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A list of all pages that have property "Title" with value "Forwards Rev 1 to Defueled Security Plan.Rev Withheld". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML20196L336  + (Forwards Rev 1 to Cycle 11 COLR for WCGS, IAW TS Section 6.9.1.9)
  • ML20012B366  + (Forwards Rev 1 to Cycle 12 Reload Rept,Changing Assumed RCS Flow & Correcting Typo)
  • NG-95-3442, Forwards Rev 1 to Cycle 14,COLR, for Duane Arnold Energy Ctr  + (Forwards Rev 1 to Cycle 14,COLR, for Duane Arnold Energy Ctr)
  • ML20095K998  + (Forwards Rev 1 to Cycle 5 COLR, Per TS 6.8.1.6.c)
  • 3F0790-06, Forwards Rev 1 to Cycle 8 Core Operating Limits Rept, Correcting Typo in Note 1 of Figures 1-8 & Note 2 of Figures 1,2 & 4-8  + (Forwards Rev 1 to Cycle 8 Core Operating Limits Rept, Correcting Typo in Note 1 of Figures 1-8 & Note 2 of Figures 1,2 & 4-8)
  • RC-95-0048, Forwards Rev 1 to Cycle 9 Core Operating Limts Rept  + (Forwards Rev 1 to Cycle 9 Core Operating Limts Rept)
  • ML20236B732  + (Forwards Rev 1 to D-0050, Engineering Action Plan)
  • ML20207F423  + (Forwards Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504, IAW 10CFR50.4.NRC Evaluated Exercise Has Been Rescheduled for 991208,since NRC Did Not Evaluate 990504 Exercise)
  • ML17329A503  + (Forwards Rev 1 to DC Cook Nuclear Plant Unit 2,Cycle 9 Core Operating Limits Rept, Per Generic Ltr 88-16)
  • ML17329A504  + (Forwards Rev 1 to DC Cook Nuclear Plant Unit 2,Cycle 9 Core Operating Limits Rept, Per Generic Ltr 88-16)
  • ML17334A591  + (Forwards Rev 1 to DC Cook Nuclear Plant Unit 2 Cycle 12 Colr)
  • ML17334A592  + (Forwards Rev 1 to DC Cook Nuclear Plant Unit 2 Cycle 12 Colr.)
  • ML17334B391  + (Forwards Rev 1 to DC Cook Nuclear Plant Unit 1 Cycle 12 Core Operating Limits Rept, Per Generic Ltr 88-16, Removal of Cycle-Specific Parameter Limits Tech Specs. Proprietary Rept Pages Withheld)
  • ML17328A820  + (Forwards Rev 1 to DC Cook Nuclear Plant Unit 1 Cycle 12 Core Operating Limits Rept, Per Generic Ltr 88-16, Removal of Cycle-Specific Parameter Limits Tech Specs. Proprietary Rept Pages Withheld)
  • ML20127P576  + (Forwards Rev 1 to DC-5, Independent Assessment Program Electrical Sys Review Criteria,Phase IV, Rev 1 to DC-4, ...Mechanical Design Review Criteria & App N to Rev 0 to TR-84056-01, Independent Assessment Program,Phase 4)
  • ML20127P579  + (Forwards Rev 1 to DC-5, Independent Assessment Program Electrical Sys Review Criteria,Phase IV, Rev 1 to DC-4, ...Mechanical Design Review Criteria & App N to Rev 0 to TR-84056-01, Independent Assessment Program,Phase 4.)
  • ML20093K314  + (Forwards Rev 1 to DECO-04-2468, Assessment of Purge Valve Pressure Differential Capabilities & Responses to Items Pending from Sser 3.Submittal Should Close Issue)
  • ML20046C693  + (Forwards Rev 1 to DOE/AL/62350-0464, Environ Assessment of Remedial Action at Naturita Uranium Processing Site Near Naturita,Co)
  • ML20129F301  + (Forwards Rev 1 to DOE/AL/62350-211, Long-Term Surveillance Plan for Ambrosia Lake,Nm Disposal Site, for Jul 1996. W/One Oversize Drawing)
  • ML20247G422  + (Forwards Rev 1 to DOE/AL/62350-243, Interim Long-Term Surveillance Plan for Cheney Disposal Site Near Junction, Co, for Apr 1998)
  • ML20238E848  + (Forwards Rev 1 to DOE/AL/62350-246, Final Audit Rept of Remedial Action Construction at Umtra Project,Slick Rock,Co, Sites. Rept Summarizes Environ Restoration Div/Technical Assistance Contractor QA Surveillances)
  • ML20214W928  + (Forwards Rev 1 to DPC-NE-1003, Rod Swap Methodology Rept for Startup Physics Testing)
  • ML20199G625  + (Forwards Rev 1 to Davis Besse Unit 1,Cycle 11 COLR, Revising Section 1.0 to Ref Operating Cycle Licensed Length & Replaces Figure 5 W/Revised Figure)
  • ML20097A523  + (Forwards Rev 1 to Decommissioning Funding Assurance Rept & Certification,Submitted Per 10CFR50.33(k)(2),10CFR30.35 & 10CFR50.75,Vermont Yankee Nuclear Power Station)
  • ML20058Q370  + (Forwards Rev 1 to Decommissioning Plan for Fort St Vrain Nuclear Generating Station. Rev Reflects Changes Discussed in 930304,0609,0909 & 1209 Quarterly Repts of Changes,Tests & Experiments,Per 921123 Decommissioning Order)
  • ML20044F193  + (Forwards Rev 1 to Defueled Security Plan.Rev Withheld)
  • ML20046B006  + (Forwards Rev 1 to Defueled Security Training & Qualification Plan as Approved by NRC in Ltr Dtd 921013.Rev Withheld)
  • ML20137M741  + (Forwards Rev 1 to Defueling Canisters, Technical Evaluation Rept.Rev Incorporates Util 850815 Response to NRC Comments on Original Rept & Includes TMI-2 Transfer Sys Criticality...Rept & ...Drain Pool Scenario.)
  • ML20137M735  + (Forwards Rev 1 to Defueling Canisters, Technical Evaluation Rept.Rev Incorporates Util 850815 Response to NRC Comments on Original Rept & Includes TMI-2 Transfer Sys Criticality...Rept & ...Drain Pool Scenario)
  • RBG-23-991, Forwards Rev 1 to Description of Changes to Initial Test Program ST-30D Originally Submitted on 860528  + (Forwards Rev 1 to Description of Changes to Initial Test Program ST-30D Originally Submitted on 860528)
  • LD-93-098, Forwards Rev 1 to Design Alternatives to Sys 80+ Nuclear Power Plant, Covering Cost/Benefit Based on Recently Revised PRA  + (Forwards Rev 1 to Design Alternatives to Sys 80+ Nuclear Power Plant, Covering Cost/Benefit Based on Recently Revised PRA)
  • ML17262A174  + (Forwards Rev 1 to Design Analysis EWR 4525-1, Fault Current Analysis of Power Distribution Sys & Rev 1 to Design Analysis EWR 4525-2, Adequacy of Electric Sys.... NRC Will Be Notified of Util Intended Corrective Action by 901030)
  • ML17262A175  + (Forwards Rev 1 to Design Analysis EWR 4525-1, Fault Current Analysis of Power Distribution Sys & Rev 1 to Design Analysis EWR 4525-2, Adequacy of Electric Sys.... NRC Will Be Notified of Util Intended Corrective Action by 901030)
  • ML20202G157  + (Forwards Rev 1 to Design Calculation, MCNP 1-D & 2-D Shielding Analyses for ANO MSB Transfer Cask (Mtc), Per 990127 Telcon RAI Re LAR 98-01 Which Addresses Storage of B&W Fuel with Bpras in Vsc Sys)
  • ML20083K921  + (Forwards Rev 1 to Design Document SL-4984, Quad Cities Units 1 & 2 Core Shroud Repair,Design Reliant Structures Insp Requirements & Acceptance Criteria, in Response to NRC RAI in 950427 Telcon)
  • ML20083A644  + (Forwards Rev 1 to Design Guide DG-VIII.50, Instrument Setpoints, Per 910711 Conference Call)
  • ML20023B692  + (Forwards Rev 1 to Design Rept for Recirculation Sys & RHR Sys Weld Overlay Repairs & Flaw Evaluation at Ei Hatch Nuclear Power Plant,Unit 1.)
  • ML20023B690  + (Forwards Rev 1 to Design Rept for Recirculation Sys & RHR Sys Weld Overlay Repairs & Flaw Evaluation at Ei Hatch Nuclear Power Plant,Unit 1)
  • ML20080P411  + (Forwards Rev 1 to Design Rept for Weld Overlay Repairs at Brunswick Steam Electric Plant Unit 2, Per 831128 Commitment.Weld Joints Containing Intergranular Stress Corrosion Cracking Indications Will Be Reinspected)
  • BECO-84-159, Forwards Rev 1 to Detailed Control Design Review, Per 831026 Commitment & NUREG-0737,Item 1.D.1  + (Forwards Rev 1 to Detailed Control Design Review, Per 831026 Commitment & NUREG-0737,Item 1.D.1)
  • BECO-84-134, Forwards Rev 1 to Detailed Control Room Design Review Program Plan, Per NUREG-0737,Item I.D.1 & Suppl 1 to NUREG-0737  + (Forwards Rev 1 to Detailed Control Room Design Review Program Plan, Per NUREG-0737,Item I.D.1 & Suppl 1 to NUREG-0737)
  • ML20093A387  + (Forwards Rev 1 to Detailed Control Room Design Review Summary Rept, Per Suppl 1 to NUREG-0737.Rept Documents Apr & June 1984 Environ Surveys Addressing Concerns Identified in Util 840321 & NRC s)
  • ML20212B611  + (Forwards Rev 1 to Diesel Generator Load Analysis & Vols 1 & 2 of Sequoyah Nuclear Plant Electrical Calculation Program Assessment, Final Rept.Corrective Actions for Problems in Auxiliary Power Sys & Control Power Sys Noted)
  • ML20236T866  + (Forwards Rev 1 to Document Use of GIP for New & Replacement Equipment & Parts (Nare) Revised to Address NRC Questions & Comments)
  • ML20207Q827  + (Forwards Rev 1 to Document on Licensing Basis Events for Std Modular High Temp gas-cooled Reactor for Review & Approval)
  • ML20203M980  + (Forwards Rev 1 to Draft 5 to OGR/B-3, Ofc of Geologic Repositories QA Plan for High Level Radwaste Repositories & Suppls,For Review & Approval)
  • ML20205S874  + (Forwards Rev 1 to Draft GJO-99-88-TAR, Final Site Observational Work Plan for Umtra Project Old Rifle Site, for NRC Review & Comment.Rept Reflects EPA Final Ground Water Protection Stds Issued in Jan 1995)
  • ML20217M628  + (Forwards Rev 1 to Draft MD 6.4, Generic Issue Program. Informs That OGC Requested That Stated Paragraph Be Inserted Into Introduction Section of MD to Clarify Nature & Purpose of MD)
  • ML20081A700  + (Forwards Rev 1 to Draft Rept Confirmatory Survey of Radwaste Bldg,Suppression Pool,Phase 2 & Phase 3 Sys, Shoreham Nuclear Power Station,Brookhaven,Ny)
  • ML20081A711  + (Forwards Rev 1 to Draft Rept Confirmatory Survey of Reactor Bldg & Phase 4 Sys,Shoreham Nuclear Power Station, Brookhaven,Ny)
  • ML20198G494  + (Forwards Rev 1 to Draft SER & Request for Addl Info Based on Info Received from Applicant Up to & Including Amend 15 to PSAR)
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