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List of results

• ML19220C671  + (Submits Current Preliminary Chronology,Package of Operational Charts & Results of Interviews W/Operators & Others Re TMI Incident)
• ML20073R993  + (Submits Current Requalification Program W/Proposed Changes Marked W/Side Bars)
• ML20134G980  + (Submits Current Results of Neorsd Samples)
• RC-96-0261, Submits Current Review Status & Planned Action,In Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions  + (Submits Current Review Status & Planned Action,In Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions)
• ML20209C919  + (Submits Current Schedule for Developing Specific Elements for Facility License Condition.Applicant Shall Identify, Examine & Evaluate All Relevant Geologic & Seismic Data,Info & Interpretations Available Since 1979 ASLB Hearing)
• ML20207N170  + (Submits Current Scheduled Dates for Activities,As Noted in Resnikoff Rept Review Plan)
• ML20085B254  + (Submits Current Status & Mods to Control Rod Drive Mechanisms Testing Program.Temporary Relubrication of Clutch Splines Reported in Will Continue Until Proposed Mods Become Permanent)
• ML20084U896  + (Submits Current Status Rept on AO 50-265/74-32;on 741226-27, MSIV 2-203-1A,B & C Exceeded Leak Rate Limits.Valves Cleaned & Lapped.Ao 50-265/75-9 Reporting 750314 Event to Be Submitted When Work Complete)
• ML20134M107  + (Submits Current Status of Analyses Being Performed to Demonstrate Acceptable Fuel Grid Response to Specified LOCA Conditions)
• ML18089A246  + (Submits Current Status of Conformance w/830708 Generic Ltr 83-28 Re Required Actions Based on Generic Implications of Reactor Trip Breaker Failures on 830222 & 25)
• ML18089A247  + (Submits Current Status of Conformance w/830708 Generic Ltr 83-28 Re Required Actions Based on Generic Implications of Reactor Trip Breaker Failures on 830222 & 25)
• U-600455, Submits Current Status of Design,Const & Preoperational Phase Testing.Progress Continues to Support Goal for Fuel Load During First Quarter 1986.Activities Needed to Support Fuel Load & Preparations for Testing Listed  + (Submits Current Status of Design,Const & Preoperational Phase Testing.Progress Continues to Support Goal for Fuel Load During First Quarter 1986.Activities Needed to Support Fuel Load & Preparations for Testing Listed)
• BECO-87-195, Submits Current Status of Improvements Being Implemented in Response to NUREG-0737,Item II.F.2 & Generic Ltr 84-23. Improvements Include Instrumentation for Reactor Water Level Sys & Installation of Analog Trip Sys  + (Submits Current Status of Improvements Being Implemented in Response to NUREG-0737,Item II.F.2 & Generic Ltr 84-23. Improvements Include Instrumentation for Reactor Water Level Sys & Installation of Analog Trip Sys)
• U-600506, Submits Current Status of Plant Design,Const & Preoperational Phase Testing.Util in Final Process of Testing Plant in Preparation for Fuel Load.Fuel Load Anticipated in Late June or Early Jul 1986  + (Submits Current Status of Plant Design,Const & Preoperational Phase Testing.Util in Final Process of Testing Plant in Preparation for Fuel Load.Fuel Load Anticipated in Late June or Early Jul 1986)
• ML20093F589  + (Submits Current Status of Recent Tube Plugging Efforts.Info Suppls 840627 & 0703 Data.Schedule Submitted in Will Be Revised.Table of Tubes Plugged Since 840627 Encl)
• ML13330A118  + (Submits Current Status of Structural Evaluations & Summary of Program for Evaluation of Piping & Equipment.Detailed Evaluations of Plant Structures Are Scheduled for Completion in June 1981)
• ML20125D934  + (Submits Current Status of Work on Tech Spec Limiting Condition for Operation 4.1.9 Re Core Region Temp Rise. Calculational Differences Between Thermal/Hydraulic Analyses Being Investigated.Summary of Open Items Provided)
• ML20054B484  + (Submits Current Test Data for Butterfly Isolation Valves, in Response to & Supplementing 810827 & 1223 Responses.Testing Schedule Will Continue Per App J to 10CFR50)
• ML20234D304  + (Submits Current Thoughts on Plant ECCS & Containment)
• NLS8800486, Submits Current plant-specific Seismic Verification Plans for Facility,In Response to Generic Ltr 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46  + (Submits Current plant-specific Seismic Verification Plans for Facility,In Response to Generic Ltr 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46)
• ML17258A906  + (Submits Currently Scheduled Completion Dates for Evaluations of Certain Items in SEP Topics III-6, Seismic Design Considerations & III-11, Component Integrity)
• ML20024B391  + (Submits Customer Svc Dept Monthly Activities Rept for Jul 1979)
• GO2-96-235, Submits Cycle 12 Startup Rept for Plant Per Ts.Encl Repts Provide Descriptions of Startup & Power Ascension Testing Activities  + (Submits Cycle 12 Startup Rept for Plant Per Ts.Encl Repts Provide Descriptions of Startup & Power Ascension Testing Activities)
• ML19246A725  + (Submits Cycle 2 Summary Startup Test Rept)
• HNP-15-065, Submits Cycle 20 Startup Test Report  + (Submits Cycle 20 Startup Test Report)

• GO2-15-089, Submits Cycle 23 Core Operating Limits Report, Revision 0  + (Submits Cycle 23 Core Operating Limits Report, Revision 0)

• ML20207T361  + (Submits Cycle 4 Radial Peaking Factor Limit Rept,Per Tech Specs.Graphs Encl)
• ML20082B643  + (Submits Cycle 7 Fuel Performance Rept,Based on Results of Cycle 7 Fuel Insps.Full Rept on Insps Will Be Included as Part of Util Program W/Doe)
• ML20206H113  + (Submits DHEAT2 Parametric Calculations for Plant,Per 860620 Discussions.Calculations Run Assuming Any Steam Spike Would Develop Too Slowly to Contribute to DCH Peak Pressure)
• ML20132C863  + (Submits DOE Position Re Timing of Preliminary Determination of Suitable Sites for Development as Repositories,Per Nuclear Waste Policy Act of 1982,Section 114(f).Act Left to Decision to Secretary)
• ML19224B898  + (Submits Daily Digest for 790509)
• ML19224B899  + (Submits Daily Digest for 790509)
• ML19224B862  + (Submits Daily Digest for 790517)
• ML19224B900  + (Submits Daily Digest for 790521)
• ML19224B825  + (Submits Daily Digest for 790525.Forwards Order Re TMI Records)
• ML19224C526  + (Submits Daily Digest for 790531)
• ML17054C005  + (Submits Daily Highlight & Notification of 851118 Meeting W/Util in Bethesda,Md,To Discuss Insp & Possible Corrective Actions for Stub Tubes Which May Be Identified as Degraded)
• ML20245F706  + (Submits Daily Highlight Notifying of 890817 Meeting W/Util in Rockville,Md to Discuss Qualification of Decay Heat Pump at Low Flows)
• ML20071H278  + (Submits Daily Highlight Re 820203 Insp of Steam Generator B to Determine Location of 820125 Ruptured Tube Event.Eddy Current Tests Performed on Tube Near Periphery on Hot Leg Side & Four Adjacent Tubes)
• ML20071N287  + (Submits Daily Highlight Re 820210 Meeting W/Util Concerning Requirements to Be Met Prior to Restart of Facility.No Sufficient Basis Presented at This Time to Permit Plant to Return to Operation)
• ML20023A511  + (Submits Daily Highlight Re 820301 Meeting W/Util Re Proposed Recovery Program for Facility.Nrc Concurred W/Proposal to Remove Small Number of Steam Generator Tube Sections for Metallurgical Exam)
• ML20023A510  + (Submits Daily Highlight Re 820301 Meeting W/Util & 820302 Meeting W/Westinghouse in Bethesda,Md to Discuss Recovery Activities at Facility & Generic Steam Generator Tube Degradation,Respectively)
• ML20023A513  + (Submits Daily Highlight Re 820323 Meeting W/Util & Westinghouse Concerning Status of Proposed Repair activities.Twenty-four Tubes Removed from Steam Generator B. Foreign Object Found in Wedge Area 4)
• ML20237J362  + (Submits Daily Highlight Re 870715 Primary to Secondary Leak Event.Event Further Analyzed by Licensee.Max Leak Rate Approx 637 Gpm.Eddy Current Testing Scheduled to Commence on 870719.Data Analysis Scheduled for Completion on 870721)
• ML20005E071  + (Submits Daily Highlight Re 891227 Meeting W/Numarc in Rockville,Md,To Discuss Draft Augumented Guidance Prepared by NUMARC Re Station Blackout rule,10CFR50.63)
• ML20043F989  + (Submits Daily Highlight Re 900613 Meeting W/Util in Rockville,Md to Discuss Status of Crdr at Facilities)
• ML20045B270  + (Submits Daily Highlight Re 930617 Meeting W/Util in Rockville,Md to Discuss Licensee Response to NRC Bulletin 93-003)
• ML20045G021  + (Submits Daily Highlight Re 930707 & 08 Meeting w/ABB-CE in Rockville,Md to Discuss Sys 80+ Reactor Sys Related Unresolved Issues)
• ML20046A793  + (Submits Daily Highlight Re 930722 Meeting W/Util in Rockville,Md to Discuss Licensee Plans for Load Testing Station Blackout Alternate AC Source)
• ML20046A560  + (Submits Daily Highlight Re 930727 Meeting W/Ge in Rockville,Md to Discuss Selected ABWR Tier 1 Info for Five Bldg Design Descriptions & Associated ITAAC)
• ML20056E529  + (Submits Daily Highlight Re 930812 Meeting w/ABB-CE in Rockville,Md to Review Staff Comments Re ABB-CE Nuplex 80+ Stds)