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• NRC-95-4494, Forwards Rev 4 of AP600 Ssar,Closing Many Dser Open Items. Itemization of Items Closed by Transmittal Will Be Provided by Separate Cover.Ssar Contains Proprietary Info.Proprietary Info Withheld Per 10CFR2.790  + (Forwards Rev 4 of AP600 Ssar,Closing Many Dser Open Items. Itemization of Items Closed by Transmittal Will Be Provided by Separate Cover.Ssar Contains Proprietary Info.Proprietary Info Withheld Per 10CFR2.790)
• DCL-95-134, Forwards Rev 4 of Diablo Canyon Security Force Training & Qualification Plan.Encl Withheld Per 10CFR2.790(d)  + (Forwards Rev 4 of Diablo Canyon Security Force Training & Qualification Plan.Encl Withheld Per 10CFR2.790(d))
• ML20196D454  + (Forwards Rev 4 of Mechanical Review Issues List (Ril). Rev Includes Review Issue 10 Re Component Cooling Water Sys Butterfly Valve at Outlet of Residual Heat Removal Hx.Rev of Ril Reflects Info That Cygna Gained Prior to Dec 1987)
• ML20096C386  + (Forwards Rev 4 of NSPNAD-8608-A, Reload Safety Evaluation Methods for Application to Monticello Nuclear Generating Plant)
• ML20056F958  + (Forwards Rev 4 of Physical Security Plan,Reflecting Removal of Door 5 & Installation of Improved Locks & Lockguards on Outer Perimeter of Door 6.Rev Withheld,Per 10CFR2.790(d)(1))
• ML20235R196  + (Forwards Rev 4 of Pipe Support Review Issues List. Any Procedural Control Issues Associated W/Author Original Pipe Support Reviews of Gibbs & Hill Being Processed as Part of Ongoing Design Control Assessments)
• ML20154P422  + (Forwards Rev 4 of Portsmouth Nuclear Criticality Safety (NCS) Program Cap,Reflecting Current Status of NCS CAP Tasks.Changes Are Reflected by Margin Bars on right-hand Side of Document)
• ML20210U686  + (Forwards Rev 4 of Project Procedure PP-07, Discrepancy Repts, Which Incorporates Addl Reviews Performed by Technical Advisory Group)
• ML20093F585  + (Forwards Rev 4 of Re Ginna Nuclear Power Plant Training & Qualification Plan for Security Officers.Encl Withheld)
• NSD-NRC-98-5642, Forwards Rev 4 of Section 2.1 of AP600 Certified Design Matl, ,for Staff Review.Revised Section Is Based on Changes to Rev 3,dtd 970516  + (Forwards Rev 4 of Section 2.1 of AP600 Certified Design Matl, ,for Staff Review.Revised Section Is Based on Changes to Rev 3,dtd 970516)
• NSD-NRC-98-5648, Forwards Rev 4 of Section 2.6, Electric Power Sys of AP600 Certfified Design Matls,Dtd 980406.Section Transmitted in Advance of Planned Submittal for Rev 4 to Allow Earlier Staff Review  + (Forwards Rev 4 of Section 2.6, Electric Power Sys of AP600 Certfified Design Matls,Dtd 980406.Section Transmitted in Advance of Planned Submittal for Rev 4 to Allow Earlier Staff Review)
• ML20064N530  + (Forwards Rev 4 of Training & Qualification Plan & Rev 10 & Page Changes to Rev 9 to Physical Security Plan.Revs & Pages Withheld (Ref 10CFR73.21))
• NOC-AE-000130, Forwards Rev 4 to 0ERP01-ZV-IN01, Emergency Classification. Proposed Changes Presented to State & Local Authorities & Provided Approval  + (Forwards Rev 4 to 0ERP01-ZV-IN01, Emergency Classification. Proposed Changes Presented to State & Local Authorities & Provided Approval)
• W3P90-1162, Forwards Rev 4 to 10-Yr Inservice Insp Program First Interval 1985-1995  + (Forwards Rev 4 to 10-Yr Inservice Insp Program First Interval 1985-1995)
• ML20133K550  + (Forwards Rev 4 to 1000-PLN-7200.02, Gpu Nuclear Corp Recovery QA Plan for TMI Unit 2. Rev Notes Changes in Organizational Structure & Incorporates 840613 Commitments)
• ML20133K554  + (Forwards Rev 4 to 1000-PLN-7200.02, Gpu Nuclear Corp Recovery QA Plan for TMI Unit 2. Rev Notes Changes in Organizational Structure & Incorporates 840613 Commitments)
• ML20203A938  + (Forwards Rev 4 to 15737-2-M72-DS01, TMI-2 Div Sys Description for Dewatering Sys for Defueling Canisters. Changes Reflect Mods to Sys Resulting from Startup & Test Operations)
• ML20128A157  + (Forwards Rev 4 to 1958, Fire Protection Evaluation Rept, Incorporating New Matl Re Safe Shutdown.Deviations from 10CFR50,App R Will Be Transmitted Separately.Rev 5 Will Include Deviations as New Section of Rept)
• ML20206G208  + (Forwards Rev 4 to 2BVM-179, ASME Code Baseline Document)
• ML20203N167  + (Forwards Rev 4 to 3526-004, Div Sys Description for Auxiliary Bldg Emergency Liquid Cleanup Sys (Epicor II))
• ML20214L232  + (Forwards Rev 4 to 3527-006, Submerged Demineralizer Sys, Technical Evaluation Rept & Rev 5 to 3527-005, Submerged Demineralizer Sys, Sys Description,As Annual Update Per NRC 820204 Request)
• ML20214P453  + (Forwards Rev 4 to 4350-3153-85-1, Load Handling Inside Containment & Over Fuel Pool a SER, for Review & Approval. Load Drop in Stated Area Unlikely.Rev Deletes Lift Height Restrictions for General Containment.Fee Paid)
• ML20238C618  + (Forwards Rev 4 to 4710-3255-86-0007, SAR for Pressurizer Defueling Sys, for Review & Approval.Rev Supersedes Rev 3 Submitted on 870721 & Permits Addition of Filter Canister to Primary Sys Flowpath)
• PY-CEI-NRR-0223, Forwards Rev 4 to 80A4425, Preservice Insp Program Plan: RCIC, 80A4426, ...:Feedwater Sys & 80A4423,...:LPCS Sys. Revs Replace Preservice Insp Program Plans Submitted w/841214 Ltr  + (Forwards Rev 4 to 80A4425, Preservice Insp Program Plan: RCIC, 80A4426, ...:Feedwater Sys & 80A4423,...:LPCS Sys. Revs Replace Preservice Insp Program Plans Submitted w/841214 Ltr)
• ML20199G552  + (Forwards Rev 4 to AP-404, Loss of Decay Heat Removal & Rev 4 to AP-604, Waterbox Tube Failure)

• NRC-94-4078, Forwards Rev 4 to AP600 Design Certification Test Program Overview  + (Forwards Rev 4 to AP600 Design Certification Test Program Overview)

• NSD-NRC-97-5224, Forwards Rev 4 to AP600 Emergency Response Guidelines Which Completes Westinghouse Response to RAI Re Open Item Tracking Sys Item 5519 That Is Now Closed  + (Forwards Rev 4 to AP600 Emergency Response Guidelines Which Completes Westinghouse Response to RAI Re Open Item Tracking Sys Item 5519 That Is Now Closed)
• NRC-95-4510, Forwards Rev 4 to AP600 Pra. Encl Contains PRA Sensitivity & Importance Analyses,Rtnss Focused PRA Sensitivity Study, Low Power & Shutdown Pra,Winds,Floods & Other External Events Evaluation & Updated Results Chapter  + (Forwards Rev 4 to AP600 Pra. Encl Contains PRA Sensitivity & Importance Analyses,Rtnss Focused PRA Sensitivity Study, Low Power & Shutdown Pra,Winds,Floods & Other External Events Evaluation & Updated Results Chapter)
• ML20090H928  + (Forwards Rev 4 to Administrative Procedure APA-ZZ-00010, Conduct of Operations-Operations. Rev More Clearly Defines Shift Advisor Responsibilities)
• ML13303B162  + (Forwards Rev 4 to Amend Applications 78 & 64 to Licenses NPF-10 & NPF-15,respectively,re Spent Fuel Reracking & Proposed Tech Spec on Request from Staff Requiring Min Spent Fuel Pool Boron Concentration)
• ML13303B163  + (Forwards Rev 4 to Amend Applications 78 & 64 to Licenses NPF-10 & NPF-15,respectively,re Spent Fuel Reracking & Proposed Tech Spec on Request from Staff Requiring Min Spent Fuel Pool Boron Concentration)
• ML20215M375  + (Forwards Rev 4 to Application for Renewal of License SNM-778 in Response to NRC Questions & Changes to Organization of Lynchburg Research Ctr.Lynchburg Research Ctr Will Change to Naval Nuclear Fuel Div Research Lab)
• ML20198G751  + (Forwards Rev 4 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section))
• ML20059A519  + (Forwards Rev 4 to Artifical Island Security Plan,Per 10CFR50.54(p).Rev Withheld)
• ML20135A743  + (Forwards Rev 4 to Aug 1979 Security Force Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld (Ref 10CFR73.21))
• ML20212G072  + (Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site)
• ML20140E772  + (Forwards Rev 4 to B&Roe-COM4-1-NP, Corporate Operations Manual Part IV - Functional Manuals,Section I,Nuclear QA Manual. Changes Implemented on 860101)
• ML20140E776  + (Forwards Rev 4 to B&Roe-COM4-1-NP, Corporate Operations Manual Part IV - Functional Manuals,Section I,Nuclear QA Manual. Changes Implemented on 860101)
• ML20206M957  + (Forwards Rev 4 to BAW-1919, B&W Owners Group Safety & Performance Improvement Program. Rev Includes Sensitivity Study by MPR Assoc.Study Is Not Sufficient Basis for Drawing Final Conclusions & Should Not Be Used for Design Purposes)
• ML20153H115  + (Forwards Rev 4 to CASE-TR4, Topical Rept QA Program for Nuclear Section of Coordinating Agency for Supplier Evaluation, for Review & Approval.Rept Addresses Actions Taken by Case to Resolve NRC Concerns Expressed on 871019)
• ML20076K479  + (Forwards Rev 4 to CNEI-0400-24, Catawba Unit 1 Cycle 8 Colr. Rev Moves Listed Values to Colr,As Required by Amend 125 to Cns,Unit 1 TS)
• ML20082K150  + (Forwards Rev 4 to CNEI-0400-25, Catawba Unit 2 Cycle 7 Colr)
• ML20086H751  + (Forwards Rev 4 to CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components, Per Commitments Stated in Ref Documents)
• ML18066A414  + (Forwards Rev 4 to COLR, Containing Limits for Fuel Cycle 14 & Future Cycles)
• ML18066A415  + (Forwards Rev 4 to COLR, Containing Limits for Fuel Cycle 14 & Future Cycles)
• ML20138H769  + (Forwards Rev 4 to CPC-2A, QA Program Description for Operational Nuclear Power Plants, Due to Organizational Changes)
• ML20138H773  + (Forwards Rev 4 to CPC-2A, QA Program Description for Operational Nuclear Power Plants, Due to Organizational Changes)
• ML20085C735  + (Forwards Rev 4 to CPSES Inservice Testing Program Plan, Incorporating line-by-line Description of Changes to Reflect Format Identical to Changes Provided for Fsar,Per Generic Ltr 89-04)
• ML20073L640  + (Forwards Rev 4 to CPSES Unit 1 & 2 IST Plan for Pumps & Valves First Interval)
• ML20215M624  + (Forwards Rev 4 to CRGR Charter Issued to Conform to New NRC Organization Effective on 870412.Identical Ltrs Sent to Individuals on Encl List.W/O Rev)
• ML20133L123  + (Forwards Rev 4 to Calculation MCC-1227.00-00-0048, Dose Consequence Impact of Mark-BW Fuel Reload for Accidents Analyzed in Chapter 15 of McGuire Fsar)