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A list of all pages that have property "Title" with value "Requests Addl Info Re Plant Design Criteria". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML20205F922  + (Requests Addl Info Re Operational QA Program to Complete Evaluation of Section 1.7 to 860701 Rev 7 to Updated Fsar. Justification for Addition of Paragraph to Section 1.7.1.7 Re Control of Purchased Matl Requested)
  • ML18031A113  + (Requests Addl Info Re Operator Licensing to Complete Review of Application for Operating Licenses)
  • ML19318B023  + (Requests Addl Info Re Organizational Changes Discussed in .Info Needed to Demonstrate That Changes Will Not Result in Less Effective QA Program)
  • ML19249A565  + (Requests Addl Info Re Organizational Description in Order to Complete Review of 780629 Application Requesting Approval of QA Program.Info Should Be Submitted within 30 Days)
  • ML20210P863  + (Requests Addl Info Re Origin of Blue Topaz Gems Imported from Brazil,Prior to Further NRC Inquiries W/Gemological Inst of America Into Radioactivity of Gems)
  • ML20054F274  + (Requests Addl Info Re Outlined Topics to Assist in Evaluation of License Renewal Request,Per 820521 Telcon.Info Should Be Submitted by 820630)
  • ML17212B567  + (Requests Addl Info Re Overpressure Mitigation Sys.Info Requested by 820517)
  • ML19319C143  + (Requests Addl Info Re Overpressurization Protection on Locking Out Power to Decay Heat Removal Isolation Valves by 770214.Review of Overpressurization & Staff Position Encl)
  • ML19326D512  + (Requests Addl Info Re PMF Level Analysis.Specific Request Encl)
  • ML19276F433  + (Requests Addl Info Re Packaging Containment Vessel Closure Bolt Matl & Sufficiency of Prescribed Torque to Maintain Seal)
  • ML19317F762  + (Requests Addl Info Re Packaging of Radioactive Matl Per 751107 Section of Application,If NRC Approval Deemed Necessary)
  • ML19249C205  + (Requests Addl Info Re Page Changes to Fundamental Nuclear Matl Control Plan.Determines That Pages Attached to Contains Info of Type Specified in 10CFR2.790)
  • ML20127B265  + (Requests Addl Info Re Part 21 Repts Issued by Tdi Since Apr 1984 Re Problems W/Emergency Diesel Generators.Info to Be Used in Preparation of SER to Close Out Tdi Engine Reliability Issues)
  • ML20041F490  + (Requests Addl Info Re Part 7.3, Item Control, of Revision 11 to Fundamental Nuclear Matl Control Plan)
  • ML20217F739  + (Requests Addl Info Re Peach Bottom Atomic Power Station Units 2 & 3 Appendix R Exemption Requests)
  • ML20248L132  + (Requests Addl Info Re Pedestrian Traffic on Parish Road 39, Property Values in Forest Grove & Center Spring & Impacts of Relocating Road on Property Values,To Support Staff Rev of Feis,Per CLI-98-3 Addressing NEPA Contentions)
  • ML19344E971  + (Requests Addl Info Re Permanent Dewatering Sys Proposed for Site Per Hydrologic & Geotechnical Engineering Branch Review)
  • ML19269E874  + (Requests Addl Info Re Physical Security Plan for Review of OL Application.Security Info Withheld (Ref 10CFR2.790))
  • ML20137W993  + (Requests Addl Info Re Pilgrim Nuclear Power Station,To Credit Containment Overpressure in Net Positive Suction Head Analysis for ECC Pumps Generated as Result of NRC Staff Review of Licensee Info Submitted on 970120)
  • ML13333A329  + (Requests Addl Info Re Pipe Breaks Inside Containment. Forwards Ltr Summarizing Current Criteria Re Pipe Breaks for SEP Plants)
  • ML19345C903  + (Requests Addl Info Re Piping & Instrumentation Diagrams for Review of Application Re Inservice Insp of Pressure Isolation Valves.Conformance to Encl Mechanical Engineering Branch Position Should Be Discussed)
  • ML19247B269  + (Requests Addl Info Re Plans to Determine Actual Chemistry of Closure Head Weld & Rept on Elevated Temp Data.Schedule for Response Should Be Provided as Soon as Possible)
  • ML17053A417  + (Requests Addl Info Re Plans to Install Radioactive Waste Solidification & Handling Sys in Order to Complete NRC Review.Encl Questions to Be Answered & Submitted by 790301)
  • ML17333A617  + (Requests Addl Info Re Plant Amend Request to Incorporate 2 Volt SG Tube Support Plate Repair Criterion)
  • ML18036B049  + (Requests Addl Info Re Plant Component & Piece Parts Qualification Program,Per & 0915 Meeting to Discuss Util Proposal)
  • ML20127K546  + (Requests Addl Info Re Plant Design Criteria)
  • ML17348B315  + (Requests Addl Info Re Plant Individual Plant Evaluation Final Rept.Addl Questions Encl.Response Requested within 30 Days of Receipt of Ltr)
  • ML17341A587  + (Requests Addl Info Re Plant Layout for Use in Review of Containment Sump Performance.Burns & Roe & Table 1 Overview of Info Re Unresolved Safety Issue A-43 Encl)
  • ML20245H232  + (Requests Addl Info Re Plant Reactor Cavity Neutron Dosimetry Program for Review.Response within 45 Days Requested)
  • ML20125A882  + (Requests Addl Info Re Plant Reliance on Control Room Operators Not to Take Action in Specific Time Periods.Info Requested within 30 Days of Receipt of Ltr)
  • ML20045B958  + (Requests Addl Info Re Plant Request for Amend Revising TS to Permit Use of SAFER/GESTR-LOCA Methodology for Accident Analyses)
  • ML20045B800  + (Requests Addl Info Re Plant Response to GL 92-08, Thermo- Lag 330-1 Fire Barriers)
  • ML20057F156  + (Requests Addl Info Re Plant Response to GL-92-01,Rev 1 on Chemistry Contents of Beltline Matls Under Question 2.b.5)
  • ML19332G271  + (Requests Addl Info Re Plant Staff Experience to Determine If Util Meets Commitment for Hot Operating Experience Described in Util .Listed Info Should Be Provided by 891229)
  • ML20236U995  + (Requests Addl Info Re Plant TS Change Request 356,increase in Allowable Main Steam Isolation Valve Leakage Rate)
  • ML20058P180  + (Requests Addl Info Re Plant Third 10-yr Interval Inservice Insp Program Plan & Associated Requests for Relief within 60 Days of Ltr Receipt)
  • ML20133B428  + (Requests Addl Info Re Plant Third 10-yr ISI Program Plan Associated Requests for Relief from ASME Boiler & Pressure Vessel Code,Section Xi.Response to Be Submitted within 60 Days of Ltr Receipt)
  • ML17332A912  + (Requests Addl Info Re Plant,Units 1 & 2,circumferential Cracking of SG Tubes)
  • ML20129E034  + (Requests Addl Info Re Porous Concrete sub-foundation at Unit 3)
  • ML20215M067  + (Requests Addl Info Re Portion of Direct Testimony of Dt Hartgen & Rc Millspaugh in OL-3 Proceeding.Info Requested Includes Similar Info on Cars Re Traffic Assignment Model. Related Correspondence)
  • ML19210B226  + (Requests Addl Info Re Possession & Use of Snm.Proposed Mod of Std OL & Sample Addition to Tech Specs Which Will Be Required Encl)
  • ML20206A753  + (Requests Addl Info Re Possibility of Gaps Forming in Boraflex in Facility Spent Fuel Pool Storage Racks & Description of Measuring Techniques for Detecting Degraded Boraflex in Inservice Surveillance Program)
  • ML19209B442  + (Requests Addl Info Re Possibility of Main Steam Line Break Inside Containment as Result of Overpressurization of Containment at Sites)
  • ML15238A534  + (Requests Addl Info Re Postulated Radiation Levels Assumed in 810918 Response to Request for Environ Qualification of Equipment Info)
  • ML19339A871  + (Requests Addl Info Re Postulated Spent Fuel Cask Drop Accident Evaluation.Description of Accident Consequences, Cask Handling & Transfer Operations, & Yard Crane Sys Mods Basis & Details Requested Before 721028)
  • ML19220B932  + (Requests Addl Info Re Potential Addl Energy Release from Steam Generators After Reflooding of Core in Analysis of Postulated Reactor Coolant Sys Cold Leg Pipe Breaks)
  • ML20003F996  + (Requests Addl Info Re Potential Effects of Quarry Blasting on Curing Concrete for Class I Structures at Facility)
  • ML20151Z709  + (Requests Addl Info Re Potential Improper Disposal of Licensed Matl,Per Listed Questions & Insp Rept 50-271/88-09, Specifically NRC Recommendations Re Disposition of Estimated 13,500 Cubic Ft of Sludge)
  • ML20004F989  + (Requests Addl Info Re Potential Transport Through State of Mi of Irradiated Nuclear Fuel Elements.Also Requests That NRC Suspend All Shipments Through State,Pending Satisfactory Resolution of Concerns)
  • ML19326A223  + (Requests Addl Info Re Potential for Excessive Control Rod Guide Tube Wear at Facilities Using B&W Design)
  • ML20041G285  + (Requests Addl Info Re Power Sys.Info Required for Continued Review of Application for CP)
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