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Home > About NRC
> How We Regulate > Licensing > Topical Reports > Recently Approved
Topical Reports Approved through FY2006
Publicly available topical reports
may be found in the Agencywide Document
Access and Management System.
List of Reports Approved through FY2006
On this page
Boiling Water Reactor Vessel and Internals Project (BWRVIP) Reports
| Task ID (TAC No.) |
Title |
| MB8969 |
BWRVIP-02, “Core Shroud Repair Design Criteria, Revision 2” |
| MA5140 |
BWRVIP-02-A,
“Core Shroud Repair Design Criteria, Revision 2” |
| MC0744 |
BWRVIP-04-A, “Guide for Format and Content of Core Shroud Repair Design
Submittals” |
| MC0745 |
BWRVIP-06-A, "Safety Assessment of BWR Reactor Internals” |
| MA5140 |
BWRVIP-18-A, “BWR Vessel and Internals Project
Boiling Water Reactor Core Spray Internals Inspection and Flaw Evaluation
Guidelines" |
| MA5140 |
BWRVIP-26-A, “BWR Vessel and Internals Project
Boiling Water Reactor Top Guide Inspection and Flaw Evaluation Guidelines" |
| MC1024 |
BWRVIP-27-A,“BWR Standby Liquid Control Plate Delta P Inspection and Flaw Evaluation
Guidelines” |
| MA5140 |
BWRVIP-28-A, “BWR Vessel and Internals Project
Assessment of Jet Pump Riser Elbow to Thermal Sleeve Weld Cracking" |
| MA5140 |
BWRVIP-42-A, “BWR Vessel and Internals Project Boiling Water Reactor Low
Pressure Coolant Injection and Flaw Evaluation Guidelines" |
| MB9698 |
BWRVIP-44, “Underwater Weld Repair of Nickel Alloy Reactor Vessel Internals” |
| MA5140 |
BWRVIP-47-A, “BWR Vessel and Internals Project Boiling Water Reactor Lower Plenum Inspection and Flaw Evaluation Guidelines" |
| MA1138 |
BWRVIP-48-A,"Vessel ID Attachment weld Inspection and Flaw Evaluation
Guidelines" |
| MA1226 |
BWRVIP-49-A,“Instrument Penetration Inspection and Flaw Evaluation Guidelines” |
| MA5140 |
BWRVIP-50-A, “BWR Vessel and Internals Project Top Guide/Core Plate Repair Design Criteria" |
| MA5140 |
BWRVIP-51-A, “BWR Vessel and Internals Project Jet Pump Repair Design Criteria" |
| MA5140 |
BWRVIP-52-A, “BWR Vessel and Internals Project
Shroud Support and Vessel Bracket Repair Design Criteria" |
| MA5140 |
BWRVIP-56-A, “BWR Vessel and Internals Project LPCI Coupling Repair Design Criteria" |
| MA5140 |
BWRVIP-57-A, “BWR Vessel and Internals Project Instrument Penetration Repair Design Criteria" |
| MA5057 |
BWRVIP-60-A, “Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel
Materials in the BWR Environment” |
| MC0746 |
BWRVIP-74-A, “BWR Reactor Pressure Vessel Inspection and Flaw Evaluation Guidelines” |
| MB9014 |
BWRVIP-84, “Guidelines for Selection and Use for Materials and Repairs” |
| MC0747 |
BWRVIP-86-A, “Updated BWR Integrated Surveillance Program (ISP) Implementation Plan” |
| MB3947 |
BWRVIP-96, “Sampling and Analysis Guidelines for Determining the He Content of Reactor Internals” |
| MB3951 |
BWRVIP-99, “Crack Growth Rates in Irradiated BWR SS Internal Components” |
| MB9765 |
BWRVIP-114, -115, -117, and -121, “RAMA Fluence Methodology Procedures Manual” |
Electric Power Research Institute (EPRI) Reports
| Task ID (TAC No.) |
Title |
| MA6484 |
EPRI MOV Addendum 2 |
AREVA NP/PWR Owners Group (formerly B & W Owners Group) Reports
| Task ID (TAC No.) |
Title |
| MC4260 |
ANF-1358, "Loss of Feedwater Heating Transient in Boiling Water Reactors" |
| MA8237 |
BAW-10046, REV. 4, Method of Compliance with Fracture Toughness & Operational
Requirements |
| MB0591 |
BAW-10164,(NP), Rev.1, "Limited Scope High Burn-Up Lead Test Assemblies" |
| MC0341 |
BAW-10166, BEACH APPENDICES H&I - Best Estimate Analyses for Core Heat Transfer, A
Computer Program for Reflood Heat Transfer During LOCA |
| MB9684 |
BAW-10179, Rev. 5, "Safety Criteria and Methodology for Acceptable Cycle Reload
Analyses" |
| MC6394 |
BAW-10179, Rev. 6, "Safety Criteria and Methodology for Acceptable Cycle Reload
Analyses" |
| MB7548 |
BAW-10186, Rev 1, Supplement 1 Mark BW Extended Burnup |
| MC4262 |
BAW-10199(P), Addendum 3, "The BWU CHF Correlations" |
| MB7547 |
BAW-10231-P- COPERNIC MOX Application |
| MB7550 |
BAW-10238,"MOX Fuel Report" |
| MB7551 |
BAW-10239,"Advanced MARK-BAW Fuel Assembly Design" |
| MB7553 |
BAW-10240, "Incorporation of M5 Properties in Framatome ANP Approved Methods" |
| MB7033 |
BAW-10241, "BHTP DNB Correlation Applied with LYNXT" |
| MB9977 |
BAW-10242 (NP), Zero Power Physics testing for B&W Reactors |
| MC4531 |
BAW-10243(P) "Statistical Fuel Assembly Hold Down Methodology |
| MC0671 |
BAW-10244, "MK-BW CHF Correlations, Applied with XCOBRA-III C" |
| MC3783 |
BAW-10252(P), Revision 0, "Analysis of Containment Response to Postulated Pipe
Ruptures Using GOTHIC" |
| MC1762 |
BAW-1543(NP) Rev. 4, Suppl. 5, Supplement to the Master Integrated Reactor Vessel
Surveillance |
| MB9474 |
BAW-2241-P, Revision 2, Fluence and Uncertainty Methodologies |
| MB6336 |
BAW-2308, "Initial RT NDT of LINDE 80 Weld Material" |
| MB7831 |
EMF-2103-P, Realistic Large-Break LOCA Methodology |
| MB7680 |
EMF-2310 (P)(A), Clarification of Safety Evaluation for EMF-2310 (P)(A), SRP Chapter
15 Non-LOCA Methodology |
| MB6335 |
EMF-85-74-Clarification of Exposure Limit Applicable to Framatome ANP BWR Fuel
RODEX2A |
| MB7552 |
EMF-85-74- Clarification of Exposure Limit Applicable to Framatome ANP BWR Fuel
RODEX2A |
| MC3223 |
EMF-92-153, Revision 1, "HTP [High Thermal Performance]: Departure From Nucleate
Boiling For High Temperature Performance Fuel" |
| MC5665 |
EMF-93-177, Rev. 1, "Mechanical Design for BWR Fuel Channels" |
| MC0329 |
EMG-2310 (P) Rev. 1, "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water
Reactors" |
| MB7557 |
PSC 2-00, “Core Flood Tank Line LOCA without LOOP” |
General Electric Nuclear Energy (GENE)/Global Nuclear Fuel (GNF)/Boiling
Water Reactor Owners Group (BWROG) Reports
| Task ID (TAC No.) |
Title |
| MB2774 |
GESTR-LOCA AND SAFER Model Supplement 1, “Upper Bound PCT Calculation” |
| MB3311 |
NEDC-3272-P, REV.2, “GE Stacked Disk ECCS Suction Strainer” |
| MB3094 |
NEDC-32851, “GEXL14 Correlation for GE14 Fuel and NEDC-32464, REV. 2 GEXL10 Correlation
for GE12 Fuel” |
| MA9537 |
NEDC-32938-P, “Generic Guidelines for GE BWR Thermal Power Optimization” |
| MA9891 |
NEDC-32983-P, “GE Methodology for RPV Fast Neutron Flux Evaluation” |
| MC3788 |
NEDC-32983P-A, “Confirmatory Calculations” |
| MB1054 |
NEDC-32988, “Risk-Informed Modification to Selected Required Action End State
for BWRs” |
| MB2510 |
NEDC-33004-P, “Constant Pressure Power Uprate” |
| MB2211 |
NEDC-33035-P, "TRACG Licensing - ECCS/LOCA Analysis” |
| MC4595 |
NEDC-33046,"Primary Containment Isolation Valve AOT Extension" |
| MB1737 |
NEDC-33075-P, "GE BWR Detect and Suppression Solution" |
| MC0666 |
NEDC-33107-P,“GEXL80 Correlation for SVEA96+ Fuel” |
| MC1798 |
NEDC-33139P, “Cladding Creep Collapse” |
| MC0347 |
NEDE-24011-P, "Amendment 27 to GESTAR II" |
| MC4078 |
NEDE-24011-P,"Amendment 28 to GESTAR II" |
| MC5039 |
NEDE-32906, “TRACG Application for Anticipated Operational Occurrences Transient
Analysis” |
| MB6359 |
NEDE-32906-P, “TRACG Application for ATWS Overpressure Transient Analyses |
| MB9642 |
NEDO-33091, "Improved BPWS Control Rod Insertion Process" |
Siemens Westinghouse Power Corporation Reports
| Task ID (TAC No.) |
Title |
| MB7964 |
CT-27332, Revision 2, "Missile Probability Analysis For Siemens 13.9m2 Retrofit
Design of Low-Pressure Turbine" |
PWR Owners Group (formerly Westinghouse Owners Group - WOG) Reports
| Task ID (TAC No.) |
Title |
| MB5754 |
WCAP-14040, R03-NP, "Methodology used to Develop Cold Overpressure Mitigating
Systems Set Points and RCS Heat Up” |
| MA7995 |
WCAP-14572,RI-NP-A, Addendum 1, "Augmented Piping Inspection Programs-WOG Risk
Informed ISI" |
| MB0983 |
WCAP-15376-P and WCAP-15377-NP, “Risk-informed RTS and ESFAS Surveillance Test Interval” |
| MB9516 |
WCAP-15604,
“Limited Scope High Burnup Lead Test Assemblies” |
| MB2819 |
WCAP-15666, “Extension of RCP Motor Flywheel Examination” |
| MB5751 |
WCAP-15791, Rev. 0 " Risk-Informed Evaluation of Extensions to Containment Isolation
Valve Completion Times" |
| MB9020 |
WCAP-15872,
"Use of Alternate Decay Heat Removal in Mode 6 Refueling" |
| MB6805 |
WCAP-15973,
"Low-Alloy Steel Component Corrosion Analysis Supporting Alloy 600/690
Nozzle Repair Program" |
| MB6982 |
WCAP-15996,
"Technical Description Manual for the CENTS Code" |
| MB8724 |
WCAP-16011,
"Startup Test Activity Reduction Program" |
| MC3974 |
WCAP-16083-NP,
"Benchmark Testing of FERRET Code" |
| MC5800 |
WCAP-16396,
“Reactor Coolant Pump Seal Performance for Appendix R” |
Westinghouse Vendor Reports
| Task ID (TAC No.) |
Title |
| MC1646 |
WCAP-10125-P-A, Addendum 1-A, "Extended Burnup Evaluation of Westinghouse Fuel, Revision
to Design Criteria" |
| MC4958 |
WCAP-12472,
Add. 1, "Beacon Core Monitoring and Operation Support System" |
| MB6803 |
WCAP-12945-P-A
and WCAP-14449-P-A, Addendum 1, “Method for satisfying 10 CFR 50.46
Reanalysis Requirements for Best-Estimate LOCA Evaluation Models" |
| MB8041 |
WCAP-14342,"Optimized
ZIRLO" |
| MB9483 |
WCAP-14565,
"Realistic Large-Break LOCA Evaluation Methodology using the Automatic
Statistical Treatment of Uncertainty Method (ASTUM)" |
| MB9509 |
WCAP-14565-P,
Addendum 1, and WCAP-15306 - NP-A, Addendum 1, "Qualification of ABB
Critical Heat Flux Correlation with VIPRE-01 Code" |
| MB5740 |
WCAP-15836-P, Revision 0, " Rod Design Methods for Boiling Water Reactors - Supplement
1" |
| MC4592 |
WCAP-15942-P, "Fuel Assembly Mechanical Design Methodology for BWRs.” |
| MB8040 |
WCAP-16045, "Qualification of Two-Dimensional Transport Code Paragon" |
| MB8042 |
WCAP-16047, "BWR SVEA Fuel" |
| MB8721 |
WCAP-16072-P, "Implementation of Zirconium Diboride Burnable Absorber Coating in CE
Nuclear Power Fuel Assembly Designs" |
| MB8908 |
WCAP-16078, "Westinghouse BWR ECCS Evaluation Model: Supplement 3 to Code
Description, Qualification and Application to SVEA-96 Optimal Fuel" |
| MB9011 |
WCAP-16081,"10x10 SVEA Fuel Critical Power Experiments and CPR Correlation: SVEA 96
Optima 2" |
| MC2294 |
WCAP-16096,"Software Program Manual for Common Q Systems" |
| MC1644 |
WCAP-16182,"Westinghouse BWR Control Blade CR99 Licensing Report" |
| MC3036 |
WCAP-16259,"Westinghouse Methodology for Application of 3-D Transient Neutronics to
Non-LOCA Accident Analysis |
| MC3065 |
WCAP-16260,"Spatially Corrected Inverse Count Rate (SCICR) Method for Subcritical
Reactivity Measurement" |
| MC0327 |
WCAP-8963/4 Addendum 1 "Revised Fuel Rod Interval Pressure" |
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