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• B11611, Forwards Responses to Questions Re Equipment Raised During Sqrt Audit on 850304-08.Questions Raised During Pump & Valve Operability Review Team Audit on 850304-08 Successfully Resolved  + (Forwards Responses to Questions Re Equipment Raised During Sqrt Audit on 850304-08.Questions Raised During Pump & Valve Operability Review Team Audit on 850304-08 Successfully Resolved)
• ML19269E269  + (Forwards Responses to Questions Re Getr Phase II Geological Investigation)
• ML20073A120  + (Forwards Responses to Questions Re Identification of safety- Related Structures,Sys & Components by Crbr QA Program.Info Should Enable NRC to Complete Review of QA List & Close Out SER Open Item 6)
• ML20071L706  + (Forwards Responses to Questions Re Industry Approach on Implementing 10CFR52)
• ML19242B728  + (Forwards Responses to Questions Re Initial Test Program Requirements)
• ML19261D816  + (Forwards Responses to Questions Re Inservice Insp Program Contained in NRC)
• ML20055B468  + (Forwards Responses to Questions Re Need for Power Issue. Revised Section to Application for Site Certification & Environ Rept Currently Being Developed Addressing Available Forecasts Consistent W/Draft Regional Power Plan)
• ML20053A697  + (Forwards Responses to Questions Re Occupational Exposure Associated W/Operation,Maint & Mod of Commercial Nuclear Power Plants,In Response to)
• ML20070L998  + (Forwards Responses to Questions Re PSAR Section 9.3, Auxiliary Liquid Metal Sys, Section 9.13, Plant Fire Protection Sys & Other Related Sections.Response to Questions from 821214-15 Chapter 9 Working Meeting Encl)
• ML20092B510  + (Forwards Responses to Questions Re Panthers/Pcc Data)
• ML20039F395  + (Forwards Responses to Questions Re Phase I,Cycle 6 Reload Application & CETOP-O Code Structure & Modeling Methods for Calvert Cliffs Units 1 & 2,CEN-191(B)-P. Rept Withheld (Ref 10CFR2.790))
• ML19270G398  + (Forwards Responses to Questions Re Plant Instrumentation & Controls)
• ML20006A865  + (Forwards Responses to Questions Re Portland General Electric 881024 Rept, Trojan Nuclear Plant Reactor Vessel Supports, Design Basis & Evaluation Summary, Raised During 890822 Meeting W/Nrc Re Resolution of Generic Safety Issue 15)
• NSD-NRC-97-5452, Forwards Responses to Questions Re Pressure Isolation Valves & Safety Classification of Portions of Chemical & Vol Control Sys & FSER Open Item 720.429F.Draft SSAR Changes Included.Changes Will Be Included in SSAR Rev 18  + (Forwards Responses to Questions Re Pressure Isolation Valves & Safety Classification of Portions of Chemical & Vol Control Sys & FSER Open Item 720.429F.Draft SSAR Changes Included.Changes Will Be Included in SSAR Rev 18)
• ML13331A803  + (Forwards Responses to Questions Re Proposed Change 130 & Proposed Tech Spec Section 6.0, Administrative Controls. Onsite & Offsite Organization Charts Revised)
• ML20004D080  + (Forwards Responses to Questions Re Proposed Spent Fuel Storage Mods.Design Info Describing Vendor Final Design Will Be Used to Develop Responses to Remaining Open Items. Complete Rept Will Follow Addl Responses)
• ML20062B178  + (Forwards Responses to Questions Re Proposed Changes to Tech Specs Submitted on 780322)
• B16979, Forwards Responses to Questions Re Proposed Rev to TS Instrumentation Surveillances  + (Forwards Responses to Questions Re Proposed Rev to TS Instrumentation Surveillances)
• ML19352A983  + (Forwards Responses to Questions Re Proposed Revision 5 to TVA-TR75-1A, QA Program Description for Design,Const, Operation of TVA Nuclear Power Plants, Per)
• W3P83-0519, Forwards Responses to Questions Re Proposed Installation of Insulco/Hemyc Sys as Fire Protective Envelope for Class IE Electrical Cables.Insulco/Hemyc Sys Presentation Data Encl  + (Forwards Responses to Questions Re Proposed Installation of Insulco/Hemyc Sys as Fire Protective Envelope for Class IE Electrical Cables.Insulco/Hemyc Sys Presentation Data Encl)
• ML20002A468  + (Forwards Responses to Questions Re Proposed Mods to ECCS for Core 13 Per 770325 Request)
• ML17339B216  + (Forwards Responses to Questions Re Proposed Installation of Condensate Polishing Demineralizers.Responses Suppl Info Previously Submitted in 800318 & 0527 Ltrs.Oversize Drawings Encl)
• L-80-231, Forwards Responses to Questions Re Proposed Installation of Condensate Polishing Demineralizers.Responses Suppl Info Previously Submitted in 800318 & 0527 Ltrs.Oversize Drawings Encl  + (Forwards Responses to Questions Re Proposed Installation of Condensate Polishing Demineralizers.Responses Suppl Info Previously Submitted in 800318 & 0527 Ltrs.Oversize Drawings Encl)
• ML20052E177  + (Forwards Responses to Questions Re RCS Vents Per TMI Action Item II.B.1)
• ML19323F667  + (Forwards Responses to Questions Re Radiological Parameters, Discussed in 800417 Meeting)

• L-79-134, Forwards Responses to Questions Re Reload Safety Evaluation  + (Forwards Responses to Questions Re Reload Safety Evaluation)

• ML20137F736  + (Forwards Responses to Questions Re Review of Revised Lga Procedures Generation Package.Revised Page 3 of Attachment 5 to 850628 Submittal & Response to Draft SER Question A.6 Also Encl)
• ML20004B908  + (Forwards Responses to Questions Re Safeguards Contingency Plan.Encl Withheld (Ref 10CFR2.790))
• ML19340E130  + (Forwards Responses to Questions Re Section 7 of Des,Per NRC 801201 Telecopy Request)
• ML20248C068  + (Forwards Responses to Questions Re Shaff Concerns Described in on Mark I Containment Sys & Evacuation Plans for Plant)
• ML20079H354  + (Forwards Responses to Questions Re Standby Shutdown Sys Per NRC 821203 Request)
• ML20079H017  + (Forwards Responses to Questions Re Station Blackout)
• ND-86-0018, Forwards Responses to Questions Re Util 860825 Tech Spec Change Request Concerning Steam Generator Tube Plugging  + (Forwards Responses to Questions Re Util 860825 Tech Spec Change Request Concerning Steam Generator Tube Plugging)
• ML17312A754  + (Forwards Responses to Questions Related to Power Uprate Amend Request,Suppl 1)
• NSD-NRC-97-5441, Forwards Responses to Questions Related to Plugging of Screens & Safety Classification of Paint & Draft SSAR Changes.Listed Open Items Will Be Statused as Action N or Confirm W Pending Inclusion in SSAR Rev  + (Forwards Responses to Questions Related to Plugging of Screens & Safety Classification of Paint & Draft SSAR Changes.Listed Open Items Will Be Statused as Action N or Confirm W Pending Inclusion in SSAR Rev)
• ML19326C787  + (Forwards Responses to Questions Requested in Telcons W/ J Burdoin & R Snaider Re re-evaluation of ECCS Performance)
• ML20245B431  + (Forwards Responses to Questions Resulting from Operational Safety Team Insp.Sys Engineer Performs Independent Technical Review of Maint Order)
• ML20034F612  + (Forwards Responses to Questions That Were Raised During 930210 Mtg W/Nrc Staff to Discuss Oak Ridge National Laboratory Candu Sys Research Study)
• ML20031B294  + (Forwards Responses to Questions Transmitted During 810925 Telcon W/Nrc Re Facility Emergency Response Plan.Encl Info Will Be Included in Next Revisions to Emergency Response Plan & FSAR)
• ML20127K852  + (Forwards Responses to Questions Transmitted Via NRC on ABWR Shutdown Risk Study (App 19Q))
• ML20057E067  + (Forwards Responses to Questions Transmitted Via NRC Re PWR Reactor Vessel Head Alloy 600 CRDM Penetration Issue)
• TXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span  + (Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span)
• ML20247A057  + (Forwards Responses to Questions for Record of Subcommittee 880512 Hearing on Nuclear Waste Transportation,Per 880519 Request)
• ML20207C736  + (Forwards Responses to Questions for Record of Subcommittee 880512 Hearing on Nuclear Waste Transportation)
• ML20004E173  + (Forwards Responses to Questions from 810512 Telcon Re Survivability of Hydrogen Recombiners & Containment Temp Profile)
• ML20206P653  + (Forwards Responses to Questions from 851030 Hearing on High Level Waste Program.Responses Consistent W/Staff Analysis)
• ML20078R646  + (Forwards Responses to Questions from 950112 417th ACRS Meeting Re Capability of Isolation Condenser to Withstand Loadings Resulting from Tube Rupture & Issue of Mitigation of Consequences of Break in RWCU Line)
• ML17272A196  + (Forwards Responses to Questions from Csb,Core Performance Branch,& Geosciences Branch,As Well as Responses or Updates to Previous Questions from Csb.(Only 1 Copy of Ref Repts Sent,Filed in Geosciences Branch,259pp.))
• ML20024G730  + (Forwards Responses to Questions from Expressing Support for Upgrading Physical Security at Us Nuclear Power Reactors Licensed by NRC & Requesting Reversal of 910115 Denial of Request for Emergency Implementation)
• L-78-175, Forwards Responses to Questions from NRC Regarding Cycle 2 Reload Safety Evaluation  + (Forwards Responses to Questions from NRC Regarding Cycle 2 Reload Safety Evaluation)
• ML19343A387  + (Forwards Responses to Questions from QA Branch.Matl Will Be Incorporated in Next FSAR Amend.First Three Pages Correct Numbering Problem W/Nrc Questions.Last Four Pages Provide Info Inadvertently Omitted from Last Amend)