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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 12,986 total.
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- CY-80-120, Forwards Nissho-Iwai American Corp Application for License to Export 39.186 Kg U-235 to Japan & End Use Statement.End Use Statement Only Encl
- CY-80-247, Forwards Amend to 770211 Application for License to Export Fuel Elements to Iran.Requests Issuance of License to Export 24.4 Kg U-235,contained in 26.2 Kg U.End Use Statement Encl
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- L-79-197, Responds to NRC Re Violations Noted in IE Insp Rept 70-1143/79-05.Disagrees W/Nrc & Requests Item of Noncompliance Be Dropped.Figures Re Improperly Centered Subcriticals & Overlapping Areas Encl
- L-81-068, Responds to NRC Re Violations Noted in IE Insp Rept 50-201/81-03.Corrective Actions:Notice to All Employees Posted Reiterating Purpose,Procedure & Importance of Special Work Permits
- L-81-078, Forwards Response to Quetion 260.4,contained in NRC Re FSAR Table 3.2-1.Response Includes Revisions to FSAR Text Which Will Formally Be Submitted by Amend
- 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-79-028, Forwards Nonproprietary & Proprietary Versions of Description & Listing of C-E Shake Computer Code. Proprietary Version Withheld (Ref 10CFR2.790).Affidavit Encl
- LD-79-031, Discusses Initial Review of Task Force to Evaluate Safety Implications for Nuclear Plant Design & Operation of TMI Accident.Individual ACRS Recommendations Will Be Evaluated
- LD-79-034, Requests Extension to File Addl Info Re CESSAR-F pre-docketing Amend
- LD-79-036, Forwards Info Requested by IE Bulletin 78-12,Atypical Weld Matl in Reactor Pressure Vessel Welds Which Addresses All Applicable Matls Used in Fabrication of Reactor Vessels. W/O Encl
- LD-79-038, Forwards Nonproprietary Amend 3 to FSAR
- LD-79-067, Submits Evaluation of Potential Impact of Heating Rate Dependent Burst Temp on C-E Licensing Calculations.Peak Cladding for C-E Operating Plants Would Not Be Significantly Affected by Heating Rate Dependent Rupture Temp Model
- LD-79-074, Forwards CESSAR FSAR & Affidavit.W/O Encl
- LD-80-019, Forwards Proprietary & Nonproprietary Versions of Slides Presented at NRC 800430 Meeting.Affidavit for Withholding Proprietary Info Encl.Proprietary Version Withheld (Ref 10CFR2.790)
- LD-80-050, Informs That Util Has Contracted C-E for Technical Support & Consultation in Order to Respond to Questions Re Aspects of 800611 Natural Circulation Cooldown at Facility.Responds to NRC Requesting Technical Opinion & Advice
- LD-80-053, Forwards Affidavit Supporting Proprietary Designation,Per 10CFR2.790,for Apps D & E of Cycle 5 Reload License Submittal
- LD-80-072, Requests That CESSAR Preliminary Design Approval (PDA-2) Be Extended Until NRC Issues Final Design Approval or Application Is Withdrawn.Lack of Approved Ref Design Adds to Uncertainty Facing Util
- LD-80-073, Forwards Fsar.W/O Encl
- LD-81-011, Forwards Amend 1 to CESSAR-F.Application to Review Amend & Responses to NRC 790323 Questions Encl
- LD-81-012, Forwards Info Re RCS Cold Leg Piping,For Use in Bnwl Confirmatory Piping Analysis of Safety Injection Sys Piping, Per NRC 810220 Request.Reservations Exist as to Whether Simplified Analysis Will Yield Accurate Results
- LD-81-014, Requests That Instrumentation & Control Independent Design Review Be Rescheduled at First Available Opportunity.Delays Will Have Significant Impact on Sar,Fsar & CESSAR-F Review
- LD-81-017, Forwards Non Proprietary Amend 2 to CESSAR Fsar,Providing App B Re NUREG-0737, Clarification of TMI Action Requirements. Revised App a Page,Correcting Statement in Amend 1,encl
- LD-81-023, Forwards Agenda for Auxiliary Sys Branch 810609-10 Meeting
- LD-81-024, Forwards Agenda for 810622 Meeting to Provide Responses to Mechanical Engineering Branch SER Questions
- LD-81-028, Forwards Nonproprietary Amend 3 to Chapter 4 of CESSAR-F.W/o Encl.Amends to Chapters 6 & 15,covering Addl Minor Changes Re Fuel Cycle Extension,To Be Transmitted by mid-Jul 1981
- LD-81-031, Forwards Proposed Schedule for Responding to NRC 810522 Request for Addl Info Re CESSAR FSAR
- LD-81-036, Forwards Info Bulletin 81-04,summarizing Details of Severe Damage to Steam Generator Feedring.Damage Occurred During Feedline Water Hammer Test Conducted on 810330.Other C-E Plants Not Affected.No Operational Difficulties Observed
- LD-81-039, Forwards Amend 4 to Fsar,Adding New Large Break LOCA Analysis,Incorporating Extended Fuel Cycle Parameters & Mod of post-LOCA long-term Cooling Section to Discuss Emergency Procedure Guidelines
- LD-81-040, Forwards Summary of 810622-25 SER Meeting in Windsor,Ct W/Mechanical Engineering Branch & Aps/Bechtel Re CESSAR-F, Chapter 3
- LD-81-044, Forwards Vols 1-4 of Transcript Re Independent Design Review of Sys 80 Instrumentation & Controls Safety Sys
- LD-81-060, Informs That Topical Rept Re Extended Burnup Fuel Cycles Similar to Info Described in NRC 810602 Request,Will Be Submitted in Early 1982.Document Will Minimize Unit & cycle- Specific Analyses for Extended Burnup Targets
- LD-81-064, Forwards Draft Input for CESSAR-F as App C to Describe Reactor Operation at Reduced Power Level W/Operation of Two Reactor Coolant Pumps Diametrically Opposed.Certain Sections Will Be Supplemented in Subsequent Amend by 811130
- LD-81-066, Forwards Slide Presentation Entitled Sys 80 Guide Tube Wear Resolution, Presented at 810924 Meeting.Requests That Encl Be Withheld Per 10CFR2.790
- LD-81-070, Forwards Addl Response to NRC Questions on CESSAR-F, Chapter 3,re Capability of ASME Class 1,2 & 3 Piping Sys Omitted from
- LD-81-076, Notifies of Resolution of Four SER Open Items.Items Include Low Temp Overpressure Protection Alarm & Shutdown Cooling Sys Isolation Valve Position Alarm
- LD-81-079, Provides Resolution of Potential Open Items Re Cladding Collapse & Supplemental ECCS Calculations for Ser.Applicant Will Verify That Cladding Collapse Will Not Result During Design Lifetime of C-E Fuel
- LD-81-080, Submits Addl Info Re SER Potential Open Items.Will Verify That Cladding Collapse Will Not Occur During Design Lifetime of C-E Fuel on or Before 811130.Supplemental ECCS Calculations Will Be Submitted by 811130
- LD-81-082, Forwards Responses to ACRS CESSAR Subcommittee Requesting Info on Facility Design
- LD-81-083, Forwards Amend 5 to CESSAR-F
- LD-81-085, Forwards Response to 811029 Request for Info on Sys 80 Design Features Re Unresolved Issues A-1,water Hammer, A-4,steam Generator Tube integrity,A-11,reactor Vessel Matls Toughness & A-12,steam Generator & Reactor Coolant Pump
- LD-81-087, Transmits Corrected Affidavit for Withholding CEN-185,Suppl 2-P, Heated Junction Thermocouple Phase 2 Test Rept. W/O Encl
- LD-81-088, Forwards Draft Input for CESSAR-F to Be Submitted as App C Re Description of Reactor Operation at Reduced Power Level W/Operation of Two Reactor Coolant Pumps Diametrically Opposed.Includes Info Provided in 811002 Submittal
- LD-81-089, Forwards Corrected Copy of Ae Scherer Ltr to DM Crutchfield Transmitting Proprietary Info Affidavit for CEN-185,Suppl 2-P, Heated Junction Thermocouple Phase 2 Test Rept
- LD-81-092, Provides Info Re Pressurized Thermal Shock,In Response to Question Raised at ACRS CESSAR Subcommittee 811119 Meeting. Main Steam Line Isolation Break Transient Analysis Shows No Potential for Shock for Design Life of 40 Yrs
- LD-81-096, Forwards Supplemental Emergency Core Cooling Analysis in Response to Confirmatory Issue 5 of CESSAR SER
- LD-81-097, Forwards Nonproprietary Version of Amend 6 to CESSAR-F. Addl Amend Being Prepared for Submittal Which Will Incorporate Balance of CESSAR-F Changes Provided in C-E .Table Listing Changes in Amend Encl
- LD-81-099, Forwards Revised Response to Reactor Sys Branch Round 1 Question 440.82,closing Out Confirmatory NUREG-0737 Item II.K.3.25 Re Effects of Loss of Ac Power on Pump Seals
- LD-82-001, Forwards Proprietary & Nonproprietary Versions of Cesec Digital Sumulation of C-E Nsss. Proprietary Version Available in Central Files Only
- LD-82-003, Forwards Responses to Fuel Performance Analyses Identified in CESSAR SER Confirmatory Item 3.Encl Transmitted for NRC Review of FSAR
- LD-82-008, Forwards Formal Response to Eg&G Comments on Revision 2 to CENPD-255,revised Section 3.11 to CESSAR-F & Revision 3 to Class IE Qualification of Class IE Electrical Equipment
- LD-82-009, Forwards Proprietary & Nonproprietary Copies of Response to Round 1 Question 440.40 on CESSAR Fsar,To Be Used as Part of Cesec Review
- LD-82-012, Forwards Response to Staff Questions Re Statistical Combination of Uncertainties.Info Intended to Complete C-E Input Needed to Close Out SER Confirmatory Item
- LD-82-013, Notifies That Facilities Ref CENPD-210,Revision 3 Per 820202 Request.Info Based on Review of PSARs
- LD-82-014, Forwards CESSAR SER Input Closing Out Section 1.8, Confirmatory Items 8,11 & 13.Encls Contain Revised Responses to FSAR First Round Questions & marked-up Text Pages.Changes Will Be Incorporated Into Next FSAR Amend
- LD-82-016, Forwards Revised Chapter 15 Analyses for NRC FSAR Review. Input Intended to Close Out Confirmatory Items Re Small Steam Line,Feedwater Line & Steam Line Break Analyses,Steam Generator Tube Rupture & Fuel Handling Accident Analyses
- LD-82-018, Forwards Response to SER Open Item 2,fuel Rod Pressure Limits,Confirmatory Item 4,cladding Collapse Analysis & Potential Condition of License,Fuel Burnup Limitation
- 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-82-027, Forwards Revised Tables 3.2.-1,3.11B-1 & 9.3-8 to CESSAR-F Re Safety Class 1,2 & 3 Valves,Mechanical Equipment Qualification Requirements & Chemistry & Vol Control Sys List of Active Valves,Respectively,Per 820108 Request
- LD-82-029, Forwards Review of Depressurization & Decay Heat Removal Capabilities for C-E Sys 80 NSSS, in Response to NRC 820208 Request
- LD-82-030, Submits Addl Info Re Fuel Burnup Criteria Used in 820218 C-E Calculations Per Request.Accumulative 38,100 Mwd/Mtu Core Average Burnup Used in Fuel Burnup Criteria.Ser Open Item 2 & Confirmatory Item 4 Should Be Closed Out
- LD-82-036, Forwards Nonproprietary Version of, Qualification Test Rept for Electrical Filter Assembly
- LD-82-039, Forwards Proprietary & Nonproprietary Documentation Packages for Sys 80 Plants Re Reactor Power Cutback Sys
- LD-82-040, Forwards Rept on Time to Loss of Offsite Power Following Turbine Trip for Sys 80 Plants,Per Util 820212 Submittal to Closeout SER Confirmatory Items Re CESSAR FSAR Chapter 15 Analyses
- LD-82-045, Forwards Amend 7 to CESSAR-F.List of Topics of Revision Encl
- LD-82-046, Advises That Extensive Period of Time Will Be Required for Adequate Response to NRC 820326 Request for Addl Info Re CESSAR Rapid depressurization.C-E Owners Group Will Aid in Defining Program to Respond
- LD-82-051, Forwards Response to NRC Accident Monitoring Sys CESSAR Questions.Info Transmitted for Review of CESSAR-F & Intended to Close Out Open Item 4 Identified in SER Section 1.7
- LD-82-052, Informs That Addl Action Will Be Required in Order to Fully Comply W/Asme Code Requirements for Radiography of safe-end Welds.Discrepancy Will Be Resolved by re-radiographing Affected Welds
- LD-82-054, Forwards Proprietary & Nonproprietary Versions of Statistical Combination of Uncertainties:Combination of Sys Parameter Uncertainties in Thermal Margin Analyses for Sys 80
- LD-82-058, Forwards Review of Depressurization & Decay Heat Removal Capabilities of C-E Sys 80 Units,Justifying Full Power Operation Pending Resolution of Potential for Adding Valves to Facilitate Rapid Depressurization of RCS
- 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-82-064, Forwards Proprietary & Nonproprietary Comprehensive Vibration Assessment Program for Prototype Sys 80 Reactor Internals,Palo Verde Nuclear Generating Station,Unit 1. Proprietary Version Withheld (Ref 10CFR2.790)
- 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-82-081, Provides Preliminary Info as Result of Fuel Insp That Revealed Need to Modify Some Batch C Fuel Assemblies to Provide Addl Space for Axial Growth of Fuel Rods
- LD-82-084, Withdraws App C to CESSAR-F Supporting Operation of Sys 80 NSSS at Reduced Power Level W/Two Pumps from NRC Review.Partial Loop Operation Not Required for Issuance of Final Design Approval
- 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-83-037, Forwards Proprietary & Nonproprietary Response to NRC Questions on CESSAR-F Statistical Combination of Uncertainties in Thermal Margin Analysis for Sys 80, (SER Item 7).Proprietary Response Withheld (Ref 10CFR2.790)
- LD-83-042, Forwards Nonproprietary & Proprietary Responses to Questions 440.5,10,11 & 12 on Steam Line Break Method,Resolving SER Confirmatory Items 14 & 15.Proprietary Responses Withheld (Ref 10CFR2.790).Affidavit Encl
- LD-83-044, Forwards Amend 8 to CESSAR-F.List of Rev Topics Encl
- LD-83-046, Forwards Amended Table 3-1 of Section II.F.2,App B Reflecting Clarification of Addressing TMI Action Item II.F.2 Re Inadequate Core Cooling Detection Instrumentation, Open Item 4 of CESSAR-F SER
- 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-83-058, Forwards Depressurization & Dhr,Response to NRC Questions. Recommends NRC Base Cost/Benefit Analysis in Existing Sys 80 Plants on Possible Design Change
- 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-84-008, Forwards Proprietary & Nonproprietary Comprehensive Vibration Assessment Program for Palo Verde,Unit 1 (Sys 80 Prototype), Per SER (NUREG-0852).Proprietary Rept Withheld (Ref 10CFR2.790)
- 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-87-006, Informs of Reclassification of Proprietary Documents for Period 1983-1984 Re Core Support Barrel from Proprietary to Nonproprietary
- 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-87-035, Emphasizes Need to Adhere to Previously Agreed Upon Schedule for Review of CENPD-275-P, C-E Methodology for Core Design Containing Gadolinia-Urania Burnable Absorbers, in Order to Support Reload for Cycle 5 of Plant
- LD-87-037, Forwards Proprietary Viewgraphs from 870709 Presentation to NRC Re Elimination of RTD Bypass Line,Per NRC Concerns During 870615 Telcon
- LD-87-038, Forwards Steam Generator Tube Vibration Evaluation Program Progress Rept,Per Gw Knighton & Author 870410 Commitment.Rept Provides General Description of Program, Results to Date & Anticipated Direction of Future Efforts
- 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-88-032, Responds to J Lieberman to Pl Mcgill Requesting C-E to Describe Plans for Assessing Windsor Fuel Fabrication Facility Radiation Protection Program.Requests 30-day Extension on Preparing Final Response to Subj Ltr
- 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-88-041, Provides Info Re C-E Plans for Reassessing Adequacy of Windsor Fuel Fabrication Facility Operations,Per WT Russell 880125,J Lieberman 880421 & GL Sjoblom 880606 Requests