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• ST-HL-AE-1848, Forwards Responses to NRC Comments Re Procedures Generation Package,Transmitted W/Np Kadambi .Westinghouse Owners Group Emergency Response Guidelines Low Pressure Ref Plant Description Also Encl  + (Forwards Responses to NRC Comments Re Procedures Generation Package,Transmitted W/Np Kadambi .Westinghouse Owners Group Emergency Response Guidelines Low Pressure Ref Plant Description Also Encl)
• ML20091A129  + (Forwards Responses to NRC Comments Re Radiological Emergency Exercise,Per .Revised Scope & Objectives of Exercise,Incorporating NRC Comments & New Exercise Date,Also Encl)
• ML20210U516  + (Forwards Responses to NRC Comments Re Reactor Bldg Sump Criticality Ser.Insignificant Mass of Fuel Suspected Under Reactor Vessel Based on Exposure Rates Measured by Ion Chamber Probe)
• ML20056G626  + (Forwards Responses to NRC Comments Re SAR for NAC Storable Transport Cask (NAC-STC), SAR for NAC Storable Transport Cask, Rev 2 & Application for Withholding Proprietary Section of Rept)
• ML20236A881  + (Forwards Responses to NRC Comments Re Slick Rock Draft Remedial Action Plan & Site Conceptual Design.Meeting W/Nrc & State of Co Proposed)
• ML19246B516  + (Forwards Responses to NRC Comments at 790606 Meeting Re Offsite Dose Calculation Manual,For NRC Review Prior to 790716 Meeting)
• ML20207H872  + (Forwards Responses to NRC Comments in Ltr on NEI 99-01 Final Draft Rev 4 , Methodology for Development of Eals)
• ML20148D064  + (Forwards Responses to NRC Comments on 60% Design for Green River,For Consideration.Response Should Clarify Issues Raised About Potential Groundwater Contamination at Disposal Site)
• ML20236W165  + (Forwards Responses to NRC Comments on Completion Rept for Gunnison,Co,Vicinity Property GU-029S.Rev 1 to Vicinity Completion Rept for Subject Property,Encl.Responses Resulted in Revised Rept)
• ML20195H583  + (Forwards Responses to NRC Comments on EPRI Graded Approach to Monitoring of Emergency Diesel Generator Reliability,Per Commitment During 881102 Meeting.Concept of Accelerated Testing Conflicts W/Intent of Reliability Based Program)
• ML20138A076  + (Forwards Responses to NRC Comments on Early Defueling SER Transmitted by NRC 850729 & 0813 Ltrs.Addl Input Being Prepared to Respond to NRC Question Re Onsite Testing of Canisters)
• ML20197G617  + (Forwards Responses to NRC Comments on FL50 Container. Comments Should Be Included as Amend to Initial Rept.Encl Withheld)
• ML20196F441  + (Forwards Responses to NRC Comments on Final Remedial Action Plan (RAP) for Naturita,Co,Umtra Project Site.Page Changes to Previous Version of RAP,DOE/AL/62350-249,rev 0,encl)
• LD-83-108, Forwards Responses to NRC Comments on Leak Before Break Evaluation of Main Loop Piping of C-E RCS, Per 831026 Meeting & 830614 Submittal.Max Seismic Moment Has No Impact on Loading of Axial Slot in Elbow  + (Forwards Responses to NRC Comments on Leak Before Break Evaluation of Main Loop Piping of C-E RCS, Per 831026 Meeting & 830614 Submittal.Max Seismic Moment Has No Impact on Loading of Axial Slot in Elbow)
• ML20046C549  + (Forwards Responses to NRC Comments on Mexican Hat/Monument Valley,Az Remedial Action Plan)
• ML20011A823  + (Forwards Responses to NRC Comments on Physical Security Plan.Responses Withheld (Ref 10CFR2.790).Affidavit Encl)
• U-600066, Forwards Responses to NRC Comments on Revised SPDS (TMI Action Plan Item I.D.2) for Review.Scheduling of Design Validation Audit in mid-Oct to Support Final Closure Requested  + (Forwards Responses to NRC Comments on Revised SPDS (TMI Action Plan Item I.D.2) for Review.Scheduling of Design Validation Audit in mid-Oct to Support Final Closure Requested)
• ML20045C836  + (Forwards Responses to NRC Comments on Startup Test Matl & on pre-operational Test Matl)
• ML20197D967  + (Forwards Responses to NRC Comments on Tuba City Preliminary Design Package)
• ML20045H685  + (Forwards Responses to NRC Comments on Usis/Gsis,Including 930709 Telcon & Addition of Issue C-8 to Issue Group Resolved W/No New Requirements)
• ML20052G954  + (Forwards Responses to NRC Comments on Util 820219 Submittal of Revision 4 to Rept on NUREG-0588 Re Equipment Qualification)
• W3P83-1484, Forwards Responses to NRC Concerns Raised at 830218 Meeting W/Util to Close Out Open Items Re Emergency Feedwater Control Sys,Per NUREG-0787,Suppl 1.W/23 Oversize Drawings. Aperture Cards Are Available in PDR  + (Forwards Responses to NRC Concerns Raised at 830218 Meeting W/Util to Close Out Open Items Re Emergency Feedwater Control Sys,Per NUREG-0787,Suppl 1.W/23 Oversize Drawings. Aperture Cards Are Available in PDR)
• ML20023E161  + (Forwards Responses to NRC Concerns Re 830110 Amend 6 to License DPR-6 Covering Spent Fuel Rack Addition.On 830516, SER Identified Five Remaining Unresolved Items,Including Shear Key Capacity & Effects of Cracking on Length)
• ML19224D795  + (Forwards Responses to NRC Concerns Re Calculation of Local Stresses in Spherical Shell at Penetrations in Sargent & Lundy Rept Stress Rept for Primary Containment Penetration. Oversized Drawings Available in Central Files)
• AECM-84-0241, Forwards Responses to NRC Concerns Re Diesel Generator & Gas Turbine Reliability,Per 840405 Meeting.Safety Relief Valves Sequentially Operated to Maintain Reactor Pressure Below Relief Valve Setpoint  + (Forwards Responses to NRC Concerns Re Diesel Generator & Gas Turbine Reliability,Per 840405 Meeting.Safety Relief Valves Sequentially Operated to Maintain Reactor Pressure Below Relief Valve Setpoint)

• PY-CEI-NRR-2203, Forwards Responses to NRC Concerns Re ECCS Suction Strainer Mods  + (Forwards Responses to NRC Concerns Re ECCS Suction Strainer Mods)

• ML20203G370  + (Forwards Responses to NRC Concerns Re Items 10 & 11 of Study on Electrical Interconnections Between Redundant Divs, to Resolve SER Confirmatory Issue 25)
• ML20038D068  + (Forwards Responses to NRC Concerns Re NUREG-0737 Items II-B.3 (post-accident Sampling) & II.F.1 (Suppression Pool Water Level) & to Question 8 (Fire Detection Devices) & Evaluation of License Condition 10 (Util Organization))
• BECO-88-047, Forwards Responses to NRC Concerns Re Rev 1A of Inservice Testing (IST) Program for Pumps & Valves for Plant.Util Plan for Upgrading Current IST Program Establishes More Viable Pump & Valve Testing Program W/O Major Impact on NRC Review  + (Forwards Responses to NRC Concerns Re Rev 1A of Inservice Testing (IST) Program for Pumps & Valves for Plant.Util Plan for Upgrading Current IST Program Establishes More Viable Pump & Valve Testing Program W/O Major Impact on NRC Review)
• AECM-86-0229, Forwards Responses to NRC Concerns Re Spent Fuel Decay Heat Capability & Associated Operating Procedures,Per 860716 Telcon.Requests That OL Amend for High Density Racks Be Granted on 860818  + (Forwards Responses to NRC Concerns Re Spent Fuel Decay Heat Capability & Associated Operating Procedures,Per 860716 Telcon.Requests That OL Amend for High Density Racks Be Granted on 860818)
• ML20206T095  + (Forwards Responses to NRC Concerns on Emergency Operating Procedures,Per 860911 & 15 Requests.Documents Describing Generation of Procedure ECA 3.1 Also Encl)
• ML18026A513  + (Forwards Responses to NRC Concerns on Transportation Incidents in Vicinity of Facilities)
• AECM-81-194, Forwards Responses to NRC Criteria for Determining Whether Plant Readiness for Near Term OL Control Room Design Review & Estimate of Current Control Room Status  + (Forwards Responses to NRC Criteria for Determining Whether Plant Readiness for Near Term OL Control Room Design Review & Estimate of Current Control Room Status)
• ML20132G786  + (Forwards Responses to NRC Detailed Comments on Topical Rept NUH-001 Re Horizontal Modular Storage Sys for Irradiated Nuclear Fuel)
• ML20050D960  + (Forwards Responses to NRC Discussing NRC 820104-15 Emergency Preparedness Appraisal.Requests That Item 7 of Encl 1 Be Reviewed by 820501,per Requirements of NUREG-0696)
• NRC-96-4862, Forwards Responses to NRC Dser Section 3.12 Open Items  + (Forwards Responses to NRC Dser Section 3.12 Open Items)
• ML19282B400  + (Forwards Responses to NRC Environ Review Questions & Responses to R Zussman at Argonne Natl Lab.This Info Will Be Incorporated Into App A.4 of Suppl 6 to Er in Mar 1979)
• ML20054F709  + (Forwards Responses to NRC Feb,Mar & Apr Requests for Addl Info,To Be Incorporated Into Amend 69 to PSAR)
• AECM-81-347, Forwards Responses to NRC Formal & Informal Requests for Addl Info Re Fsar.Changes Will Be Incorporated Into Future FSAR Amend  + (Forwards Responses to NRC Formal & Informal Requests for Addl Info Re Fsar.Changes Will Be Incorporated Into Future FSAR Amend)
• AECM-81-340, Forwards Responses to NRC Formal & Informal Requests for Addl Info Re Fsar.Changes Will Be Incorporated Into Future FSAR Amend  + (Forwards Responses to NRC Formal & Informal Requests for Addl Info Re Fsar.Changes Will Be Incorporated Into Future FSAR Amend)
• ML18024B284  + (Forwards Responses to NRC Forwarding Notice of Violation,Notice of Imposition of Civil Penalties & Order Modifying License.Outlines Corrective Actions Taken.Forwards Civil Penalty Fee)
• ML19350E199  + (Forwards Responses to NRC Generic Ltr 81-04 Re Loss of Ac Power.Includes Description of Transmission & Power Distribution Sys & Actions for Power Restoration)
• ML20033C984  + (Forwards Responses to NRC Geotechnical FSAR Questions 241.6 & 241.7)
• ML20040B437  + (Forwards Responses to NRC Human Engineering Findings.Meeting Suggested for Either 820128 or Wk of 820208)
• B10413, Forwards Responses to NRC Info Request Re SAR for SEP Topic III-4.A Re Tornardo Missiles  + (Forwards Responses to NRC Info Request Re SAR for SEP Topic III-4.A Re Tornardo Missiles)
• ML19309H421  + (Forwards Responses to NRC Info Requests 212.102,212.107 & 212.72 Re Fsar.Plant Will Employ Leakage Return & Leakage Detection Sys Which Assist in Identifying & Controlling post-LOCA ECCS Leakage)
• ML20083P632  + (Forwards Responses to NRC Informal Questions Re IE Bulletin 80-11, Masonry Walls. All Load Combinations in Design Criteria,Including Obe,Sse & Tornado Depressurization,Addressed)
• NRC-92-0038, Forwards Responses to NRC Mechanical Engineering Branch 920221 Request for Addl Info on 910924 Proposed Amend to License NPF-43 Re Uprated Power Operation.Responses Withheld (Ref 10CFR2.790)  + (Forwards Responses to NRC Mechanical Engineering Branch 920221 Request for Addl Info on 910924 Proposed Amend to License NPF-43 Re Uprated Power Operation.Responses Withheld (Ref 10CFR2.790))
• NSD-NRC-96-4857, Forwards Responses to NRC Mechanical Engineering Branch Questions Including high-energy Line Break  + (Forwards Responses to NRC Mechanical Engineering Branch Questions Including high-energy Line Break)
• ML20236X219  + (Forwards Responses to NRC Notices of Violation & Deviation from 871026-1123 in Response to Pb Block Request.Related Correspondence)
• ML20236N376  + (Forwards Responses to NRC Oct 1986 Questions Re Topical Rept USG-684-1 on Environstone Gypsum Cement as Solidification Media,Per 10CFR61)