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List of results

• ML19224B651  + (Final Rept, Sys Description:Safety Features Actuation Sys, Ref B&R Drawing 3011,Revision 7,Sheets 1 & 2)
• ML19224B286  + (Final Rept, Sys Description:Steam Generator Secondary Side Vents & Drains Sys, Ref Burns & Roe Drawing 2414,Revision 7)
• ML19224B298  + (Final Rept, Sys Description:Sump Pump Discharge Sys, Ref Burns & Roe Drawing 2496,Revision 8)
• ML20055C946  + (Final Rept, TMI - Unit 2 Safety Advisory Board, for Mar 1981 - Dec 1989)
• ML20206M286  + (Final Rept, Technical Evaluation Rept on Submittal-Only Review of Individual Plant Exam of External Events at Fort Calhoun Station)
• ML20212L354  + (Final Rept, Technical Evaluation Rept on Submittal-Only Review of IPEEE at San Onofre Nuclear Generating Station, Units 2 & 3)
• ML20209G756  + (Final Rept, Technical Evaluation Rept on Submittal-Only Review of Individual Plant Exam of External Events at Comanche Peak Steam Electric Station,Units 1 & 2)
• ML20097J766  + (Final Rept, Technical Evaluation Rept on IPE Submittal Human Reliability Analysis, Rev 1)
• ML20077P929  + (Final Rept, Verification of Fort St Vrain Activation Analysis)
• ML20133C005  + (Final Rept,Connecticut Yankee Plant Design Change External Review Group)
• ML20094H081  + (Final Rept,Employee Concerns Program 1995 Re-Baseline Evaluation,Sept 1995,STP,HL&P)
• ML20127L622  + (Final Rept,Hydraulic Model Studies of Alvin W Vogtle Nuclear Plant Containment Pump ECCS Recirculation Intakes)
• ML20127L611  + (Final Rept,Hydraulic Model Studies of Alvin W Vogtle Nuclear Plant Flow Conditions to Containment Emergency Sumps)
• ML20215E945  + (Final Rept,Mgt Audit of Brown & Root QA Program,770509-20)
• ML20149F993  + (Final Rept,Msiv Solenoid Valve Failure,Analytical Chemistry Results)
• ML19276F641  + (Final Rept,Ncr HNP-A-021,on Wiring Discrepancies in High Pressure Core Spray Diesel Generator Control Switchgear. Lists Discrepancies Found.Problems Have Been Identified & Will Be Corrected)
• ML19331D332  + (Final Rept,Per 10CFR21 & IE Bulletin 80-16,re Rosemount Model 1152 Pressure Transmitter Safety Hazards.Twelve Transmitters Could Have False Instrument Outputs Caused by Overrange Condition.Instruments to Be Modified or Replaced)
• ML19270F332  + (Final Rept,Per 10CFR50.55(e),for Possible Safety/Relief Valve Control Deficiency,Supplementing .Results of Plant Unique Analysis Presented in Design Assessment Closure Rept.Mod of Closing Setpoints to Be Implemented in Future)
• ML20081E517  + (Final Rept,Response to 10CFR50 App R `Alternate Shutdown Capability)
• ML20141H527  + (Final Rept,Rev 0 to CEOG Response to NRC GL 97-01, Degradation of CEDM Nozzle & Other Vessel Closure Head Penetrations)
• W3P84-2963, Final Rept,Rev 1,on Significant Const Deficiency 84 Re Tube Track Welding.Reevaluation Performed by Ebasco Engineering to Establish Max Stress Levels Expected to Exist at Tube Track Welded Connections  + (Final Rept,Rev 1,on Significant Const Deficiency 84 Re Tube Track Welding.Reevaluation Performed by Ebasco Engineering to Establish Max Stress Levels Expected to Exist at Tube Track Welded Connections)
• ML20093K867  + (Final Rept,Significant Const Deficiency 109 Re Inadequate Design of Qspds/Pps Circuit Interface.Initially Reported on 840524.PMP 302,preparation of Station Mod Packages,Revised to Include Grounding Requirements for All Changes)
• ML20041G420  + (Final Rept,Surveillance of Earthwork UHS & UHS Dam)
• ML20080G365  + (Final Rept,Survey of Mgt Practices Affecting Organizational Responsiveness for South Tx Project Electric Generating Station)
• ML19254D937  + (Final Rept,Svc Water Intake Structure Settlement Effects & Related Work)

• ML19209B054  + (Final Rept,Task Force on NRC Safeguards Policy)

• ML20032A077  + (Final Rept,Vol I,Results of Geologic Excavation Mapping)
• ML20032A082  + (Final Rept,Vol Ii,Results of Geologic Excavation Mapping)
• ML19274D146  + (Final Rept--Postoperational Hydrothermal Surveys June 1976- Nov 197 Dtd Sept 1978.Concludes That Facility & Adjacent Nine Mile Point Plant Impose No Significant Ecological Impact on Aquatic Environment)
• ML20214H034  + (Final Rept-Colorado River Entrainment & Impingement Monitoring Program,Phase 2 Studies,Jul 1983 - Nov 1985)
• ML20148P456  + (Final Rept.Deficient 312 Stainless Steel Buttering on Flued Head Fittings for Primary Component Penetrations at Subj Facil.Circumferential Linear Indications Present in All 12 Fittings Prior to Shipment to Site.Fittings Will Be Removed)
• ML20147H800  + (Final Rept:3-D Exper Proj Air-Water Upper Plenum Expers. Proj Purpose Was to Gain Basic Understanding of 2-phase Flow Characteristics in Upper Core & Upper Plenum Regions of PWR During Core Reflooding Following a LOCA)
• ML20151K267  + (Final Rept:Failure Modes & Effects Analysis of Integrated Control Sys/Non-Nuclear Instrumentation Electric Power Distribution Circuitry, Vol 1 - Main Rept & Vol 2 - App a)
• ML20064F982  + (Final Rept:Failure of Back Draft Damper in Main Control Room Air Handling Unit Discovered During Routine Mod of Sys. Damper Lost All Blades Due to Excessive Blade Bearing Wear. Failed Dampers Replaced w/high-pressure Units)
• ML20128C976  + (Final Rept:Shallow,High-Resolution Seismic Profiling of Five Georgia River Localities. Draft PA Sobel Memo to Alterman Re Seismology Review of Bechtel Rept, Studies of Postulated Millett Fault Encl)
• ML20125E444  + (Final Rept:Shallow,High-Resolution Seismic Profiling of Five Georgia River Localities. Viewgraphs of 820914 Presentation on Postulated Millet Fault Encl)
• ML19309H187  + (Final Rept:Significance of Monticello Reservoir Earthquake of 780827)
• ML20116E817  + (Final Rept:Task Analysis & Verification of Snupps Control Room)
• ML25119A284  + (Final Request for Additional Information (Redacted))
• ML24107A146  + (Final Request for Additional Information Re VR-09)
• ML21123A298  + (Final Request for Additional Information Set 3 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure)
• ML21091A003  + (Final Request for Additional Information Set 2 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure 1 - RAIs)
• ML21091A002  + (Final Request for Additional Information Set 2 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email)
• ML20297A322  + (Final Request for Additional Information - Steam Generator Tube Sleeve LAR)
• ML23102A101  + (Final Request for Additional Information – NEI 16-03, Guidance for Monitoring of Fixed Neutron Absorbers in Spent Fuel Pools, Revision 1)
• ML19155A050  + (Final Request for Additional Information for the Safety Review of the Surry Power Station, Units 1 and 2 Subsequent License Renewal Application (L-2018-RNW-0023/000951) - Set 1)
• ML21322A099  + (Final Request for Additional Information Set 5 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure)
• 0CAN102101, Final Request for Additional Information Concerning Generic Letter 2004-02  + (Final Request for Additional Information Concerning Generic Letter 2004-02)
• ML19164A333  + (Final Request for Additional Information for the Safety Review of the Surry Power Station, Units 1 and 2 Subsequent License Renewal Application Set 2 June 11, 2019)
• ML25252A199  + (Final Request for Additional Information - Topical Report SSP-14-P01/028 (NRC Project No. 0816), Generic Application of the Studsvik Scandpower Core Management System to Pressurized Water Reactors)
• ML25252A192  + (Final Request for Additional Information - Topical Report SSP-14-P01/028 (NRC Project No. 0816), Generic Application of the Studsvik Scandpower Core Management System to Pressurized Water Reactors)