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List of results
- ML20101F069 + (Forwards Results of Evaluations of Minor Discrepancies Found on Walkdown on Expansion Anchors Included on Reinsp of Mercury N1 Instrumentation Installations)
- PY-CEI-NRR-0759, Forwards Results of Evaluations of Valve & Power Supply Configurations to Maximize RCIC Sys Reliability & Availability.Evaluations Address NRC Pursuit of Resolution to Generic Issue 87, Failure of HPCI Steam Line W/O.. + (Forwards Results of Evaluations of Valve & Power Supply Configurations to Maximize RCIC Sys Reliability & Availability.Evaluations Address NRC Pursuit of Resolution to Generic Issue 87, Failure of HPCI Steam Line W/O..)
- ML20195J539 + (Forwards Results of Evaluations on safety-related Pumps & Justification for Continued Operation,Per NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Final Evaluation Will Not Be Completed Until Early 1989)
- ML17292A273 + (Forwards Results of Exam & Evaluation of Flaw in Recirculation Piping Weld 20RRC(6)-8 in Ltrs Dtd 950526 & 15.Procedure Encl)
- GO2-95-097, Forwards Results of Exam & Evaluation of Flaw in Recirculation Piping Weld 20RRC(6)-8.Concludes That Structural Integrity of Weld Will Be Maintained During Next Operating Cycle.Weld Will Remain in GL 88-01 Categorg F + (Forwards Results of Exam & Evaluation of Flaw in Recirculation Piping Weld 20RRC(6)-8.Concludes That Structural Integrity of Weld Will Be Maintained During Next Operating Cycle.Weld Will Remain in GL 88-01 Categorg F)
- GO2-96-102, Forwards Results of Exam & Evaluation of Flaw in Recirculation Piping Weld 20RRC(6)-8 in Ltrs & 15.Procedure Encl + (Forwards Results of Exam & Evaluation of Flaw in Recirculation Piping Weld 20RRC(6)-8 in Ltrs & 15.Procedure Encl)
- ML20205T047 + (Forwards Results of Exam Into Allegation 100 Re Painters Having No QC Program.Concern Expressed That Epoxy Coating on Containment Concrete Walls May Absorb Activity & Result in Excessive Radiation in Lower Levels of Containment)
- ML20128N365 + (Forwards Results of Exam Rept 50-157/OL-96-01 Conducted During Wk of 960923)
- ML20128N370 + (Forwards Results of Exam Rept 50-157/OL-96-01 Conducted During Wk of 960923)
- ML19296A738 + (Forwards Results of Examinations of Steam Generator Nozzle to Piping Welds & Piping Supports & Snubbers Associated W/ Main Feedwater Sys Piping,In Response to IE Bulletin 79-13, Revision 2)
- ML17320B097 + (Forwards Results of Exxon Nuclear Co Review of Safety Analyses.Util Concurs W/Vendor That Analyses in Compliance W/Nrc Requirements for Development & Application of Computer Codes Used in Performing Safety Analyses)
- ML17291A772 + (Forwards Results of FEMA Emergency Coordination Center Drill Evaluation Rept of 950104 Drill for State of Wa)
- ML17291A807 + (Forwards Results of FEMA Evaluation Rept of 940913-14. Requests That Licensee Follows Up W/Offsite Officials on Areas Requiring Corrective Actions & Plan Inadequacies)
- ML19220B296 + (Forwards Results of FSAR Sections 13.2 & 13.5 Review. Concludes Info Submitted Meets Approval Requirements)
- ML19271A618 + (Forwards Results of Facility Closeout Radiation Survey. Data Shows Results to Be Well within Acceptable Surface Contamination Levels for Removable Contamination)
- ML18031A383 + (Forwards Results of Facility Entrainment Demonstration Program Developed to Meet Requirements of Special Condition C,Part C of NPDES Permit PA 0047325)
- PLA-1191, Forwards Results of Facility Entrainment Demonstration Program Developed to Meet Requirements of Special Condition C,Part C of NPDES Permit PA 0047325 + (Forwards Results of Facility Entrainment Demonstration Program Developed to Meet Requirements of Special Condition C,Part C of NPDES Permit PA 0047325)
- ML19329A657 + (Forwards Results of Facility Hydrogen Purge Dose)
- ML20196D186 + (Forwards Results of Facility Sixth Refueling Outage Steam Generator Tube Inservice Insp Rept.Rept Contains Number & Extent of Tubes Inspected & Identification of Tubes Plugged)
- ML17339A460 + (Forwards Results of Facility Steam Generator Insps & Discusses Insp Criteria & Results.Approval to Return Facility to Power Operation Requested.Util Will Be Ready to Resume Power Operation by 800126.Class III Fee Encl)
- ML20080G535 + (Forwards Results of Faegre & Benson Investigation of Allegations by T Quinn Concerning Gpu Nuclear Corp. Rept Relates to Allegation of Psychological Testing Practices Which Appeared to Have Nexus to Proceeding.W/Svc List)
- ML18153A332 + (Forwards Results of Failure/Metallurgical Analysis,As Committed to in Licensee .Results Include Structural Integrity Evaluation of RHR Piping.List of Util Commitments,Encl)
- ML20003F131 + (Forwards Results of Feb 1981 Survey of Essential Raw Cooling Water Sys & Addl Info Re Const Activities on Essential Raw Cooling Water Sys Dike Between Mar & Sept 1980.Settlement Monitoring Program Should Be Completed by Sept 1985)
- 2CAN038207, Forwards Results of Feb 1982 Response Times of Primary Sys Resistance Temp Detectors,Per 820129 Commitment.Changes Varied Randomly from Baseline Data + (Forwards Results of Feb 1982 Response Times of Primary Sys Resistance Temp Detectors,Per 820129 Commitment.Changes Varied Randomly from Baseline Data)
- ML18136A307 + (Forwards Results of Feedwater Sys Piping Insps,In Response to IE Bulletin 79-13,Revision 2 Re Cracking in Feedwater Piping)
- L-94-173, Forwards Results of Field Survey Completed on 940606,per TS 4.7.6.1.1 + (Forwards Results of Field Survey Completed on 940606,per TS 4.7.6.1.1)
- L-89-227, Forwards Results of Field Survey for Plant Beach Survey Procedure Completed on 890524 & Reduction of Field Survey Data Completed on 890605.Dune Condition Acceptable,Per Unit 1 Tech Spec 5.1.3 + (Forwards Results of Field Survey for Plant Beach Survey Procedure Completed on 890524 & Reduction of Field Survey Data Completed on 890605.Dune Condition Acceptable,Per Unit 1 Tech Spec 5.1.3)
- ML20094K616 + (Forwards Results of Fifth Refuel Outage SG ISI)
- ML20133M942 + (Forwards Results of Fifth Refueling Outage SG Inservice Insp Tube Plugging)
- ML20206A246 + (Forwards Results of Filter Test on Facility Control Room Ventilation (VC) Recirculation Charcoal Filters.Requests Prompt NRC Review & Approval in Order to Declare Facility VC Operable)
- ML18005A620 + (Forwards Results of Final Control Room Surveys,Per Section 6.1.3.2 of Crdr Final Summary Rept.Survey Results Indicate That No Significant Discrepancies w/NUREG-0700 Guidelines Exist.License Condition 2.C(6) Considered Closed)
- ML20141B663 + (Forwards Results of Final Rept Configuration Control Self Assessment, in Response to Notice of Violation Included in NRC Insp Rept 50-285/96-17)
- ML20141B670 + (Forwards Results of Final Rept Configuration Control Self Assessment, in Response to Notice of Violation Included in NRC Insp Rept 50-285/96-17)
- ML20087E689 + (Forwards Results of Final Structural Evaluation of Prestressed Concrete Reactor Vessel During Decommissioning & Prestressing Tendons Detensioned)
- ML19344B288 + (Forwards Results of Finite Element Analyses,Confirming That Refined Displacement Multiplication Factors Are at or Below 800628 Criteria.Wall Mod Designs Will Use Conventional Reinforced Concrete Members,Using Stress Criteria in FSAR)
- ML19305E379 + (Forwards Results of Fire Protection Review,Item 3.1.8,fire Barrier Penetations.Recommends NRC Consider Design & Const of Penetration Seals as Conditionally Acceptable.Typical H Penetration Requires Addl Test Data)
- ML19330A841 + (Forwards Results of Fire Protection Review Re Items 3.1.27 & 3.2.2 on Water Demand Analysis.Licensee Should Be Requested to Modify High Pressure Svc Water/Fire Protection Water Sys to Provide Protection for Turbine Lube Oil Tank)
- ML20043A950 + (Forwards Results of First Quarter 1990 Insp of Contaminated Water from Containment Vessel Sump.Analysis Received on 900508 Indicated That Activity Concentration of Sr-90, Co-60 & Cs-137 Exceeded 10CFR20,App B Limits)
- ML20126B098 + (Forwards Results of First Semiannual Survey of Settlement of Class 1 Structures as Part of Settlement Monitoring Program, to Support Amends 167 & 147 to Licenses NPF-4 & NPF-7, Respectively,Issued on 921005)
- ML18153D280 + (Forwards Results of Fitness for Duty Program Blind Performance Test,Including Details of Apparent Discrepancies & Ltr from HHS-certified Lab Re Followup Investigation)
- ML20037C882 + (Forwards Results of Five high-burnup Fission Gas Release Calculations Based on Riso Natl Lab data.GAPCON-2 Continues to Exhibit Intrinsic Thermal Conservatisms)
- ML20195G491 + (Forwards Results of Flaw Evaluation Performed on Indication in Base Metal of Plant Main Steam Piping Sys Elbow,Which Was Identified During Ultrasonic Exam of Weld 1MS-07-01.01)
- ML13322B180 + (Forwards Results of Flexure Fatigue Analysis of Thermal Shield Support Sys Replacement,Per 900625-27 Meetings)
- ML20064P082 + (Forwards Results of Flow Verification Test for Essential Raw Cooling Water Sys.Recommendations Included Supersede Commitments Made in Previous Response to IE Bulletin 81-03)
- ST-HL-AE-3584, Forwards Results of Fog Monitoring Program at Facilities,Per Section 6.2.4.2 of Environ Rept + (Forwards Results of Fog Monitoring Program at Facilities,Per Section 6.2.4.2 of Environ Rept)
- ML19346A312 + (Forwards Results of Followup Analysis of Identified Discrepancies for Normally Inaccessible safety-related Piping Per Item 4B of IE Bulletin 79-14)
- ML20247Q422 + (Forwards Results of Fourth Inservice Insp of Steam Generator Tubes)
- ML20247R162 + (Forwards Results of Fracture Toughness Analysis Completed for Unit 2 Using Methods Approved in Reg Guide 1.99,Rev 2. Util Authorized Rev of Pressure/Temp Curves Per Rev 2.FSAR Will Be Amended Following NRC Approval of Analysis)
- ML20082G461 + (Forwards Results of Fuel Channel Measurements & Bow Model Data Following Channel Measurements at End of Cycle 12)
- 2CAN948403, Forwards Results of Fuel Insps at End of Third Cycle.Rept Completes FSAR Commitment for Fuel Insp Submittals + (Forwards Results of Fuel Insps at End of Third Cycle.Rept Completes FSAR Commitment for Fuel Insp Submittals)
- ML20235J844 + (Forwards Results of Fuel Oil Samples Collected from Diesel Fuel Oil Storage Tank Coating & Analyzed in Response to NRC Concerns Re Potential for Dissolution of Zinc from Tanks)