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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20217F632 | 7 October 1999 | Forwards Insp Repts 50-254/99-01 & 50-265/99-01 on 990721- 0908.No Violations | |
| ML20212K942 | 5 October 1999 | Informs That NRC Accepts 990513 Inservice Inspection Relief Request CR-31 for Quad Cities Nuclear Power Station,Units 1 & 2 | |
| ML20212J045 | 21 September 1999 | Forwards Safety Evaluation of Licensee USI A-46 Program at Quad Cities Nuclear Power Station,Units 1 & 2,established in Response to GL 87-02 Through 10CFR50.54(f) Ltr | |
| ML20212D823 | 20 September 1999 | Informs That Effectieve 991101,NRC Region III Will Be Conducting Safety System Design & Performance Capability Pilot Insp at Quad Cities Nuclear Power Station.Insp Will Be Performed IAW NRC Pilot Insp Procedure 71111-21 | |
| ML20212C696 | 15 September 1999 | Forwards Insp Repts 50-254/99-17 & 50-265/99-17 on 990823- 0827.No Violations Noted | Enforcement Discretion |
| ML20217H566 | 9 September 1999 | Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl | Significance Determination Process |
| ML20211Q796 | 9 September 1999 | Forwards Correction to Administrative Error on Page 8 of NRC Insp Repts 50-254/99-16 & 50-265/99-16,transmitted by Ltr, | |
| ML20211Q651 | 8 September 1999 | Informs That NRC Tentatively Scheduled Initial Licensing Exam for Quad Cities Operator License Applicants During Wk of 000327.Validation of Exam Will Occur at Station During Wk of 000306 | |
| ML20211F825 | 25 August 1999 | Forwards Insp Repts 50-254/99-15 & 50-265/99-15 on 990816-20.No Violations Noted.Insp Evaluated Effectiveness of Maint Rule Program & Review Periodic Evaluation Specifically Required for 10CFR50.65 | |
| ML20211B869 | 20 August 1999 | Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed | |
| ML20211C760 | 19 August 1999 | Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program | |
| ML20211D149 | 19 August 1999 | Forwards Insp Repts 50-254/99-16 & 50-265/99-16 on 990719-22.Staff Identified Major Discrepancy Re Accuracy of Data Submitted to NRC for Protected Area Security Equipment Performance | |
| ML20210R745 | 13 August 1999 | Forwards Insp Repts 50-254/99-11 & 50-265/99-11 on 990601-0720.NRC Identified Several Issues Which Were Categorized as Being of Low Risk Significance.Two Issues Involved NCVs of Regulatory Requirements | |
| ML20210T994 | 13 August 1999 | Forwards Insp Repts 50-254/99-12 & 50-265/99-12 on 990628-0716.Violations Noted | |
| ML20210R954 | 10 August 1999 | Informs That During 990804 Telcon Between J Bartlet & M Bielby,Arrangements Were Made for NRC to Insp License Operator Requalification Program at Plant.Insp Planned for Wks of 991018 & 25 | |
| ML20210M546 | 6 August 1999 | Discusses 990804 Telcon Between J Bartlet & M Bielby,Where Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wks of 991018 & 25 | |
| ML20210L837 | 2 August 1999 | Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety Related Motor-Operated Valves | |
| ML20210M469 | 30 July 1999 | Forwards Insp Repts 50-254/99-14 & 50-265/99-14 on 990713-15.One NCV Was Identified & Discussed in Encl Insp | |
| ML20210H466 | 29 July 1999 | Forwards Insp Repts 50-254/99-13 & 50-265/99-13 on 990628-0702.No Violations Noted.Insp Consisted of Selective Examination of Procedures & Representative Records, Observations of Activities & Interviews with Personnel | High Radiation Area |
| ML20210B707 | 16 July 1999 | Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) | |
| ML20209B208 | 29 June 1999 | Discusses Closure of Response to RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rvid,Version 2 Issued as Result of Review of Responses.Info Should Be Reviewed & Comments Submitted by 990901 | |
| ML20196F792 | 24 June 1999 | Forwards Meeting Summary,Nrc Meeting Handout & Licensee Handout from 990608 Meeting | Missed surveillance Scram Discharge Volume Systematic Assessment of Licensee Performance |
| ML20196E713 | 23 June 1999 | Forwards Insp Repts 50-254/99-09 & 50-265/99-09 on 990421-0531.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy | Scram Discharge Volume |
| ML20196E482 | 21 June 1999 | Discusses 990617 Meeting by Region III Senior Reactor Analysts (SRA) in Cordova,Il to Meet with PRA Staff to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff | Probabilistic Risk Assessment |
| ML20212J054 | 17 June 1999 | Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First | Weld Overlay |
| ML20195K141 | 16 June 1999 | Forwards Safety Evaluation Authorizing Relief Request RV-23A for Duration of Current 10 Yr IST Interval on Basis That Compliance with Code Requirements Would Result in Hardship Without Compensating Increase in Level of Quality & Safety | Stroke time |
| ML20195J640 | 14 June 1999 | Discusses Licensee 990331 Remediation Plan for Welds Susceptible to Intergranular Stress Corrosion Cracking at Quad Cities Nuclear Power Station,Unit 1 & Requests Licensee Address Concerns Discussed & Propose Plan to Implement C/A | Weld Overlay |
| ML20207H617 | 14 June 1999 | Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-254/99-01 & 50-265/99-01,per 990217 & 0401 Ltrs Which Transmitted NOV Associated with Insp Repts 50-254/98-23 & 50-265/98-23 | |
| ML20206Q311 | 18 May 1999 | Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety | |
| ML20206S398 | 14 May 1999 | Forwards Insp Repts 50-254/99-06 & 50-265/99-06 on 990307-0420.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy | |
| ML20206S113 | 13 May 1999 | Informs That on 990505 NRC Staff Held Planning Meeting for Plant to Identify Insp Activities at Facility Over Next 6 to 12 Months | |
| ML20206S156 | 12 May 1999 | Informs of Plans to Conduct Public Meeting on 990608 in Rock Island,Il to Present Planned Changes to NRC Regulatory Processes & Pilot Plant Program for Quad Cities Station | |
| ML20206N962 | 11 May 1999 | Forwards Insp Repts 50-254/99-08 & 50-265/99-08 on 990419-23.No Violations Noted.Insp Examined Efforts in Addressing Actions Requested in NRC GL 96-01, Testing of Safety Related Logic Circuits | |
| ML20206P851 | 11 May 1999 | Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-254/98-21 & 50-265/98-21.Corrective Actions Will Be Examined During Future Insp | |
| ML20206P681 | 11 May 1999 | Confirms Discussion Between Members of Staff to Have Mgt Meeting at Qcs on 990608 in Training Bldg,Meeting Open to Public.Purpose of Meeting to Discuss Qcs Performance Described in PPR | |
| ML20206F322 | 4 May 1999 | Second Final Response to FOIA Request for Documents.Forwards Documents Listed in App B Maintained in PDR Under Request Number 99-134.Documents in App C Being Released in Part (Ref FOIA Exemptions 6) | |
| ML20206Q570 | 3 May 1999 | Informs That on 990420-21 NRC Senior Managers Met to Evaluate Nuclear Safety Performance of Operation Reactors, Fuel Cycle Facilities & Other Matl Licenses | |
| ML20206E062 | 30 April 1999 | Refers to Ceco Which Committed to Perform Future FW Nozzle Insps in Accordance with BWROG Alternate BWR FW Nozzle Insp Requirements Rept.Informs of Misunderstanding Re Condition 6 Implications in SER Which Approved Rept | |
| ML20205T428 | 22 April 1999 | Informs That Encl FEMA Correspondence Was Received on 990322,transmitting FEMA Evaluation Rept for 981007 Annual Medical Drill Conducted at Rock Island County for Quad City Nuclear Power Station.No Violations Were Noted | |
| ML20205Q519 | 16 April 1999 | Forwards SER Concluding That Quad Cities Nuclear Power Station,Unit 1 Can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained | Weld Overlay |
| ML20205P464 | 15 April 1999 | Forwards for Review & Comment Draft Info Notice That Describes Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station Unit 2,Arkansas Nuclear One Unit 2 & Ja Fitzpatrick NPP | Reactor Vessel Water Level |
| ML20205P059 | 14 April 1999 | Ninth Partial Response to FOIA Request for Documents.App Records Already Available in Pdr.Records in App T Encl & Being Made Available in Pdr.App U Records Being Released in Part (Ref FOIA Exemption 7).App V Records Withheld Entirely | Fire Barrier Fire Watch |
| ML20205N954 | 9 April 1999 | Forwards Insp Repts 50-254/99-03 & 50-265/99-03 on 990308-12.No Violations Noted.Longstanding Materiel Condition Issues Continue to Be Problem,However Progress Had Been Made in Listed Areas | |
| ML20205J569 | 7 April 1999 | First Partial Response to FOIA Request for Documents. Documents Listed in App a Being Released in Their Entirety | |
| ML20205F803 | 2 April 1999 | Forwards Draft Info Notice Describing Unanticipated Reactor Water Draindown of Listed Plants | Reactor Vessel Water Level |
| ML20205J289 | 1 April 1999 | Forwards Insp Repts 50-254/99-01 & 50-265/99-01 on 990121-0306.Violations Identified Involving Failure to Follow Station Procedures for Use of Shutdown Cooling & Failure to Follow Station out-of-svc Tagging Procedures | |
| ML20196K900 | 31 March 1999 | Forwards Radiation Protection Insp Repts 50-254/99-07 & 50-265/99-07 on 990309-12.No Violations Were Identified.Insp Consisted of Review of Solid Radwaste Processing & Control Program & Radioactive Matls Shipping Program | |
| ML20205G581 | 26 March 1999 | Advises of Completion of Plant Performance Review on 990201 to Develop Integrated Understanding of Safety Performance. Overall Performance of Plant Acceptable.Plant Issues Matrix & Insp Plan Encl | Safe Shutdown Unanalyzed Condition Enforcement Discretion Temporary Modification Locked High Radiation Area Missed surveillance Scram Discharge Volume Systematic Assessment of Licensee Performance Maintenance Rule Program Fire Watch Downpower |
| ML20204E061 | 18 March 1999 | Discusses Review of Rev 8Q to Portions of Plant Emergency Plan Site Annex | |
| ML20207L751 | 15 March 1999 | Informs That Staff Offers No Objections to Util 990121 Change to Licenses DPR-29 & DPR-30,App a TSs Bases Sections 3/4.10.K & 3/4.10.L.Changes Clearly Identifies That RHR Scs Not Designed to Be Throttled Sufficiently to Maintain Rc | Shutdown Margin |