/CP-0312 | Proceedings of the Radon Barriers Workshop | August 2019 | ML19239A170 |
| NUREG-0750, V88 | Nuclear Regulatory Commission Issuances, July 1, 2018 – December 31, 2018 | September 2019 | ML19246A716 |
| NNUREG/CP-0152, V10 | Proceedings of the 13th NRC/ASME Symposium on Valves, Pumps, and Inservice Testing: Held at DoubleTree by Hilton Hotel Washington DC Silver Spring, MD July 17–18, 2017 | August 2019 | ML19219A165 |
| NUREG-2216, DFC | Standard Review Plan for Spent Fuel Transportation - Draft Report for Comment | July 2019 | ML19214A229 |
| NUREG/BR-0006, R9, DFC | Instructions for Completing Nuclear Material Transaction Reports: (DOE/NRC Forms 741 and 740M) - Draft Report for Comment | July 2019 | ML19214A180 |
| NUREG/BR-0007, R8, DFC | Instructions for the Preparation and Distribution of Material Status Reports (DOE/NRC Forms 742 and 742C) - Draft Report for Comment | July 2019 | ML19212A768 |
| NUREG/CP-0310 | Proceedings of the Public Meeting on Additive Manufacturing for Reactor Materials and Components | July 2019 | ML19214A205 |
| NUREG-2214 | Managing Aging Processes In Storage (MAPS) Report: Final Report | July 2019 | ML19214A111 |
| NUREG/CP-0311 | Proceedings of the Information-Sharing Workshop on High Energy Arcing Faults (HEAFS) | July 2019 | ML19212A150 |
| NUREG-1437, S10, Second Renewal, DFC | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Subsequent License Renewal for Peach Bottom Atomic Power Station Units 2 and 3 – Draft Report for Comment | July 2019 | ML19210D453 |
| NUREG/CR-6525, R2 | SecPop Version 4: Sector Population, Land Fraction, and Economic Estimation Program: User Guide, Model Manual, and Verification Report | June 2019 | ML19182A284 |
| NUREG/CR-7257 | Paleoliquefaction Studies in Moderate Seismicity Regions with a History of Large Events | June 2019 | ML19182A337 |
| NUREG/IA-0510 | MELCOR-ASTEC Crosswalk of the Accident at Fukushima-Daiichi Unit 1: Phase I Analysis | June 2019 | ML19163A241 |
| NUREG/BR-0254, R9 | Payment Methods | June 2019 | ML19163A244 |
| NUREG/CR-7254 | Seismic Isolation of Nuclear Power Plants Using Sliding Bearings | May 2019 | ML19158A513 |
| NUREG-0090, V41 | Report to Congress on Abnormal Occurrences – Fiscal Year 2018 | June 2019 | ML19157A308 |
| NUREG/IA-0513 | Semiscale S-NC-02 and S-NC-03 Natural Circulation Tests Performed by RELAP5/MOD3.3 Patch05 | April 2019 | ML19128A339 |
| NUREG/CR-7260 | CFD Validation of Vertical Dry Cask Storage System | April 2019 | ML19123A127 |
| NUREG-1415, V33, N1 | Office of the Inspector General Semiannual Report to Congress | April 2019 | ML19149A535 |
| NUREG/IA-0512, R1 | Simulation of ROSA-2 Test 3 Counterpart with TRACE5 – Application to Nuclear Power Plant | April 2019 | ML19115A104 |
| NUREG/IA-0505, R1 | Assessment of TRACE 5.0 Against ROSA-2 Test 5, Main Steam Line Break with Steam Generator Tube Rupture | April 2019 | ML19114A236 |
| NUREG-0750, V87 | Nuclear Regulatory Commission Issuances, January 1, 2018 – June 30, 2018 | April 2019 | ML19130A239 |
| NUREG/IA-0509 | LBLOCA Uncertainty Analysis of Maanshan Nuclear Power Plant with RELAP5/SNAP and DAKOTA | April 2019 | ML19112A268 |
| NUREG-0750, 73 – 82, Indexes | Nuclear Regulatory Commission Issuances, NRCI Indexes, January 2011 through December 2015 | April 2019 | ML19123A342 |
| NUREG/CR-2907, V21 | Radioactive Effluents from Nuclear Power Plants: Annual Report 2015 | April 2019 | ML19099A385 |
| NUREG/CR-1621 | A Characterization of Faults in the Appalachian Foldbelt | September 1980 | ML19053A642 |
| NUREG/CR-7103, V4 | Pacific Northwest National Laboratory Investigation of Stress Corrosion Cracking in Nickel-Base Alloys: Behavior of Alloy 152 And 52 Welds | April 2019 | ML19099A200 |
| NUREG/IA-0508 | Validation of RELAP5/MOD3.3 Friction Loss and Heat Transfer Model for Narrow Rectangular Channels | March 2019 | ML19092A050 |
| NUREG-0713, V39 | Occupational Radiation Exposure at Commercial Nuclear Power Reactors and other Facilities 2017, Fiftieth Annual Report | March 2019 | ML19091A130 |
| NUREG/IA-0512 | Simulation of ROSA-2 Test 3 Counterpart with TRACE5 – Application to Nuclear Power Plant | March 2019 | ML19085A076 |
| NUREG/IA-0505 | Assessment of TRACE 5.0 Against ROSA-2 Test 5, Main Steam Line Break with Steam Generator Tube Rupture |
March 2019 | ML19085A036 |
| NUREG-1437, S5, Second Renewal | Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Subsequent License Renewal for Turkey Point Nuclear Generating Unit Nos. 3 and 4 | March 2019 | ML19078A330 |
| NUREG-2226, V2 | Environmental Impact Statement for an Early Site Permit (ESP) at the Clinch River Nuclear Site: Final Report | April 2019 | ML19073A109 |
| NUREG-2226, V1 | Environmental Impact Statement for an Early Site Permit (ESP) at the Clinch River Nuclear Site: Final Report | April 2019 | ML19073A099 |
| NUREG/KM-0013 | Credibility Assessment Framework for Critical Boiling Transition Models: A generic safety case to determine the credibility of critical heat flux and critical power models, Draft for Comment | March 2019 | ML19073A249 |
| NUREG-1556, V13, R2 | Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Commercial Radiopharmacy Licenses, Final Report | March 2019 | ML19079A207 |
| NUREG-1100, V35 | Congressional Budget Justification: Fiscal Year 2020 | March 2019 | ML19065A279 |
| NUREG/BR-0117, N17-04 | NMSS Quarterly Newsletters – Spring 2017 | March 2019 | ML19071A021 |
| NUREG/IA-0502 | Post-Test Analysis of Cold Leg Small Break 4.1% at PSB-VVER Facility using TRACE V5.0 | March 2019 | ML19066A174 |
| NUREG/IA-0507 | Natural Circulation (Interruption) Analysis with MELCOR 2.2 during Asymmetric Cooldown Transients | March 2019 | ML19065A152 |
| NUREG/IA-0504 | Assessment of TRACE 5.0 Against ROSA-2 Test 3 Counterpart Test to PKL | March 2019 | ML19064B308 |
| NUREG/IA-0500 | Post-Test Calculation of the ROSA-2 Test 3 Using RELAP5/MOD3.3 | February 2019 | ML19064A676 |
| NUREG/IA-0501 | Investigation of the Loop Seal Clearing Phenomena for the ATLAS DVI Line and Cold Leg SBLOCA Tests Using MARS-KS and RELAP5/MOD3.3 | March 2019 | ML19064A244 |
| NUREG/IA-0511 | Simulation of ROSA-2 Test-2 Experiment: Application to Nuclear Power Plant | March 2019 | ML19063B345 |
| NUREG/CR-7255 | Seismic Isolation of Nuclear Power Plants using Elastomeric Bearings | March 2019 | ML19063A541 |
| NUREG/IA-0503 | Post-Test Analysis of ROSA-2 Test 2 (IBLOCA) with TRACE | February 2019 | ML19057A271 |
| NUREG-1100, V35 | Congressional Budget Justification: Fiscal Year 2020 Summary | March 2019 | ML19065A278 |
| NUREG/IA-0496 | The Analysis and Study of ELAP Event and Mitigation Strategies Using TRACE Code for Maanshan PWR | February 2019 | ML19056A357 |
| NUREG/IA-0497 | IBLOCA Analysis for Vandellòs-NPP Using RELAP5/MOD3.3. Sensitivity Calculations to EOP Actions | February 2019 | ML19056A201 |
| NUREG/IA-0499 | Post-Test Calculation of the PKL-2 Test G7.1 Using RELAP5/MOD3.3 | February 2019 | ML19056A075 |
| NUREG/CR-7253 | Technical Considerations for Seismic Isolation of Nuclear Facilities | February 2019 | ML19050A422 |
| NUREG/IA-0491 | Assessment of the Wall Film Condensation Model with Non-condensable Gas in RELAP5 and TRACE for Vertical Tube and Plate Geometries | February 2019 | ML19039A013 |
| NUREG-1830, V15 | Office of Investigations – Annual Report FY 2018 | February 2019 | ML19039A014 |
| NUREG-1307, R17 | Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities | February 2019 | ML19037A405 |
| NUREG/IA-0495 | Assessment of NEPTUN Reflooding Experiments 5050 and 5052 with TRACE V5.0 Patch 5 | February 2019 | ML19035A429 |
| NUREG/IA-0493 | The Ultimate Response Guideline Simulation and Study for Lungmen (ABWR) Nuclear Power Plant Using RELAP5/SNAP | February 2019 | ML19035A005 |
| NUREG/KM-0011 | Critical Heat Flux Data Used to Generate the 2006 Groeneveld Lookup Tables | January 2019 | ML19029B306 |
| NUREG-1885, R11 | Report to Congress on the Security Inspection Program for Commercial Power Reactors and Category I Fuel Cycle Facilities: Results and Status Update – Annual Report for Calendar Year 2017 | July 2018 | ML19029A036 |
| NUREG-1650, R6, S1 | Answers to Questions from the Peer Review by Contracting Parties on the United States of America Seventh National Report for the Convention on Nuclear Safety | January 2019 | ML19022A327 |
| NUREG/CR-7244 | Response of Nuclear Power Plant Instrumentation Cables Exposed to Fire Conditions | January 2019 | ML19022A293 |
| NUREG/IA-0489 | RELAP5 Model of a CANDU-6 (Embalse) Nuclear Power Plant: Application to a Turbine Trip Event | January 2019 | ML19022A011 |
| NUREG/IA-0488 | Simulation of the LSTF-PKL Counterpart G7.1 Test at PKL Facility Using TRACE 5 | January 2019 | ML19017A012 |
| NUREG/IA-0487 | Simulation of the PKL-G7.1 Experiment in a Westinghouse Nuclear Power Plant Using RELAP5/Mod3.3 | January 2019 | ML19015A027 |
| NUREG/IA-0506 | Using SNAP/RADTRAD and HABIT to Establish the Analysis Methodology for Maanshan PWR | January 2019 | ML19009A407 |
| NUREG/CR-7249 | Overview of Nuclear Data Uncertainty in Scale and Application to Light Water Reactor Uncertainty Analysis | December 2018 | ML19009A313 |
Page Last Reviewed/Updated Tuesday, September 08, 2026
Page Last Reviewed/Updated Tuesday, September 08, 2026