LD-93-016, Submits Summary of CESSAR-DC Safety Analyses Reanalyzed to Reflect Resolution of Dser Open Items.Summary of Remaining Reanalyses Will Be Submitted by End of Feb 1993
LD-93-012, Forwards Draft Sys 80+ Certified Design Descriptions & Associated ITAAC
LD-93-011, Forwards Responses to 22 Issues Re Closure of Sys 80+ Draft SER Issues
LD-93-014, Forwards Addl Certified Design Descriptions & ITAAC for Sys 80+
LD-92-072, Forwards Description of Human Reliability Analysis Methodology Used in Probabilistic Risk Assessment
LD-92-067, Forwards Rev 0 to Dctr 12, Sys 80+ Reactor Coolant Pump Seal Loss of Seal Cooling,Test Data Rept, to Fulfill Commitment Made at 920422-23 Piping & Mechanical Design Review Meeting
LD-92-064, Forwards Info to Supplement Previous RAI Responses Re Sys 80+.Encls Include Info Re Size & Type of Modeling Elements Used in Analysis of Containment Structure & Commitment to Use More Conservative Radiological Dispersion Factors
LD-92-022, Forwards NRC Re Addl Info for NRC Staff Review of CESSAR-Design Certification
LD-92-017, Forwards Response to NRC Re Addl Info for NRC Staff Review of CESSAR Design Certification
LD-92-033, Provides Revised Responses to NRC Requests for Addl Info Re Human Factors Engineering,Per
LD-92-027, Forwards Summary of Interface Requirements for Sys 80+ Std Design & Corresponding Revs to C-E SSAR - Design Certification
LD-94-041, Responds to Re Violations Noted in Nonconformance Insp Rept 99900401/94-01.Corrective Actions:Purchase Order Issued to Stone & Webster Engineering Corp & Suppls Issued Cited Purchase Orders to Duke Engineering Svcs,Inc
LD-93-147, Forwards Human Factors Engineering Issues Re Response to cross-branch Chapter 18 Questions & Design Process Requirements A-3.6 Availability Verification
L-93-003, Forwards Request for Authorization to Introduce Special Nuclear Material in Bldgs 230 & 256-1
L-93-052, Provides Request for Addl Info Re Decommissioning Funding Plan Submitted on 920702
L-93-047, Application for Amend to License SNM-33,reflecting Changes in Plant & Organization Over Past Few Yrs Re Hematite Nuclear Fuel Mfg Facility
L-93-034, Submits 30 Day Rept of 930804 Criticality Alarm Sys Inoperability.Caused by Tripped Circuit Breaker Due to Inadvertent Circuit Overload.Circuits Walked Down & Checked by Electrician
LD-93-131, Forwards Formally Printed Amend R to Std SAR - Design Certification (CESSAR-DC). W/Two Oversized Figures
L-93-032, Requests Changes to Windsor Low Level Radioactive Storage Amend Ltrs & 1223 Re Interim Storage of Low Level Radwaste
LD-93-129, Submits Assessment of Potential for Changes to Tier 1 Design Descriptions & Insps,Tests,Analysis & Acceptance Criteria (Dd/Itaac),Submitted from 930430-0630
LD-93-100, Forwards Matl to Close follow-on Questions to Dser Responses.Attachment 1 Provides Responses to Questions on Fire & Flood Portions of PRA
L-93-023, Forwards Applications to Bifurcate License SNM-1067 Into Two Separate Licenses,Consisting of Mfg License & Lab License. Purpose of Separation Is to Simplify Shutdown of Mfg Operations W/O Impacting Ongoing R&D Operations
LD-93-059, Forwards Results for Levels 2 & 3 of Sys 80+ PRA & Revised Response to Open Item 19.1.2.1.1.8-1
L-93-019, Forwards Rev 0 to Hematite Nuclear Fuel Mfg Facility Emergency Plan & Discussion of Changes to Plan in Response to NRC Comments
L-93-106, Requests Withdrawal to Bifurcate License SNM-1067.Purpose Was to Bifurcate License to Cover Manufactoring & Lab Operations Which Have Been Discontinued
LD-93-025, Forwards Small Break LOCA Realistic Evaluation Model Topical Rept,Cen 420-P,Vol 1,Part 1,describing Calculation Models.Withheld (Ref 10CFR2.790)
LD-93-058, Forwards Requested Info Re Sys 80+ Fire Protection & Revised Dser Responses
LD-93-057, Forwards Revisions to Chapters 2 & 3 of CESSAR-DC Sys 80+ SAR - Seismic/Structural Changes
L-93-011, Application for Amend to License SNM-33,re Hematite Consolidation Equipment,Bldgs & Processes
LD-93-038, Forwards Eleven Prototype Sys Design Descriptions & Associated ITAAC for Review & Approval