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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

• PLA-1074, Summarizes 820301 Meeting W/Nrc to Discuss Design Control Program for Facilities.Description of Program & Slides Presented at Meeting Encl.Independent Piping Design Review Will Be Completed About 820601  + (ML18026A387)
• ML18026A388  + (ML18026A388)
• ML18026A389  + (ML18026A389)
• ML18026A393  + (ML18026A393)
• PLA-3438, Requests Waiver of Compliance from Tech Spec 3.8.1.1 to Evaluate Increase in Action from 72 H to 15 Days Re Ac Sources Based on 900829 Borescopic Insp of Emergency Diesel Generator  + (ML18026A394)
• PLA-3445, Forwards Proposed Amend 87 to License NPF-22,changing Tech Specs to Support Cycle 5 Reload.Reload Summary Rept Also Encl  + (ML18026A395)
• ML18026A396  + (ML18026A396)
• ML18026A398  + (ML18026A398)
• ML18026A399  + (ML18026A399)
• ML18026A401  + (ML18026A401)
• PLA-3516, Suppls 890612 & 1221 Responses to Enforcement Action 89-042 Re Exceeding Tech Spec Reactor Vessel Cooldown Rate Limit on 890112.Requests Formal NRC Review of Util Response  + (ML18026A404)
• ML18026A405  + (ML18026A405)
• ML18026A408  + (ML18026A408)
• PLA-3630, Responds to NRC Request for Addl Info Re Requested Rev to Tech Specs for Facility Ses Related to Rwcu/Hpci/Rcic Temp Based Steam Leak Detection Isolation Setpoints  + (ML18026A410)
• PLA-3681, Forwards Set of Viewgraphs Describing Principal Activities of Nuclear Safety Assessment Group & Paper Presented at American Nuclear Society Reactor Operations Div Topical Meeting Last Aug in Bellevue,Wa  + (ML18026A413)
• ML18026A415  + (ML18026A415)
• PLA-3732, Forwards Response to NRC 910730 Request for Addl Info Re Proposed Amend 137 to License NPF-14 & Proposed Amend 91 to License NPF-22 Re Elimination of Temp Leak Detection Isolation Function in RHR Room  + (ML18026A416)
• PLA-3745, Forwards Revised Response to NRC Station Blackout Safety Evaluation ,revising Diesel Generator Target Reliability to 0.975,based on NRC Position.Resolution of Cabinet Temp Concern Will Be Submitted by 920501  + (ML18026A417)
• ML18026A418  + (ML18026A418)
• PLA-3817, Forwards Presentation Matl from 920717 SALP Meeting Discussing Most Recent NRC Assessment of Util Performance  + (ML18026A420)
• 05000387/LER-1992-016, :on 920416,discovered That Existing Analysis for Two Spent Fuel Storage Pools Did Not Reflect Current Fuel Design & Plant Operation.Caused by Failure to Modify FSAR Analysis.Fsar Will Be Revised  + (ML18026A423)
• ML18026A424  + (ML18026A424)
• PLA-3933, Responds to NRC Re Violations Noted in Insp Repts 50-287/92-23 & 50-388/92-23.C/As:surveillance Procedures Will Be Revised to Address Types of Fire Barrier Matl to Be Inspected to Provide Acceptance Criteria for Fire Barrier  + (ML18026A425)
• 05000388/LER-1990-007, :on 900705,primary Power Supply to RPS a Power Distribution Panel Lost When One Electrical Protection Assembly (EPA) Breaker Tripped.Epa Logic Cards Reviewed & RPS Power Supply Will Be Redesigned  + (ML18026A426)
• PLA-3996, Forwards Discussion on Perspective on Licensing Basis of Spent Fuel Pool Cooling Sys for Plants  + (ML18026A427)

• ML18026A428  + (ML18026A428)

• ML18026A429  + (ML18026A429)
• ML18026A430  + (ML18026A430)
• ML18026A432  + (ML18026A432)
• PLA-4032, Forwards Responses to NRC Questions,Revised Pages to Emergency Plan,Revised Pages to Technical Basis & Proposed Eals,In Response to NRC 930609 Request for Addl Info on Rev to Emergency Plan Which Implemented NUMARC NESP-007  + (ML18026A433)
• PLA-3949, Provides Revised Plan & Commitments for Completion of Tasks Necessary to Meet Guidelines of GL 89-10 & Justification for Deferral of Work on Valves Associated W/Msivlcs within GL 89-10 Program.Rev 1 to Calculation EC-VALV-0503 Encl  + (ML18026A435)
• ML18026A436  + (ML18026A436)
• PLA-4112, Responds to Request for Addl Info Re SGTS Performance for Loss of SFP Cooling Following Seismic Event,Per NRC  + (ML18026A437)
• PLA-3991, Forwards Rev 4 to Fire Protection Review Rept  + (ML18026A438)
• PLA-4115, Forwards Rev 5 to Susquehanna Ses Fire Protection Review Rept. Changes Consist of Addition of List of Effective Pages,Changes in Pagination & Administrative Correction of Rev Date on Table DR11-1  + (ML18026A440)
• ML18026A441  + (ML18026A441)
• ML18026A442  + (ML18026A442)
• PLA-4142, Requests Approval of Change to FSAR to Revise Biennial Review of Nuclear Plant Procedures.Proposed SSES FSAR Chapter 17.2 & Justification for Rev to Biennial Review Requirements Encl  + (ML18026A443)
• ML18026A444  + (ML18026A444)
• ML18026A445  + (ML18026A445)
• ML18026A446  + (ML18026A446)
• ML18026A447  + (ML18026A447)
• PLA-4228, Forwards Proposed Amends 178 & 132 to Licenses NPF-14 & NPF-22,respectively,eliminating MSIV-LCS Including PCIVs Associated w/MSIV-LCS & Increasing Allowable TS MSIV Leakage Rates  + (ML18026A448)
• ML18026A449  + (ML18026A449)
• PLA-4233, Submits Core Shroud Insp Scope & Schedule for Unit 1 in Response to Requirements of GL 94-03  + (ML18026A450)
• PLA-4274, Responds to NRC 950203 RAI Re Plant MSIV Leakage Control Sys  + (ML18026A452)
• PLA-4298, Forwards Proposed Rev to SSES Emergency Plan for Review & Approval.Proposed Rev Contains Listed Changes,Including Relocation of EOF to Northeast Div Headquarters,Eof Activation & Relocation of ERDS  + (ML18026A454)
• PLA-4321, Responds to Request for Addl Info Re App R Safe Shutdown Analysis Fire Protection Review Rept,Rev 4  + (ML18026A455)
• ML18026A459  + (ML18026A459)
• PLA-4362, Informs NRC of Affect of Installation Phase of Plant Integrated Computer Sys Project on Electronically Transmitted Data for Emergency Planning  + (ML18026A460)
• PLA-4363, Forwards Justification for Proposed QA Program Change Re Elimination of Biennial Procedure Review Requirements  + (ML18026A461)