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List of results

• ML18018B584  + (Forwards Rev 2 to Emergency Plan,Per Ser.Changes Reflect Cancellation of Unit 2,interfaces W/State of Nc Radiological Emergency Response Plan & Evacuation Time Study Results)
• ST-HL-AE-1658, Forwards Rev 2 to Emergency Plan,Per Util . Complete Data Not Provided in Some Cases Due to Unavailability of Design Detail.Ten & fifty-mile Maps Incomplete.Final Emergency Plan Will Be Submitted in June  + (Forwards Rev 2 to Emergency Plan,Per Util . Complete Data Not Provided in Some Cases Due to Unavailability of Design Detail.Ten & fifty-mile Maps Incomplete.Final Emergency Plan Will Be Submitted in June)
• ML20076D465  + (Forwards Rev 2 to Emergency Plan,Section 8.6,Page 50 & Rev 13 to EPIP-6,Pages 2 & 3 of 4,Attachment 1,Pages 1 & 2 of 2 & EPIP-14,Attachment 1,Page 1 of 1)
• ML20205A722  + (Forwards Rev 2 to Emergency Plan.Plan Became Detached in Processing of Author)
• ML20136C195  + (Forwards Rev 2 to Emergency Plan.Rev Addresses Concerns Expressed in NRC Re Draft SER on Emergency Preparedness)
• ML20100K278  + (Forwards Rev 2 to Emergency Preparedness Plan,Incorporating All Changes in)
• AECM-89-0196, Forwards Rev 2 to Emergency Preparedness Transition Plan. Plan Originally Submitted as Info to Support Review of Amend  + (Forwards Rev 2 to Emergency Preparedness Transition Plan. Plan Originally Submitted as Info to Support Review of Amend)
• SNRC-1009, Forwards Rev 2 to Emergency Preparedness Implementing Procedures 4-7, Public Affairs Emergency Organization, Incorporating Changes Resulting from Administrative Review. Revised Table of Contents Encl  + (Forwards Rev 2 to Emergency Preparedness Implementing Procedures 4-7, Public Affairs Emergency Organization, Incorporating Changes Resulting from Administrative Review. Revised Table of Contents Encl)
• ML20101K294  + (Forwards Rev 2 to Emergency Response Capability Implementation Plan Schedule,In Response to Generic Ltr 82-33,Suppl 1 to NUREG-0737.First Emergency Preparedness Exercise Date Accelerated Approx 3 Months to 850904)
• ML20034E091  + (Forwards Rev 2 to Encl 2 of License Amend Request 92-01 to TS Re Spent Fuel Storage Pool Capacity Increase,Submitted on 920327 & Supplemented by 920511,28,0908 & 1008 Ltrs)
• ML20023D503  + (Forwards Rev 2 to Engineering Program Plan & Rev 3 to Project QA Plan Re Independent Design & Const Verification Program)
• ML20023D504  + (Forwards Rev 2 to Engineering Program Plan & Rev 3 to Project QA Plan Re Independent Design & Const Verification Program)
• ML20094M985  + (Forwards Rev 2 to Environ Qualification Master Equipment List. Requests Rev Be Reflected in SER for Purposes of Future IE Audit of Compliance w/10CFR50.49)
• B12343, Forwards Rev 2 to Environ Qualification Electrical Equipment Master List.Changes Made Based on Equipment Replacement & Clarification of Equipment/Component Certification Data  + (Forwards Rev 2 to Environ Qualification Electrical Equipment Master List.Changes Made Based on Equipment Replacement & Clarification of Equipment/Component Certification Data)
• ML20138N394  + (Forwards Rev 2 to Environ Qualification of Electrical Equipment Important to Safety, in Response to SER Outstanding Issue 6)
• ML20138N399  + (Forwards Rev 2 to Environ Qualification of Electrical Equipment Important to Safety, in Response to SER Outstanding Issue 6)
• ML20077N007  + (Forwards Rev 2 to Evacuation Estimates within Plume Exposure Pathway Emergency Planning Zone for Braidwood Nuclear Generating Station)
• ML20077M395  + (Forwards Rev 2 to Evaluation of Drywell Insulation Debris Effects on ECCS Pump Performance, Completing Response to Generic Issues Branch 830721 Request)
• ML20151Y487  + (Forwards Rev 2 to Event Rept (Er) 97-21,rev 2 to Er 97-22 & Rev 2 to Er 98-05,each Re Autoclave Safety Sys Failures IAW 10CFR76.120(c)(2).Revs Are Submitted to Identify That More than One Reporting Criterion Was Met as Result of Events)
• ML20137N688  + (Forwards Rev 2 to Exemption Request 2-008 Re Requirements of 10CFR50,App R Per NRC Audit,Correcting Error in Installation of Fire Barriers in Area 2-005.List of Fire Doors to Be Included in Exemption Request 1-041 Encl)
• FVY-84-140, Forwards Rev 2 to FSAR for Vermont Updated Yankee Nuclear Power Plant,Consisting of Updated Pages Reflecting Plant Conditions 6 Months Prior to 840531 Filing  + (Forwards Rev 2 to FSAR for Vermont Updated Yankee Nuclear Power Plant,Consisting of Updated Pages Reflecting Plant Conditions 6 Months Prior to 840531 Filing)
• ML20091C208  + (Forwards Rev 2 to FSV-P-SCP-100, Fort St Vrain Initial Radiologial Site Characterization Program to Replace Proprietary Version Transmitted by)
• ST-HL-AE-2024, Forwards Rev 2 to Facility Emergency Plan,Incorporating Resolutions to NRC 870330 Telcon Comments.Appeals NRC Rejection of Util Commitment to Provide Nuclear Engineer within 1 H of Site Vs NUREG-0654 30 Minutes,Per Encl  + (Forwards Rev 2 to Facility Emergency Plan,Incorporating Resolutions to NRC 870330 Telcon Comments.Appeals NRC Rejection of Util Commitment to Provide Nuclear Engineer within 1 H of Site Vs NUREG-0654 30 Minutes,Per Encl)
• NRC-99-0002, Forwards Rev 2 to Fermi 2 Improved Tss.Attachment 1 Contains Brief Abstract of Changes & Attachment 2 Contains Revised Pages Along with Rev Instructions  + (Forwards Rev 2 to Fermi 2 Improved Tss.Attachment 1 Contains Brief Abstract of Changes & Attachment 2 Contains Revised Pages Along with Rev Instructions)
• ML20204F302  + (Forwards Rev 2 to Figure 2 of Technical Data Rept 580 Re Isolation Condenser Sys Piping Cracked Welds,Repair & Failure Analysis)
• ML20153D364  + (Forwards Rev 2 to Final Rept Updated Probabilistic Seismic Hazard Analyses for Paducah Gaseous Diffusion Plant Paducah, Ky, for NRC Approval.Deviations from Procedural Requirements Identified & Corrective Actions Implemented)

• ML17214A627  + (Forwards Rev 2 to Fire Hazard Analysis)
• L-83-603, Forwards Rev 2 to Fire Hazard Analysis  + (Forwards Rev 2 to Fire Hazard Analysis)

• B12484, Forwards Rev 2 to Fire Hazard Analysis,Millstone Unit 1  + (Forwards Rev 2 to Fire Hazard Analysis,Millstone Unit 1)
• B12483, Forwards Rev 2 to Fire Hazards Analysis,Millstone Unit 2, Including Updates to Analysis Through Dec 1986  + (Forwards Rev 2 to Fire Hazards Analysis,Millstone Unit 2, Including Updates to Analysis Through Dec 1986)
• ML20214U914  + (Forwards Rev 2 to Fire Protection Program Manual,App F, Updated Fire Hazards Analysis Rept,Rancho Seco Nuclear Generating Station, Omitted from Util 860116 Request for License DPR-54 Amend Rev)
• ML20247E149  + (Forwards Rev 2 to Fire Protection Program Plan for Fort St Vrain Unit 1)
• TXX-8942, Forwards Rev 2 to Fire Protection rept.Page-by-page Description of Changes Encl.Group Number Assigned Level of Significance for Each Change Made to Fire Protection Rept Consistent W/Util  + (Forwards Rev 2 to Fire Protection rept.Page-by-page Description of Changes Encl.Group Number Assigned Level of Significance for Each Change Made to Fire Protection Rept Consistent W/Util)
• ML20042G254  + (Forwards Rev 2 to Ford Nuclear Reactor Requalification Program, for Review & Approval)
• ML20118A391  + (Forwards Rev 2 to Fort Calhoun Station Cycle 14 Core Operating Limits Rept. Section 6.0 & Figure 3 Revised to Reflect Increase in Peak Linear Heat Rate)
• ML20083P221  + (Forwards Rev 2 to Fsar,Including Page 14-106 Inadvertently Omitted from Rev 1)
• ML20215J280  + (Forwards Rev 2 to Fundamental Nuclear Matl Control Plan. Rev Withheld (Ref 10CFR2.790))
• ML20125A980  + (Forwards Rev 2 to GE Drf 00664 Index 9-4, ASME Section Viii Evaluation of Oyster Creek Drywell for W/O Sand Case..., Incorporating Changes from Internal Review Which Identified Need for Mesh Refinement in Finite Element Model)
• ML20141E792  + (Forwards Rev 2 to GE MDE-137-0585, Analysis to Extend Operator Action Time for Alternate Shutdown Panels in Support of Fitzpatrick Compliance to App R, Clarifying 850614 Rept & Justifying Exemption from Section III.L.1)
• ML20141E797  + (Forwards Rev 2 to GE MDE-137-0585, Analysis to Extend Operator Action Time for Alternate Shutdown Panels in Support of Fitzpatrick Compliance to App R, Clarifying 850614 Rept & Justifying Exemption from Section III.L.1)
• TXX-6395, Forwards Rev 2 to Generic Issues Rept,Evaluation & Resolution of Generic Technical Issues for Conduits & Conduit Supports & Vols I-III Ref Documents  + (Forwards Rev 2 to Generic Issues Rept,Evaluation & Resolution of Generic Technical Issues for Conduits & Conduit Supports & Vols I-III Ref Documents)
• ML18031B232  + (Forwards Rev 2 to Generic Procedure, Corrective Action, Incorporated Into Part I,Section 2.16 of Nuclear QA Manual.Procedure Part of Util Commitment to Meet Requirements of NRC Order EA-85-049 Modifying License)
• ML18031B233  + (Forwards Rev 2 to Generic Procedure, Corrective Action, Incorporated Into Part I,Section 2.16 of Nuclear QA Manual.Procedure Part of Util Commitment to Meet Requirements of NRC Order EA-85-049 Modifying License)
• RBG-27036, Forwards Rev 2 to Geotechnical Calculation G(c)-232 in Response to NRC Request.Info in Support of Application for Amend to License NPF-47 Re Settlement Monitoring Submitted by  + (Forwards Rev 2 to Geotechnical Calculation G(c)-232 in Response to NRC Request.Info in Support of Application for Amend to License NPF-47 Re Settlement Monitoring Submitted by)
• DCL-85-270, Forwards Rev 2 to Guard Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21)  + (Forwards Rev 2 to Guard Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21))
• ML20148Q222  + (Forwards Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45, Addressing Resolution of Issues from 871207 Meeting W/Nrc)
• ML18012A363  + (Forwards Rev 2 to Harris Unit 1 Cycle 7 COLR, Incorporating Requirements of TS 3.3.3.2 Re Movable Incore Detectors,Relocated from TS Amend 65 to Facility Operating Licensed by NRC on 960724)
• HNP-96-153, Forwards Rev 2 to Harris Unit 1 Cycle 7 COLR, Incorporating Requirements of TS 3.3.3.2 Re Movable Incore Detectors,Relocated from TS Amend 65 to Facility Operating Licensed by NRC on 960724  + (Forwards Rev 2 to Harris Unit 1 Cycle 7 COLR, Incorporating Requirements of TS 3.3.3.2 Re Movable Incore Detectors,Relocated from TS Amend 65 to Facility Operating Licensed by NRC on 960724)
• HNP-95-011, Forwards Rev 2 to Harris Unit 1,Cycle 6 Colr  + (Forwards Rev 2 to Harris Unit 1,Cycle 6 Colr)
• ML18011A779  + (Forwards Rev 2 to Harris Unit 1,Cycle 6 Colr.)
• ML17055B334  + (Forwards Rev 2 to High Energy Line Break Evaluation Rept (Effect on Nonsafety-Related Control Components) Nine Mile Point Unit 2, Superseding 851211 Rev 1.High Energy Line Break in Turbine Bldg Bounded by Chapter 15 of FSAR)
• ML17055B335  + (Forwards Rev 2 to High Energy Line Break Evaluation Rept (Effect on Nonsafety-Related Control Components) Nine Mile Point Unit 2, Superseding 851211 Rev 1.High Energy Line Break in Turbine Bldg Bounded by Chapter 15 of FSAR)