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 Issue dateTitleTopic
A12714, Public Svc Corp Prenuclear Pelton Wheel Cavitation Rept2 August 1973Public Svc Corp Prenuclear Pelton Wheel Cavitation ReptSafe Shutdown
Weld Overlay
A13175, Investigation Into Cause & Consequence of Fort St Vrain Pelton Wheel Incipient Fractures16 October 1974Investigation Into Cause & Consequence of Fort St Vrain Pelton Wheel Incipient FracturesSafe Shutdown Earthquake
A13742, Status Rept on Reserve Shutdown Sys25 November 1975Status Rept on Reserve Shutdown SysBoric Acid
A13823, Fort St Vrain Dew Point Moisture Monitor Sys Post-Mod Test Results (RT-355C)9 February 1976Fort 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 Penetration30 September 1976Investigation 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 Station30 November 1985Conformance 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/-330 November 1994Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3
ML17334B03330 November 1986Input 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.
ML17334B07231 March 1987Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Cook Units 1 & 2 & Haddam Neck.
ML17347A59331 July 1987Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept
ML18040A22631 May 1994Technical Evaluation Rept,Technical Basis for Reduction of Torus Shell Condensation Oscillation Loads for Niagra Mohawk Power Corp Nine Mile Point Unit 1.Hydrostatic
ML18040B18931 August 1987Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs.
ML18052B19330 June 1987Conformance 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
ML18141A30531 December 1983Definition of Operable,Kewaunee Nuclear Power Plant.
ML18150A11930 April 1987Conformance 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
ML18150A18830 April 1987Conformance 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
ML18152A58330 April 1987Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2.
ML19317H18931 July 1978In-Plant Source Term Measurements at Fort Calhoun Station- Unit 1.Boric Acid
Grab sample
ML19326D71831 January 1980Technical 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.
ML19332A75121 July 1980Primary Coolant Sys Pressure Isolation Valves,Millstone Unit 2, Technical Evaluation Rept
ML19332A78031 July 1980Safety Evaluation of Inservice Testing Program for Pumps & Valves, Interim Rept 790426-801025Boric Acid
Stroke time
Exemption Request
ML19332B58230 September 1989Conformance to Reg Guide 1.97:Millstone-2, Technical Evaluation ReptPost Accident Monitoring
ML19332B61431 October 1989Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety-Related Components:Quad Cities 1 & 2, Final Technical Evaluation ReptSafe Shutdown
ML19347E10930 April 1981Orturb:A Digital Computer Code to Determine the Dynamic Response of Fort St. Vrain Reactor Steam Turbines
ML19350E64718 June 1981Equipment Environ Qualification,Millstone Unit 2, Technical Evaluation ReptSafe Shutdown
Boric Acid
Shutdown Margin
Post Accident Monitoring
ML20003H27624 October 1980Primary Coolant Sys Pressure Isolation Valves,Fort Calhoun Unit 1, Technical Evaluation ReptHydrostatic
ML20004F2708 June 1981Evaluation of TMI Action Plan Application to Fort St Vrain, Monthly Rept for Period Ending 810615Coatings
ML20005C00431 October 1981Aquatic Impacts from Operation of Three Midwestern Nuclear Power Stations.Fort Calhoun Station,Unit No. 1 Environmental Appraisal ReportGrab sample
Biofouling
ML20009C37430 June 1981Tech Specs for Redundant Decay Heat Removal Capability, Millstone Nuclear Power Station,Unit 2, Technical Evaluation Rept
ML20023A4862 September 1982Ei Hatch Nuclear Plant Units 1 & 2 Inservice Insp Program, Technical Evaluation ReptHydrostatic
Nondestructive Examination
VT-2
Incorporated by reference
ML20023A48910 September 1982Inservice Insp Program, Technical Evaluation Rept
ML20023A49317 September 1982Radiological Effluent Tech Spec Implementation (A-2), Millstone Nuclear Power Station Unit 2, Technical Evaluation ReptBoric Acid
Offsite Dose Calculation Manual
Annual Radiological Environmental Operating Report
Process Control Program
ML20023A53530 September 1982Degraded Grid Protection for Class IE Power Sys,Fort St. Vrain, Ltr Rept,Revision 1
ML20023E17831 May 1983Copper in the Intake and Discharge Zones of the Surry and Salem Nuclear Power Stations
ML20027A89926 August 1982Nonproprietary Vols 1 & 2 of, Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SER (F-11 & B-60), Technical Evaluation Rept
ML20027D21631 August 1982Adequacy of Station Electric Distribution Sys Voltage,Fort St Vrain Nuclear Generating Station.
ML20027E71210 November 1982Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Fort Calhoun Station, Vols I & Ii,Technical Evaluation ReptBoric Acid
ML20038A76931 October 1981Aquatic Impacts from Operation of Three Midwestern Nuclear Power StationsGrab sample
Biofouling
ML20039A91130 November 1981Adequacy of Station Electric Distribution Sys Voltages, Fort Calhoun Nuclear Station Unit 1,informal Rept
ML20039B81031 October 1981Evaluation of Emergency Response Facilities for Fort Calhoun Station - Unit 1.Health Physics Network
High winds
ML20039F04331 December 1981THREE-DIMENSIONAL Thermodelastic Analysis of a Fort St. Vrain Core Support Block
ML20039G40530 December 1981Tech Specs for Redundant Decay Heat Removal Capability, Millstone Nuclear Power Station,Unit 2.
ML20040D16516 December 1981Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Rept, Request for Addl Info
ML20041A36016 February 1982Tech Specs for Redundant Decay Heat Removal Capability, Millstone Nuclear Power Station,Unit 2, Revised Page
ML20041C27731 January 1982Snupps Auxiliary Feedwater System Reliability Study Evaluation
ML20042A23328 February 1982Technical Evaluation Rept for Containment Purging & Venting During Normal Operation of Fort Calhoun Station.
ML20042D17431 October 1989Final Technical Evaluation Rept on Response from Niagara Mohawk Power Corp to Generic Ltr 88-01 Pertaining to Nine Mile Point,Unit 1.Weld Overlay
ML20052B83128 February 1982Safety Evaluation Rept,Pumps & Valves Inservice Testing Program,Nine Mile Point Nuclear Station,Unit 1.Stroke time
Hydrostatic
Power-Operated Valves
ML20054F51031 May 1982Response of the Zion & Indian Point Containment Buildings to Severe Accident Pressures
ML20054K05913 May 1982Technical Evaluation Rept on Proposed Design Mods & Tech Spec Changes on Grid Voltage Degradation for Millstone Nuclear Power Station,Unit 1
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