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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 Motion27 July 1984Informs 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-84-049, 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 Conditions7 September 1984Forwards 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-84-074, 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 Meeting13 December 1984Forwards 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 Adequate11 January 1985Forwards 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-85-009, 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)7 March 1985Forwards 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-85-033, 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 Prepared18 July 1985Forwards 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 PreparedSafe Shutdown
Reactor Vessel Water Level
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)30 August 1985Forwards 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)30 August 1985Forwards Proprietary & Nonproprietary Rev 0 to Cpc/Ceac Software Mods for CPC Improvement Program. Proprietary Rept Withheld (Ref 10CFR2.790)
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)10 February 1986Forwards 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 112 February 1986Requests 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-86-024, 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 Paid21 May 1986Forwards 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 Burnups1 August 1986Forwards 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 Base5 September 1986Provides Info for Reactor Coolant Pump Data Bases on C-E Designed NSSS 80 for facilities.WPPSS-3 Should Be Added to Data Base
LD-87-017, 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 Days10 April 1987Responds 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-87-056, Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request18 September 1987Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request
ML17194B73030 September 1983Forwards Proprietary Dresden 2/3 Nuclear Generating Plant Suppression Pool Temp Response, Ei Hatch Nuclear Power Station Units 1 & 2 Suppression Pool Temp Response & Mark I 830825 Meeting Viewgraphs.Repts Withheld (Ref 10CFR2.790)
ML17296B28611 March 1981Requests That Instrumentation & Control Independent Design Review Be Rescheduled at First Available Opportunity.Delays Will Have Significant Impact on Sar,Fsar & CESSAR-F Review
ML17297B6052 July 1982Forwards 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)
ML17300A97416 June 1987Discusses Actions Taken in Investigation of Bechtel Deficiency Rept DER 86-29 Re Cracked Reactor Coolant Inlet Nozzle on Letdown Hx.Utils Should Be Notitified to Perform Visual Exam of Inlet & Outlet Nozzles.Part 21 Related
ML17303A48513 July 1987Forwards Steam Generator Tube Vibration Evaluation Program Progress Rept,Per Gw Knighton 870327 Ltr & Author 870410 Commitment.Rept Provides General Description of Program, Results to Date & Anticipated Direction of Future EffortsFlow Induced Vibration
ML17304B05123 February 1989Requests That Sending of NRR Correspondence W/Util Re Plant to Recipient Continue,In Response to 890216 Ltr
ML17321A90030 September 1985Notifies of Error in 10CFR50.46 LOCA Analyses Performed for Facilities.Input Error in TOODEE2 Code Used to Calculate Fuel Rod Heatup Resulted in Rod Decay Heat Power Too Low & Subsequent Underpredicted Cladding Temp.Part 21 Related
ML18142A0487 August 1984Requests Proprietary Comparison to Alternate Code Calculations Be Withheld (Ref 10CFR2.790).Affidavit Encl
ML19324C31520 February 1989Informs of Change in Vendor Plans for Inspecting Fuel Rods Containing Fuel Pellets Supplied by Ge.Ultrasonic Insp of Fuel Rods at Oconee 1 Found No Failed Rods in three-cycle, Discharged Fuel Assemblies
ML19325E90019 October 1989Forwards Text of Info Communicated to All Util W/ Westinghouse NSSS Design on Pressurizer Safety Valve Set Pressure Deviation Info Request ResponseLoop seal
ML19327A84411 October 1989Forwards Pleadings,Motions & Orders Filed in Alchemie Reorganization Action.Alchemie Currently Preparing Reorganization Plan Which Will Serve as Framework for Future Company Business Activities
ML19327A8515 October 1989Forwards Wh Arowood 890907 Ltr & Other Supplemental Info to Replace Info Previously Filed
ML19327B2496 October 1989Forwards Justification for Extension of Applicability of 890807 SER Re Acceptance of BAW-10175, Rod Exchange Methodology Topical Rept.
ML20009G47527 July 1981Advises That 16-cylinder PC-2.5 Engine for Marine Contract Suffered Burned Exhaust Valve Cage During Factory Tests. Specified Cages Will Be Inspected for Adequate Torquing of Holdowns Prior to Startup of Facilities
ML20024F09924 August 1983Forwards Proprietary Thermocouple/Core Cooling Monitor,Vols 1 & 2. Repts Withheld (Ref 10CFR2.790)
ML20027B40224 April 1978Forwards GE Program for Reactor Internals Vibration Measurement & Insp of BWR/6 Class Plants In,Response to NRC Request for Info in Item 2 of Table 1-3 of 251 & 238 NSSS Gessar Sers.Affidavit Encl
ML20028E14814 January 1983Part 21 Rept Re Possible Adverse Effects of Cross Flow on Control Rod Assemblies for Facilities.Concern Not Substantial Safety Hazard.Design Change Will Be Implemented
ML20040H41410 February 1982Notifies That Facilities Ref CENPD-210,Revision 3 Per 820202 Request.Info Based on Review of PSARs
ML20052F0904 May 1982Informs 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
ML20052F5196 April 1982Forwards Proprietary & Nonproprietary Versions of Response to NRC Questions on Improved Thermal Design Procedures. Authorizes Use of Proprietary Info by Comm Ed.Proprietary Info Withheld (Ref 10CFR2.790).Affidavit (AW-76-60) Encl
ML20063N43516 December 1981Discusses Overpressure Events in Reactor Primary Sys.Impact of Transients on Structural Integrity of Reactor Vessel Evaluated.Related Info EnclHydrostatic
ML20065B88227 January 1983Part 21 Rept Re 170 Wire Tendon post-tensioning Sys.Problem Lies W/Poor Const Techniques Not Nonconforming Threads. Nonconforming Threads Not Responsible for Failures Exhibited at Job Sites.Qa Procedure Encl
ML20070C76310 December 1982Part 21 Rept Re Problem W/Brown Boveri Electric,Inc Low Voltage Circuit Breakers W/Solid State Trip Devices.Units from San Onofre 2 & 3 Failed Due to long-term Degradation of Filter Capacitor C205.Suspect Trip Units Should Be Tested
ML20072K7197 March 1983Forwards Evaluation of Small Break LOCA Operating Procedures & Effectiveness of Emergency Feedwater Spray for B&W-Designed Operating Nsss
ML20077G66627 July 1983Part 21 Rept Re Circuit Breakers Mfg Between Nov 1981 & Feb 1982.Breakers Should Be Inspected for Broken Puffer Linkage Studs.Stud Identified as Part Number 192247A.List of Circuit Breakers for Nuclear Plants Encl
ML20077S1791 July 1983FOIA Request for Structural Integrity Test Rept for Facilities
ML20078P48528 March 1983Submits Further Followup Re Enchancement of Penetrameter Images on Radiographic Films.Film Reviews Completed to Date Confirm Weld Quality.Training Progress Initiated & Audits Performed
ML20080D96320 January 1984Application for Withholding Rept, Snupps Steam Generator Tube Plugging Margin Evaluation (Ref 10CFR2.790)
ML20082S8736 July 1982Responds to IE Bulletin 82-01 Re Associated Piping & Engineering Furnished Radiographs for Piping Welds 1/2 Inch & Less in Thickness.Smud Will Be Contacted to Return Radiographs for Review.Info Deleted
ML20083M84411 April 1984Application for Withholding Proprietary Westinghouse Interconnecting Wiring Diagrams & Process Control Block Diagrams Associated W/Pressurizer Pressure Input (Ref 10CFR2.790).W/affidavit
ML20084N24712 January 1972Expresses Concern Re Way Names of Vendor & Us Steel Corp, Pipe Were Used in Recent Telegrams to Util Concerning Main Steam Ejection at facility.Follow-up Telegram Showing That Failure Was Not Due to Faulty Matl Requested
ML20084N25127 December 1971Expresses Concern Re Use of Name in Correspondence Concerning 711010 Main Steam Ejection at Facility.List of Recipients of Telegram Re Occurrence Requested to Complete Followup
ML20084V11529 September 1969Submits Results of Investigation of RCPB Valves
ML20087N61822 March 1984Application for Withholding Proprietary Response to NRC Questions on Setpoint Methodology
ML20088A2723 April 1984Authorizes Use of Encl 761201 Affidavit Re Withholding Proprietary Westinghouse Info from Public Disclosure
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