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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- ML18018B655 + (Forwards Addl Info Re Equipment Qualification Program,Per 840321 Request.Summary of Radiation Considerations for Equipment Qualification in Mild/Harsh Environs Also Encl)
- ML20211K967 + (Forwards Addl Info Re Equipment Qualification Under Superheat Conditions,Including Response to Seven NRC Questions & Discussion of Modeling Methodology & Heat Transfer Coefficient Used,Per 870120 Request)
- ML20050C840 + (Forwards Addl Info Re Equipment Qualification,In Response to NRC 820125 Request)
- ML20070D253 + (Forwards Addl Info Re Equipment Survivability Per 821209 Telcon Request,Revising 821129 Submittal.Core Exit Thermocouples Located within Pressure Vessel & Not Exposed to Hydrogen Burning)
- ML19345B142 + (Forwards Addl Info Re Eruption of Mount St Helens & Effect on Facility Per 801030 Request)
- ML18018B650 + (Forwards Addl Info Re Essential Svcs Chilled Water Sys,In Response to NRC 840411 Request)
- ML20028B390 + (Forwards Addl Info Re Evaluating Voltage Drops in Relation to Adequacy of Station Electric Distribution Sys Voltages)
- ML20202H282 + (Forwards Addl Info Re Evaluation & Disposition of Potential Concerns Relative to Pressure Locking And/Or Thermal Binding for 24 Valves Identified in Insp Repts 50-424/97-04 & 50-425/97-04)
- ML17261A605 + (Forwards Addl Info Re Evaluation Performed to Determine Min Accuracy Requirements Necessary to Fully Benefit from Reactor Vessel Level Indication Sys,Per NUREG-0737,Item II.F.2 Justification for Sys Accuracy of 10%)
- ML17261A606 + (Forwards Addl Info Re Evaluation Performed to Determine Min Accuracy Requirements Necessary to Fully Benefit from Reactor Vessel Level Indication Sys,Per NUREG-0737,Item II.F.2 Justification for Sys Accuracy of 10%)
- ML17304A430 + (Forwards Addl Info Re Evaluation Results for Auxiliary Feedwater Pumps & Status of Review for Remaining Pumps,Per NRC Bulletin 88-004 Concerning Potential Loss of safety- Related Pumps Due to Deficiencies in Flow Design)
- ML19260B610 + (Forwards Addl Info Re Evaluation of Impact of NRC Proposed Rupture/Blockage Model Used in Vendor Evaluation Model. No Adverse Impact from New Rupture Burst Data or Use of NRC Rupture/Blockage Model on Licensing Calculation Results)
- ML20065S843 + (Forwards Addl Info Re Evaluation of Loss of Offsite Power, Per 901113 Response to Station Blackout Safety Evaluation. Rev to SE to Reflect Info & Reestablish Coping Duration as 4 H Requested)
- ML13322A993 + (Forwards Addl Info Re Evaluation of Transient Response of Crankshaft Under Various Assumed Conditions,Per 890427 Telcon W/Nrc Re Rept FaAA-84-12-14,Rev 1.0)
- AECM-81-335, Forwards Addl Info Re Evaluations of Class IE Electrical Equipment,Per NUREG-0588 + (Forwards Addl Info Re Evaluations of Class IE Electrical Equipment,Per NUREG-0588)
- ML20042G822 + (Forwards Addl Info Re Events Leading to 900509 Emergency Tech Spec (TS) Request Re TS 4.6.1.8,per Ds Hood 900510 Telcon & Requests That Changes Also Be Made to Unit 2 Ts. Proposed TS Encl)
- ML20209F916 + (Forwards Addl Info Re Exceptions to Reg Guide 1.97.Portable Instrumentation Used for post-accident Surveys Determine Whether or Not Areas Surveyed Available for Access During post-accident Conditions)
- ML20148D134 + (Forwards Addl Info Re Exemptions from Requirements Previously Unacceptable Covering Personnel Airlock,Bellows Leakages & Water Testing for Feedwater Check Valves.W/ Oversize Drawings)
- ML20127H550 + (Forwards Addl Info Re Existing Fire Protection Provisions at Facility W/Recommendations Contained in Standard Review Plan 9.5.1)
- ML19323G846 + (Forwards Addl Info Re Extended Operation of Lwbr Core in Shippingport Power Station,Per 800508 Request.Releases of Radioactiivity Continue to Be Below Applicable Stds as Documented in Annual Environ Repts)
- ML17053D747 + (Forwards Addl Info Re FSAR & Environ Rept - OL Stage Per NRC 830329 Request.List of Repts Submitted Encl)
- ML18003A913 + (Forwards Addl Info Re FSAR Amend 5 Per NRC Request.Info Includes Responses to Safety Review Questions,Revs to Reg Guide Positions in FSAR Chapter 1 & Revs to Nuclear Operations Dept Organization)
- RBG-16-702, Forwards Addl Info Re FSAR Changes & Supplemental Clarifications to Previously Submitted Responses,Per 820202 & 831114 Requests.Fsar Changes Will Be Included in Next Amend + (Forwards Addl Info Re FSAR Changes & Supplemental Clarifications to Previously Submitted Responses,Per 820202 & 831114 Requests.Fsar Changes Will Be Included in Next Amend)
- SNRC-1101, Forwards Addl Info Re FSAR Chapter 13, Conduct of Operations, Submitted as Part of Amend 51 to License Application.Resumes for Watch Engineers Assigned to Shift Crews Encl,Per Reg Guide 1.8 + (Forwards Addl Info Re FSAR Chapter 13, Conduct of Operations, Submitted as Part of Amend 51 to License Application.Resumes for Watch Engineers Assigned to Shift Crews Encl,Per Reg Guide 1.8)
- ML20246H495 + (Forwards Addl Info Re FSAR Chapter 8 Review,Including Calculation & Test Results for Esf,Per Ci Grimes 890216 Request.Validity of Mathematical Model Used in Performance of Voltage Profile Established)
- ML20236D896 + (Forwards Addl Info Re FSAR Chapter 8 Review,Per 890216 Request)
- TXX-8901, Forwards Addl Info Re FSAR Review of 3.11,per 881116 Request + (Forwards Addl Info Re FSAR Review of 3.11,per 881116 Request)
- ML20052F565 + (Forwards Addl Info Re FSAR Round 1 Question 430.17 on Diesel Generator Load Sequencing Sys)
- ST-HL-AE-1712, Forwards Addl Info Re FSAR Section 15.2.8, Feedwater Sys Pipe Break, Incorporating Revised Analyses for Feedwater Line Break Transient.Revs Will Be Incorporated in Upcoming Amend to FSAR + (Forwards Addl Info Re FSAR Section 15.2.8, Feedwater Sys Pipe Break, Incorporating Revised Analyses for Feedwater Line Break Transient.Revs Will Be Incorporated in Upcoming Amend to FSAR)
- ML20003E584 + (Forwards Addl Info Re FSAR Section 4.2 Re Fuel Sys Design in Response to NRC 810225 Request.Significant Wear of Clad or Grid Supports Is Not Expected During Life of Fuel Assembly)
- ML20050A347 + (Forwards Addl Info Re FSAR Sections 4.4,6.1,7,8,9.5 & 13 for SER Reviews,In Response to NRC Request.Items Addressed Include Loose Part Monitoring Sys,Disodium Phosphate & Time Delay Generator Breaker Closing)
- ML19341C577 + (Forwards Addl Info Re FSAR for Facilities,In Response to NRC 810107 Request.Info Provided Re leak-tightness of Control Room,Toxic Gas Protection,Control Room Emergency Ventilation Sys & Habitability Sys)
- ML20206F222 + (Forwards Addl Info Re Facility & Status Rept for Performance Enhancement Program in Response to 860523 Request)
- ML20195F665 + (Forwards Addl Info Re Facility 10CFR50,App R Ltrs 5211-87-2028 & 5211-87-2034,dtd 870210,per 880907 Request. Info Re Open Items Concerning NRC Review of TMI-1 Associated Circuits Studies (as Identified in Insp Rept 50-289/86-23))
- ML112370648 + (Forwards Addl Info Re Facility Compliance w/10CFR50,App I, Per 760903 Request.W/Eight Oversize Drawings)
- NRC-87-0074, Forwards Addl Info Re Facility Conformance W/Provisions of TMI Action Plan Item II.K.3.28, Verify Qualification of Accumulators on Automatic Depressurization Sys Valves, Per NRC 861205 Request + (Forwards Addl Info Re Facility Conformance W/Provisions of TMI Action Plan Item II.K.3.28, Verify Qualification of Accumulators on Automatic Depressurization Sys Valves, Per NRC 861205 Request)
- ML18153C370 + (Forwards Addl Info Re Facility Containment Isolation Valve Type C Test,Per 900914 10CFR50,App J Exemption Request)
- ML20055D348 + (Forwards Addl Info Re Facility Crdr & Isap,Including Justification for Human Engineering Discrepancies Dispositioned for No Corrective Action)
- ML20148F312 + (Forwards Addl Info Re Facility Environ Rept Requested in NRC 800610 Ltr.Addl Distribution of Info Has Been Completed Per NRC 800806 Instructions)
- ML20148F308 + (Forwards Addl Info Re Facility Environ Rept Requested in NRC .Addl Distribution of Info Has Been Completed Per NRC 800806 Instructions)
- ML20002C450 + (Forwards Addl Info Re Facility Fire Hazards Analysis Per NRC 780329 Request)
- ML19345B146 + (Forwards Addl Info Re Facility Fire Protection Program,Per NRC 800324 request.Twenty-one Oversize Drawings Encl)
- ML20203K133 + (Forwards Addl Info Re Facility Phase II Welding Project Repts,Per NRC 860610 Request)
- ML19344D650 + (Forwards Addl Info Re Facility Preservice Insp Program in Response to NRC 800403 Request.Insp Plan for Class 1 & 2 Components Presented Which Identifies Items to Be Inspected)
- ML20238C388 + (Forwards Addl Info Re Facility Radiological Emergency Plan, in Response to NRC Request During 871215 Site Visit.Info on Alternate Alerting Sys Design for City of Newburyport,Ma Suppls Info Provided in Util)
- ML20234F402 + (Forwards Addl Info Re Facility Responses to IE Bulletin 85-003,per NRC 870818 Request.Water Hammer Due to Valve Closure Not Considered in Determination of Differentials for Valves Listed in 860730 Response)
- BECO-88-076, Forwards Addl Info Re Facility Restart Plan Requested by R Blough During 880504 Telcon W/R Ledgett,Consisting of Current Status of Performance Excellence Indicators & Current Organization Chart.Addl Info Will Be Provided + (Forwards Addl Info Re Facility Restart Plan Requested by R Blough During 880504 Telcon W/R Ledgett,Consisting of Current Status of Performance Excellence Indicators & Current Organization Chart.Addl Info Will Be Provided)
- ML20212L307 + (Forwards Addl Info Re Facility safety-related motor-operated Valve Program,Per NRC 870219 request.Motor-operated Valve Program,Revised to Incorporate New Info & Response to IE Bulletin 85-003 Also Encl)
- ML17192A630 + (Forwards Addl Info Re Failure of Control Rods to Insert Fully on Scram in Response to NRC 800110 & 11 Ltrs.Dresden 1 Experienced No Control Rod Failures in 1978-79.Failure at Other Facilities Caused by Leakage Past Worn Piston Seals)
- ML20199B993 + (Forwards Addl Info Re Failure of a 12 Wt% Triga Fuel Element in Air,In USGS Facility Reactor Bay,Per 970909 Request.Info Being Executed IAW 10CFR50.30(b) as Signed Original Under Oath or Affirmation & Is Reanalysis of Info in)
- ML20248J946 + (Forwards Addl Info Re Failure to Identify Functional Failures on Main Steam Sys.Info on Insp Item Re Performance of Periodic Assessment of Maintenance Effectiveness as Required by 10CFR50.65(a)(3))