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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20043H943 | 27 April 1990 | Requests Withholding of Proprietary WCAP-12351, North Anna Unit 1 Evaluation for Tube Vibration Induced Fatigue, from Public Disclosure Per 10CFR2.790 | |
| ML18094B414 | 27 March 1990 | Outlines Plan & Basis for Plan to Update Steam Generator Tube Fatigue Evaluations Performed by Westinghouse in Response to NRC Bulletin 88-002 | |
| ML18094B254 | 8 January 1990 | Requests Info Re Procedures to Expedite NRC Qualification of Control Sys Products for Nuclear Power Plant Backfitting to Enable Vendor to Market Products in Us.Negotiations W/Pse&G Underway Re Purchase of Feedwater Control Sys | |
| ML20246D752 | 4 August 1989 | Requests That Proprietary Topical Rept WCAP-12349, North Anna Unit 1 Steam Generator Update Tube Bundle Structural Integrity Presentation, Be Withheld (Ref 10CFR2.790) | |
| ML20244B703 | 23 May 1989 | Requests That Rev 1 to North Anna Unit 1 890225 Steam Generator Leak Event Rept Be Withheld from Public Disclosure (Ref 10CFR2.790) | |
| ML20012D758 | 3 May 1989 | Requests That Proprietary WCAP-12265, North Anna Unit 2 Evaluation for Tube Vibration Induced Fatigue, Be Withheld from Public Disclosure (Ref 10CFR2.790) | |
| ML20245K728 | 19 April 1989 | Requests That Proprietary Steam Generator Leak Event Rept, Be Withheld from Public Disclosure,Per 10CFR2.790(b)(4) | |
| ML20155D157 | 12 August 1988 | Requests That Proprietary WCAP-11929, Safety Evaluation: Zirconium Base Advanced Cladding Matls Usage in North Anna Unit 1 Demonstration Fuel Assemblies, Be Withheld,Per 10CFR2.790(b)(4) | |
| NRC-87-3280, Forwards Type I & II Ltrs Re Steam Generator Tube Rupture Event,In Response to Request for Info on Generic Implications of Tube Rupture for Use in Preparing Presentation to NRC on 871109.Part 21 Related | 28 October 1987 | Forwards Type I & II Ltrs Re Steam Generator Tube Rupture Event,In Response to Request for Info on Generic Implications of Tube Rupture for Use in Preparing Presentation to NRC on 871109.Part 21 Related | Grab sample Flow Induced Vibration |
| ML20235K414 | 23 September 1987 | Requests Proprietary WCAP-11601, North Anna Unit 1 Steam Generator Tube Rupture & Remedial Actions Technical Evaluation, Be Withheld from Public Disclosure (Ref 10CFR2.790) | |
| NRC-87-3266, Forwards Proprietary WCAP-11601 & Nonproprietary WCAP-11602, North Anna Unit 1 Steam Generator Tube Rupture & Remedial Actions Technical Evaluation & Application for Withholding of Proprietary Info (Ref 10CFR2.790) | 23 September 1987 | Forwards Proprietary WCAP-11601 & Nonproprietary WCAP-11602, North Anna Unit 1 Steam Generator Tube Rupture & Remedial Actions Technical Evaluation & Application for Withholding of Proprietary Info (Ref 10CFR2.790) | |
| NRC-87-3261, Forwards Proprietary North Anna 1 Steam Generator Tube Rupture & Remedial Actions Technical Evaluation. Rept Withheld (Ref 10CFR2.790) | 13 September 1987 | Forwards Proprietary North Anna 1 Steam Generator Tube Rupture & Remedial Actions Technical Evaluation. Rept Withheld (Ref 10CFR2.790) | |
| ML18093A240 | 8 July 1987 | Forwards Proprietary Viewgraphs from 870709 Presentation to NRC Re Elimination of RTD Bypass Line,Per NRC Concerns During 870615 Telcon | |
| ML20207R929 | 11 March 1987 | Requests Withholding of Proprietary Info Re Plant Demonstration Fuel Assemblies from Public Disclosure (Ref 10CFR2.790) | |
| NRC-87-3208, Forwards Proprietary Info Re Plant Demonstration Fuel Assemblies.Encl Withheld (Ref 10CFR2.790) | 11 March 1987 | Forwards Proprietary Info Re Plant Demonstration Fuel Assemblies.Encl Withheld (Ref 10CFR2.790) | |
| ML20205S451 | 10 March 1987 | Requests Withholding of Proprietary Viewgraphs from 870305 Meeting Re Steam Generator Tube Integrity from Public Disclosure Per 10CFR2.790.Affidavit Encl | |
| ML20210T078 | 5 February 1987 | Requests That Encl Proprietary Viewgraphs of Facility Demonstration Assembly Irradiation Program Be Withheld (Ref 10CFR2.790) | |
| NRC-87-3201, Forwards Nonproprietary & Proprietary Viewgraphs of Facility Demonstration Assembly Irradiation Program,Per NRC Request for Info Re Use of Advanced Fuel Rod Cladding.Proprietary Viewgraphs Withheld (Ref 10CFR2.790) | 5 February 1987 | Forwards Nonproprietary & Proprietary Viewgraphs of Facility Demonstration Assembly Irradiation Program,Per NRC Request for Info Re Use of Advanced Fuel Rod Cladding.Proprietary Viewgraphs Withheld (Ref 10CFR2.790) | |
| NRC-86-3160, Submits Updated List of Plants Affected by Changes in ECCS Evaluation Model Described in Rev 1 to Addendum 3 to WCAP-9561-P | 8 September 1986 | Submits Updated List of Plants Affected by Changes in ECCS Evaluation Model Described in Rev 1 to Addendum 3 to WCAP-9561-P | |
| ML20213D792 | 20 August 1986 | Requests Proprietary WCAP-11163, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for North Anna Units 1 & 2, Be Withheld (Ref 10CFR2.790) | |
| ML18092B147 | 9 May 1986 | Responds to NRC 860324 Ltr Re Deviations on Training of QC Inspectors Noted in Insp Repts 50-272/86-05 & 50-311/86-05. Corrective Actions:Personnel Trained Per IE Bulletin 79-19 | |
| ML18142A048 | 7 August 1984 | Requests Proprietary Comparison to Alternate Code Calculations Be Withheld (Ref 10CFR2.790).Affidavit Encl | |
| ML18089A562 | 28 March 1984 | Requests Withholding Proprietary Info from Public Disclosure Under Previously Submitted Encl 770406 Application for Withholding AW-77-18 & Affidavit Approved on 771028 | |
| ML18087A804 | 24 March 1983 | Responds to 830323 Request for Info Re 830113-18 Westinghouse Servicing of Breakers.Uv Trip Attachment Cleaned & Lubricated W/Calforex 78-A | |
| ML18087A787 | 22 March 1983 | Submits Updated Info Re Investigation of Reactor Trip Switchgear Malfunctions.Technical Bulletin Recommending Independent Testing of Undervoltage & Shunt Trip Attachments for Manual Reactor Trip Expected by 830325 | |
| ML18086B101 | 25 November 1981 | Authorizes Utilization of Encl 761201 Affidavit for Withholding Info from Public Disclosure in Support of Util Document Entitled, Reactor Actuation Sys Setpoint Methodology. | |
| ML18139B485 | 28 July 1981 | Requests That Vendor Proprietary Info Forwarded in Util 810724 Ltr Re High Pump Burnup Radiological Consequences Be Withheld (Ref 10CFR2.790).Authorizes Use of Original Affidavit AW-76-51 Dtd 761018 | |
| ML20040C266 | 23 December 1980 | Application for Withholding Proprietary Summary Rept: Westinghouse Reactor Vessel Level Instrumentation Sys for Monitoring Inadequate Core Cooling (Microprocessor Sys). | Boric Acid Loop seal Safe Shutdown Earthquake Post Accident Monitoring Affidavit |
| ML19320A963 | 25 June 1980 | Lists Topical Repts for Which Responses to Outstanding Questions Will Be Provided to Allow SER to Proceed & to Avoid Delays in Approval of Full Power Operation.Includes WCAP-9226,-9230 & -9236 | |
| ML18085A915 | 22 May 1980 | Requests That Util Proprietary Info Re Environ Qualification of safety-related Equipment Be Withheld (Ref 10CFR2.790) | |
| ML18082A492 | 12 May 1980 | Forwards Schedule for Evaluation of Westinghouse Steam Generator Row One U Bends.Requests Delay of NRC Issuance of Generic Ltrs to near-term OL Plants Requiring Plugging of Row One Tubes,In Confirmation of 800415 Meeting | Nondestructive Examination |
| ML19312D186 | 14 March 1980 | Forwards Turbine Disc Integrity Task Force Concensus Response to Generic Questions Contained in NRC 800225 Ltr Re Turbine Disc Integrity.Portions Withheld (Ref 10CFR2.790) | Coatings Liquid penetrant |
| ML19296C472 | 20 February 1980 | Forwards Corrected Copy of Matl Properties of Facility Disc 4 & Tables of A/Acr.Encls Withheld (Ref 10CFR2.790) | |
| ML19305B959 | 7 November 1979 | Discusses Undetectable Failure in Engineered Safety Features Actuation Sys.Failure of P-4 Permissive Circuit in Both Redundant Protection Trains Could Result in Failure of Sys to Automatically Initiate Protective Function.Details Encl | |
| ML20125B939 | 5 November 1979 | Notifies That Westinghouse Briefed Utils Re Problems W/ Stress Corrosion Cracking in Westinghouse Low Pressure Rotors & Problems w/1,800 Rpm Low Pressure Turbines, Reportable Per 10CFR50.55(e) or 10CFR21.W/lists of Plants | Turbine Missile |
| ML19268C032 | 5 October 1979 | Responds to IE Bulletin 79-03 Followup Rept.Data Developed on Generic Basis & Considered Applicable to All Snupps Units.Fabrication & Installation of Youngstown Pipe Spools Will Proceed W/All Matl Analyzed Prior to Use | |
| ML19209A394 | 10 September 1979 | Responds to IE Bulletin 79-15, Deep Draft Pump Deficiencies, Re safety-related Application,Mfg & Overall Dimensions | |
| ML18078A671 | 12 January 1979 | Forwards Westinghouse Rept Evaluation of the Reactor Coolant Sys Considering Subcompartment Pressurization Following a LOCA for Unit. | |
| ML18078A687 | 12 January 1979 | Forwards Fuel Grid Impact Loads for Salem Unit No 2 (Proprietary),Synopsis of WCAP-9283(nonpropietary).W/encl Applications for Withholding AW-79-04 & AW-77-27 | Earthquake |
| ML18078A692 | 12 January 1979 | Forwards Fuel Grid Impact Loads for Salem Unit No 2 (Nonproprietary) | |
| ML18078A480 | 1 December 1978 | Forwards Proprietary & non-proprietary Reptdynamic Analysis of the Reactor Coolant Sys for Loss of Coolant Accidents:Salem Nuc Generating Stations I & II, Affidavit for Withholding & Appl for Withholding | |
| ML20150D344 | 28 November 1978 | Advises NRC That Due to Extension of Date for FSAR Submission,B&W Will Defer Submission of Revs to Topical Repts BAW-10026 & 10026P Reactor Vessel Model Flow Tests for 145 Fuel Assembly Cores | |
| ML18085A917 | 27 August 1976 | Requests That Proprietary Info Re Equipment Qualification Programs & Thermal Environ Qualification Curve Be Withheld (Ref 10CFR2.790).Original Affidavit AW-76-39 Dtd 760903 Encl |