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Issue date | Title | Topic | |
---|---|---|---|
ML18153C366 | 20 September 1990 | Forwards Topical Rept VEP-NE-3-A, Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code. | |
ML20065D567 | 20 September 1990 | Forwards Rev 15 to Security Personnel Training & Qualification Plan.Rev Withheld | |
ML18153C370 | 18 September 1990 | Forwards Addl Info Re Facility Containment Isolation Valve Type C Test,Per 900914 10CFR50,App J Exemption Request | Exemption Request |
ML18152A234 | 14 September 1990 | Requests Exemption from 10CFR50,App J Section III.D.3 Re Local Leak Rate Testing During Every Reactor Shutdown. Basis & Justification for Exemption Encl | Exemption Request |
ML20059J334 | 13 September 1990 | Forwards Rev 15 to Nuclear Security Personnel Training & Qualification Plan.Rev Withheld | |
ML20059H739 | 10 September 1990 | Forwards Rev 15 to ISFSI Nuclear Security Personnel Training & Qualification Plan.Rev Withheld | |
ML20059H293 | 7 September 1990 | Advises of Review & Approval of ASME Section XI Inservice Insp Program Interval 1 Repair & Replacement Program Change to Applicable Code Edition & Addenda | |
ML20064A520 | 7 September 1990 | Responds to NRC Re Violations Noted in Insp Repts 50-338/90-15 & 50-339/90-15.Corrective Actions:Procedures Revised to Include Tolerance Bands for Temp Control Switch Setpoints & Involved Personnel Counseled | |
ML18151A290 | 31 August 1990 | Forwards Rev 10 to Updated FSAR for Surry Power Station Units 1 & 2,representing Second Updated FSAR Submitted This Yr | |
ML20059E548 | 31 August 1990 | Forwards Supplemental Info Re Deletion of Pressurizer Safety Valve Requirement During Mode 5.Current Tech Spec Requiring One Operable Safety Valve in Mode 5 Unnecessary & May Be Deleted | |
ML18153C345 | 29 August 1990 | Forwards Proprietary Semiannual Fitness for Duty Program Performance Data Rept for 900103-0630.Rept Includes Summaries of Mgt Sanctions Imposed,Actions Taken to Correct Program Weaknesses & Events Reported to Nrc.Encl Withheld | Fitness for Duty |
ML18153C338 | 22 August 1990 | Responds to NRC 900723 Ltr Re Violations Noted in Insp Rept 50-280/90-21 & 50-281/90-21.Corrective actions:as-found-as- Left Conditions of Auxiliary Feedwater Evaluated & Found Operable | |
ML18153C339 | 22 August 1990 | Requests Approval for Use of Plugs Fabricated of nickel- chromium-iron Uns N-06690 Matl (Alloy 690) to Plug Tubes in Steam Generators for Mechanical & Welded Applications | |
ML20063Q124 | 15 August 1990 | Provides Supplemental Info for 900115 Tech Spec Change Request Re Max Allowable Control Rod Drop Time.Retained DNBR Margin Tracked & Documented by Calculational Note | |
ML20058N594 | 8 August 1990 | Responds to NRC Re Violations Noted in Insp Repts 50-338/90-11 & 50-339/90-11.Corrective Actions:Procedure Revised to Limit Applicablity to Small Refueling Cavity Leaks & Listed Evaluations & Revs Will Be Made to EOP | |
ML18153C317 | 1 August 1990 | Resubmits Synopsis of Changes to Updated Operational QA Program Topical Rept Vep 1-5A | |
ML18153C316 | 1 August 1990 | Provides Supplemental Response to NRC 900629 Ltr Re Electrical Crossties,Load Shedding on Nonblackout Unit & Emergency Diesel Generator Reliability.Emergency Diesel Generator Reliability Program in Place,Per Reg Guide 1.155 | |
ML18153C309 | 30 July 1990 | Provides Outline of Plan to Meet 10CFR50 App G Requirements, for Low Upper Shelf Energy Matls,Per NRC 900521 Request | |
ML18153C306 | 30 July 1990 | Forwards Revised Tech Spec Pages,Addressing Constitution of Quorum & Timeliness of Mgt Safety Review Committe Meeting Minutes,Per NRC Request | Offsite Dose Calculation Manual Process Control Program |
ML18153C310 | 26 July 1990 | Forwards Decommissioning Financial Assurance Certification Rept..., Nuclear Decommissioning Trust Agreement & Nonqualified Nuclear Decommissioning Trust Amended & Restated Trust Agreement, Per 10CFR50.75 | |
ML18153C305 | 26 July 1990 | Advises That Util Submitted Decommissioning Funding Plan & Financial Assurance Info W/Isfsi License Application | Decommissioning Funding Plan |
ML18153C304 | 26 July 1990 | Responds to NRC 900626 Ltr Re Violations Noted in Insp Rept 50-281/90-20.Corrective Actions:Leaking Drain Plug & Upper Drain Plug on Motor Replaced W/Oil Drain Assemblies Composed of Piping & Valves | Condition Adverse to Quality |
ML18153C303 | 26 July 1990 | Advises of Withdrawal of Request for NRC Review & Approval of Engineering Evaluation 8.Revised Evaluation Will Be Maintained Onsite for NRC Audit During Future Insps,Per Generic Ltr 86-10 | |
ML20055H565 | 20 July 1990 | Requests for Temporary Waiver of Compliance from Requirement of Tech Spec 3.3.1.1,Table 2.3-2 Re Response Time Testing. Request Does Not Pose Significant Hazards Consideration | |
ML18153C290 | 18 July 1990 | Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Listed Transmitters Compiled.Transmitters Found Installed within Reactor Protection or ESFAS Have Been Replaced | |
ML20055F936 | 16 July 1990 | Advises That No 30-day Rept Will Be Made Re Degradation of Seismic Support Bolts of post-accident Hydrogen Recombiners 1-HC-HC-1 & 2-HC-HC-1 | |
ML20044B350 | 13 July 1990 | Forwards Monthly Operating Repts for June 1990 & Corrected May 1990 Rept Pages for North Anna Power Station | |
ML18153C286 | 12 July 1990 | Requests Cancellation of Operator Licenses for Listed Individuals.Licenses No Longer Required | |
ML18153C287 | 11 July 1990 | Responds to Violations Noted in Insp Repts 50-280/90-18 & 50-281/90-18.Corrective Actions:Permanent Drain Line Installed & Matrix Which Describes Proper Ventilation Alignment for Plant Conditions Provided for Personnel Use | High Radiation Area Temporary Modification |
ML20055E812 | 9 July 1990 | Requests Cancellation of Licenses Listed | |
ML18153C285 | 6 July 1990 | Forwards Response to Generic Ltr 90-04 Re Status of Generic Safety Issues | Scram Discharge Volume |
ML18153C283 | 3 July 1990 | Advises That MW Hotchkiss No Longer Needs Operator License SOP-20548-1.Cancellation of License Requested | |
ML18153C282 | 3 July 1990 | Requests Exemption from 10CFR50,App J,Paragraph III.A.6(b), Which Requires That When Two Consecutive Periodic Type a Tests Fail to Meet Applicable Acceptance Criteria Type a Test Shall Be Performed at Plant | Exemption Request |
ML20055D484 | 3 July 1990 | Requests That Operator Licenses for Listed Individuals Be Cancelled.Licenses No Longer Required | |
ML20055D483 | 3 July 1990 | Requests That Operator License for Bl Shriver Be Cancelled. License No Longer Required | |
ML20055D770 | 29 June 1990 | Submits Supplemental Response to Violations Noted in Insp Repts 50-338/90-04 & 50-339/90-04 Re Failure to Take Timely Corrective Action for Repair of B Low Head Safety Injection Pump (1-SI-P-1B).No Addl Purchasing Procedure Required | |
ML18153C359 | 28 June 1990 | Responds to SALP Repts 50-280/90-16 & 50-281/90-16 for Period 890701-900331.Corrective Actions Focus on Issues of Maint Backlog,Maint planning,post-maint Testing,Staffing & Procurement | Systematic Assessment of Licensee Performance |
ML18153C261 | 21 June 1990 | Responds to NRC 900522 Ltr Re Violations Noted in Insp Repts 50-280/90-07 & 50-281/90-07.Corrective actions:as-built Configurations of 120-volt Ac & Dc Vital & Semivital Panel Breaker Installations Verified to Be Acceptable | Time of Discovery |
ML20043H942 | 21 June 1990 | Forwards Proprietary WCAP-12351, North Anna Unit 1 Evaluation for Tube Vibration Induced Fatigue, Per Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. Rept Withheld (Ref 10CFR2.790) | |
ML18153C259 | 18 June 1990 | Forwards Response to NRC 900524 Request for Addl Info Re NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Engineering Will Initiate Study to Evaluate Enhancements of Cooldown & Possible Heatup Operation | |
ML18153C258 | 18 June 1990 | Forwards Reissued Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989. Rept Contains Info Re SR-89,Sr-90 & Fe-55 Analytical Results for Liquid Composite Samples | |
ML20055C866 | 15 June 1990 | Forwards Application for Reissuance of NPDES Permit | |
ML18153C254 | 15 June 1990 | Forwards Corrected Tech Specs Page 3.1-3,per Identification of Typo in 900522 Application for Amends to Licenses DPR-32 & DPR-37 | |
ML20043G571 | 15 June 1990 | Forwards Response to Request for Addl Info Re Insp Rept 50-339/89-20 Concerning Plant Safety Sys Outage Mod Insp. Response Withheld (Ref 10CFR73.21) | |
ML20043H113 | 15 June 1990 | Concludes That Removal of Temporary Loose Parts Monitoring Sys Does Not Increase Probability of Acccident,Create Possibility of New Kind of Accident & Does Not Reduce Margin of Safety | |
ML20043G873 | 14 June 1990 | Discusses Evaluation of ASME Section XI Testing for Outside Recirculation Spray Pumps | |
ML18153C252 | 14 June 1990 | Responds to NRC 900515 Ltr Re Violations Noted in Insp Repts 50-280/90-09 & 50-281/90-09.Corrective Actions:Abnormal Procedures & Fire Contingency Action Procedures Being Upgraded Via Technical Procedure Upgrade Program | |
ML20043H209 | 13 June 1990 | Forwards List of Corrective Actions & Current Status in Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. | |
ML20043F453 | 8 June 1990 | Forwards, Core Surveillance Rept for North Anna 2,Cycle 7 W/Extended License Burnup Limit. Rept Contains Specific Power Distribution Limits Applicable for Cycle 7 Operation W/Burnup Limit Extension | |
ML18153C250 | 8 June 1990 | Confirms That Primary Policy Re Onsite Property Damage Insurance,Provided by Nuclear Mutual Limited |