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Issue date | Title | Topic | |
---|---|---|---|
ML20062G658 | 20 November 1990 | Documents 901011 drop-in Meeting Re Refueling Outage Progress,Recent Allegations & NRC Insps | |
ML20062F273 | 20 November 1990 | Forwards Request for Response to Allegation NRR-90-A-0050. Encl Withheld (Ref 10CFR9.17 & 9.21) | |
ML20062F368 | 14 November 1990 | Forwards Safeguards Insp Rept 50-271/90-11 on 900829-31 & Notice of Violation | |
ML20058G496 | 8 November 1990 | Advises That Maint Activity for Control Rod Relatch Witnessed by NRC on 901104.Activity Successful | |
ML20197H697 | 6 November 1990 | Forwards Resident Safety Insp Rept 50-029/90-16 on 900821- 1001 & Notice of Violation | Emergency Lighting |
ML20058F215 | 2 November 1990 | Forwards Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Item 1.2, Post-Trip Review - Data & Info Capability | |
ML20058F260 | 31 October 1990 | Forwards Ref Matl Requirements for Reactor Operator Licensing Exams Scheduled for Wk of 910211 | |
ML20058D350 | 30 October 1990 | Forwards Safety Insp Rept 50-029/90-17 on 900730-0803. Unresolved Items Noted | |
ML20058E079 | 26 October 1990 | Advises That NRC Will Perform fitness-for-duty Program Insp. Util Written Policies & Procedures Requested | |
ML20058D241 | 26 October 1990 | Requests Written Policies & Procedures Required by 10CFR26.20 Providing Background for fitness-for-duty Insp | |
ML20058D265 | 23 October 1990 | Forwards Insp Rept 50-271/90-80 on 900806-17 & Notice of Violation | |
ML20058C390 | 22 October 1990 | Forwards Amend 137 to License DPR-3 & Safety Evaluation. Amend Modifies Surveillance Requirement 4.1.3.4 | |
ML20062B890 | 19 October 1990 | Forwards one-time Exemption from 10CFR55.59(c)(3)(i)(A)-(L) Re Annual Operator Simulator Training | |
ML20058D281 | 19 October 1990 | Discusses Violations Noted in Insp Rept 50-029/90-14 & Forwards Notice of Violation | |
ML20058B551 | 18 October 1990 | Advises That 900922 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-08,Item 2.2 Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable | |
ML20062B698 | 12 October 1990 | Extends Invitation to Participate in 910220 Symposium & Workshop in King of Prussia,Pa Re Engineering Role in Plant Support | |
ML20062B867 | 12 October 1990 | Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant. Interest to Participate,Intent to Attend & Approx Number of Representatives to Attend Requested by 901115 | |
ML20059P016 | 12 October 1990 | Advises That 900920 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 | |
ML20059N712 | 10 October 1990 | Responds to Util Re Discovery of Flaws in Feedwater Check Valves 27B & 96B.NRC Believes Valve 96B Should Be Reinspected at Next Reload Outage to Verify Util Fracture Mechanics Analyses | |
ML20059N480 | 3 October 1990 | Forwards Maint Team Insp Rept 50-029/90-81 on 900709-20 & 0806-10.Weaknesses & Unresolved Item Noted | |
ML20059N135 | 28 September 1990 | Forwards Safety Insp Rept 50-271/90-09 on 900703-0812 & Notice of Violation | |
ML20059M051 | 26 September 1990 | Forwards Corrected Pages to Amend 136 to License DPR-3 | |
ML20059M530 | 25 September 1990 | Forwards Safety Insp Rept 50-029/90-12 on 900619-0820. Violations Noted But Not Cited | |
IR 05000271/1990006 | 14 September 1990 | Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-271/90-06 | |
ML20059J241 | 12 September 1990 | Advises That 900828 Revised Diesel Generator Test Plan for Qualification & Preoperational Testing Acceptable.Tech Spec Changes to Enable Util Achieve Credit for Increased Generator Capacity Will Be Considered When Proposed | |
ML20059H567 | 12 September 1990 | Advises That NRC Terminated Review of YAEC-1710, Yankee Nuclear Power Station Pilot Evaluation Rept for Plant License Renewal, Per Util 900716 Request.Resolution of Issues Will Occur as Part of Review of Application | License Renewal |
ML20059K711 | 10 September 1990 | Forwards Insp Rept 50-029/90-14 on 900802-27.Enforcement Conference Scheduled for 900921 | |
ML20059H060 | 7 September 1990 | Discusses Unescorted Access to Licensee Facilities & fitness-for-duty Program,Per .Nrc Regulations Do Not Prohibit Licensee from Accepting Access Authorization Program of Another Licensee,Contractor or Vendor | |
ML20059G223 | 6 September 1990 | Forwards Amend 135 to License DPR-3 & Safety Evaluation. Amend Modifies Tech Spec Surveillance Requirement 4.5.2a to Change ECCS Pump Surveillance Frequency from Monthly to Quarterly | |
ML20059E301 | 31 August 1990 | Forwards Safety Assessment of Yae 1735, Reactor Pressure... Evaluation Rept for Yankee Nuclear Power Station, Submitted w/900705 Ltr.Nrc Calculations Recognizing Uncertainties Conclude That Plant May Operate Until Feb 1992 | |
ML20058P070 | 9 August 1990 | Forwards Insp Rept 50-029/90-11 on 900619-22.No Violations Noted | |
ML20058N068 | 6 August 1990 | Discusses Licensee Engineering Initiatives.Cooperative Effort Would Promote Efficiency & Enhance Effectiveness of Nuclear Power Plant Activities | |
ML20058M622 | 6 August 1990 | Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Mgrs Forum to Foster Disciplined & Coordinated Approach to Initiatives | |
ML20056A934 | 3 August 1990 | Forwards Radiological Safety Insp Rept 50-029/90-13 on 900709-13.One Noncited Violation Noted | |
ML20056A931 | 2 August 1990 | Forwards Safety Insp Rept 50-271/90-08 on 900716-20.No Violations Noted | |
ML20058L024 | 2 August 1990 | Forwards Amend 133 to License DPR-3 & Safety Evaluation. Amend Incorporates Wording from Std Westinghouse Tech Specs Into Util Limiting Condition for Operation Specs 3.10.3 & 3.10.4 | |
ML20058L533 | 2 August 1990 | Forwards Rept from NRC Consultant Gr Odette Re Yankee Rowe Reactor Vessel Integrity.Response Requested by 900806 | |
ML20058L598 | 2 August 1990 | Forwards Amend 134 to License DPR-3 & Safety Evaluation. Amend Incorporates NRC Guidance in Generic Ltr 88-17 to Facility Tech Specs.Three New Tech Specs Added & Change Also Addresses Low Temp Overpressurization | |
ML20055J486 | 31 July 1990 | Requests Performance of PTS Probablistic Analysis Using Broad Range of Matl Properties Re Reactor Pressure Vessel Evaluation Rept | |
ML20055J265 | 27 July 1990 | Forwards Request for Addl Info Re Yankee Rowe Severe Accident Closure Submittal.Questions Concern Individual Plant Exam,Containment Performance Improvement Program & Accident Mgt.Response Requested within 1 Month | |
ML20056A402 | 25 July 1990 | Forwards Radiological Controls Insp Rept 50-271/90-06 on 900618-22 & Notice of Violation | |
IR 05000029/1989080 | 25 July 1990 | Ack Receipt of Re Violations Noted in Insp Rept 50-029/89-80 | |
ML20058L476 | 25 July 1990 | Forwards Exam Rept 50-029/90-06OL on 900619-21 | |
ML20055H001 | 17 July 1990 | Confirms 900703 Telcon W/J Pelletier & J Durr Announcing SSFI to Be Conducted at Facility During Wks of 900806 & 17. Requests Info Listed in Encl 1 Forwarded No Later than 900720 | |
ML20055G799 | 16 July 1990 | Forwards Safety Insp Rept 50-029/90-09 on 900515-0618.No Violations Noted | |
ML20055C853 | 18 June 1990 | Forwards Amend 132 to License DPR-3 & Safety Evaluation. Amend Changes Title of Technical Svc Supervisor & Establishes New Positions Entitled Maint Support Supervisor & Operations Support Supervisor |