An example of High Quality Verification and Validation
Verification and Validation-How to Determine the Accuracy of Fire Models
http://www.fpemag.com/archives/article.asp?issue_id=41&i=296
By: Mark Henry Salley, P.E.; Jason Dreisbach; …; and Bernard Gautier
UNITED STATES NUCLEAR REGULATORY COMMISSION
NUREG-1824
Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications
NUREG1788
CFD Analysis of Full-Scale Steam Generator Inlet Plenum Mixing During a PWR Severe Accident
NUREG-1781
CFD Analysis of 1/7th Scale Steam Generator Inlet Plenum Mixing During a PWR Severe
Accident
Prepared by C.F. Boyd, K. Hardesty
7-volume report, "Verification and Validation of Selected Fire Models for Nuclear Power Plant
Applications,"3 (NUREG1824). available on the NRC's Web site (www.nrc.gov/reading-rm/doccollections/nuregs/staff/).
Models: 2 Correlation models, 2 CFD codes, 1 LES code
 (1) NRC Fire Dynamics Tools (FDTS),
 (2) the EPRI Fire-Induced Vulnerability Evaluation (FIVE),
 (3) the NIST zone model Consolidated Fire And Smoke Transport (CFAST),
 (4) the Electricité de France zone model MAGIC8
 (5) the NIST computational fluid dynamics (CFD) model Fire Dynamics Simulator.
Test cases:
 Factory Mutual & Sandia National Laboratories (FM/SNL) Test Series
(5 Tests of simple gas-fired burner, heptane pool, methanol pool, and solid polymethyl-methacrylate (PMMA) fires)

The National Bureau of Standards (NBS) Test Series

The International Collaborative Fire Model Project (ICFMP) Benchmark Exercise Test Series – 4 Full scale buidings , 1-4 MW
fires
Figure 3. Measured vs. Predicted Hot Gas
Layer Temperature Rise.
- 45 Tests: gas-fired burner in three-room suite
Figure 4. Measured
vs. Predicted Radiation Heat Flux onto
Horizontally and Vertically Oriented Targets.
NUREG1781
CFD Analysis of 1/7th Scale Steam Generator Inlet Plenum Mixing During a PWR Severe
Accident
Prepared by C.F. Boyd, K. Hardesty
Health and Science Laboratory, Buxton, UK
1Gobeau, N., et al., "Guidance for HSE Inspectors: Smoke movement in complex enclosed spaces and Assessment of Computational Fluid Dynamics,"
HSL/2002/29, Health and Safety Laboratory, Buxton, UK, 2002. Available from http://www.hse.gov.uk/ research/hsl_pdf/2002/hsl02-29.pdf.
2Gobeau, N., Zhou, X.X. "Evaluation of CFD to predict smoke movement in complex enclosed spaces Application to three real scenarios: an underground
station, an offshore accommodation module and a building under construction" HSL CM/02/12, Health and Science Laboratory, Buxton, UK, 2002.
Document
Identifier
Title
NUREG-75/087
Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants
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USNRC Staff Practice and Procedure Digest: Commission, Appeal Board and Licensing Board Decisions
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Licensed Fuel Facility Status Report: Inventory Difference Data July 1, 2001 - June 30, 2002
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Fault Tree Handbook
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NRC Collection of Abbreviations
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Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities
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Control of Heavy Loads at Nuclear Power Plants
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Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants
NUREG-0696
Functional Criteria for Emergency Response Facilities
NUREG-0700
Human-System Interface Design Review Guidelines
NUREG-0711
Human Factors Engineering Program Review Model
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Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities
NUREG-0725
Public Information Circular for Shipments of Irradiated Reactor Fuel
NUREG-0737
Clarification of TMI Action Plan Requirements
NUREG-0750
Nuclear Regulatory Commission Issuances, Hardbound Editions
NUREG-0800
Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants
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Safety Evaluation Report Related to the operation of Watts Bar Nuclear Plant, Units 1 and 2
NUREG-0933
Resolution of Generic Safety Issues
NUREG-0936
NRC Regulatory Agenda: Semiannual Report
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Nuclear Regulatory Legislation: 109th Congress
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Operator Licensing Examination Standards for Power Reactors
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Event Reporting Guidelines 10 CFR 50.72 and 50.73
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Improving Quality and the Assurance of Quality in the Design and Construction of Nuclear Power Plants
NUREG-1065
Acceptable Standard Format and Content for the Fundamental Nuclear Material Control (FNMC) Plan Required for Low-Enriched Uranium Facilities
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Performance Budget
NUREG-1122
Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors
NUREG-1123
Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling Water Reactors
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Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants
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Training Review Criteria and Procedures
NUREG-1262
Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators' Licenses
NUREG-1280
Standard Format and Content Acceptance Criteria for the Material Control and Accounting (MC&A) Reform Amendment
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Report on Waste Burial Charges
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Information Digest
NUREG-1415
Office of the Inspector General Semiannual Report to Congress
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Standard Technical Specifications Babcock and Wilcox Plants
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Standard Technical Specifications Westinghouse Plants
NUREG-1432
Standard Technical Specifications Combustion Engineering Plants
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Standard Technical Specifications General Electric Plants, BWR/4
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Standard Technical Specifications General Electric Plants, BWR/6
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Generic Environmental Impact Statement for License Renewal of Nuclear Plants
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Shutdown and Low-Power Operation at Commercial Nuclear Power Plants in the United States
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Accident Source Terms for Light-Water Nuclear Power Plants - Final Report
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Operator Licensing Examiner Standards for Research and Test Reactors
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Background as a Residual Radioactivity Criterion for Decommissioning
NUREG-1505
A Nonparametric Statistical Methodology for the Design and Analysis of Final Status Decommissioning Surveys
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Integrated Safety Analysis Guidance Document
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Background as a Residual Radioactivity Criterion for Decommissioning
NUREG-1516
Management of Radioactive Material Safety Programs at Medical Facilities
NUREG-1520
Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility
NUREG-1536
Standard Review Plan for Dry Cask Storage Systems
NUREG-1542
NRC's Performance and Accountability Report
NUREG-1552
Fire Barrier Penetration Seals in Nuclear Power Plants
NUREG-1555
Standard Review Plans for Environmental Reviews for Nuclear Power Plants
NUREG-1556
Consolidated Guidance About Materials Licenses
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Branch Technical Position on the Use of Expert Elicitation in the High-Level Radioactive Waste Program
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Standard Review Plan for Spent Fuel Dry Storage Facilities
NUREG-1569
Standard Review Plan for In Situ Leach Uranium Extraction License Applications
NUREG-1574
Standard Review Plan on Transfer and Amendment of Antitrust License Conditions and Antitrust Enforcement
NUREG-1575
Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM)
NUREG-1576
Multi-Agency Radiological Laboratory Analytical Protocols Manual
NUREG-1577
Standard Review Plan on Power Reactor Licensee Financial Qualifications and Decommissioning Funding Assurance
NUREG-1609
Standard Review Plan for Transportation Packages for Radioactive Material
NUREG-1614
Strategic Plan
NUREG-1617
Standard Review Plan for Transportation Packages for Spent Nuclear Fuel
NUREG-1620
Standard Review Plan for the Review of a Reclamation Plan for Mill Tailings Sites Under Title II of the Uranium Mill Tailings Radiation Control Act
NUREG-1628
Staff Responses to Frequently Asked Questions Concerning Decommissioning of Nuclear Power Reactors
NUREG-1635
Review and Evaluation of the Nuclear Regulatory Commission Safety Research Program
NUREG-1640
Radiological Assessments for Clearance of Equipment and Materials from Nuclear Facilities
NUREG-1649
Reactor Oversight Process
NUREG-1650
United States National Report for the Convention on Nuclear Safety
NUREG-1700
Standard Review Plan for Evaluating Nuclear Power Reactor License Termination Plans
NUREG-1703
Characterization of Radioactive Slags
NUREG-1705
Safety Evaluation Report Related to the License Renewal of Calvert Cliffs Nuclear Power Plant, Units 1 and 2
NUREG-1713
Standard Review Plan for Decommissioning Cost Estimates for Nuclear Power Reactors
NUREG-1714
Final Environmental Impact Statement for the Construction and Operation of an Independent Spent Fuel Storage Installation on the Reservation of the Skull Valley Band of Goshute Indians and the
Related Transportation Facility in Tooele County, Utah
NUREG-1717
Systematic Radiological Assessment of Exemptions for Source and Byproduct Materials
NUREG-1718
Standard Review Plan for the Review of an Application for a Mixed Oxide (MOX) Fuel Fabrication Facility
NUREG-1720
Re-Evaluation of the Indoor Resuspension Factor for the Screening Analysis of the Building Occupancy Scenario for NRC’s License Termination Rule
NUREG-1723
Safety Evaluation Report Related to the License Renewal of Oconee Nuclear Station, Units 1, 2 and 3
NUREG-1725
Human Interaction with Reused Soil: An Information Search
NUREG-1736
Consolidated Guidance: 10 CFR Part 20 - Standards for Protection Against Radiation
NUREG-1739
Analysis of Public Comments on the Improved License Renewal Guidance Documents
NUREG-1743
Safety Evaluation Report Related to the License Renewal of Arkansas Nuclear One, Unit 1
NUREG-1748
Environmental Review Guidance for Licensing Actions Associated with NMSS Programs
NUREG-1757
Consolidated Decommissioning Guidance
NUREG-1758
Evaluation of Fire Models for Nuclear Power Plant Applications: Cable Tray Fires
NUREG-1759
Safety Evaluation Report Related to the License Renewal of Turkey Point Nuclear Plant, Units 3 and 4
NUREG-1761
Radiological Surveys for Controlling Release of Solid Materials
NUREG-1762
Integrated Issue Resolution Status Report
NUREG-1764
Guidance for the Review of Changes to Human Actions
NUREG-1765
Basis Document for Large Early Release Frequency (LERF) Significance Determination Process (SDP) Inspection Findings that May Affect LERF
NUREG-1766
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
NUREG-1767
Environmental Impact Statement on the Construction and Operation of a Mixed Oxide Fuel Fabrication Facility at the Savannah River Site, South Carolina
NUREG-1768
USNRC Package Performance Study Test Protocols
NUREG-1769
Safety Evaluation Report Related to the License Renewal of Peach Bottom Atomic Power Station, Units 2 and 3
NUREG-1772
Safety Evaluation Report Related to the License Renewal of McGuire Nuclear Station, Units 1 and 2, and Catawba Nuclear Station, Units 1 and 2
NUREG-1773
Environmental Impact Statement for the Proposed Idaho Spent Fuel Facility at the Idaho National Engineering and Environmental Laboratory in Butte County, Idaho
NUREG-1774
A Survey of Crane Operating Experience at U.S. Nuclear Power Plants from 1968 through 2002
NUREG-1775
ISCORS Assessment of Radioactivity in Sewage Sludge: Radiological Survey Results and Analysis
NUREG-1776
Regulatory Effectiveness of the Station Blackout Rule
NUREG-1777
Regulatory Effectiveness Assessment of Option B of Appendix J
NUREG-1778
Knowledge Base for Post-Fire Safe-Shutdown Analysis
NUREG-1779
Safety Evaluation Report Related to the License Renewal of St. Lucie Nuclear Plant, Units 1 and 2
NUREG-1780
Regulatory Effectiveness of the Anticipated Transient Without Scram Rule
NUREG-1781
CFD Analysis of 1/7th Scale Steam Generator Inlet Plenum Mixing During a PWR Severe Accident
NUREG-1782
Safety Evaluation Report Related to the License Renewal of the Fort Calhoun Station, Unit 1
NUREG-1783
ISCORS Assessment of Radioactivity in Sewage Sludge: Modeling to Assess Radiation Doses
NUREG-1784
Operating Experience Assessment - Effects of Grid Events on Nuclear Power Plant Performance
NUREG-1785
Safety Evaluation Report Related to the License Renewal of H. B. Robinson Steam Electric Plant, Unit 2
NUREG-1786
Safety Evaluation Report Related to the License Renewal of R. E. Ginna Nuclear Power Plant
NUREG-1787
Safety Evaluation Report Related to the License Renewal of the Virgil C. Summer Nuclear Station
NUREG-1788
CFD Analysis of Full-Scale Steam Generator Inlet Plenum Mixing During a PWR Severe Accident
NUREG-1789
10 CFR Part 52 Construction Inspection Program Framework Document
NUREG-1790
Environmental Impact Statement for the Proposed National Enrichment Facility in Lea County, New Mexico - Final Report
NUREG-1791
Guidance for Assessing Exemption Requests from the Nuclear Power Plant Licensed Operator Staffing Requirements Specified in 10 CFR 50.54(m) - Final Report
NUREG-1792
Good Practices for Implementing Human Reliability Analysis (HRA)
NUREG-1793
Final Safety Evaluation Report Related to Certification of the AP1000 Standard Design
NUREG-1795
FAVOR Code Versions 2.4 and 3.1 Verification and Validation Summary Report
NUREG-1796
Safety Evaluation Report Related to the License Renewal of the Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Units 1 and 2
NUREG-1800
Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants
NUREG-1801
Generic Aging Lessons Learned (GALL) Report
NUREG-1803
Safety Evaluation Report Related to the License Renewal of the Edwin I. Hatch Nuclear Plant, Units 1 and 2
NUREG-1804
Yucca Mountain Review Plan
NUREG-1805
Fire Dynamics Tools (FDTs) Quantitative Fire Hazard Analysis Methods for the U.S. Nuclear Regulatory Commission Fire Protection Inspection Program
NUREG-1806
Technical Basis for Revision of the Pressurized Thermal Shock (PTS) Screening Limit in the PTS Rule (10 CFR 50.61)
NUREG-1807
Probabilistic Fracture Mechanics - Models, Parameters, and Uncertainty Treatment Used in FAVOR Version 04.1
NUREG-1811
Environmental Impact Statement for an Early Site Permit (ESP) at the North Anna ESP Site
NUREG-1814
Status of the Decommissioning Program - 2006 Annual Report
NUREG-1815
Environmental Impact Statement for an Early Site Permit (ESP) at the Exelon ESP Site
NUREG-1816
Independent Verification of the Mitigating Systems Performance Index (MSPI) Results for the Pilot Plants
NUREG-1817
Environmental Impact Statement for an Early Site Permit (ESP) at the Grand Gulf ESP Site
NUREG-1821
Final Safety Evaluation Report on the Construction Authorization Request for the Mixed Oxide Fuel Fabrication Facility at the Savannah River Site, South Carolina
NUREG-1823
U.S. Plant Experience with Alloy 600 Cracking and Boric Acid Corrosion of Light-Water Reactor Pressure Vessel Materials
NUREG-1824
Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications
NUREG-1825
Safety Evaluation Report Related to the License Renewal of the Joseph M. Farley Nuclear Plant, Units 1 and 2
NUREG-1826
APEX-AP1000 Confirmatory Testing To Support AP1000 Design Certification (Non-Proprietary)
NUREG-1827
Safety Evaluation Report for the National Enrichment Facility in Lea County, New Mexico, Louisiana Energy Services
NUREG-1828
Safety Evaluation Report Related to the License Renewal of the Arkansas Nuclear One, Unit 2
NUREG-1829
Estimating Loss-of-Coolant Accident (LOCA) Frequencies Through the Elicitation Process
NUREG-1830
Office of Investigations Annual Report
NUREG-1831
Safety Evaluation Report Related to the License Renewal of the Donald C. Cook Nuclear Plant, Units 1 and 2
NUREG-1832
Analysis of Public Comments on the Revised License Renewal Guidance Documents
NUREG-1833
Technical Bases for Revision to the License Renewal Guidance Documents
NUREG-1834
Environmental Impact Statement for the Proposed American Centrifuge Plant in Piketon, Ohio
NUREG-1835
Safety Evaluation Report for an Early Site Permit (ESP) at the North Anna ESP Site
NUREG-1836
Standard Review Plan for Releasing Part of a Reactor Facility or Site for Unrestricted Use Before Approval of the License Termination Plan
NUREG-1837
Regulatory Effectiveness Assessment of Generic Issue 43 and Generic Letter 88-14
NUREG-1838
Safety Evaluation Report Related to the License Renewal of the Millstone Power Station, Units 2 and 3
NUREG-1839
Safety Evaluation Report Related to the License Renewal of the Point Beach Nuclear Plant, Units 1 and 2
NUREG-1840
Safety Evaluation of Early Site Permit Application in the Matter of System Energy Resources, Inc., a Subsidiary of Entergy Corporation, for the Grand Gulf Early Site Permit Site
NUREG-1842
Evaluation of Human Reliability Analysis Methods Against Good Practices
NUREG-1843
Safety Evaluation Report Related to the License Renewal of the Browns Ferry Nuclear Plant, Units 1, 2, and 3
NUREG-1844
Safety Evaluation Report for an Early Site Permit (ESP) at the Exelon Generation Company, LLC (EGC) ESP Site
NUREG-1850
Frequently Asked Questions on License Renewal of Nuclear Power Reactors
NUREG-1851
Safety Evaluation Report for the American Centrifuge Plant in Piketon, Ohio
NUREG-1852
Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire
NUREG-1853
History and Framework of Commercial Low-Level Radioactive Waste Management in the United States
NUREG-1854
NRC Staff Guidance for Activities Related to U.S. Department of Energy Waste Determinations, Draft Final Report for Interim Use
NUREG-1855
Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making (NUREG-1855) - Draft Report For Comment
NUREG-1856
Safety Evaluation Report Related to the License Renewal of the Brunswick Steam Electric Plant, Units 1 and 2
NUREG-1860
Feasibility Study for a Risk-Informed and Performance-Based Regulatory Structure for Future Plant Licensing, Volumes 1 and 2
NUREG-1861
Peer Review of GSI-191 Chemical Effects Research Program
NUREG-1862
Development of a Pressure Drop Calculation Method for Debris-Covered Sump Screens in Support of Generic Safety Issue 191
NUREG-1863
Review of Responses to NRC Bulletin 2003-02-Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity
NUREG-1864
A Pilot Probabilistic Risk Assessment Of a Dry Cask Storage System At a Nuclear Power Plant
NUREG-1865
Safety Evaluation Report Related to the License Renewal of the Monticello Nuclear Generating Plant
NUREG-1871
Safety Evaluation Report Related to the License Renewal of Palisades Nuclear Plant
NUREG-1872
Draft Environmental Impact Statement for an Early Site Permit (ESP) at the Vogtle Electric Generating Plant Site
NUREG-1873
Environmental Impact Statement for License Renewal Of the National Bureau of Standards Reactor
NUREG-1875
Safety Evaluation Report Related to the License Renewal of Oyster Creek Generating Station
NUREG-1880
ATHEANA User’s Guide
NUREG-1885
Report to Congress on the Security Inspection Program for Commercial Power Reactor and Category I Fuel Cycle Facilities: Results and Status Update - Annual Report for Calendar Year 2006
NUREG-1886
Joint Canada – United States Guide for Approval of Type B(U) and Fissile Material Transportation Packages (NUREG-1886) - Draft Report for Comment
NUREG-1887
RASCAL 3.0.5: Description of Models and Methods
NUREG-1888
Environmental Impact Statement for the Reclamation of the Sequoyah Fuels Corporation Site in Gore, Oklahoma - Final Report
NUREG-1890
Evaluating Igneous Activity at Yucca Mountain, Technical Basis for
Decisionmaking
NUREG-1891
Safety Evaluation Report Related to the License Renewal of Pilgrim Nuclear Power Station
NUREG-1900
Safety Evaluation Report Related to the License Renewal of Nine Mile Point Nuclear Station, Units 1 and 2
NUREG-1903
Seismic Considerations For the Transition Break Size
NUREG-1910
Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities - Draft Report for Comment