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Category:VENDOR/MANUFACTURER TO NRC
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Pages in category "VENDOR/MANUFACTURER TO NRC"
The following 200 pages are in this category, out of 3,340 total.
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- L-88-104, Discusses Progress in Constructing New Shipping/Receiving Area at Hematite Site.Bldg Will Be Placed in Use on or About 881005.Figure Illustrating New Area Encl
- L-89-004, Forwards Response to NRC Re Violations Noted in Insp Rept 70-1151/88-19 on 881226-28.Response Withheld (Ref 10CFR2.790)
- LD-78-081, Requests Combustion Engr Standard Safety Analysis Rept Preliminary Design Approval 2 Be Extended Until 801231.Also Finds Imposition of Fee for Pda 2 Extension Inappropriate
- LD-78-086, Responds to NRC Request for List of All Appl & Request for Review to Be Submitted Between 781117 & 811231.FSAR Was Submitted 781020 & No Others Anticipated
- LD-78-095, Forwards Amend 2 to Appendix a to CESSAR-FSAR Tendering Draft
- LD-82-025, Forwards Sample Environ Test Rept of Type Which Will Be Generated by Use of Topical Rept on Class IE Qualification, CENPD-255.Rept Withheld (Ref 10CFR2.790)
- LD-82-063, Provides Descriptions of Methods Used in Thermal Equivalence & Time Margin Analyses.Submittal Completes Action on Open Item 1 to CESSAR FSAR
- LD-82-068, Responds to 820312 Request for Info Re Conformance W/Cessar Interface requirements.Safety-related Interface Requirements Are Documented in SAR & Addressed in SER (NUREG-0852)
- LD-82-075, Forwards Itemized Review of Compliance of CESSAR FSAR w/10CFR20,50 & 100.Sys 80 NSSS Design Similar to Earlier C-E NSSS Which Met NRC Regulations
- LD-82-076, Forwards Long-Term Iodine Control in Reactor Containment Bldgs Using C-E Iodine Removal Sys, Per CESSAR SER Confirmatory Item 12.Rept Incorporates 820309 Discussion W/ NRC Re Containment Sampling & Radiolysis of Hydrazine
- LD-82-078, Forwards Rept Responding to Confirmatory Item 9 of CESSAR Ser.Rept Presents Evaluation of Natural Circulation Cooldown W/Controlled Voiding in Sys 80 Nsss.Confirmatory Item 9 Closed Out
- LD-83-004, Informs That Schedule Will Be Provided by 830228 in Response to Questions Re Application of Statistical Combination of Uncertainties Methodology to Sys 80TM Reactor Design
- LD-83-005, Advises That Administrative Slippage in CESSAR-F Schedule Unwarranted & counterproductive.CESSAR-F Final Design Approval Should Be Issued by Mar 1983
- LD-83-008, Requests CESSAR-F Ser,Section 5.4.3, Shutdown Cooling Sys, Be Changed to Reflect Commitment to Perform Boron Mixing Testing on First Sys 80 Reactor
- LD-83-010, Forwards Proprietary & Nonproprietary Statistical Combination of Uncertainties Part Ii,Uncertainty Analysis of Limiting Conditions for Operation,C-E Sys 80 NSSS, Part Iii. Proprietary Versions Withheld (10CFR2.790)
- LD-83-013, Responds to NRC 820326 Request Re Info Concerning Rapid Depressurization & DHR Capability.Some Responses Will Rely on plant-specific Info from Balance of plant.C-E Owners Group Rept Will Be Submitted by 830630
- LD-83-015, Forwards Proprietary & Nonproprietary Versions of Sys 80 CESSAR FSAR Responses to Questions on Cesec. Affidavit Encl.Proprietary Version Withheld (Ref 10CFR2.790)
- LD-83-016, Advises That Response to NRC Re Util 820330 Submittal on Core Protection Calculators Will Be Submitted by 830331
- LD-83-017, Forwards Draft Mods to Sys 80 Fuel Design for CESSAR-F. Mods Include Completion of Seismic & LOCA Loading Analyses. Changes Will Be Formally Incorporated Into CESSAR-F in Next Amend
- LD-83-018, Advises That Results of CESSAR-F Load Limiter Tests in Reactor Vessel Lower Key Horizontal Supports Will Be Provided to Az Public Svc During Second Quarter 1983 for Inclusion in Dockets for Palo Verde Plants
- LD-83-019, Forwards Amended CESSAR-F Section 15.3.3, Single Reactor Coolant Pump Rotor Seizure W/Loss of Offsite Power, in Response to NRC 820115 Request & SER Comfirmatory Item 16
- LD-83-024, Provides Ref Info in Order to Close Out NUREG-0737,Items II.K.2.13, Thermal-Mechanical Rept, II.K.2.17, Potential Voiding in RCS & II.K.3.30, 10CFR50 App K Small Break LOCA Methods
- LD-83-025, Submits Addl Info Re Natural Circulation Cooldown of C-E Sys 80 NSSS, Transmitted by Per SER Confirmatory Item 9.Analysis Shows Available condensate,300,000 Gallons, Provides More than Sufficient Cooling Water
- LD-83-027, Forwards Response to Questions 1-4 Re Feedwater Line Break Methodology,As Rev to App 15B of CESSAR-F, Methods for Analysis of Loss of Feedwater Inventory Events. Rev Will Be Incorporated Into Next CESSAR-F Amend
- LD-83-029, Advises That Response to Questions Re Parts II & III of Statistical Combination of Uncertainties Rept Will Be Provided by 830429,per SER Open Item 3
- LD-83-031, Forwards Proprietary & Nonproprietary Responses to 830131 Questions Re Core Protection Calculators & Reactor Power Cutback Sys for CESSAR-F.Proprietary Responses Withheld (Ref 10CFR2.790)
- LD-83-034, Forwards Revised Long-Term Iodine Control in Reactor Containment Bldgs Using C-E Iodine Removal Sys, Per 830323 Meeting Commitment to Revise CESSAR-F SER Confirmatory Item 12
- LD-83-035, Forwards Nonproprietary & Proprietary Versions of, CESSAR Fuel & Control Element Assembly Design Evaluation Summary Rept, in Response to NRC Request.Proprietary Version Withheld (Ref 10CF2.790)
- LD-83-036, Forwards Sys 80 CESSAR Fsar,Responses to Questions on Steam Line Break Method, Per SER Confirmatory Item 14.Proprietary Responses Withheld (Ref 10CFR2.790)
- LD-83-044, Forwards Amend 8 to CESSAR-F.List of Rev Topics Encl
- LD-83-049, Forwards Review of CESSAR-F Against Requirements of Cp/Ml Rule 10CFR50.34(f) & Selective Sections of App B & Chapter 3 of CESSAR-F.Only Fraction of Rule Requirements within Scope of CESSAR-F.CESSAR-F Complies W/Rule
- LD-83-051, Summarizes 830425 Meeting W/Nrc Re Natural Circulation Cooldown Analysis for CESSAR-F.Reanalysis to Be Submitted by 830729
- LD-83-053, Forwards Basis for Design of Plant W/O Pipe Whip Restraints for RCS Main Loop Piping, to Demonstrate That guillotine-type Failure of RCS Main Loop Piping Need Not Be Considered in Design Basis for Sys 80
- LD-83-054, Clarifies plant-specific Info Needed Re CESSAR-F Supplemental Ser,Section 4.4.6, Statistical Combination of Uncertainties. No plant-specific Submittal Planned Since Verification of Values to Be Documented Internally
- LD-83-066, Forwards Reanalysis of Steam Generator Tube Rupture Event W/Loss of Offsite Power & Addl Single Failure,Per NRC 830426 Request.Info Completes SER Confirmatory Item 18
- LD-83-073, Forwards Proposed Rev to CESSAR-F Section 5.4.13 & App 5A, Reflecting Revised Pressurizer Relief Valve Blowdown Analysis.Proposed Changes Will Be Incorporated Into CESSAR-F in Future Amend
- LD-83-074, Forwards Computer Simulation of Natural Circulation Cooldown
- LD-83-076, Forwards Proprietary & Nonproprietary Encl 2-P & 2-NP to LD-83-010,Rev 1, Statistical Combination of Uncertainties Part III, Per SER Proprietary Rept Withheld (Ref 10CFR2.790).Affidavit Encl
- LD-83-085, Discusses Impact of Problems W/Reactor Coolant Pumps, Resistance Temp Detector Thermowells,Safety Injection Nozzle Thermal Sleeves & Control Element Assembly Identified During Palo Verde Hot Functional Testing
- LD-83-087, Forwards Rev to CESSAR-F Chapter 16 Proposed Tech Specs for Nsss.Changes Will Be Incorporated Into Future Amend
- LD-83-089, Discusses Referenceability of CESSAR-F Final Design Approval.Nrc Support for Standardization as Abstract Concept for Future Plants W/O Resolving Present Issues Inconsistent
- LD-83-096, Comments on NRC Sept 1983 Evaluation of Need for Rapid Depressurization Capability for C-E Plants.Evaluation Should Delete Requirement to Add PORVs Pending Outcome of Unresolved Safety Issue A-45
- LD-83-105, Informs That Reactor Vessel Lower Key Horizontal Support Load Limiting Device Test Results Will Not Be Available in Support of Palo Verde OL Schedule Until First Quarter 1984. Detainment Due to Unexpected Delays in Performing Tests
- 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
- LD-84-009, Forwards Interface Requirements Re Block Valves on Atmospheric Dump Valves to Close Out Confirmatory Item 2 of Sser 2 Re Steam Generator Tube Rupture Analysis
- LD-84-012, Forwards for Review,Amend 9 to C-E Std Sar.Major Changes Result from Response to Confirmatory Items & NRC Questions
- LD-84-013, Forwards Interface Requirement Re Shutdown Cooling Analysis of Reactor Coolant Gas Vent Sys Per Sser 2.Confirmatory Item Closed
- LD-84-022, Informs That Info Re Operability of Shutdown Cooling Sys Relief Valves in CESSAR Design Will Be Provided by Aug 1984 Upon Resolution of Co Thomas 840424 Concerns
- LD-84-039, Informs of Planned Mod to C-E Control Element Assembly Guide Tube Wear Sleeve.Mod Includes Relocation of Sleeve Flare,Sleeve Expansion Over Full Length of Sleeve & Relocation of Crimp,Providing Resistance to Axial Motion
- LD-84-041, Responds to 840327 Request for Info Re Potential Single Failure in Auxiliary Pressurizer Spray sys.C-E Completed Preliminary Review of Info Requested.Info Expected to Be Provided by Sept 1984
- LD-84-042, Forwards Items for Updating When SER Generated to Close Out Remaining Issues.Items Include Steam Generator Tube Rupture,Radiological Consequences of DBA & Shutdown Cooling (RHR) Sys
- LD-84-049, Forwards Response to Mechanical Engineering Branch 840424 Request for Addl Info Re Operability of Shutdown Cooling Sys Relief Valves Used on Sys 80 Std Plant.Valves in Question Will Function Under Anticipated Design Conditions
- LD-84-051, Discusses Potential Single Failure of Sys 80 Auxiliary Pressurizer Spray Sys.Potential Failure Involves Possibility of Valve CH-240 Sticking in Full Open Position.Info Closes Out CESSAR Confirmatory Issues 1 & 2,per NUREG-0852
- LD-84-055, Advises That Requested Addl Info Re SER Confirmatory Issue 4 Listed in Suppl 2 to NUREG-0852 Concerning Inadequate Core Cooling Instrumentation Will Be Submitted by Dec 1984
- LD-84-060, Forwards Minor Mods to CESSAR Chapter 14 to Facilitate Improved Testing Procedure.Changes Only Affect Tests Performed After Fuel Loading & Do Not Affect NRC Requirements.Mods Will Be Incorporated Into Amend to CESSAR
- LD-84-064, Responds to 841022 Request for Description of Measures Undertaken to Address Apparent Inconsistencies Between Palo Verde Tech Specs & CESSAR-F.Slides from 841004 Meeting, Discussing Verified & Possible Inconsistencies,Encl
- LD-84-067, Recommends Mods to Severe Accident Policy Statement (SECY-84-370).Any Ref Design,W/Valid Final Design Approval, Should Be Automatically Granted Referenceability for New Applications
- LD-84-069, Forwards marked-up CESSAR FSAR Pages Reflecting Review of Tech Specs Re First Sys 80 Plant.Rev Involves Interface Requirements for MSIV & Main Feedwater Isolation Valve Closure Time
- LD-84-070, Forwards Proposed Changes to CESSAR Re Startup Testing for Review.Changes Currently in FSAR Change Process & Will Be Incorporated in CESSAR Amend 10
- LD-84-071, Forwards CESSAR Changes Re Reduced HPSI Pump Flow.Reanalysis of Most Limiting Small Break LOCA Demonstrates That Sys Performance Is within Acceptance Criteria of 10CFR50.46
- LD-84-074, Forwards Summary Rept on Design Basis of Shutdown Cooling Sys Relief Valves for CESSAR Sys 80 & Summary Rept on Operability of Shutdown Cooling Sys Relief Valves for Palo Verde Units 1,2 & 3, Per 841109 Meeting
- LD-85-004, Forwards Palo Verde Technical Audit of Safety Analysis & Applicable CESSAR-F Analyses,Per .No Serious Technical Errors,Safety Concerns or Systematic Error Patterns found.C-E Design Process Adequate
- LD-85-007, Forwards List of Submittals to Close Out Final Design Approval on CESSAR Issues.Concurrence Requested That Future Submittals Will Be Reviewed & Approved in Timely Manner on CESSAR Docket to Meet Schedular Needs
- LD-85-009, Forwards Proprietary & Nonproprietary Comprehensive Vibration Assessment Program for Palo Verde Nuclear Generating Station Unit 1 (Sys 80 Prototype),Evaluation of Predictions.... Proprietary Rept Withheld (Ref 10CFR2.790)
- LD-85-012, Forwards Revised CESSAR Interface Requirements Re Atmospheric Dump Block Valves to Be Included in Future CESSAR Amend,Resolving Confirmatory Issue 2
- LD-85-013, Discusses CESSAR Confirmatory Issues 1 & 2 Re Single Failure Vulnerability of Auxiliary Pressurizer Spray.Power Supply Isolators for Valves CH-239 & CH-240 Will Be Added If Sufficient to Close Confirmatory Issues 1 & 2
- LD-85-014, Forwards Revs to 1984 Final Repts Re Removal of Safety Injection Nozzle Thermal Sleeve & CEA Guide Tube Brackets. Corrective Actions for Reactor Coolant Pumps & Temp Detector Thermowell Listed.Concurrence Requested by 850430
- LD-85-016, Informs of Transportation Error in 830811 Rev to CESSAR App 5A Re Nozzle Elevation of Pressurizer Safety Valve. Corrected Elevation Will Be Included in Future Amend to CESSAR
- LD-85-019, Forwards Comparison of NRC Secondary Water Chemistry Guidance W/Palo Verde/Cessar Proposed Water Chemistry & Response to NRC Questions Re Chemistry Program.Condenser Inservice Insp Program Beyond Scope of CESSAR Design
- LD-85-020, Requests Finalization of CESSAR Chapter 16 Tech Specs & Meeting in Bethesda,Md to Discuss Scope of Review.Impact of Review Should Be Minimized Based on Tech Specs Compared on word-by-word Basis W/Palo Verde Tech Specs
- LD-85-021, Withdraws Encl Info Re Proposed CESSAR Changes to Reduce Min Required LPSI & HPSI Flows.Reanalysis of CESSAR Events Provided on plant-specific Basis.Evaluation of Events for HPSI & LPSI Changes Impractical
- LD-85-022, Responds to 841126 Request for Addl Info Re Modified Acceptance Criteria for CESSAR-F Section 14.2.12.5.17 on Main & Emergency Feedwater Sys Test.Listed Criterion Will Be Added to Future Amend
- LD-85-024, Forwards Proposed Final Version of CESSAR Chapter 16 Sys 80 Tech Specs,Per 850502 Meeting W/Nrc.Completion of Review of Tech Specs Requested by End of June 1985 to Include Revs in Amend 10 to CESSAR
- LD-85-028, Forwards CESSAR FSAR Clarifications Re Safety Injection Sys Delay Time.Changes Identified as Part of Cleanup Effort to Close Out Amend 10
- LD-85-029, Forwards Results of CESSAR Analysis of Increased Blowdown for Pressurizer Safety Valves,Per Reactor Sys Branch Request.Analysis Consistent W/Analysis Submitted by Arizona Public Svc
- LD-85-033, Forwards Comments on Proof & Review Tech Specs,Per 850703 Request.Concurs W/Proposed Tech Specs.Ltr from Northeast Utils to NRC & marked-up Tech Specs Encl.Responses to Questions Per Being Prepared
- LD-85-034, Forwards Responses to 850710 Questions Re Review of CESSAR Sys 80 Tech Specs Covering Reactor Protective Sys Trip Setpoint Limits
- LD-85-039, Informs That Vendor Will Add Interface to CESSAR App B Item III.A.1.2 (Upgrade Emergency Support Facilities) to Facilitate Closeout of SPDS Issue.Requirement Will Be Added to CESSAR in Amend 10 or 11
- LD-85-042, Requests That Encl Forward Referenceability Provision Be Included in 850802 Application for Amend to CESSAR Final Design Approval,Per Section 8.3.6(1) of Commission Policy Statement on Severe Reactor Accidents..
- LD-85-043, Forwards Nonproprietary Revs 00 to CEN-304-NP & CEN-305-NP & Proprietary Revs 00 to CEN-304-P & CEN-305-P,per NRC Request for Generic Design Specs.Proprietary Repts Withheld (Ref 10CFR2.790)
- LD-85-044, Forwards Proprietary & Nonproprietary Rev 0 to Cpc/Ceac Software Mods for CPC Improvement Program. Proprietary Rept Withheld (Ref 10CFR2.790)
- LD-85-057, Forwards for Review,Amend 10 to C-E Std SAR in Response to Final Design Approval Issues,Nrc Questions & Tech Spec Consistency Review
- LD-85-063, Forwards Corrected Final Draft CESSAR Sys 80 Sts.Certifies That Tech Specs Adequately Envelope Design Basis Events & Consistent W/Cessar Up to & Including Amend 10 & Ssers 1 & 2
- LD-86-012, Forwards Revs 0 to Proprietary CEN-323-P & Nonproprietary CEN-323-NP, Reload Data Block... & Revs 3 to Proprietary CEN-39(A)-P & Nonproprietary CEN-39(A)-NP, CPC Protection Algorithm.... Proprietary Repts Withheld (Ref 10CFR2.790)
- LD-86-013, Requests Clarification That NRC Review of Ref Portion of Plant Application Closed to Extent That Util Commits to CESSAR as Approved Through Final Design Approval & Amend 1
- LD-86-015, Informs of Incorporation of 850311 Responses,Committing to Perform post-test Analysis of Semiscale Test S-UT-8 & Providing Results of post-test Analysis,To Close TMI Items II.K.3.30 & II.K.3.31
- LD-86-022, Forwards Proprietary Suppl 1,Rev 3 to CEN-39(A)-P & Nonproprietary Suppl 1,Rev 3 to CEN-39(A)-NP, CPC Protection Algorithm Software Change Procedure. Affidavit Encl.Proprietary Rept Withheld (Ref 10CFR2.790).Fee Paid
- LD-86-024, Forwards Proprietary & Nonproprietary Rev 0 to CEN-330,Rev 01 to CEN-304 & Rev 01 to CEN-305 Re Improvement Program. Proprietary Repts Withheld (Ref 10CFR2.790).Affidavit for Withholding Repts Encl.Fee Paid
- LD-86-034, Forwards Performance Info for C-E Supplied Nuclear Fuel for CY85 on plant-by-plant Basis,Per NRC 860618 Request.Info Includes Number of Fuel Assemblies & Fuel Rods Irradiated &/Or Discharged & Batch Average Burnups
- LD-86-038, Provides Info for Reactor Coolant Pump Data Bases on C-E Designed NSSS 80 for facilities.WPPSS-3 Should Be Added to Data Base
- LD-87-009, Forwards Response to 851029 Request for Addl Info Re Review of CESSAR Confirmatory Issues on Natural Circulation Cooldown & Steam Generator Tube Rupture.Info Needed to Complete Review
- LD-87-012, Forwards Generic Design Info in Response to 10CFR50.62, Requirements for Reduction of Risk from ATWS Events for Light Water-Cooled Nuclear Power Plants. Requirements Will Be Met When Existing Supplementary Protection Sys Modified
- LD-87-013, Informs That CESEC-III Computer Code Applicable to Analysis of FSAR Chapter 14 Events (Excluding ATWS) for Facility. Models Included in Code Applicable to Operating Conditions at Plant & Cover All Features of Facility NSSS
- LD-87-017, Responds to 870327 Questions Re Steam Generator Tube Vibration Observed at Palo Verde Units 1 & 2.Definition & Scope of Program to Review Phenomenon Will Be Available for Review W/Nrc in Approx 90 Days
- LD-87-019, Forwards Proprietary CENPD-275-P, C-E Methodology for Core Designs Containing Gadolinia-Urania Burnable Absorbers, in Support of Facility May 1989 Cycle 5 Startup.Fee Paid.Rept Withheld (Ref 10CFR2.790)
- LD-87-021, Provides Formal Description of C-E Efforts to Advance Sys 80R PWR Design & Advises That Sys 80 Design Including Consideration of EPRI Advanced LWR Design Requirements Document Revised
- LD-87-050, Requests NRC Adoption of Proposed Docketing Process for Forthcoming Revs to C-E Std SAR
- LD-87-051, Provides Design Info to Support Conclusion That Sys 80R in Compliance W/Atws Rule.Requests Closure of Issuance on CESSAR - F Docket.Response to NRC Evaluation of CEN-315,Sys 80R Encl
- LD-87-052, Requests That Steam Generator Tube Vibration Issue Be Closed on C-E Std SAR - FSAR (CESSAR-F) Docket.Any Potential Design Improvements for Future Steam Generators Can Be Reviewed as Part of Review of Improved Design Sys 80+
- LD-87-053, Forwards Revised Steam Generator Tube Rupture Analysis for Fsar.Rev Incorporates Revised Analysis Using Reactor Coolant Gas Vent Sys for Depressurization Purposes
- LD-87-054, Forwards Amend 12 to CESSAR Fsar,Modifying Sys 80R Design. Enhanced & Expanded Sys 80 Design Will Be Called Sys 80 Tm
- LD-87-056, Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request
- LD-87-068, Forwards Proposed Amend to CESSAR FSAR Describing Sys 80 Plus Design.Mods Comply W/Standardization & Severe Accident Policy Statements & Results in Upgrading of Final Design Approval FDA-2.Clarification of NRC Fees Requested
- LD-88-001, Corrects Record Re Info Previously Provided in Re post-accident Uncertainties Associated W/Core Exit Thermocouple Sys Supplied by C-E.NRC Should Disregard Inclusion of Plant in Previous Info Package
- LD-88-008, Forwards Proprietary Base Line Level 1 PRA for Sys 80r NSSS Design. Rept Presents Methodology & Results of Sys 80 PRA to Be Used for Evaluation of Design trade-offs for Sys 80+ Std Design
- LD-88-010, Forwards Proprietary Slides Used at 880202 Meeting Re Rev 01-P to CEN-203-P, Response to NRC Action Plan Item II.K.3.30,Justification of Small Break LOCA Methods. Encl Withheld (Ref 10CFR2.790)
- LD-88-014, Forwards Fee for 880120 Application for Amend to License SNM-1067,increasing Weight Percent of Enriched U That Can Be Processed at Facility
- LD-88-019, Forwards Addl Info Re Chemical & Vol Control Sys for Sys 80+TM Std Design,Per 871217 Request.Proposed Rev to C-E Std SAR, Design Certification Also Encl
- LD-88-020, Responds to NRC Request for Addl Info Re Chapter 1 Concerning Safeguards.Proposed Revision to C-E Engineering Std SAR & Responses to Specific Questions Also Encl
- LD-88-021, Forwards Response to NRC 871208 Request for Addl Info Re Reg Guides That Appear in CESSAR-DC,QA.Suggest That Meeting W/Nrc Staff Be Scheduled to Allow Overview Program Changes
- LD-88-025, Submits Clarifications to Re Organizational Changes & Appropriate Communication Channels Between Organizations.Organizational Chart & Other Pertinent Info Encl
- LD-88-026, Forwards Draft Revs to C-E Chapters 1,4,5 & 9 to C-E Std Sar.Meeting to Resolve Issues Re Schedule & Composition of Submittals as Part of Draft Licensing Review Bases & Related Issues,Requested
- LD-88-029, Remits Fee for 880427 Application for Renewal of License SNM-1067
- LD-88-033, Forwards Response to NRC 880226 Request for Addl Info on Chapter 17 to Rev 4 to Topical Rept CENPD-210A, QA Program, Including Revs to C-E 871130 & 880411 Responses
- LD-88-034, Provides Addl Info on CESSAR-DC Chapter 10 Re Secondary Water Chemistry,Per NRC 880225 request.CESSAR-DC Section 10.3.5.1 Revised to Make Clear That C-E Secondary Water Chemistry Program Includes Immediate Shutdown Limits
- LD-88-036, Forwards Response to Observations & Recommendations of Insp Rept 70-1100/86-04 on 860818-21.Meeting to Provide Clarifications Would Be Welcomed
- LD-88-038, Provides Proposed Resolutions for Four of Six Issues Which Make Up Topic Paper Set 2,including in-vessel Hydrogen Generation,Core Melt Progression & Vessel Failure & Hydrogen Ignition & Burning.Remaining Issues Submitted in 30 Days
- LD-88-039, Forwards Addl Info Re Chapters 1 & 10 to CESSAR-DC,per NRC 880311 Request
- LD-88-042, Provides Proposed Resolutions to Remaining Two Issues Committed to in Re Direct Containment Heating (Idcor Issue 8) & Debris Coolability (Idcor Issue 10).C-E Plans to Adopt 14 Resolutions Previously Submitted
- LD-88-046, Forwards Response to NRC 880315 Request for Addl Info Re CESSAR-DC,Chapter 10, Plant Sys Branch
- LD-88-047, Forwards Amend C to CESSAR-DC (Design Certification), Chapters 5,6 & 10.Summary of Significance of Revs Also Encl
- LD-88-054, Remits Fee for 880713 Application for Amend to License SNM-1067
- LD-88-059, Forwards Fee for 880701 Amend to Certificate of Compliance 9022 for Model CE-250-2.Fee Paid
- LD-88-061, Provides Overview of Further Anticipated Changes to Facilities,Proposed for Next Two Yrs & Independent of Current Commitments to Upgrade Facilities.Requests Encl Be Withheld Per 10CFR2.790
- LD-88-063, Forwards Rev to 880701 Application for Amend to Certificate of Compliance 9022,providing Addl Criticality Analysis & Computer Output Associated W/Criticality Analysis
- LD-88-064, Forwards Addl Info & Clarifications in Support of 880120 Application for Amend to License SNM-1067 to Increase Weight of Enriched U That Can Be Processed from 4.1 to 5%,per NRC 880125 Meeting Request
- LD-88-065, Requests That NRC Grant Condition to License SNM-1067, Authorizing Possession of U-235 Up to 5.0 Weight %,But Not Allowing Processing of Fuel Above 4.1 Weight % & Terminating Condition Upon Approval of Amend Request
- LD-88-066, Forwards DOE Advanced Reactor Severe Accident Program Proposed Resolutions for Severe Accident Issues,Topic Set 3. Resolutions to Listed Items Will Be Adopted in Development of Sys 80+ Std Design
- LD-88-068, Forwards Response to Request for Addl Info Re CESSAR-DC Chapters 1 & 5 Re Sabotage Protection,Per
- LD-88-069, Informs of Finalizing Review of QA Program Description of Rev 5 to CESSAR Topical Rept CENPD-210 & Anticipates Transmitting Review to NRC by Third Quarter 1988.Submittal Will Address Remaining QA Questions in Road Map
- LD-88-070, Provides Addl Info to Supplement Licensee Re Assessment of Facility Radiation Protection Program
- LD-88-075, Forwards Incident Rept on Shipping Container,Model CE-250-2. Shipping Container Found Damaged on 880714.Damage Occurred During Handling at Windsor as Result of Improper Handling & Handling Device Not Properly Maintained
- LD-88-081, Transmits Addl Info & Clarifications Requested by Bidinger Including,Tabulation of Affected Pages & Rev Numbers & Provides Proposed Change Pages Supporting Amend Request
- LD-88-088, Provides Proposed Resolution for Single Issue of Advanced Reactor Severe Accident Program Topic Paper Set 4, Essential Equipment Performance
- LD-88-089, Forwards Addl Info Re CESSAR-DC,Chapter 4,in Response to NRC 880628 Request
- LD-88-091, Forwards Summary of Sabotage Protection Considerations & Draft Requirements for Sabotage Design from EPRI Advanced LWR Requirements Document,Per NRC .Basis for Program Listed
- LD-88-098, Responds to NRC Re Violations Noted in Insp Rept 70-1100/88-07 on 880725-29.Effort Currently Underway to Reconstruct Log Sheets from Other Sources & Steps Being Taken to Prevent Recurrence
- LD-88-099, Responds to NRC Request for Addl Info Re Chapters 5 & 9 of CESSAR-DC Re Steam Generator Secondary Water Chemistry, Reactor Coolant Water Chemistry,Fire Protection Sys,Letdown Purification Line & Hydrogen Ignition
- LD-88-103, Forwards Nuclear Fuel Mfg Facility Independent Task Force Review Status Rept, Per Commitment 5 of
- LD-88-105, Forwards Fee for 880923 Request for Extension to 30-day Reporting Requirement for SNM Receipt Insp Measurement Data
- LD-88-106, Forwards Amend D to CESSAR Fsar,Including Revs to Chapters 2-7 & 18.Technical Review Should Be Allowed to Proceed Unencumbered Pending Settlement of Dispute Re Fees
- LD-88-108, Forwards Fee for 880930 Application for Amend to Certificate of Compliance 9022 for Model CE-250-2.Fee Paid
- LD-88-112, Remits Fee for 881011 Application for Amend to License SNM-33 to Reflect Use of New Warehouse & Removal of Bldg 251 & Portions of Bldg 250
- LD-88-113, Remits Fee for 881010 Application,Extending License SNM-33 from Dec 1988 to Dec 1989
- LD-88-114, Forwards Results of Radiological Survey for Bldgs 250 & 251. Release of Bldgs for Unrestricted Use Requested
- LD-88-117, Forwards Presentation Matls from 880927 Meeting on Fuel Facility Revitalization
- LD-88-119, Responds to NRC Request for Addl Info on Chapter 17 of CESSAR-DC.NRC Question 260.2 Incorporated in CENPD-210,Rev 5 as Part of Sections III.1,III.3 & Table III-1
- LD-88-128, Forwards QA Program in Response to NRC Request for Addl Info Re Chapter 17,CESSAR-DC QA
- LD-88-131, Forwards Rev 1 to Part 2 of C-E Nuclear Fuel Integrated Improvement Progam, W/Status of Commitments as of 881024
- LD-88-132, Forwards Advanced Reactor Severe Accident Program Topic Paper Set 6, Development of Severe Accident Mgt Program, for Review
- LD-88-134, Forwards Pages Inadvertently Omitted from Rev 1 to Part 2 of C-E Nuclear Fuel Integrated Improvement Program,
- LD-88-137, Forwards Fee for 881111 Application for Amend to License SNM-33,reflecting Organizational Changes,Per 10CFR170.31
- LD-88-222, Forwards Corrections of Typos & Incorporates Clarifications & Technical Revs Suggested by Into Application for Amend to License SNM-1067
- LD-89-017, Forwards Application for Amend to License SNM-33,reflecting Changes to U Hexafluoride to U Oxide Process Line.Vendor Plans to Commence Installation of Initial Phase of Mod in Late Feb 1989.Fee Paid
- LD-89-027, Confirms 890307 Discussion W/Nrc Re Response to NRC .Response to Ltr Will Be Provided by 890317
- LD-89-028, Forwards Amend E to C-E Std SAR Group E2 Re Design Certification.Summary of Revs Also Encl
- LD-89-029, Forwards Vol Viii to DOE/ID-10216, Mods for Development of MAAP-DOE Code:Vol Viii:Resolution of Outstanding Nuclear Fission Product Aerosol Transport & Deposition Issues Wbs 3.4.2, Per 881011 Request
- LD-89-030, Responds to 890206 Request for Addl Info Re Design Changes to CE-250-2 Shipping container.C-E Initiated Steps Re Discontinued Use of Shipping Container Late in 1989
- LD-89-032, Provides Environ Info Supporting Startup Testing & Production Operations of Revitalized Facility,Including Encl Supplemental Environ Impact Info Re Revitalization of Nuclear Fuel Mfg Facility
- LD-89-033, Forwards Design Certification Licensing Review Basis, for Review & Concurrence
- LD-89-035, Forwards Vols 1-17,consisting of Chapters 1-18,to CESSAR Design Certification, for Approval,Per 10CFR52
- LD-89-038, Requests one-time Waiver of Direct Measurement of U-235 Content in Low Level Waste Containers
- LD-89-054, Requests Temporary License Condition Allowing Use of Roller Receipt Area.Wording for Temporary License Condition Suggested
- LD-89-063, Responds to Violations Noted in Insp Rept 70-1100/89-200. Response Withheld (Ref 10CFR2.790(d))
- LD-89-064, Submits Results of Criticality Evaluation for CE-250-2 Shipping Container.Work Proceeding on Revitalization of Fuel Mfg Facilities.Anticipates Discontinuation of Use of CE-250-2 Container by End of 1989
- LD-89-066, Forwards Revised 890307 Amend Request Re Windsor Nuclear Fuel Mfg Facility organization.C-E Will Institute Facility Review Group to Assume Oversight Function Re Facility Operations.Tabulation of Affected Pages Also Encl
- LD-89-071, Forwards Application for Amend to License SNM-33,revising Organization & Adding Function of Plant Safety Committee. New Position of Supervisor of Health Physics Established & General Staff Increases Made Throughout Plant.Fee Paid
- LD-89-073, Advises That Informational Public Meeting Could Be Effective Way of Communicating Info Re Pending Amend to License SNM-33 & Licensed Facility,Per 890630 & 0707 Ltrs for Hearing
- LD-89-078, Requests Prompt Issuance of Pending License Amend Authorizing Limited Use of Depleted U at Hematite Facility. Prompt NRC Approval Will Allow for Orderly Testing of New Equipment
- LD-89-083, Responds to NRC Re Violations Noted in Insp Rept 70-1100/89-03.Corrective Action:Evaluation of Bioassay Results Conducted
- LD-89-087, Responds to NRC Re Violations Noted in Insp Rept 70-1100/89-01.Corrective Action:Procedures Revised to Be Consistent W/Nrc Interpretation of License Requirements
- LD-89-091, Forwards Responses to 881020 Request for Addl Info Re CESSAR-DC,Chapter 10, Emergency Feedwater Sys
- LD-89-092, Forwards Slides from 890616 Meeting Re CESSAR-DC Baseline PRA for Sys 80+ Std Design Described in SAR on Design Certification
- LD-89-093, Forwards Supplemental Info Re 890501 Application for Amend to License SNM-33 for Pellet Production W/Enriched U in New Bldgs & Equipment at Fuel Mfg Facilities
- LD-89-097, Confirms That C-E Application for Design Certification for Sys 80+ Std Design Considered Submitted Per 10CFR52.45
- LD-89-099, Forwards Proprietary CEN-373-P,Vol 2,Suppl 1-P, Realistic Small Break LOCA Evaluation Model,Application of Evaluation Model to Calvert Cliffs Units 1 & 2. Rept Withheld (Ref 10CFR2.790)
- LD-89-103, Responds to NRC Re Violation Noted in Insp Rept 70-1100/89-04.Corrective Actions:Next Facility Emergency Evacuation Drill Will Include Participation of Offsite Support Agencies to Test Communication Sys & Procedures
- LD-89-107, Forwards Addl Info Re CESSAR-DC Chapter 7
- LD-90-039, Informs of Organizational Changes Affecting Reporting Chain for Selected Individuals Involved in Implementation of Fnmcp.Licensee Has Determined That Changes Do Not Decrease Effectiveness of Plan & as Such,Changes Implemented
- LD-90-042, Forwards Rev 1 to EPIP 3.01, Fire/Explosion, for Info. Meeting W/Town of Windsor Fire Chief Held on 900612 Re Needs of Fire Dept in Response to Emergency Situations at Facility
- LD-90-046, Forwards Addl Copies of Amend G to CESSAR-DC
- LD-90-048, Forwards Certification of Financial Assurance for Decommissioning Under License SNM-1067
- LD-90-050, Forwards Certification of Financial Assurance for Decommissioning Under License SNM-33
- LD-90-055, Forwards Request for Withdrawal of 900213 Amend Request to License SNM-1067
- LD-90-058, Forwards Revised Pages to Hematite Radiological Contingency Plan.Rev Reflects Changes to Facility Bldgs & Equipment Resulting from Revitalization Program
- LD-90-060, Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per
- LD-90-067, Advises That Redeployed Pellet Shop in Windsor Fuel Mfg Facility Needs Reconfiguring to Accommodate New Pellet & Rod Handling Equipment.Necessary Walls,Ceilings & Structural Steel Will Be Erected to Permit Installation
- LD-90-068, Advises That Planned Work in Redeployed Pellet Shop of Facility Includes Relocating Centrifuge Sys from Present Location
- LD-90-075, Forwards Amend H to CESSAR - Design Certification
- LG-87-053, Forwards Rev 1 to Attachment a of Westinghouse Informing NRC of Actions Taken to Correct Violation Noted in Insp Rept 70-1151/87-12.Rev Corrects Incorrect Refs to Specific Paragraphs in 10CFR61