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Issue date | Title | Topic | |
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ML20195C055 | 25 May 1999 | Forwards Reactor License Application for P Simpson. Certification of Medical Exam by Facility Licensee Encl with License Application.Certification of Medical Exam Withheld | |
ML20206P289 | 11 May 1999 | Forwards Revised Rept of Reactor Operation for Jan-Dec 1998 for Ford Nuclear Reactor Michigan Memorial - Phoenix Project Univ of Mi,Ann Arbor, Correcting Omission of Section 5.0 | |
ML20154E902 | 30 September 1998 | Informs That Jc Lee Has Assumed Duties of Interim Director of Michigan Memorial Phoenix Project (Mmpp) at Univ of Mi. All Future Correspondences & Notifications Re Ford Nuclear Fuel Should Now Be Directed to Jc Lee | |
ML20153B938 | 18 September 1998 | Informs of Changes Re self-contained Breathing Apparatuses at Univ of Michigan Ford Nuclear Reactor.Changes Do Not Decrease Effectiveness of Emergency Plan Per 10CFR50.54(q) | |
ML20249A641 | 13 June 1998 | Responds to NRC Re Violations Noted in Insp Rept 50-002/98-202.Corrective Actions:Nrc Issued Amend 44 on 980416 Which Puts Licensee in Full Compliance | |
ML20236U079 | 1 May 1998 | Requests That Attachment to Indemnity Agreement E-34 Between Univ of Mi & Us Aec,Be Amended by Replacing,In Entirety, Language Under Item 3 - Location W/Listed Sentence,To Make Location Consistent w/R-28 Reactor License | |
ML20217N996 | 27 April 1998 | Discusses Predecisional Enforcement Conference Held on 980422 Re Routine Safety Insp Rept 50-002/98-202 | |
ML20217E390 | 22 April 1998 | Responds to NRC Ltr Re Violations Noted in Insp Rept 50-002/98-202 on 980223-27.Corrective Actions:Temporary Operating Instruction to Lower Outlet Temperature Setpoint to 126 F Was Issued on 961008 | |
ML20203A494 | 14 November 1997 | Requests List of Names & Mailing Addresses of State Governor Designees for Advance Notifications of Shipment of Irradiated Reactor Fuel.Univ Shipping Fuel to DOE Site in South Carolina in mid-summer of 1998 | |
ML20217Q857 | 14 August 1997 | Notifies of Change of Staff in HP Position at Fnr.Am Jackson Is Being Rotated to HP Position at Univ Hosp & Ht Downey Will Be Taking Over Pml/Fnr HP Position,Effective 970908 | |
ML20196J431 | 2 July 1997 | Forwards Rev 16 to Ford Nuclear Reactor Emergency Plan. Rev Corrects Various Minor Typos & Revised Significant Radiation Exposures to Reflect Current 10CFR20 Guidance as Listed | |
ML20129J028 | 28 October 1996 | Submits Rev 15 to Ford Nuclear Reactor Emergency Plan | |
ML20057D232 | 30 September 1993 | Responds to NRC Re Violations Noted During Insp of Facility.Corrective Actions:Purchased New Model MGS0500 Mixed Gamma Std to Use for Germanium Detector Calibr,Per HP-105.Contests Part of Violation Re Fnr HP Procedures | |
ML20057C581 | 15 September 1993 | Forwards Rev 3 of Page 5 of Requalification Program.Rev Makes Requalification Program Consistent W/Requirements of 10CFR55.53(F)(2) Re Extended Absence from Operation | |
ML20056G373 | 27 August 1993 | Informs of Plans to Conduct Series of off-line Periods to Evaluate Reactor Sys,Procedures & Drawings,Evaluate Effluent Paths from Reactor Facility,Test Upgraded Equipment & Train Operators on Equipment & to Modify Procedures & Manuals | |
ML20126E657 | 29 October 1992 | Forwards Amend 38 to Ford Nuclear Reactor TS Redefining Specification 3.1,under License R-28 for Phoenix Project | Shutdown Margin High Radiation Area |
ML20126E735 | 27 October 1992 | Responds to Commitment to Evaluate Effects of Unanticipated Reactivity Insertions at Facility & to Conduct Thorough Review of Procedures & Ts.Info on Corrective Actions Planned & Completed Related Reportable Occurrence 15 Encl | Shutdown Margin High Radiation Area |
ML20055H111 | 18 July 1990 | Forwards, Requalification Program Ford Nuclear Reactor, in Response to NRC 900706 Request for Addl Info | |
ML20055G308 | 17 July 1990 | Submits Info Re 10CFR50.33 & 50.75 Decommissioning Funds | |
ML20248G241 | 20 September 1989 | Responds to NRC Questions Re Pool Leakage at Facility. Summary of Pool Water Makeup,Surface Evaporation & Leakage for Most Recent Two Quarters of 1989 & for Preliminary Measurement Conducted from 890915-18 Provided | |
ML20244B125 | 30 May 1989 | Provides Correlation Between Rev Numbers & Content & Listing of Revs on Review Sheet of Emergency Plan | |
ML20247F310 | 16 May 1989 | Forwards Revised Figure 6.1, Organization Chart for Ford Nuclear Reactor, Reflecting Reorganization of Health Physics Organization.Figure Should Be Included w/890508 Rev 1 to Tech Specs | |
ML20245F098 | 20 April 1989 | Forwards Rev 5 to Emergency Plan Ford Nuclear Reactor. Changes Involve Time Limit on Ltrs of Agreement W/Ann Arbor Police Dept,Fire Dept & Ambulance Svc and Definition of Emergency Staff Members | |
ML20196E752 | 4 November 1988 | Requests Approval of Alternate Routing for Shipment of Spent Triga Fuel from Cheyenne,Wy to Denver,Co | |
ML20148D757 | 15 March 1988 | Forwards Revised Page 17 of Emergency Plan Re Modifying Section 3.2.1,per 880309 Request | |
ML20244B133 | 15 January 1988 | Requests Listed Mods to Facility Emergency Plan | |
ML20235Y996 | 13 October 1987 | Advises That on 871012,last High Enrichment U Fuel Shipped to Savannah River,Sc Site.Requests Issuance of Revised Security Plan Submitted on 860715 Reducing Security Requirements Re Low Enrichment U Fuel | |
ML20237K963 | 14 August 1987 | Forwards Proposed Revs to Emergency Plan,Reflecting Reorganization of Facility Mgt.Reactor Operators Are Not Required to Be in Line of Succession for Emergency Director | |
ML20237J151 | 4 August 1987 | Forwards Proposed Revs to Pages 13-15 of Emergency Plan, Reflecting Facility Mgt Reorganiztion Including Addition of Second Assistant Reactor Manager | |
ML20212R111 | 15 April 1987 | Forwards Response to NRC Re Security Insp on 870316-19.W/o Encl | |
ML20215K467 | 26 March 1987 | Requests Approval of Route to Be Used for Transport of Spent Reactor Fuel.Proposed Route Attached | |
ML20210F912 | 5 February 1987 | Advises That 861203 Revs to Emergency Plan Implemented,Per NRC 870116 Approval | |
ML20244B131 | 3 December 1986 | Provides Changes to Listed Sections of Plant Emergency Plan, for Review & Approval.Changes Result of Region III Emergency Preparedness Insp | |
ML20211C988 | 16 October 1986 | Responds to Re Security Plan.Revised Plan,W/All Mods Delineated,Encl.Encl Withheld (Ref 10CFR2.790) | |
ML20203P110 | 8 October 1986 | Advises That Changes to Emergency Plan Submitted on 860813 Fully Implemented | |
ML20203F271 | 15 July 1986 | Forwards Security Plan,Amending License R-28,per 10CFR50.90. Revised Sections Provide Decreased Security Arrangements Due to Conversion to Low Enriched Fuel & Organization Changes. Plan Withheld (Ref 10CFR2.790) | |
ML20214A735 | 28 January 1986 | Requests Approval of Route for Transporting Spent Reactor Fuel.Proposed Route Encl | |
ML20136E645 | 3 January 1986 | Forwards Revised Pages 5.7 & 18 to QA Program,Reflecting Elimination of Supervisor of Reactor Operations.Assistant Reactor Manager Assumed Responsibilities Formerly Assigned to Position | |
ML20137X039 | 4 December 1985 | Responds to NRC Re Noncompliance Noted in Safety Insp on 851120-22.Corrective Actions:License Amend Request Submitted on 851202 to Remove Position of Supervision of Reactor Operations from Tech Specs | |
ML20136F553 | 7 November 1985 | Responds to NRC Re Violations Noted in Insp on 851002-04.Corrective Actions:Rubber Sealing Gasket on Final 5-micron Filter Replaced & Fourth Sentence in Section 5.10.3 of Retention Tank Dumping Procedure HP 115 Revised | |
ML20138L494 | 17 August 1985 | FOIA Request for Records of Conversion from High to Low Enriched U Fuel,Including Safety Analyses,Empirical Test Data,Feasibility Studies & Studies Re Applicability of Conversion to Other Research Reactors | |
ML20138L589 | 28 February 1985 | Forwards Revised Tech Specs & Safety Analysis as Part of OL Renewal Request,Including Page 5 of Section 1.0 Re Establishment of Surveillance Frequencies & Page 9 of Section 3.0 Re Shutdown Margin Requirements | Shutdown Margin |
ML20138L553 | 2 April 1980 | Forwards Application for Amend to License R-28 & Safety Evaluation for Low Enrichment U Fuel.Nrc Questions & Safety Analysis Satisfactorily Addressed | |
ML20126B845 | 3 March 1980 | Advises That on 800301,approx 47 Mci Br-82 Released Up Facility Exhaust Stack.Caused by Broken Sample.Max Possible Release Over 24-h Less than 0.7% Max Permissible Concentration | |
ML20197B923 | 24 October 1978 | Responds to 781003 NRC Ltr Re Noncompliance Noted in Inspec on 780906-08.Corrective Actions:Calibr of Gamma Spectrometry Equip & Preparation of Health Physics Procedure Req Quarterly Calibr of Gamma Spectrometry Equip by 781201 | |
ML20138L512 | 12 June 1978 | Forwards Addl Info Supporting 770630 Amend Request to Utilize Aluminide & Oxide Fuels.Request to Utilize UO2 Withdrawn,As Use Not Anticipated |