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Issue date | Title | Topic | |
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ST-HL-AE-3578, Forwards 1RE02 Inservice Insp Summary Rept for Welds & Component Supports..., Describing Exams Performed During Period of 900329-0621,per 1983 Edition of ASME Code,Section XI & Summer 1983 Addenda | 20 September 1990 | Forwards 1RE02 Inservice Insp Summary Rept for Welds & Component Supports..., Describing Exams Performed During Period of 900329-0621,per 1983 Edition of ASME Code,Section XI & Summer 1983 Addenda | |
ST-HL-AE-3577, Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule | 18 September 1990 | Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule | |
ST-HL-AE-3567, Requests NRC Review of Proposed Rev to Schedule for Inservice Insp Exam of Class 1,Category B-D Vessel Nozzles | 14 September 1990 | Requests NRC Review of Proposed Rev to Schedule for Inservice Insp Exam of Class 1,Category B-D Vessel Nozzles | Nondestructive Examination |
ST-HL-AE-3570, Forwards Rev 5 to, South Texas Project Unit 1 Pump & Valve Inservice Test Plan | 14 September 1990 | Forwards Rev 5 to, South Texas Project Unit 1 Pump & Valve Inservice Test Plan | |
ST-HL-AE-3553, Forwards WCAP-12629, Analysis of Capsule U from South Texas Unit 1 Reactor Vessel Radiation Surveillance Program. Pressure-temp Curves Currently in Use in Facility Tech Specs Are More Conservative than Presented in App a of Rept | 10 September 1990 | Forwards WCAP-12629, Analysis of Capsule U from South Texas Unit 1 Reactor Vessel Radiation Surveillance Program. Pressure-temp Curves Currently in Use in Facility Tech Specs Are More Conservative than Presented in App a of Rept | |
ST-HL-AE-3565, Forwards Rev 8 to Operations QA Plan. Plan Revised in Order to Include More Detailed Criteria of Chapter 17.2 of Updated Fsar.Approval Requested | 10 September 1990 | Forwards Rev 8 to Operations QA Plan. Plan Revised in Order to Include More Detailed Criteria of Chapter 17.2 of Updated Fsar.Approval Requested | |
ST-HL-AE-3550, Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990,per 10CFR26.71(d) | 28 August 1990 | Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990,per 10CFR26.71(d) | Fitness for Duty |
ST-HL-AE-3540, Provides Schedule Under Which Facility Turbine Components Inspected for Functional Integrity.Required Insp Intervals Calculated to Maintain Probability of Missile Generation for Each Low Pressure Rotor | 28 August 1990 | Provides Schedule Under Which Facility Turbine Components Inspected for Functional Integrity.Required Insp Intervals Calculated to Maintain Probability of Missile Generation for Each Low Pressure Rotor | Turbine Missile |
ST-HL-AE-3546, Forwards Corrected Semiannual Radioactive Effluent Release Rept for Second Half of 1989 | 28 August 1990 | Forwards Corrected Semiannual Radioactive Effluent Release Rept for Second Half of 1989 | |
ST-HL-AE-3551, Forwards Responses to NRC 900807 Request for Addl Info Re Probabilistic Safety Assessment Human Reliability Analysis. Paper on Quantification of Human Error Rates Using slim-based Approach Encl | 26 August 1990 | Forwards Responses to NRC 900807 Request for Addl Info Re Probabilistic Safety Assessment Human Reliability Analysis. Paper on Quantification of Human Error Rates Using slim-based Approach Encl | Probabilistic Risk Assessment |
DCL-90-202, Forwards Public Version of Corporate Emergency Response Plan Implementing Procedures (Ip),Including Rev 7 to IP 2.2,Rev 4 to IP 3.6,Rev 10 to IP 4.3 & Rev 8 to IP 4.9 | 7 August 1990 | Forwards Public Version of Corporate Emergency Response Plan Implementing Procedures (Ip),Including Rev 7 to IP 2.2,Rev 4 to IP 3.6,Rev 10 to IP 4.3 & Rev 8 to IP 4.9 | |
ML20043H619 | 21 June 1990 | Forwards 1989 Annual Financial Repts for Licensees for Plant | |
ML20043H597 | 19 June 1990 | Forwards Responses to Open Items Resulting from Sandia Draft Rept on Probabilistic Safety Assessment.Dominant Sequence Model Encl,Per NRC Reviewers Request | |
ML20043H778 | 18 June 1990 | Forwards Rev 1 to SER Commitment Status for Plant,Per NUREG-0781.List of Action Items Completed But Not Incorporated Into Sser & List of Items for Actions Not Completed Also Encl | Stroke time Post Accident Monitoring Internal Flooding Hydrostatic |
ML20043F626 | 11 June 1990 | Forwards Rev 0 to Unit 1 Cycle 3 Core Operating Limits Rept. | |
ML20043F319 | 4 June 1990 | Responds to NRC 900504 Ltr Re Violations Noted in Insp Repts 50-498/90-01 & 50-499/90-01.Corrective Actions:Compressed Gas Cylinders Removed from Power Block & Nashua 357 Tape Returned to Nuclear Purchasing Matl Mgt Co | |
ML20043D324 | 1 June 1990 | Forwards Rev 10 to Safeguards Contingency Plan.Rev Withheld (Ref 10CFR73.21) | |
ML20043B165 | 21 May 1990 | Advises That Qualified Display Processing Sys on Line Parameter Update Mod Will Be Completed During Next Refueling Outages,Per 900312 Ltr | |
ML20043A413 | 17 May 1990 | Forwards Response to Violations Noted in Insp Repts 50-275/90-02 & 50-323/90-02 Re Unauthorized Individuals Gaining Access to Vital Areas & Failure to Protect Safeguards Matl.Response Withheld | |
ML20043A608 | 16 May 1990 | Forwards Rev 16 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) | |
ML20043A995 | 16 May 1990 | Discusses Actions Taken Re Prompt Notification Sys.Util Found Autodialer Sys Offer Acceptable Alternative to Replacing Majority of Tone Alert Radios | |
ML20043H653 | 16 May 1990 | Forwards Plant Owner Draft Decommissioning Certificate & Util & City Public Svc Board of San Antonio Decommissioning Master Trust Agreements for South Texas Project | |
ML20043A864 | 14 May 1990 | Clarifies Operation of Telephone Autodialer Sys,As Part of Prompt Notification Sys.Autodialer Sys,As Currently Configured,Can Autodial & Deliver Prerecorded Message to Residents at Rate of Approx 20 Calls Per Minute | |
ML20043A327 | 10 May 1990 | Forwards Endorsements 7 & 6 to Maelu Certificates M-113 & M-116,respectively & Endorsement 6 to Nelia Certificates N-113 & N-116 | |
ML20042G649 | 10 May 1990 | Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) | |
ML20042G864 | 9 May 1990 | Comments on SALP Repts 50-498/90-06 & 50-499/90-06 for Jan 1989 to Jan 1990.Util Working on Areas Identified During SALP Rept & Mgt Meeting on 900425 | Systematic Assessment of Licensee Performance |
ML20042F957 | 7 May 1990 | Responds to NRC 900405 Ltr Re Violations Noted in Insp Repts 50-498/90-05 & 50-499/90-05.Corrective Actions:Surveillances of Emergency Response Equipment in Technical Support Ctrs Performed to Ensure That Emergency Requirements Satisfied | |
ML20042F117 | 1 May 1990 | Submits Special Rept Re Evaluation of third-yr Containment Tendon Surveillance.Tendons Which Had Voids Have Been Filled & No Evidence of Grease Leakage from Sheathing Exists | |
ML20042F363 | 30 April 1990 | Provides Summary of Expected Sequence of Events for Updates to Prompt Notification Sys | |
ML16341F690 | 26 April 1990 | Forwards Public Version of Rev 9 to Corporate Emergency Response Plan 4.3, Radiological Analyses & Protection. | |
ML20042E636 | 20 April 1990 | Forwards Revised Organization Chart,Correcting Postion Titles Reflected in 900326 Submittal | |
ML20042E542 | 12 April 1990 | Responds to 900316 Notice of Violation for Insp Repts 50-498/90-08 & 50-499/90-08.Violation Addressed in LER 90-003 Re Failure to Perform Tech Spec Required Surveillance Due to Deficient Procedure | |
ML20042E159 | 5 April 1990 | Provides Listed Guidelines for Development of Operating Procedures Re Ac Power Restoration to Respond to Station Blackout Event,Per 10CFR50.63, Loss of All AC Power. | |
ML20012F288 | 2 April 1990 | Provides Rept of Nuclear Insurance Protection,Per 10CFR50.54(w)(2).NEIL-II Decontamination Liability & Excess Property Policy Increased Effective 891115 | |
ML20012F283 | 2 April 1990 | Informs of Deferral of Facility Mods to Install Permanent RHR Pump Motor Current Indication.Mod Will Be Completed Before Next Reduced RCS Inventory Conditions on Unit | |
ML17083C249 | 2 April 1990 | Forwards Response to Questions on Geology/Seismology/ Geophysics/Tectonics in long-term Seismic Program Final Rept.Proprietary Data Withheld (Ref 10CFR2.790).W/one Oversize Drawing | Earthquake |
ML20012E226 | 26 March 1990 | Forwards Rev 17 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21) | |
ML16341F643 | 20 March 1990 | Forwards Public Version of Rev 8 to Corporate Emergency Response Plan Implementing Procedure 4.3, Radiological Analysis & Protection. | |
ML20042H042 | 20 March 1990 | Forwards Public Version of Rev 8 to Corporate Response Plan Implementing Procedure 4.3, Radiological Analysis & Protection. | |
ML20012D873 | 19 March 1990 | Forwards Revised Correspondence Distribution List of Designated Recipients | |
ML20012C617 | 16 March 1990 | Forwards Status of Actions Committed to Re NRC Bulletin 88-004 in Response to G Dick Request | |
ML20012C612 | 16 March 1990 | Forwards NRC Regulatory Impact Survey Questionnaire Sheets in Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Brief Summary Table of Questionnaire Data Also Encl | |
ML20012C281 | 12 March 1990 | Forwards Suppl 3 to Qualified Display Processing Sys (Qdps) Verification & Validation Process Final Rept & Summary of Qualified Display Processing Sys (Qdps) Recurring Component Failure Data. | |
ML20012C064 | 12 March 1990 | Forwards Rev 15 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) | |
ML20012B765 | 9 March 1990 | Responds to Generic Ltr 88-17, Loss of Dhr. Util Will Revise Appropriate Procedures to Require Entering Reduced Inventory Operation at 3 Ft Below Reactor Vessel Flange | |
ML20042D670 | 8 March 1990 | Responds to NRC Generic Ltr 89-19, Resolution of USI A-47,Safety Implication of Control Sys in LWR Nuclear Power Plants. Plant Design Meets Criteria of Generic Ltr 89-19 for Automatic Steam Generator Overfill Protection | Safe Shutdown Affidavit |
ML20012A129 | 1 March 1990 | Forwards Responses to Questions Raised by Sandia During Review of Plant PRA Covering Steam Generator Dryout | Safe Shutdown Time to boil |
ML17347B588 | 1 March 1990 | Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits | |
ML15217A103 | 28 February 1990 | Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals | Offsite Dose Calculation Manual Process Control Program |
ML18094B322 | 28 February 1990 | Forwards Executed Amend 14 to Indemnity Agreement B-74 |