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A list of all pages that have property "Title" with value "Safety Evaluation Final Integrated Plan". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

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List of results

  • ML20205M526  + (Safety Evaluation Denying Util 860819 Proposal to Reproduce Radiographs on Microfilm)
  • ML20236J162  + (Safety Evaluation Denying Util 870731 Request to Amend Licenses NPF-10 & NPF-15,consisting of Proposed Change PCN-26,to Delete Tech Spec Requirement to Rept Toxic Gas Cargo Traffic on Interstate 5.US Spill Average Has No Basis)
  • ML20148T257  + (Safety Evaluation Denying Util 870807 Proposed Amend to License NPF-47 to Modify Diesel Generator Reliability Due to Problems That Can Be Encountered When Paralleling Generator W/Offsite Power Source)
  • ML17222A657  + (Safety Evaluation Denying Util 871127 Request Re Use of Proposed C-E Methodology for Adjusted Ref Temp Calculations)
  • ML20207M043  + (Safety Evaluation Denying Util 880711 Request for Relief from Hydrostatic Test Requirements of Section XI of ASME Code for Class 2 Portion of Main Steam Lines Between Outboard MSIVs & Turbine Stop Valves)
  • ML13303A980  + (Safety Evaluation Denying Util 880811 Application to Amend Licenses NPF-10 & NPF-15,deleting Tech Spec Sections 6.5.3.4a & 6.5.3.4.g Re Requirement That Nuclear Safety Group Review Events Requiring 24 H Notification to NRC)
  • ML20216K066  + (Safety Evaluation Denying Util 900221 & 0622 Requests for Exemption from App R of 10CFR50 for Fire Area 34B,upper Electrical Penetration Room.Current Level of Fire Protection Does Not Meet Section III.G.2 Requirements)
  • ML17289A880  + (Safety Evaluation Denying Util 911203 Relief Requests RP-7 & RV-26 to Inservice Testing Program for Pumps.Testing Should Be Performed in Accordance W/Requirements of Section XI)
  • ML13317A261  + (Safety Evaluation Denying Util Request for Exemptions from 10CFR50,App J Re Airlock Testing Requirements)
  • ML20154H272  + (Safety Evaluation Describing Relationship of Util Nuclear Performance Plan,Vol 3,Part Ii,Section 2.6, QA to TVA-TR75-1A, QA Program Description for Design,Const... W/Proper Implementation,Qa Program Description Acceptable)
  • ML19340B046  + (Safety Evaluation Determines That No Changes in Operating Limitations Necessary as Result of Fuel Densification Considerations)
  • ML18030A975  + (Safety Evaluation Diesel Generators Not Seismic)
  • ML17179A469  + (Safety Evaluation Disagreeing W/Classification of Weld PS2A/202-1B as Category E & Concluding That Licensee Actions Provide Reasonable Assurance That Facility Can Be Safely Operated in Current Configuration)
  • ML18153C403  + (Safety Evaluation Disapproving Util Response to Station Blackout Rule.Licensee Should Reevaluate Areas of Concern Identified in Safety Evaluation)
  • ML20148F132  + (Safety Evaluation Discussing Main Steam Isolation Valve Integrity During Accident Conditions.Combination of Analysis & Scale Model Testing Acceptable)
  • ML16342C950  + (Safety Evaluation Discussing Resolution of Deviations from RG 1.97,previously Identified in Ltr)
  • ML19282B328  + (Safety Evaluation Discussing Util Application for Amend to Operating License to Increase Capacity of Spent Fuel Pool)
  • ML19210C814  + (Safety Evaluation Documenting Acceptability of Addl Cooling of Electrical Equipment Areas Vital to Safety)
  • ML19210C351  + (Safety Evaluation Documenting Acceptability of Operating Either Unit W/Prototype Control Element Assembly Installed in Typically Low Guide Tube Wear Location)
  • ML17340A903  + (Safety Evaluation Documenting Analysis That Radiological Effluent Releases During Plant Operations Will Conform W/Dose Design Objectives)
  • ML20132F072  + (Safety Evaluation Documenting Deficiencies in Licensee Program for Environ Qualification of Electric Equipment Important to Safety.Licensee Response to Generic Ltr 84-24 Inadequate.However,Operation at 15% Power Authorized)
  • ML20196D431  + (Safety Evaluation Documenting NRC Review of Licensee Response to Generic Ltr 83-28.Evaluation Concludes That Licensee Adequately Meets Provisions of Part 1 of Item 2.2 to Generic Ltr 83-28)
  • ML17187B147  + (Safety Evaluation Does Not Constitute NRC Approval or Endorsement of Any IPE Matl for Purposes Other than Those Associated W/Meeting Intent of GL 88-20)
  • ML17249A166  + (Safety Evaluation Endorsing QA Program for full-term OL)
  • ML110450159  + (Safety Evaluation Extended Power Uprate)
  • ML20214S413  + (Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Licensee Actively Pursuing Improvements in Auxiliary Feedwater Sys Reliability & in Reducing Challenges to Sys)
  • ML20030B808  + (Safety Evaluation Finding Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valves Isolation & Other Actuation Signals Acceptable)
  • NUREG-0822, Safety Evaluation Finding Integrated Plant SAR (NUREG-0822), Section 4.12 Complete W/Exception of Three Issues,Including Evaluation of Drywell for Concrete Subj to High Temps & Thermal Transients  + (Safety Evaluation Finding Integrated Plant SAR (NUREG-0822), Section 4.12 Complete W/Exception of Three Issues,Including Evaluation of Drywell for Concrete Subj to High Temps & Thermal Transients)
  • ML18029A597  + (Safety Evaluation Finding Licensee Response to Generic Ltr 83-28,Item 1.2 Re post-trip Review Data & Info Capabilities Acceptable)
  • ML15218A266  + (Safety Evaluation Finding Licensees Evaluation Indicates Flaw in Upper head-to-tubesheet Weld Satisfies Criteria from Paragraph IWB-3612 of Section XI of ASME Code)
  • ML20040H588  + (Safety Evaluation Finding No Significant Hazards for Amend (Change 32) to License CSF-1)
  • ML20058L271  + (Safety Evaluation Finding Overlay Repair of Weld 02C-F7 Acceptable & in Conformance W/Gl 88-01.Plant May Be Returned to Safe Operation)
  • ML18051B436  + (Safety Evaluation Finding Preventative Maint Surveillance & Trending Programs for Automatic Trip Contactors & Manual Trip Breakers Per Generic Ltr 83-28 Acceptable)
  • ML17157B020  + (Safety Evaluation Finding That Licensee Submittals Do Not Conform W/Station Blackout Rule & Guidance of Reg Guide 1.155.Recommends That Licensee Reevaluate Areas of Concern Identified)
  • ML20132E628  + (Safety Evaluation Finding Util 831104 Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing Acceptable)
  • ML23174A178  + (Safety Evaluation GA-EMS Fast Modular Reactor Principal Design Criteria Tr Revision 2)
  • ML23174A176  + (Safety Evaluation GA-EMS Fast Modular Reactor Principal Design Criteria Tr Revision 2)
  • ML20134H357  + (Safety Evaluation Granting 821203,0804,831201,840628 & 850212 Relief Requests from ASME Code Requirements of Inservice Insp Program,Except for Items B9.10-B9.40 & C5.10-C5.32 Re Pressure Retaining Welds)
  • ML20205E631  + (Safety Evaluation Granting 860606 Relief Request Re Hydrostatic Testing Requirements for Main Steam Sys Piping)
  • ML20234C767  + (Safety Evaluation Granting 870612,0814,1026 & 1119 Requests for Relief from Certain Section XI ASME Code Requirements Re First 10-yr Interval Inservice Insp Program)
  • ML20246D802  + (Safety Evaluation Granting 880524 Requests for Relief from Certain Requirements of ASME Code,Section XI)
  • ML20247H642  + (Safety Evaluation Granting 890118 Request for Relief from Hydrostatic Testing Requirements of Section XI of ASME Code)
  • ML20058B441  + (Safety Evaluation Granting 900709 Request for Relief from Requirements for Leakage Testing of RCS in ASME Code,Section XI)
  • ML20153D390  + (Safety Evaluation Granting 970707 Request to Use Guidance in GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Pilgrim Nuclear Power Station)
  • ML20236U705  + (Safety Evaluation Granting All Requests for Relief W/Exception of Requests RR-89-17 (Authorized for Class 1 Sys Only) & RR-89-21.Requests RR-13 & RR-14 Will Be Addressed in Separate Evaluation)
  • ML20236L752  + (Safety Evaluation Granting Bg&E 980527 Request for Relief from Requirement of Section IWA-5250 of ASME Code for Calvert Cliffs Unit 2.Alternatives Provide Reasonable Assurance of Operational Readiness)
  • ML20059C375  + (Safety Evaluation Granting Exemption & Approving Alternative DAC Values for Use in Place of Generic Value for Radionuclides Specified in App B to 10CFR20.1001 - 20.2402)
  • ML20034A048  + (Safety Evaluation Granting Exemption Requests from App R)
  • ML20206D420  + (Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2)
  • ML20207J893  + (Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section Iii.G for 16 Fire Areas)