Search by property

Jump to navigation Jump to search

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.

Search by property

A list of all pages that have property "Title" with value "Forwards Descriptive Matl Re NRC State Agreement Program. W/O Encl". Since there have been only a few results, also nearby values are displayed.

â§Ľshowingresultsâ§˝

View (previous 50 | next 50) (20 | 50 | 100 | 250 | 500)


    

List of results

  • ML20035B411  + (Forwards Descriptions of Changes to Security Training & Qualification Manual)
  • ML19263C951  + (Forwards Descriptions of Const Deficiencies Per 10CFR50.55(e) Since Notice of Hearing for Operating License Proceeding Was Issued on 781012)
  • ML20046A683  + (Forwards Descriptions of Facility Changes Completed,Per 10CFR50.59 for Jan & Dec 1992)
  • ML20024E399  + (Forwards Descriptions of Fire Protection Sys for Four Listed Plant Areas as Confirmatory Document of Matl Presented at 830714 Meeting W/Nrc)
  • ML20024E222  + (Forwards Descriptions of Fire Protection Sys for Four Listed Areas,Per 830714 Meeting.Util Proceeding W/Design & Const Unless Notified Otherwise.Drawings Encl)
  • ML19352A234  + (Forwards Descriptions of Functional Compliance to Shift Staffing & Augmentation Capability & Emergency Operations Facility Requirements,Per TMI Action Plan Item III.A.1.2. Personnel Levels Assure Adequate Coverage)
  • ML20209H914  + (Forwards Descriptions of How Alternate post-accident Sampling Sys Will Meet 11 NUREG-0737 Criteria,Discussion of Items Addressed in Util ,Graphs of Analysis Accuracies & One Oversize P&ID)
  • ML20134N094  + (Forwards Descriptions of Licensed NRC Operator Requalification Program & Replacement Training for Licensed Operators & Licensed Senior Operators,Per 801121 Telcon Request)
  • ML20028C837  + (Forwards Descriptions of Nine Completed License Conditions & Subsequent Commitments Addressing Outstanding Issues Per NUREG-0737.Closure of Completed License Conditions Requested)
  • ML20133L974  + (Forwards Descriptions of Objectives & Scope of 1985 Emergency Preparedness Exercise,In Response to NRC 840209 Request)
  • ML20213D982  + (Forwards Descriptions of Plans to Identify & Implement Improvements in Controlling Paperwork Burden on Licensees Per OMB 811030 Request to Chairman Palladino)
  • ML18046A565  + (Forwards Descriptions of Plans to Support SEP Milestone Dates of 810430 & 810630 in Response to 810219 Request)
  • ML19318A879  + (Forwards Descriptions of Plant Emergency Ctrs to Meet end-of-yr Requirements & Commitments.Util Not Planning to Construct New Facilities.Existing Bldgs Will Serve Functions)
  • B11904, Forwards Descriptions of Procedures for Insps of Water Control Structures & Methods of Addressing NRC Concerns Re SEP Topic III-3.C, Inservice Insp of Water Control Structures & Isap Topic 1.29, Flooding Evaluation  + (Forwards Descriptions of Procedures for Insps of Water Control Structures & Methods of Addressing NRC Concerns Re SEP Topic III-3.C, Inservice Insp of Water Control Structures & Isap Topic 1.29, Flooding Evaluation)
  • W3P81-0696, Forwards Descriptions of Programs Re Existing Mgt & Technical Capabilities,Corporate Structure,Plans for Aquisition of Vital Personnel,Plant Organization Changes & Training  + (Forwards Descriptions of Programs Re Existing Mgt & Technical Capabilities,Corporate Structure,Plans for Aquisition of Vital Personnel,Plant Organization Changes & Training)
  • NLS8400073, Forwards Descriptions of Reg Guide 1.97 Requirements & Schedule for Implementation of Emergency Response Capability,Per NUREG-0737,Suppl 1  + (Forwards Descriptions of Reg Guide 1.97 Requirements & Schedule for Implementation of Emergency Response Capability,Per NUREG-0737,Suppl 1)
  • GO2-83-345, Forwards Descriptions of Responsibilities of Nuclear Safety Assurance Group,In Confirmation of 830209 Meeting.Encl Provides Revised Response to TMI Items I.B.1.2 & I.C.5  + (Forwards Descriptions of Responsibilities of Nuclear Safety Assurance Group,In Confirmation of 830209 Meeting.Encl Provides Revised Response to TMI Items I.B.1.2 & I.C.5)
  • ML20214E308  + (Forwards Descriptions of Safety Significant Human Engineering Discrepancies (Heds) Identified During Dcrdr,Per Commitments Made in Util Comments on Draft Ser.Justification for Heds That Will Not Be Addressed Also Encl)
  • ML13324A575  + (Forwards Descriptions of Steam Generator Insp Program & Eddy Current Insp Program Required by License Condition 3.E.Insp Currently Scheduled for May or June 1985.Necessity for Insp Under Discussion W/Nrc)
  • ML20100M524  + (Forwards Descriptions of Sys & Components in Fire Area 30 Affected by App R,Planned Corrective Actions & Requests for Exemption from 10CFR50,App R,Section Iii.G.Excerpt from Original FSAR Also Encl.Fee Paid)
  • ML19336A677  + (Forwards Descriptions of Sys Changes from 770526 to Present Fsar.Two Items Not Listed in 770526 Rept,Gql 0714,also Encl.No Procedure Changes Require FSAR Mod.No Tests or Experiments Performed Not Described in FSAR)
  • ML20151D492  + (Forwards Descriptions of naturally-occurring & Accelerator Produced Radioactive Matl Incidents During Past 5 Yrs, Received from State Radiation Control Programs,Per Request. Abstracts Also Encl.Addl Repts to Be Sent as Received)
  • ML20011E385  + (Forwards Descriptive Assembly Drawing in Support of Renewal Application for Certificate of Compliance 9128 for Model C-8 Type B(U) Package)
  • ML19329F917  + (Forwards Descriptive Info for Action Item II.B.1 Requested by NRC for full-power Licensing Review.Response to NRC 800701 Request for Addl Info Re RCS Vents Will Be Provided as Soon as Possible)
  • ML20214N008  + (Forwards Descriptive Info on Loviisa Plant in Finland & Ussr PWRs Re Preheated Safety Injection Sys)
  • ML19210C290  + (Forwards Descriptive Matl Re NRC State Agreement Program. W/O Encl)
  • ML20083L759  + (Forwards Descriptive Rept of Archeological Investigation for 220-60 Transmission Line Right-of-Way in Association W/Limerick Nuclear Generating Station,Montgomery & Chester Counties,Pa & ...220-61 Transmission..)
  • ML20138D346  + (Forwards Descriptive Summaries for Projects Needed to Adequately Respond to Public Comments on Transportation of Spent Fuel Rule)
  • ML20212B547  + (Forwards Descriptive Summary of Proposed Changes to Facility Industrial Security Manual Per 10CFR73.55(a),(d)(1),(d)(7), (d)(9) & (e)(1).Encl Withheld (Ref 10CFR73.21))
  • ML20212A527  + (Forwards Descriptive Summary of Proposed Changes to Security manual,per10CFR73.55 Requirements That Licensees Submit Revs Describing How Paragraphs (a),(d)(1),(d)(7),(d)(9) & (e)(1) Will Be Met.Encl Withheld (Ref 10CFR73.55))
  • ML20009E946  + (Forwards Design & Const QA Program,Per NRC Request)
  • ML20009E947  + (Forwards Design & Const QA Program,Per NRC Request)
  • ML17249A327  + (Forwards Design Analysis Adequacy of Station Electric Distribution Sys Voltages. Some Operating Conditions Have Potential to Cause Spurious Separations of Safety Buses from Offsite Power Source.Available in Central Files)
  • ML17249A328  + (Forwards Design Analysis Adequacy of Station Electric Distribution Sys Voltages. Some Operating Conditions Have Potential to Cause Spurious Separations of Safety Buses from Offsite Power Source.Available in Central Files)
  • ML17249A508  + (Forwards Design Analysis,Rcs Subcooling Margin Monitoring Sys Error Analysis, in Response to NRC 791227 Request for Documentation Demonstrating Assumed Errors Used to Develop Subcooling Criterion for HPI Termination & Reinitiation)
  • ML17249A509  + (Forwards Design Analysis,Rcs Subcooling Margin Monitoring Sys Error Analysis, in Response to NRC 791227 Request for Documentation Demonstrating Assumed Errors Used to Develop Subcooling Criterion for HPI Termination & Reinitiation)
  • ML20003H736  + (Forwards Design Approach to Cold Shutdown. Although Designed as Hot Standby Plant W/Cp Docketed Before 780101, Facility Is Category 2 Plant & Will Be Reviewed as Specific Case Basis by NRC for Compliance W/Reg Guide 1.139)
  • ML20003H737  + (Forwards Design Approach to Cold Shutdown. Although Designed as Hot Standby Plant W/Cp Docketed Before 780101, Facility Is Category 2 Plant & Will Be Reviewed as Specific Case Basis by NRC for Compliance W/Reg Guide 1.139)
  • ML18030A260  + (Forwards Design Assessment Rept Figure Re Liner Plate Wall Embeds & Anchors.Submittal Closes NRC Concern Re Equipment Design)
  • ML19296B876  + (Forwards Design Assessment Rept, Revision 1.Requests,on Basis of Documentation,That Mark II Containment Issues Identified as Open Items at 790511 Meeting,Be Closed.Five Oversize Drawings Encl)
  • ML19296B877  + (Forwards Design Assessment Rept, Revision 1.Requests,on Basis of Documentation,That Mark II Containment Issues Identified as Open Items at 790511 Meeting,Be Closed.Five Oversize Drawings Encl)
  • ML19209C852  + (Forwards Design Assessment Rept, Revision 6,revised Pages)
  • ML19209C853  + (Forwards Design Assessment Rept, Revision 6,revised Pages)
  • ML18017A245  + (Forwards Design Assessment Rept,Revision 2. Proprietary Version Withheld (Ref 10CFR2.790))
  • ML17138B347  + (Forwards Design Assessment Rept,Revision 2. Proprietary Version Withheld (Ref 10CFR2.790))
  • ML20209J449  + (Forwards Design Baseline & Verification Program (Dbvp) Insp Repts 50-327/86-55 & 50-328/86-55 on 861103-07 & 1117-21 & 1201-04.DBVP Being Conducted Per Program Plan.Listed Deficiencies Noted)
  • ML20137A912  + (Forwards Design Bases 50.54(f) Ltr Re CRGR Meeting 296.W/o Encl)
  • ML13330B455  + (Forwards Design Bases Documentation Program Plan for Plant. Design Bases Program Represents Effort by Util to Improve Quality of Engineering at Facility)
  • ML19317F309  + (Forwards Design Basis & Description of Auxiliary Svc Water Sys, Per AEC 721031 Request for Addl Info)
  • ML20096E048  + (Forwards Design Basis Closure Rept in Response to Requirements of GL 89-10 & Suppls)
  • ML20040G021  + (Forwards Design Basis Exceptions to Reg Guide 1.97 Revision 2.Adoption of Full Scope of Instrumentation Proposed by Reg Guide Is Not Necessary for Safe Operation of Westinghouse PWRs)