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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ML20056B401  + (Safety Evaluation Approving Licensee Relief Request R14 & Denying Requests R15 & R5A Re Hydrostatic Test Requirements)
• ML20128N866  + (Safety Evaluation Approving Licensee Request to Use Code Case N-533 as Alternative to Code Requirements,Per 10CFR50.55a(a)(3))
• ML20154B721  + (Safety Evaluation Approving Licensee Request to Implement Alternatives Contained in Code Case N-546 for Current Interval at Songs,Units 2 & 3 Until Code Case Approved by Ref in Reg Guide 1.147)
• ML20216K001  + (Safety Evaluation Approving Licensee Request Re Plant Training Program for Certified Fuel Handlers)
• ML20059F308  + (Safety Evaluation Approving Licensee Requested one-time Only Exemption from 10CFR50,App J Requirements Re Auxiliary Component Cooling Water Supply Valves)
• ML20045C973  + (Safety Evaluation Approving Licensee Request to Continue to Operate Facility W/Flaw in High Pressure Core Spray Nozzle Safe End Weld KC-32)
• ML18153B164  + (Safety Evaluation Approving Licensee Response to NRC Info Bulletin 90-001,suppl 1 Re Loss of Fill Oil in Transmitters Mfg by Rosemount Company)
• ML13303B889  + (Safety Evaluation Approving Licensee Updated Fire Hazards Analysis Program Submitted w/840319 Ltr.Proposed License Conditions & SALP Input Encl)
• ML18102B500  + (Safety Evaluation Approving Licensee Use of Proposed Alternative to ASME Code Requirement & Removal of Restriction from 950505 SE That Required Weld Repairs Be Performed Offsite on SA-351)
• ML20141C008  + (Safety Evaluation Approving Merger Agreement Between Centerior Energy Corp & Ohio Edison Co Affecting NPF-58)
• ML20136D559  + (Safety Evaluation Approving Merger Between Util & Enron Corp)
• ML19339C346  + (Safety Evaluation Approving Merger of Licenses SNM-273 & SNM-723 Into One license,SNM-273)
• ML17157B118  + (Safety Evaluation Approving Methodology Contained in Topical Rept PL-NF-89-005, Qualification of Transient Analysis Methods for BWR Design & Analysis,Susquehanna Steam Electric Station,Units 1 & 2)
• ML19312E696  + (Safety Evaluation Approving Model 900 Type B Packaging)
• ML19323G666  + (Safety Evaluation Approving Model T-3 Cask)
• ML15238B425  + (Safety Evaluation Approving NFS-1001, Oconee Nuclear Station Reload Design Methodology)
• ML20155E200  + (Safety Evaluation Approving NMP 980227 Request for Extension of Reinspection Interval for Core Shroud Vertical Welds at NMP1 from 10,600 Hours to 14,500 Hours of Hot Operation)
• ML20129H283  + (Safety Evaluation Approving Order Terminating Facility License R-109)
• ML19351D853  + (Safety Evaluation Approving Overcurrent Protection Sys for Containment Electrical Penetrations)
• ML20042G884  + (Safety Evaluation Approving Package Design for Model A1W-3 Core Barrel & Thermal Shield Disposal Container)
• ML20062A118  + (Safety Evaluation Approving Pathfinder Reactor Vessel Package)
• ML20003B530  + (Safety Evaluation Approving Portion of Util 810105 Application Re Use of Two Doubly Encapsulated Ambe Sources)
• ML16162A294  + (Safety Evaluation Approving Preliminary Design for safety- Grade Anticipatory Reactor Trips on Loss of Main Feedwater & Turbine Trip)
• ML20133Q387  + (Safety Evaluation Approving Preliminary Defueling Activities)
• ML16342A035  + (Safety Evaluation Approving Preoperational Endurance Testing of Sixth Edg,Based on Evaluation of Endurance Testing & Results of Visual & Fiberscope Insps)

• ML17309A347  + (Safety Evaluation Approving Process Control Program)

• ML15238A322  + (Safety Evaluation Approving Proposals W/Assumption That Response Commitments of All Other Responders Not Listed Continues to Be IAW Emergency Plan as Approved Prior to Proposed Changes)
• ML15238A324  + (Safety Evaluation Approving Proposals W/Assumption That Response Commitments of All Other Responders Not Listed Continues to Be IAW Emergency Plan as Approved Prior to Proposed Changes)
• ML15238A323  + (Safety Evaluation Approving Proposals W/Assumption That Response Commitments of All Other Responders Not Listed Continues to Be IAW Emergency Plan as Approved Prior to Proposed Changes)
• ML20236R828  + (Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II))
• ML20203B107  + (Safety Evaluation Approving Proposed Alternative to Reactor Vessel Augmented Exam Requirement of Reactor Vessel Shell Welds,Per 10CFR50.55a(g)(6)(ii)(A)(5))
• ML17187A880  + (Safety Evaluation Approving Proposed Change to Improved STS)
• ML20116E793  + (Safety Evaluation Approving Proposed Design & Method of Dealing W/Sbo)
• ML20136B809  + (Safety Evaluation Approving Proposed Early Defueling Activities)
• ML20195D526  + (Safety Evaluation Approving Proposed ISI Program Alternative for Limited Reactor Vessel Shell Weld Exams & Relief Request from Requirements of ASME Code,Section XI)
• ML17258A315  + (Safety Evaluation Approving Proposed Mod of Spent Fuel Pool Cooling Sys)
• ML20116C462  + (Safety Evaluation Approving Proposed Organizational & Financial Restructuring of Midamerican Energy Co)
• ML18017A341  + (Safety Evaluation Approving Proposed Protective Measures to Sufficiently Protect safety-related Equipment from Flooding as Consequence of Failure of Non-Category I Seismic Sys)
• ML19332D399  + (Safety Evaluation Approving Proposed Reactor Vessel Metallurgical Sampling Activity)
• ML20217K846  + (Safety Evaluation Approving Proposed Use of Code Case N-535 at Brunswick Unit 1 During Second 10-yr Interval,Pursuant to 10CFR50.55a(a)(3)(i).Authorizes Use of Code Case N-535 Until Code Case Included in Future Rev of RG 1.147)
• ML19257A828  + (Safety Evaluation Approving QA Program Described in FSAR, Amend 39,Revision 8)
• ML20033B180  + (Safety Evaluation Approving Redesigned Isolation Condenser Loading Combinations.Isolation Condenser Supply Line Will Withstand Effect of Water Hammer Loads)
• ML17056B967  + (Safety Evaluation Approving Reduction of Condensation Oscillation Loads Provided Average Min Wall Thickness of Torus Shell Not Reduced to Less than 0.431 Inches)
• ML15218A122  + (Safety Evaluation Approving Relief Request 92-13 & for Parts A,C,D & F of Relief Request 92-12 Re Certain ASME Codes Determined to Be Impractical to Perform During Plant Second 10-year Interval ISI)
• ML17334B629  + (Safety Evaluation Approving Relief Requests REL-02,REL-05 & REL-12 & Denying Relief Requests P-1,REL-12 (Test Frequency Portion) & REL-13 for IST Program for Plant Units 1 & 2)
• ML20210Q052  + (Safety Evaluation Approving Relief Request 10 to License DPR-22 Per 10CFR50.55a(g)(6)(i).Inservice Exam for Relief Request 10,Parts A,B,C,D & E Impractical & Reasonable Assurance of Structural Integrity Provided)
• ML20058N796  + (Safety Evaluation Approving Relief Request 89-01 Re ASME Code Test Requirements for Nuclear Svc Water Sys)
• ML20093K934  + (Safety Evaluation Approving Relief Request B-J/B4.5 to Revised First 10-Year Inservice Insp Program for Arkansas Nuclear One,Unit 2)
• ML17056B361  + (Safety Evaluation Approving Relief Request from ASME Code Requirements)
• ML14183A695  + (Safety Evaluation Approving Relocation of Technical Support Ctr)
• ML15239A323  + (Safety Evaluation Approving Request for Relief to Use ASME Code Case N-416-1 in Lieu of Hydrostatic Pressure Test After Making Weld Repairs on Core Flood Tank Sys)