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A list of all pages that have property "Title" with value "Review Worksheets". Since there have been only a few results, also nearby values are displayed.

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List of results

  • RNP-RA/12-0100, Review Request for the PWR Vessel Internals Program Plan for Aging Management of Reactor Internals  + (Review Request for the PWR Vessel Internals Program Plan for Aging Management of Reactor Internals)
  • 05000325/LER-1982-093-03, Review Revealed Inability of Reactor Protection Sys Logic Functional Test PT-01.1.10 to Provide for Electrical Continuity Testing of Input Signal Contacts of Backup Scram Logic Circuitry Solenoids  + (Review Revealed Inability of Reactor Protection Sys Logic Functional Test PT-01.1.10 to Provide for Electrical Continuity Testing of Input Signal Contacts of Backup Scram Logic Circuitry Solenoids)
  • 05000395/FIN-2007004-01  + (Review Risk Assessment Credit for Dedicated Manual Operator Actions During EDG Surveillance Testing)
  • ML12073A390  + (Review Schedule Delay Due to Anticipated License Amendment Request and Hydrology Issues)
  • ML21074A425  + (Review Schedule Licensing Action Re Physical Security Amendment Request - Alternative Measures)
  • ML040910016  + (Review Schedule for Application for Renewal of the Operating Licenses for the Browns Ferry Nuclear Plant, Units 1, 2 and 3)
  • ML19282A575  + (Review Schedule for License Renewal Application Has Been Prepared According to Agreement on Interface & Div of Responsibility Between NMSS & IE, W/Minor Adjustment. Lists Milestones in Review Schedule.Requests IE Input)
  • ML22131A076  + (Review Schedule for Requested Licensing Action Regarding Amendment Request Revision to License Condition 2.C.(2))
  • ML012910044  + (Review Schedule for Sequal Topical Report, Basis for Adoption of Experience-Based Equipment Qualification (Ebseq) Methodology by Non-A46 Nuclear Power Plant)
  • ML21084A123  + (Review Schedule for the NuScale Power, LLC, Topical Report Methodology for Establishing the Technical Basis for Plume Exposure Emergency Planning Zones, TR-0915-17772, Revision 2 (PROJ0769))
  • ML18292A592  + (Review Scope of Proposed Changes to Four NUREG-0800 Standard Review Plan (SRP) Sections)
  • ML19281A250  + (Review Shipments of Specifically Licensed Matl Do Not Exceed Quantities of Type a Matls as Defined in 10CFR71.4(g), 71.1 & 71.7(b).No Plans to Establish QA Program)
  • 05000482/FIN-2012008-08  + (Review Source Range Detector Deviation)
  • ML090580422  + (Review Standard for Extended Power Uprates; Availability of Review Standard)
  • 05000482/FIN-2012008-02  + (Review Startup Transformer Fault Cause)
  • ML21335A047  + (Review Status Report 12-1-2021)
  • ML21154A123  + (Review Status Report 6-1-2021)
  • ML21154A122  + (Review Status Report 6-1-2021)
  • ML21215A009  + (Review Status Report 8-2-2021)
  • ML071630049  + (Review Status of the License Renewal Application (LRA) for the Indian Point Nuclear Generating Unit Nos. 2 and 3)
  • ML083290275  + (Review Status of the License Renewal Application for the Duane Arnold Energy Center)
  • ML090360279  + (Review Status of the License Renewal Application for the Palo Verde Nuclear Generating Stations)
  • ML19327A590  + (Review Submitting Reworded Contentions 6,8 & 12 Re Failure of power-operated Relief Valve,Eccs Performance & Environ Qualification.Certificate of Svc & Supporting Documentation Encl)
  • ML080420566  + (Review Team Findings with Respect to Inattentive Security Officers at Peach Bottom)
  • ML030800472  + (Review Temp Changes)
  • ML081010116  + (Review Topics for Safety Evaluation, Attachment 1)
  • 05000482/FIN-2012008-03  + (Review Turbine-Driven Auxiliary Feedwater Pump Mechanical Overspeed Trip Device out of Specification)
  • ML070860282  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Appendix B, Crack Driving Force and Growth Rate Estimates)
  • ML070860281  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Appendix a, Finite Element Stress Analysis of Davis-Besse CRDM Nozzle 3 Penetration)
  • ML070860256  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 4. the Davis-Besse March 2002 Event)
  • ML070860250  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 2. Principal Conclusions and Opinions)
  • ML070860293  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Appendix H, Professor R.G. Ballinger)
  • ML070860261  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 5. Worldwide Industry Response to CRDM and Other Alloy 600 Nozzle Cracking)
  • ML070860289  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Appendix F, Ronald M. Latanision, Ph.D)
  • ML070860276  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 9. Cfd Modeling of Fluid Flow in CRDM Nozzle and Weld Cracks and Through Annulus)
  • ML070860284  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Appendix C, Cfd Analysis)
  • ML070860248  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 1. Introduction, Purpose and Scope)
  • ML070860264  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 6. Boric Acid Wastage of Carbon Steel Components in Us PWR Plants)
  • ML070860271  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 8. Stress Analysis and Crack Growth Rates for Davis-Besse CRDM Nozzles 2 and 3)
  • ML070860286  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Appendix D, Leak Rate Vs. Crack Length Calculations)
  • ML070860291  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Appendix G, Daniel B. Bullen, Ph.D., P.E)
  • ML070860280  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 10. the Unique Nature of the Davis-Besse Nozzle 3 Crack and the RPV Head Wastage Cavity)
  • ML070860253  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 3. Background)
  • ML070860268  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 7. FENOC/Davis-Besse Response to CRDM Cracking and Boric Acid Corrosion Issues)
  • ML070860242  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Cover and Table of Contents)
  • ML070860288  + (Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Appendix E, Fluid Jet Cutting of Davis-Besse RPV Head Materials)
  • ML090330392  + (Review and Approval Schedule - Fourth Interval Inservice Inspection Plan and Associated Proposed Alternatives and Relief Requests)
  • ML16089A167  + (Review and Approval of Quality Assurance Plan Change Per Nuclear Energy Institute (NEI) 14-05A, Revision 1)
  • ML16194A323  + (Review and Approval of Request for Quality Assurance Plan Change Per Nuclear Energy Institute (NEI) 11-04A, Nuclear Generation Quality Assurance Program Description)
  • ML101610188  + (Review and Approval of a Flaw Evaluation)
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