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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20204H036 | 23 March 1999 | Forwards Amend 12 to License R-94 & Safety Evaluation.Amend Removes Authority from License to Operate Reactor & Authorizes Possession Only of Reactor.Amend Also Approves Decommissioning Plan | |
| ML20204B921 | 16 March 1999 | Forwards Environ Assessment & Finding of No Significant Impact Re Application for Amend 971218.Proposed Amend Would Amend License R-94 to Reflect That License Authorizes Possession But Not Operation of Reactor | |
| ML20236S426 | 20 July 1998 | Forwards Copy of Recently Approved Regulation in Fr Which Permits Colleges & Univs to self-guarantee Decommissioning Costs If Certain Criteria Are Met.Requests Provision of Criterion to Be Used If School Decides to self-guarantee | |
| ML20198E989 | 5 August 1997 | Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transferred from Regional Ofc to Nrr. Addresses Listed | |
| ML20210J471 | 7 July 1997 | Forwards Insp Rept 50-199/97-201 on 970605.No Noncompliance or Significant Issues Noted | |
| NUREG-1534, Forwards Chapter 17 Part 1 & 2 of NUREG-1537 Re Decommissioning & Possession Only License Amends.Format That Should Be Followed for Decommissioning Plan Given in App 17.1,which Lays Out step-by-step Info Required.W/O Encl | 14 May 1997 | Forwards Chapter 17 Part 1 & 2 of NUREG-1537 Re Decommissioning & Possession Only License Amends.Format That Should Be Followed for Decommissioning Plan Given in App 17.1,which Lays Out step-by-step Info Required.W/O Encl | |
| ML20134B747 | 28 January 1997 | Requests That NRC Be Informed of Plan for Future Use of Mczpr | |
| ML20134B564 | 23 January 1997 | Forwards Insp Rept 50-199/96-01 on 961209-12 & Notice of Violation | |
| ML20058Q218 | 18 October 1993 | Forwards Insp Rept 50-199/93-02 on 930929.No Violations Noted | |
| ML20128F825 | 5 February 1993 | Forwards Insp Rept 50-199/93-01 on 930119-20.No Safety Concerns or Violations Noted | |
| ML20055H314 | 19 July 1990 | Advises That Reactor Operator Licensing Written & Operating Exams Scheduled for 900920 & 21,respectively.Encl Ref Matl Requested by 900727 | Shutdown Margin Job Performance Measure |
| ML20246F847 | 10 July 1989 | Forwards Questions Re High Enriched U/Low Enriched U Conversion at Univ.Tech Spec Sections,Needed to Accomodate Conversion,Should Be Resubmitted & Preparation of Emergency Shutdown Rod for Use in Event of Error Explained | |
| ML20246P352 | 22 March 1989 | Forwards Agenda for 890418-19 Research & Test Reactor Seminars in King of Prussia,Pa.Updated Agenda to Follow.Map of Local Area Also Encl | Fitness for Duty |
| ML20204B928 | 13 October 1988 | Requests Updated Conversion Schedule for low-enriched Fuel to Properly Plan Review & Safety Analysis Which Was to Have Been Submitted by 870831 as Indicated by Schedule | |
| ML20150D864 | 18 March 1988 | Informs of Relocation of NRR to Rockville,Md.Official Mailing Address Still Remains Same & Project Managers Have New Locations & Phone Numbers.Ts Michaels Still Lead Project Manager for Facility & a Adams Will Serve as Backup | |
| ML20236W490 | 30 November 1987 | Forwards Insp Rept 50-199/87-02 on 871022-23.Insp Indicates That Radiological Controls Program Associated W/Research Reactor Well Managed & That Tech Spec Requirements Being Implemented.Areas Requiring Improvement Detailed in Rept | |
| ML20236Q586 | 13 November 1987 | Forwards Safeguards Insp Repts 50-199/87-01 & 70-2951/87-01 on 871007 & 08.No Violations Noted | |
| ML20215D681 | 11 June 1987 | Informs of Recent NRR Reorganization.T Michaels Will Be New Project Manager | New Project Manager |
| ML20214V093 | 27 May 1987 | Informs of Recent Realignment within NRC Region I,Div of Reactor Projects That Affects Responsibility for Insp of Research & Test Reactor Facilities.Div Organization Chart & 10CFR50 & 51 Re Communications Procedures Amends Encl | Backfit |
| ML20206U263 | 20 April 1987 | Ack Receipt of Proposed Schedule for Conversion of Reactor from High Enriched to Low Enriched U,Submitted Per 10CFR50.64(c)(2)(i).Requests That TS Michaels Be Informed of Any Changes or Updates to Proposed Schedule | |
| ML20205M097 | 26 March 1987 | Forwards Amend 7 to License R-94 & Safety Evaluation.Amend Authorizes Reactor Administrator to Assume Added Position & Duties of Radiation Safety Officer.Administrative Inconsistency Also Corrected,Per 870225 Telcon | |
| ML20207P448 | 9 January 1987 | Forwards Exam Rept 50-199/86-03OL of Partial Written Exam Administered on 861203 | |
| ML20207H470 | 11 July 1986 | Forwards Exam Rept 50-199/86-02 of Exam Administered on 860603-04 | |
| IR 05000199/1972001 | 8 July 1986 | Forwards Amend 3,terminating License 50-19972-01,per 860530 Request | |
| ML20205T296 | 10 June 1986 | Forwards Insp Rept 50-199/86-01 on 860513-15.No Violations Noted.Inspector Identified Need for Improving Maint & Surveillance Procedures | |
| ML20140J464 | 27 March 1986 | Informs That TC Elsasser Will Replace EC Mccabe as Cognizant Section Chief for Facility,Effective on 860331,based on Project Realignment.Ec Wenzinger Will Remain Branch Chief | |
| ML20154R380 | 26 March 1986 | Advises of NRR Reorganization.Telephone Number of J Dosa Changed.D Tondi New Section Leader for Nonpower Reactors & Safeguards Licensing Section.Correspondence Should Be Addressed to Nrc,Attention Document Control Desk | |
| ML20199F413 | 20 March 1986 | Informs That NRC-approved QA Program for Radiation Matl Packages Expired on 851231.Shipment of Spent Fuel Made on 860127 W/O Proper License | |
| ML20054L388 | 16 June 1982 | Ltr to All Research & Test Reactor Licensees Requesting That Reg Guide 2.6 (for Comment) & ANSI/ANS-15.16 (Draft II Dtd 811129) Be Used to Meet Requirement of Final Amend to 10CFR50.54(r) Re Emergency Planning.Fr Notice Encl | |
| ML20149K191 | 7 May 1980 | Generic Ltr 80-38 to All Nonpower Reactor Licensees Re NPR Physical Protection Requirements.Summary of Certain NPR Physical Protection Requirements Encl & Should Aid in Determining Safeguards Requirements Applicable to Facility | |
| ML20137G472 | 23 June 1971 | Advises That Presence & Irradiation of Explosives in Reactor Must Be Evaluated Due to Potential for Damage to Reactor. Evaluation Requested Establishing Operating Restrictions,Max Quantity of Explosives Allowed in Facility & Form |