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 Issue dateTitleTopic
ML09343079431 October 1981Evaluation of Indian Point 3 Nuclear Power Plant.High Radiation Area
ML10020023531 December 1978Evaluation of ECCS Per 10CFR50.46 & App K of 10CFR50. Describes Major Reactor Coolant Sys Pipe Ruptures on Westinghouse Model
ML10020023930 June 1977Reactor Vessel Material Surveillance Program,Analysis of Capsule T Submitted in Support of Amend 1 to Application for Amend to License DPR-26.Vessel Matl Surveillance Capsule Was Tested & EvaluatedHydrostatic
ML10027182730 September 1980Thermal - Radiation Matls Application Data. One Oversize Drawing Encl.Aperture Card Is Available in PDRBoric Acid
ML10032154531 October 1981Evaluation of Indian Point Station Unit No 2.Nondestructive Examination
Temporary Modification
ML10098027331 January 1979Support Sys Redesign for Piping Runs on North Half of Containment.
ML10098027630 April 1978Rept 03-00101,Revision 0,Piping Sys Hydraulic Shock Suppressor Removal Study, & Rept 03-00102,Revision 0, Piping Sys Hydraulic Shock Suppressor Analysis for Removal.High Radiation Area
Operating Basis Earthquake
Earthquake
ML17059A3616 July 1994Emergency Action Level Verification & Validation Rept.Earthquake
ML17311A01813 May 1994New York State EAL Upgrade Project Verification & Validation Rept.Safe Shutdown
Shutdown Margin
Reactor Vessel Water Level
Ultimate heat sink
Offsite Dose Calculation Manual
Safeguards Contingency Plan
Battery sizing
Earthquake
Fuel cladding
Pressure Boundary Leakage
Offsite Circuit
Power change
Unidentified leakage
ML19305A74228 September 1979Safety Evaluation Re Changes to Tech Specs for Mgt TitlesFire Protection Program
ML19331B83831 August 1980Compliance Study in Response to NRC 800211 Confirmatory Order Re Ucs Petition to Suspend Operation.Demonstrates Methods by Which Safety Rules & Regulations Are Implemented. Financial & Reporting Requirements Not AddressedSafe Shutdown
Boric Acid
High winds
Tornado Missile
Earthquake
Fuel cladding
ML19340E70930 November 1980Technical Evaluation of the Susceptibility of Safety- Related Sys to Flooding Caused by Failure of Noncategory I Sys for Indian Point 2.Safe Shutdown
Boric Acid
Operating Basis Earthquake
Earthquake
Fire Protection Program
ML20003C12231 January 1981Feasibility Study for Mod of Containment Cooling Sys.
ML20024B30630 April 1983Determining Portion of Regulatory Burden on Indian Point 3 Capital & O&M Expenditures 1976 - 1986:10-Yr Cost Projection Also Included.Hydrostatic
Probabilistic Risk Assessment
ML20063G05326 October 1981Evaluation of Prompt Alerting Sys for Indian Point Nuclear Power Station. NUREG/CR-2655, Evaluation of Prompt Notification Sys... & NUREG/CR-2654, Procedures for Analyzing Effectiveness for Alerting Public Encl
ML20065J67714 September 1982Testing & Repair of Siren Portion of Alert & Notification Sys for Indian Point Nuclear Power Generating Plant
ML20079N31631 July 1977Near-Field Effects of Once-Through Cooling Sys Operation on Hudson River Biota
ML20084B12230 March 1973Review of Replies to AEC Questions by Con Ed on Indian Point Unit 2 Safety & Relief Valve Installation ReanalysisLoop seal
ML20084B27511 October 1972Investigation & Consequences of Steam Generator Nozzle Debris Plug Assembly Being Inadvertently Left In-Place During Operation of RcsHydrostatic
ML20094E00226 July 1984Evaluation of Addl Issues Raised by NRC Re New York Pirg Petition to Suspend Operation of Indian Point,Units 2 & 3Earthquake
ML20094E00726 July 1984Addl Info Obtained from Ny State on New York Pirg Petition Which Suppls FEMA Rept to NRC
ML20151T46831 January 1988Experimental & Finite Element Evaluation of Spent Fuel Rack Damping & Stiffness
ML20151U99731 January 1986Status Rept:Indian Point Special Proceeding Decision CLI-85-06
ML20153F91628 April 1988Changes,Tests & Experiments - 1986High Radiation Area
Safe Shutdown Earthquake
Temporary Modification
Fire Protection Program
ML20155H25430 September 1988Rev 2 to Indian Point Unit 2 (NRC Bulletin 88-008 Thermal Stresses in Piping Connected to RCS) Indentification of Unisolable Piping & Determination of Insp LocationsNondestructive Examination
ML20196D30131 October 1988Reactor Vessel Matl Surveillance Program for Indian Point Unit 2 Analysis of Capsule V
ML20211G4113 July 1985Effective Max Beta Energy & Determination of RO-2,2A Response Factors