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Issue date | Title | Topic | |
---|---|---|---|
ML20062G451 | 21 November 1990 | Forwards List of Unimplemented GSIs at Facility,Per Generic Ltr 90-04.Timely Completion Requested | |
IR 05000416/1990022 | 15 November 1990 | Forwards Insp Rept 50-416/90-22 on 901022-26.No Violations or Deviations Noted.W/O Encl | |
ML20058E892 | 30 October 1990 | Forwards Insp Rept 50-416/90-20 on 900915-1019.No Violations or Deviations Noted | |
ML20058B432 | 25 October 1990 | Grants 900709 Request for Relief from Requirements for Leakage Testing of RCS in ASME Code,Section Xi.Se Encl | |
ML20062B170 | 19 October 1990 | Confirms That Util Actions in Comply W/Generic Ltr 89-04 Guidance Re Inservice Testing Programs | |
ML20062B168 | 19 October 1990 | Approves Scheduled Implementation of Dcrdr Mods by 920731 (Fifth Refueling Outage) | |
ML20058B077 | 17 October 1990 | Ack Receipt of 901002 Responses Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/90-15 | |
ML20062B328 | 15 October 1990 | Advises That 900924 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2, Part 2 'Vendor Interface for Safety-Related Components,' Acceptable | |
ML20062B699 | 12 October 1990 | Requests Completion of Analyses of Liquid Samples Spiked W/ Radionuclides within 60 Days of Receipt of Ltr | |
ML20058A571 | 12 October 1990 | Forwards Insp Rept 50-416/90-18 on 900917-21.No Violations or Deviations Noted | |
ML20058A247 | 11 October 1990 | Forwards Insp Rept 50-416/90-16 on 900827-31.No Violations or Deviations Noted | |
ML20059N493 | 1 October 1990 | Informs That Util Responses to Generic Ltr 88-01 Acceptable, W/Exception to Responses Re Tech Spec Changes.Safety Evaluation & Technical Evaluation Rept Encl | |
ML20059L389 | 6 September 1990 | Forwards Insp Rept 50-416/90-15 on 900721-0817 & Notice of Violation.Nrc Believes Negative Trend in Area of Attention to Detail Needs to Be Addressed | |
ML20056B343 | 20 August 1990 | Forwards Insp Rept 50-416/90-13 on 900709-13.Violations Noted But Not Cited | |
ML20058P808 | 15 August 1990 | Discusses Util 891221 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve (MOV) Testing & Surveillance. Recommends That Testing of MOVs in-situ Be Performed Under Design Basis Conditions | |
ML20059A075 | 6 August 1990 | Advises That Rev 9 to Operational QA Manual,GGNS-TOP-1A, Acceptable,Per | |
ML20058L594 | 31 July 1990 | Advises That 900717 Rev 17 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable | |
ML20058M418 | 25 July 1990 | Forwards Insp Rept 50-416/90-12 on 900616-0720.No Violations or Deviations Noted | |
ML20055G522 | 18 July 1990 | Forwards Safety Evaluation Concluding That Procedures Generation Package Must Be Revised by Addressing Both Programmatic Improvements & Results of EOP Insp | |
ML20055G530 | 17 July 1990 | Forwards Fr Notice of Withdrawal of Applications for Amend to License NPF-29 to Delete Certain Test,Vent & Drain Valves from Tech Spec Table 3.6.4-1 | |
ML20055F905 | 16 July 1990 | Forwards Safety Evaluation Supporting Criticality Analysis for Cycle 5 Fuel in Spent Fuel Storage Racks | |
ML20055G032 | 16 July 1990 | Forwards Safety Evaluation Re Criticality Analysis of Fuel in Spent Fuel Racks Including Effect of Boraflex Gaps Which Could Occur Up Through Cycle 4.Storage Racks Can Safely Accomodate Max Reactivity of Unit 1 Cycle 1 Through Cycle 4 | Shutdown Margin Earthquake |
IR 05000416/1990008 | 12 July 1990 | Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/90-08 | |
ML20055E569 | 5 July 1990 | Grants 900426 Application for Withholding of ANF-90-060(P), Criticality Safety Analysis for Grand Gulf Spent Fuel Storage Racks W/ANF-1.4 Fuel Assemblies, Per 10CFR2.790(b)(5)) | Affidavit |
ML20055H439 | 5 July 1990 | Ack Receipt of Providing Scenario for Emergency Preparedness Exercise Scheduled for Wk of 900827 | |
ML20055E887 | 2 July 1990 | Forwards Notice of Withdrawal of Util 900504 Application for Amend to License NPF-29,extending Implementation Date for Amend 65 to License,Per 900606 Request | |
ML20055F206 | 29 June 1990 | Advises That 900618 Rev 3 to Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable | |
ML20058K516 | 28 June 1990 | Advises That Units 1 & 2 Transferred to Project Directorate IV-1,effective 900604 | |
ML20055E244 | 21 June 1990 | Grants 880630 Request to Withhold GE MDE-80-0485, Tech Spec Improvement Analysis for Reactor Protection Sys for Grand Gulf Nuclear Station,Units 1 & 2, Per 10CFR2.790 | Affidavit |
ML20059M849 | 13 June 1990 | Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl | |
ML20055C392 | 26 February 1990 | Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) | |
ML20248C905 | 26 September 1989 | Forwards Insp Rept 50-416/89-20 on 890828-0901.No Violations Noted | |
ML20248G973 | 20 September 1989 | Forwards Unexecuted Amend 13 to Indemnity Agreement B-69, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu | |
ML20247N217 | 18 September 1989 | Requests Radius & Thickness (Rt),(Rt)Ndt Values for Reactor Vessel Flange Matl & Upper Shelf Energy Values for Matls,Per Generic Ltr 88-11,by 891015 | |
ML20247H641 | 12 September 1989 | Advises That 890816 Revisions to ATWS Mitigation Sys Acceptable W/Requirements of 10CFR50.62(c)(1) | |
ML20247G668 | 12 September 1989 | Forwards Insp Rept 50-416/89-19 on 890715-0825 & Notice of Violation | |
ML20247K223 | 11 September 1989 | Forwards Amends 123 & 41 to Licenses DPR-61 & NPF-49, Respectively & Safety Evaluation.Amends Change Tech Specs 4.10.1.D.1.h & 4.4.5.4.a.8 to Allow Insp of Steam Generator Tubes by Insertion of Ultrasonic Test Probe | |
ML20247G657 | 8 September 1989 | Advises That Rev 19 to Emergency Plan Consistent W/Planning Stds of 10CFR50.47(b) & Requirements of App E to 10CFR50 | |
ML20247E337 | 7 September 1989 | Forwards Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Change Tech Spec Sections 6.10.2.m & 6.10.3 Re Records Retention for Radiological Effluent Monitoring & ODCM | Offsite Dose Calculation Manual Process Control Program |
ML20247D859 | 1 September 1989 | Ack Receipt of 890821 & 25 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/89-17. Implementation of Corrective Actions Will Be Examined During Future Insps | |
ML20247A933 | 31 August 1989 | Advises That Requalification Program Evaluation Scheduled for Wks of 891113 & 27.Facility Should Furnish Approved Items Listed in Encl 1 Ref Matl Requirements by 890915 | Job Performance Measure |
ML20246Q012 | 31 August 1989 | Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted | |
IR 05000029/1989014 | 31 August 1989 | Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted | |
ML20246G354 | 25 August 1989 | Forwards Requests for Addl Info Re Gaps in Boraflex of High Density Spent Fuel Racks.Response Requested by 891015 | Design basis earthquake |