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Issue date | Title | Topic | |
---|---|---|---|
A12714, Public Svc Corp Prenuclear Pelton Wheel Cavitation Rept | 2 August 1973 | Public Svc Corp Prenuclear Pelton Wheel Cavitation Rept | Safe Shutdown Weld Overlay Overspeed trip |
A13175, Investigation Into Cause & Consequence of Fort St Vrain Pelton Wheel Incipient Fractures | 16 October 1974 | Investigation Into Cause & Consequence of Fort St Vrain Pelton Wheel Incipient Fractures | Safe Shutdown Earthquake |
A13742, Status Rept on Reserve Shutdown Sys | 25 November 1975 | Status Rept on Reserve Shutdown Sys | Boric Acid |
A13823, Fort St Vrain Dew Point Moisture Monitor Sys Post-Mod Test Results (RT-355C) | 9 February 1976 | Fort St Vrain Dew Point Moisture Monitor Sys Post-Mod Test Results (RT-355C) | |
A14049, Investigation Into Causes & Consequences of Malfunction of Static Shutdown Seal S/N 3 in Fort St Vrain Circulator C2102 from D Penetration | 30 September 1976 | Investigation Into Causes & Consequences of Malfunction of Static Shutdown Seal S/N 3 in Fort St Vrain Circulator C2102 from D Penetration | |
L-82-332, Conformance to Reg Guide 1.97,Fort St Vrain Nuclear Generating Station | 30 November 1985 | Conformance to Reg Guide 1.97,Fort St Vrain Nuclear Generating Station | |
L-94-021, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3 | 30 November 1994 | Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3 | |
ML17334B033 | 30 November 1986 | Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28. | |
ML17334B072 | 31 March 1987 | Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Cook Units 1 & 2 & Haddam Neck. | |
ML17347A593 | 31 July 1987 | Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept | |
ML18040A226 | 31 May 1994 | Technical Evaluation Rept,Technical Basis for Reduction of Torus Shell Condensation Oscillation Loads for Niagra Mohawk Power Corp Nine Mile Point Unit 1. | Hydrostatic |
ML18040B189 | 31 August 1987 | Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. | |
ML18052B193 | 30 June 1987 | Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Calvert Cliffs-1 & -2, Millstone-2 & Palisades, Final Informal Rept | |
ML18141A305 | 31 December 1983 | Definition of Operable,Kewaunee Nuclear Power Plant. | |
ML18150A119 | 30 April 1987 | Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept | |
ML18150A188 | 30 April 1987 | Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept | |
ML18152A583 | 30 April 1987 | Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. | |
ML19317H189 | 31 July 1978 | In-Plant Source Term Measurements at Fort Calhoun Station- Unit 1. | Boric Acid Grab sample |
ML19326D718 | 31 January 1980 | Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Fort Calhoun Nuclear Power Plant. | |
ML19332A751 | 21 July 1980 | Primary Coolant Sys Pressure Isolation Valves,Millstone Unit 2, Technical Evaluation Rept | |
ML19332A780 | 31 July 1980 | Safety Evaluation of Inservice Testing Program for Pumps & Valves, Interim Rept 790426-801025 | Boric Acid Stroke time Exemption Request |
ML19332B582 | 30 September 1989 | Conformance to Reg Guide 1.97:Millstone-2, Technical Evaluation Rept | Post Accident Monitoring |
ML19332B614 | 31 October 1989 | Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety-Related Components:Quad Cities 1 & 2, Final Technical Evaluation Rept | Safe Shutdown |
ML19347E109 | 30 April 1981 | Orturb:A Digital Computer Code to Determine the Dynamic Response of Fort St. Vrain Reactor Steam Turbines | |
ML19350E647 | 18 June 1981 | Equipment Environ Qualification,Millstone Unit 2, Technical Evaluation Rept | Safe Shutdown Boric Acid Shutdown Margin Post Accident Monitoring High Energy Line Break |
ML20003H276 | 24 October 1980 | Primary Coolant Sys Pressure Isolation Valves,Fort Calhoun Unit 1, Technical Evaluation Rept | Hydrostatic |
ML20004F270 | 8 June 1981 | Evaluation of TMI Action Plan Application to Fort St Vrain, Monthly Rept for Period Ending 810615 | Coatings |
ML20005C004 | 31 October 1981 | Aquatic Impacts from Operation of Three Midwestern Nuclear Power Stations.Fort Calhoun Station,Unit No. 1 Environmental Appraisal Report | Grab sample Biofouling |
ML20009C374 | 30 June 1981 | Tech Specs for Redundant Decay Heat Removal Capability, Millstone Nuclear Power Station,Unit 2, Technical Evaluation Rept | |
ML20023A486 | 2 September 1982 | Ei Hatch Nuclear Plant Units 1 & 2 Inservice Insp Program, Technical Evaluation Rept | Hydrostatic Nondestructive Examination VT-2 Incorporated by reference |
ML20023A489 | 10 September 1982 | Inservice Insp Program, Technical Evaluation Rept | |
ML20023A493 | 17 September 1982 | Radiological Effluent Tech Spec Implementation (A-2), Millstone Nuclear Power Station Unit 2, Technical Evaluation Rept | Boric Acid Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program |
ML20023A535 | 30 September 1982 | Degraded Grid Protection for Class IE Power Sys,Fort St. Vrain, Ltr Rept,Revision 1 | |
ML20023E178 | 31 May 1983 | Copper in the Intake and Discharge Zones of the Surry and Salem Nuclear Power Stations | |
ML20027A899 | 26 August 1982 | Nonproprietary Vols 1 & 2 of, Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SER (F-11 & B-60), Technical Evaluation Rept | |
ML20027D216 | 31 August 1982 | Adequacy of Station Electric Distribution Sys Voltage,Fort St Vrain Nuclear Generating Station. | |
ML20027E712 | 10 November 1982 | Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Fort Calhoun Station, Vols I & Ii,Technical Evaluation Rept | Boric Acid High Energy Line Break |
ML20038A769 | 31 October 1981 | Aquatic Impacts from Operation of Three Midwestern Nuclear Power Stations | Grab sample Biofouling |
ML20039A911 | 30 November 1981 | Adequacy of Station Electric Distribution Sys Voltages, Fort Calhoun Nuclear Station Unit 1,informal Rept | |
ML20039B810 | 31 October 1981 | Evaluation of Emergency Response Facilities for Fort Calhoun Station - Unit 1. | Health Physics Network High winds Exclusive Use |
ML20039F043 | 31 December 1981 | THREE-DIMENSIONAL Thermodelastic Analysis of a Fort St. Vrain Core Support Block | |
ML20039G405 | 30 December 1981 | Tech Specs for Redundant Decay Heat Removal Capability, Millstone Nuclear Power Station,Unit 2. | |
ML20040D165 | 16 December 1981 | Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Rept, Request for Addl Info | |
ML20041A360 | 16 February 1982 | Tech Specs for Redundant Decay Heat Removal Capability, Millstone Nuclear Power Station,Unit 2, Revised Page | |
ML20041C277 | 31 January 1982 | Snupps Auxiliary Feedwater System Reliability Study Evaluation | |
ML20042A233 | 28 February 1982 | Technical Evaluation Rept for Containment Purging & Venting During Normal Operation of Fort Calhoun Station. | |
ML20042D174 | 31 October 1989 | Final Technical Evaluation Rept on Response from Niagara Mohawk Power Corp to Generic Ltr 88-01 Pertaining to Nine Mile Point,Unit 1. | Weld Overlay Intergranular Stress Corrosion Cracking |
ML20052B831 | 28 February 1982 | Safety Evaluation Rept,Pumps & Valves Inservice Testing Program,Nine Mile Point Nuclear Station,Unit 1. | Stroke time Hydrostatic Power-Operated Valves |
ML20054F510 | 31 May 1982 | Response of the Zion & Indian Point Containment Buildings to Severe Accident Pressures | |
ML20054K059 | 13 May 1982 | Technical Evaluation Rept on Proposed Design Mods & Tech Spec Changes on Grid Voltage Degradation for Millstone Nuclear Power Station,Unit 1 |