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A list of all pages that have property "Title" with value "Discusses Re Review of Topical Programs". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

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  • ML20247H237  + (Discusses Re NRC CAL 97-7-006,dtd 970624 & CAL Suppl .Actions Which Have Been Taken or Will Be Taken to Correct Issues Identified & Initiatives Taken to Correct Safety & Quality Attitude at Facility,Acceptable)
  • ML20203C590  + (Discusses Re NRC Determination to Grant Pending Request for Confidential Treatment Under 10CFR2.790. Correction of Transcript Citation to Read, See Tr at 437, Also Discussed)
  • ML20128C163  + (Discusses Re Nonconformances W/Mine Safety Appliances Co Ultraview & Ultratwin negative-pressure Facepieces)
  • ML20216B390  + (Discusses Re Number of Issues Related to Proposed Pilot Programs to Improve Efficiency & Effectiveness of NRC Regulatory Framework,Staff Proposed Acceptance Guidelines Described in Draft RG DG-1061 & Request to Consider CDF)
  • ML20023C864  + (Discusses Re Pending Administration Action Against Nuclear Pharmacy,Inc (Npi).Doj Currently Reviewing Matter.No Operating Restrictions Placed on Licensee)
  • ML19254D898  + (Discusses Re Plans for Implementing Requirements of 40CFR190.Beginning 791201,prior to Issuance of Semiannual Radioactive Effluent Rept,Offsite Doses Due to Liquid & Gas Will Be Calculated Per NUREG-0133)
  • ML20245C892  + (Discusses Re Plans to Wash & Recertify Low Enriched UF6 Cylinders within Southwest Plant Expansion for Relocated Scrap Recovery.Attachments in Accordance w/870812 Discussion)
  • ML19343D397  + (Discusses Re Possible Breaks in GE Cooling Sys. Postulated Problem Applies to GE BWRs But Does Not Apply to Getr Since Reactor Is Electromechanical Sys)
  • ML19246B539  + (Discusses Re Potentially Atypical Reactor Vessel Weld Matl.Per B&W 790313 Assessment of Matl as Adequate, Requests Concurrence in Shifting 130 F Min Boltup Temp Back to 100 F)
  • ML20137N326  + (Discusses Re Presentation of Industry Views on U Mill Tailings.Issue of Demonstrating Significance of Radon Risk from Tailings Issue Before Tenth Circuit Court)
  • ML20138F370  + (Discusses Re Pressurized Thermal Shock Evaluation for St Lucie Units 1 & 2.Requests Review of Proprietary & non-proprietary Copies of CEOG Rept CEN-405-P,rev 2, Application of Reactor Vessel Surveillance Data)
  • ML20207D737  + (Discusses Re Process for Reclassification of non- Risk Significant Components.Forwards Concerns & Cautions for Consideration Based on Limited Review of Reclassification Process Overview That Was Provided)
  • ML20090H504  + (Discusses Re Proposed Amend to Licenses NPF-9 & NPF-17 to Allow Spent Fuel Pool Storage Capacity Expansion.Reemphasizes That Schedule Must Be Maintained to Complete All Rerack Work Prior to First Refueling)
  • ML20140H250  + (Discusses Re Proposed Change 1 to TS, License DR-15 for SEFOR Reactor.Change Would Permit Use of New Thermocouples Installed in Nickel Reflector Segments or Existing Thermocouples in Aluminum Guide Structure)
  • ML20029D347  + (Discusses Re Proposed Const of Bldg Located within Controlled Access Area at Facility in Wilmington,Nc)
  • ML17354B093  + (Discusses Re Proposed Emergency Action Level Change to Table 3-1 of Emergency Classification Table in Turkey Point Plant Emergency Plan)
  • ML19249A327  + (Discusses Re Proposed Mods & Expansion,Which Stated No Addl Info Will Be Submitted.Notes Some Relevant Sections of Fundamental Nuclear Matl Control Plan That Will Require Revision & Approval Prior to Beginning Operations)
  • B10788, Discusses Re Proposed Revs to Tech Specs for Cycle 6 Reload.Current Tech Spec Limits Provide Acceptable Margin of Safety  + (Discusses Re Proposed Revs to Tech Specs for Cycle 6 Reload.Current Tech Spec Limits Provide Acceptable Margin of Safety)
  • ML17352A444  + (Discusses Re Proposed performance-based Approach for Resolving Thermo-Lag Fire Barrier Issues at Plants)
  • ML20154A159  + (Discusses Re Radiological Risks & cost-benefit Considerations for Nuclear Power Reactors,Yucca Mountain & Waste Isolation Pilot Plant.Info Forwarded to Appropriate Ofc)
  • ML20235D049  + (Discusses Re Release of Radioactivity from Nuclear Power Reactor Proposed for Bodega Head.Aec Requires That Licensee Comply W/Encl 10CFR20 Regulation Stds for Protection Against Radiation)
  • ML19305E348  + (Discusses Re Request for Change in Tech Spec 3.7.E.1 Value for Drywell Suppression Chamber Differential Pressure from 1.47 Psid to 1.1 Psid.Requests Another Change to Tech Spec to Value of 1.0 Psi)
  • ML20211L599  + (Discusses Re Request for Confirmation That Dept Has Legal Authority to Withhold pre-decisional NRC Info from Public Disclosure Under State Public Disclosure Laws)
  • ML19340A720  + (Discusses Re Request for Exemptions from Requirements of App J.Requests Addl Info within 60 Days to Continue Review of Request)
  • ML20216F735  + (Discusses Re Request for Renewal of License TR-2)
  • ML20199E683  + (Discusses Re SP-98-097,protection of Identity of Allegers from Public Disclosure,Requesting Info of Illinois Laws,Procedures or Policies Involving Disclosure of Allegers Identity)
  • ML20112A922  + (Discusses Re Schedule for Considering & Implementing Full Power Operating Authority.Rp Barkhurst Affidavit Re Power Ascension Testing Program & Delay of Operating Authority Encl.Related Correspondence)
  • ML20059L057  + (Discusses Re Staff Interim Fatigue Curves from NUREG/CR-5999, Interim Fatigue Design Curves for Carbon Low-Alloy & Austenitic Stainless Steels in LWR Environments, as Well as Other Related Comments)
  • ML14183A360  + (Discusses Re Status of Decommissioning Funding for Plants.Explanation to Clarify Several Statements Made Requested)
  • ML19347F231  + (Discusses Re Support for True Intervenorship. Only ASLB Can Authorize Contentions or Stipulations. J Mcphillips Is Only Authorized Safe Energy Alliance of AL Representative)
  • ML20003D938  + (Discusses Re Testimony to Have Been Given at Public Hearing on 810311.Individuals Will Be Allowed to Make Oral Comments by Appointment During Course of Public Hearings)
  • ML20106F582  + (Discusses Re Understanding Beck Might Sign Protective Order.Necessity of Ltr Not Understood.Tactics Engender Distrust,Placing Unnecessary Burden on Communications Between Counsel.Related Correspondence)
  • ML20137A712  + (Discusses Re Us Origin Nuclear Items Concerned Will Be Subject to All Terms & Conditions of Agreement for Cooperation Concerning Civil Uses of Atomic Energy Between Govt of Republic of Korea & Govt of Us)
  • ML20214R628  + (Discusses Re Value Engineering (Ve) Objectives for Umtrap.Nrc Decision Not to Participate Directly in Umtrap Ve Efforts Should Be Reconsidered)
  • ML17291A407  + (Discusses Re Withdrawal of Amend Request for WNP-2)
  • ML20211J684  + (Discusses Re Withholding of Proprietary Emergency Plan Info Under Provisions of 10CFR2.790.Requests All Individuals Shown on Distribution Lists to Take Action to Ensure Confidentiality of Proprietary Info,Per)
  • ML19248D709  + (Discusses Reaction of Skirpa Granite in Sweden to Heat Applied to Bore Holes.Recommends That Experiments at Skirpa Include Steel Casing of Drill Holes)
  • ML19256F212  + (Discusses Reaction to Intervenor 791203 Motion to Compel Discovery.Nrc Has Responded Beyond Legal Obligation.Motion Violates Understanding Between Parties.Requests Listing of Nexus Between Eighth Set of Interrogatories & Contentions)
  • ML19270H189  + (Discusses Reactivation of Environ Review of CP Application. Forwards Proposed Outline of Need for the Plant Section of Fes Suppl)
  • ML20247Q895  + (Discusses Reactivity Coefficients Test at Power Scheduled to Be Performed Between 258 & 300 EFPDs to Provide More Accurate Reflection of end-of-cycle Core Behavior.Plant Core Will Reach 258 EFPDs on or About 890613)
  • HNP-95-083, Discusses Reactor Auxiliary Bldg Emergency Exhaust Sys Design & Licensing Basis Issues.Description of Proposed Changes to FSAR Which Incorporate Results of Dose Assessment Reanalysis & Details of Administrative Controls Encl  + (Discusses Reactor Auxiliary Bldg Emergency Exhaust Sys Design & Licensing Basis Issues.Description of Proposed Changes to FSAR Which Incorporate Results of Dose Assessment Reanalysis & Details of Administrative Controls Encl)
  • B11937, Discusses Reactor Cavity Pool Seal Status.Plant Procedures Used to Respond to Decreasing Reactor Cavity Water Level Remain Valid.New Permanent Seal Design Reviewed Against IE Bulletin 84-03 & All Appropriate Plant Procedures  + (Discusses Reactor Cavity Pool Seal Status.Plant Procedures Used to Respond to Decreasing Reactor Cavity Water Level Remain Valid.New Permanent Seal Design Reviewed Against IE Bulletin 84-03 & All Appropriate Plant Procedures)
  • ML19309A271  + (Discusses Reactor Coolant Pressure Boundary Component Periodic Testing & Insp Assessing Structural & Leaktight Integrity.Sample Tech Specs Encl for Guidance in Revising License Amend Request to Be Submitted within 45 Days)
  • ML20071N416  + (Discusses Reactor Coolant Pump Seal Ability to Perform Adequately After Extended Loss of Component Cooling Water, Per NUREG-0737,Item II.K.3.25 Effect of Loss of Alternating Current Power on Pump Seals. Item Resolution Requested)
  • ML17300B062  + (Discusses Reactor Coolant Pump Shaft Cracks Experience in European Power Facilities.Analysis & Evaluation of Activities Useful to Accident Analysis)
  • ML20155A253  + (Discusses Reactor Depressurization Sys Full Stroke Testing Commitments from 880602 Telcon.Util Will Inspect Internals of One Depressurizing Valve Each Refueling Outage.Tech Spec Changes & ASME Code Relief Request Will Be Submitted)
  • ML20069P035  + (Discusses Reactor Design (Chapter 4) Open Items Raised at 821125-26 Working Meeting & Forwards Addl Info Documenting NRC Issues & Project Resolutions)
  • ML20073A727  + (Discusses Reactor Internals Upflow Conversion.Baffle Preening Previously Employed at Facility Exacerbated Baffle Joint Clearance Problem at Other Baffle Joints.Video Tapes of Fuel Assembly Visual Damage Will Be Sent)
  • ML19264B540  + (Discusses Reactor Operation w/1,550 Ppm Boron in Main Coolant During Initial Day of Core 5 Operation)
  • ML20058K213  + (Discusses Reactor Operator & Senior Operator Licensing Exams Scheduled on 910226-0301.Encl Ref Matl Requested by 910102)
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