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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20059L086 | 7 September 1990 | Forwards Sys Operability Rept Commonwealth Edison Zion Nuclear Station Component Cooling Water Sys, to Document Completion of Statement of Work | |
| ML17261A854 | 13 January 1989 | Discusses 890110-11 Meetings Re Nozzle Sizing Study.Most Accurate Sizing Obtained by Collecting Data of Edge Diffracted Waves from Geometric Extremities of Flaw | |
| ML19324A111 | 19 May 1988 | Forwards Memo Describing Results of Testing of Plant Bolting Matls Under FIN A-3866,Task Assignment 12 | |
| ML19324B270 | 2 March 1988 | Forwards Rept on Metallurgical Evaluation of Five Bolts Obtained from Farley Plant.Bolts Found Acceptable | |
| ML18151A064 | 8 September 1987 | Forwards Comments on Review of Plant Scenario.Scenario Should Support Reasonable Demonstration of Licensee Emergency Response Capability.No Major Deficiencies Noted | |
| ML20207R757 | 10 March 1987 | Forwards Technical Evaluation Rept Input for South Texas Initial Plant Test Program Through FSAR Amend 56,Feb 1987 Sser & & Beaver Valley Unit 2 Initial Plant Test Program Through FSAR Amend 15 & Nov 1986 Sser | |
| ML20207S500 | 6 March 1987 | Forwards Technical Evaluation Repts for Domestic Mark III Plants (Grand Gulf,Clinton,River Bend & Perry) & Gessar Ii. Inserts to Be Included in Section 6.2.1.8 of Draft Sser 2 for Clinton,River Bend & Perry Plants Also Encl | |
| ML20195F865 | 31 October 1986 | Forwards Request for Addl Info Re MSIV Operability at Facility,Based on Initial Review of Util Rept Entitled, Final Rept 10CFR50.55(e) MSIV Actuators, Forwarded by Util | |
| ML20206H321 | 10 September 1986 | Forwards Summary Repts from 860811-14 Visit to Kewaunee Nuclear Station & 851002-03 Visit to Cooper Nuclear Station Re Generic Issue 83 on Control Room Habitability | |
| ML20206J600 | 8 August 1986 | Advises That NUREG-0956 Support Calculations Using ORNL Trends Code to Evaluate Influence of Containment Chemistry or Retention of Hi Can Also Provide Useful Info for General NUREG-1150 Issue Paper,Per Telcon Discussion | |
| ML20206H113 | 23 June 1986 | 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 | |
| ML20215N437 | 25 April 1986 | Submits Trip Rept of 860414-16 Site Visit W/Util & NRC for FIN A-3839 Re Welding Concerns.List of Attendees Encl | Nondestructive Examination |
| ML20215N433 | 18 March 1986 | Submits Trip Rept of 860226-28 Visit to Facilities in Conjuction W/Duties as Expert Welding Team Members on FIN A-3839, Evaluation of Welding Concerns at TVA Operating Reactors | |
| ML20214E172 | 25 February 1986 | Ack Receipt of 860210 & 21 Ltrs Accepting Task Orders 3 & 4 Under FIN A-3552 & Task Order 5,respectively.Orders Include Work at Palisades & LaSalle Stations & Mod Review at Davis-Besse.Modified Task Order 4 Under FIN A-3550 Encl | |
| ML20206J252 | 24 January 1986 | Forwards Early Draft of Executive Summary from Analysis of Station Blackout Accidents for Bellefonte PWR, Per Request. Initial Draft of Rept Scheduled to Be Completed by 860315 | |
| ML20206J368 | 15 January 1986 | Discusses Latest Calculations of Molecular Iodine (I2) & Organic Iodide (CH3I) Scrubbing During TC1 Sequence from Draft Plant Rept | |
| ML20136F477 | 31 December 1985 | Forwards PNL-5718, Review of Tdi Diesel Generator Owners Group Engine Requalification Program,Final Rept, Technical Evaluation Rept | |
| ML20206J403 | 13 December 1985 | Summarizes Preliminary Scoping Calculations for Molecular Iodine (I2) Scrubbing in BWR Pressure Suppression Pools. Calculations Made for Most Recent TC1 Sequence in Draft Plant Rept | |
| ML20133A314 | 27 September 1985 | Forwards Review of Section 4.7 of Technical Evaluation Rept PNL-5600, Review of Resolution of Known Problems in Engine Components for Tdi Emergency Diesel Generators, Reflecting Views Re Crankshafts for 16-cylinder Engines | |
| ML18143B362 | 17 July 1985 | Responds to Request for Estimate of Probability That Break Outside Containment During V Sequence at Facility Will Be Submerged.Best Estimate Probability Lies Between 50% & 90%, Depending on Operator Reaction.Lpsi Sys Diagrams Encl | |
| ML20128H737 | 27 June 1985 | Forwards Rev 1 to Review of Engine Base & Bearing Caps for Tdi DSRV-12,DSRV-16 & DSRV-20 Diesel Engines, Technical Evaluation Rept | |
| ML20141N298 | 29 May 1985 | Requests Listed Addl Info Re S&W 1982 Rept, Ultimate Pressure Capacity of Shoreham Primary Containment | |
| ML20126E872 | 24 May 1985 | Forwards PNL-5200-3, Review of Emergency Diesel Generator Engine & Auxiliary Module Wiring & Terminations, Dtd May 1985 | |
| ML20133N772 | 27 March 1985 | Forwards Info Telecopied on 850325 Re Locational Distribution of Three Fission Product Species for Surry V Sequence & Time Dependent Release for Fission Product Groups for Peach Bottom | |
| ML20214F510 | 13 March 1985 | Forwards List of Questions Re Plant Pra,Per 850512 Telcon. Statement of Work, Review of PRA for Seabrook Nuclear Power Plant, Encl | Probabilistic Risk Assessment |
| ML20133N346 | 20 February 1985 | Discusses Review of March Results for Surry & Peach Bottom Sequences,In Order to Quantify Expected Noble Gas Releases. March Model Appropriate for Behavior of Noble Gases | Hydrostatic |
| ML20134A101 | 20 February 1985 | Submits Results of Noble Gas Release Sequences Using March Code for Facilities | |
| ML20128P340 | 5 December 1984 | Submits Rept for Task 1 Per M Silberberg 841116 Memo Re Concerns Re Lanthanum Releases in BMI-2104.Discusses Discrepancies in Corcon Calculations,Presents Revised Tables 6.14 & 7.16 & Recommends Reanalyses | |
| ML20138N697 | 18 September 1984 | Forwards Repts Re Irradiation,Decontamination & DBA Testing, Per Request of Y Korobov of Carboline Co | Boric Acid Coatings |
| ML20134E159 | 2 August 1984 | Forwards Brief Summary Rept on Leakage Characteristics of Nuclear Containment Hatches During Severe Accident. Draft of Complete Rept Will Be Mailed Later in Aug | Finite Element Analysis |
| ML20127B922 | 20 July 1984 | Forwards PNL-5201, Review & Evaluation of Tdi Diesel Engine Reliability & Operability - Grand Gulf Nuclear Station, Unit 1 | Shutdown Margin |
| ML20127B888 | 21 May 1984 | Comments on May 1984 Draft Tdi Diesel Generator Owners Group Program Plan.Full Insp of One Engine to Owners Group Spec Recommended | |
| ML20093G482 | 2 May 1984 | Provides Summary of Battelle Subcontract W/Tdi to Evaluate Special Silicon carbide-impregnated Cylinder Liners & Piston Rings.Task Does Not Involve Dependability Tests of Tdi Engines.No Apparent Conflict Found | |
| ML20113A020 | 4 April 1984 | Forwards Requests for Addl Info Developed During Review of FSAR Chapter 14 Re Initial Plant Test Program.Review Conducted Through Amend 4.Listing of Items Requiring Resolution Encl | Safe Shutdown Ultimate heat sink |
| ML20117C942 | 3 April 1984 | Forwards Proposed Radiological Source Term Input for Facility.Encl Amended to Reflect NRC Suggested Changes | |
| ML20093C528 | 30 March 1984 | Forwards Audit of Susquehanna Unit 2 Tech Specs, Technical Evaluation Rept | |
| ML17320A971 | 6 March 1984 | Forwards First Round Questions Following Evaluation of Exxon Rept, Steam Tube Rupture Incident at Prairie Island Unit 1, PTSPWR2 Vs Data,Preliminary Benchmark Analysis. | |
| ML17320A974 | 5 March 1984 | Forwards First Round Questions on Exxon Methodology Rept for PTSPWR2.Rept Lacks Specific Details Re Biases in Initial Conditions & Boundary Conditions | |
| ML20128N657 | 22 February 1984 | Comments on Draft Vols IV-VI of BMI-2104,presented at Peer Review 840126 & 27 Meetings.Comments Concern Completed Calculations for Sequoyah Ice Condenser Plant,Recalculated Surry Results & Completed Calculations for Zion Plant | |
| ML19306A015 | 10 February 1984 | Summarizes 840206-07 Visit to Nevada Test Site Hydrogen Burn Facility to Inspect Condition of Equipment & Cable/Splice Samples After Series of Hydrogen Burn Tests Conducted by Epri.No Indication of External Damage to Equipment Noted | |
| ML17320A973 | 22 November 1983 | Forwards First Round Questions on Mods to Exxon Draft Repts, PTSPWR2 Mods for St Lucie Unit 1 & Description of Exxon Plant Transient Simulation Model for Pwrs. | |
| ML17320A972 | 30 September 1983 | Forwards First Round Questions on Exxon Plant Transient Code,Based on Review of Proprietary Rept, Description of Exxon Nuclear Plant Transient Simulation Model for Pwrs. | |
| ML20080B563 | 12 August 1983 | Forwards Draft Preliminary Review of Limerick Generating Station Severe Accident Risk Assessment,Vol I:Core Melt Frequency. Rept Satisfies Milestone for Task 1 of Project 3 Under FIN A-3393 | Fire Barrier Probabilistic Risk Assessment Earthquake |
| ML20211D597 | 11 April 1983 | Forwards Summary of Independent Development of Finite Element Models & Determination of Natural Frequencies for Piping Problems in Containment Spray Discharge Line & Accumulator Loop 4 | |
| ML20132B496 | 11 February 1983 | Forwards Evaluation of Generic Key Indicators for Project Engineering/Design Activities at Facilities | Safe Shutdown Non-Destructive Examination Hydrostatic Coatings Nondestructive Examination Stolen |
| ML20072L710 | 20 December 1982 | Forwards BNL 821213 Memeo Re Degraded Core Accidents at Facilities,Per Task III.3 Defined in Design Basis for Hydrogen Control Sys in CP & OL Applications. No-cost Extension to Contract Requested | |
| ML20079J564 | 16 December 1982 | Summarizes Findings of 821207-08 Plant Tour Re Use of PORVs or Depressurization Scheme for Removing Decay Heat.Addl Info Requested Includes General Arrangement & Isometric Drawings of Piping Near San Onofre Pressurizer | |
| ML20027D175 | 18 October 1982 | Responds to 820806 Request to Evaluate Rapid Depressurization & DHR Sys for C-E Plants W/O Porvs, Discussing Role of Task Action Plan A-45, Shutdown Heat Removal Requirements, in Supporting Evaluation of Facility | |
| ML20126F479 | 1 October 1982 | Requests Permission to Observe Upcoming Types A,B & C Tests at Listed Facilities,Per FIN B-0489, Containment Leak Rate Testing | |
| ML20072L685 | 21 September 1982 | Forwards Analysis of Full Core Meltdown Accidents in Grand Gulf Reactor Plant, Draft Informal Rept.Rept Satisfies Preliminary Rept Milestone for Task I Defined in Safety Evaluation of Core Melt Accidents:Cp,Ml & OL Applicants |