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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H8701999-10-15015 October 1999 Responds to Recipient Informing NRC of from W Simoneau to Rhode Island Atomic Energy Commmission & Proposed Minutes from Rhode Island Commission Meeting of 990923 ML20205L0991999-04-0707 April 1999 Forwards Insp Rept 50-193/99-201 on 990322-26.No Violations Noted.Insp Included Review of Activities Authorized for Facility ML20155G4431998-10-14014 October 1998 Confirms 981014 Telcon That T Tehan Will Take Two Year re- Qualification Exam at Same Time SRO License Will Be Changed from Inactive to Active Status ML20154J3051998-10-13013 October 1998 Forwards Insp Rept 50-193/98-202 on 980921-25.No Violations Noted.Various Aspects of Safety Program Inspected Including Selective Exams of Procedures & Representative Records & Interviews with Personnel ML20203E0421998-02-13013 February 1998 Forwards Insp Rept 50-193/98-201 on 980113-15.No Noncompliance or Safety Concerns Were Identified ML20199E8141997-11-12012 November 1997 Forwards Amend 25 to License R-95 & Safety Evaluation.Amend Corrects Omission from Previous TS Amend ML20211J0081997-10-0202 October 1997 Forwards Corrected Copy of Page 29 of Amend 24 of TS Re Change Made by Amend 20 ML20217E2851997-09-23023 September 1997 Forwards Amend 24 to License R-95 & Se.Amend Clarifies TS Requirements & Corrects Typographical Errors ML20198F0111997-08-0505 August 1997 Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transferred from Regional Ofc to Nrr. Addresses Listed ML20140H7241997-06-17017 June 1997 Forwards Amend 23 to License R-95 & Se.Amend Removes Reactor Coolant Inlet Temp as TS Requirement in SL & Lsss,Section 2.1.1 & 2.2.1,respectively ML20140F8331997-06-11011 June 1997 Forwards Results of 970528 Operator Initial Exam at Rhode Island Aec.W/O Encl ML20148J8071997-06-11011 June 1997 Forwards Operator Licensing Initial Exam Rept 50-193/OL-97-01 During Wk of 970526 ML20196G8941997-05-30030 May 1997 Informs of Error in ,Concerning Changes to Riaec License.Ts Page 63 Correct ML20140E7681997-04-23023 April 1997 Forwards Insp Rept 50-193/97-01 on 970311-14.No Violations Noted ML20135E1481997-03-0404 March 1997 Requests Matl Listed in Encl 1, Ref Matl for Reactor/Senior Reactor Operator Licensing Exams, at Least 60 Days Prior to 970526.Procedures for Administration & Review of Written Exams Requested ML20132E2351996-12-18018 December 1996 Forwards Amend 22 to License R-95 & Safety Evaluation.Amend Provides for Extension of Annual TS Surveillances for Safety Blade Testing & Reactivity Calculations ML20135E3531996-12-0505 December 1996 Requests One Time Extension to Allow Safety Blade Testing & Reactivity Calculations as Outlined Per Encl.One Month Extension Requested to Allow Testing to Be Done in Jan 1997 ML20134K4811996-11-13013 November 1996 Informs That B Smith,SOP-10724-1,has Retired & No Longer Needs to Maintain License ML20117A8001996-08-20020 August 1996 Forwards Info Which Constitutes Second Annual Rept Required by Rev One to TS ML20096D4081996-01-12012 January 1996 Provides Answers to Concerning Rev of Rhode Island Nuclear Science Ctr TS to Combine Radiation Safety Committee & Reactor Utilization Committee Into Single Committee Called Nuclear & Radiation Safety Committee ML20083M5121995-05-12012 May 1995 Forwards Second Rev to ECCS for Facility.Rev Incorporates Comments from Design Review Conducted by Anl ML20082S0001995-04-18018 April 1995 Advises That Shipment Id R95-030995B Made Successful Transit from Point of Origin to Destination on Schedule ML20082R9971995-04-0505 April 1995 Advises That 10CFR73 Shipment Id R95-030995A Successfully Transported from Point of Origin to Destination on Schedule ML20081J0781995-03-20020 March 1995 Forwards Rev of TS to Combine Radiation Safety Committee Reactor Utilization Committee Into Single Committee Called Nuclear & Radiation Safety Committee ML20078R3571994-12-16016 December 1994 Notifies of stand-down of Shipment W/Id Numbers R95-111894A, R95-111894B & Rescheduling of Shipment.Nrc to Be Notified of New Shipment Dates & New Id Numbers to Be Assigned ML20078R5861994-12-14014 December 1994 Proposes Rev of TS to Require Sampling of Secondary Coolant Sys for Radioactivity (TS 4.3.b) on Weekly Basis & Deletion of Requirement for Secondary Radiation Detector,Per Discussion W/Nrc.Revised TS Page 42 Encl ML20080B1411994-11-17017 November 1994 Advises That for Purposes of Completion of Notification Requirements Under 10CFR73.72,original Enrichment of Sf Assemblies Was 93%,appropriate Governors Notified According to NRC Requirements & Armed Escorts Will Be Provided ML20078B6241994-10-0707 October 1994 Forwards Ri Nuclear Science Ctr Proposed 3 MW or Higher ECCS Plan ML20072M6941994-08-24024 August 1994 Forwards Change to Physical Security Plan,Per 10CFR50.54(p)(2).Encl Withheld ML20072S2751994-08-24024 August 1994 Proposed That Section 3.7.1 of TS Be Changed as Listed, Concerning Rev of TS to More Clearly Define Allowed Reactor Operation W/O Particulate or Gaseous Stack Effluent Monitor in Svc ML19346J0111994-08-24024 August 1994 Informs That Annual Rept for 1993-1994 Would Be Administrative Burden than Technical Value.Full Rept Will Be Submitted for 1994-1995 ML20071G1801994-07-0505 July 1994 Notifies That Ef Spring Retired as Employee of Riaec & No Longer Has Need to Maintain Operators License at Facility Effective 940628.Spring RO License OP-2365-11 Should Be Expired,Per 10CFR50.74(b) ML20069H4681994-06-0101 June 1994 Forwards Rhode Island Nuclear Science Ctr Proposed 3 MW or Higher Emergency Core Cooling Sys Plan ML20069J6041994-05-17017 May 1994 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-193/94-01.Corrective Actions:Revision of Procedures & Radiation Safety Guide Has Started Which Would Be Completed by 940731 Rather than 940701 Due to Delays ML20070N7331994-04-13013 April 1994 Informs That 10CFR20 Training Requirements Fulfilled Re New Requirements Issued on 940223 Per Insp Rept 50-193/94-01 ML20063K7901994-02-18018 February 1994 Forwards Preliminary Rept on Ri Nuclear Science Ctr Conversion from HEU to LEU Fuel ML20063G0961994-01-31031 January 1994 Forwards Rev 1 to Tech Specs,Including Revs Resulting from Review Process to Date ML20058K3591993-12-0808 December 1993 Forwards Insp Rept 50-193/93-04 on 931116-18.No Violations Noted ML20058G8291993-12-0303 December 1993 Submits Change to Ri Atomic Energy Commission Physical Security Plan.Change Withheld ML20058A6551993-11-17017 November 1993 Forwards Revised Copy of Proposed TSs for License R-95, Incorporating Questions Received from NRC to Date ML20057C2411993-09-17017 September 1993 Forwards Insp Rept 50-193/93-03 on 930810-18.No Violations Noted ML20056H3101993-09-0202 September 1993 Forwards Revised Emergency Plan,Reflecting Comments from Recent NRC Region I Review of Plan.Copy of Old Plan Also Encl ML20056H2801993-08-24024 August 1993 Requests Addl Info to Continue Review of Application for Amend of OL R-95,per 921222 Submittal ML20056C1451993-03-18018 March 1993 Forwards Insp Rept 50-193/93-02 on 930223-25.No Violations Noted.Written Procedures for Some Health Physics Operations Not Formalized ML20128G6661993-02-0404 February 1993 Forwards Safeguards Insp Rept 50-193/93-01 on 930119-22.No Safety Concerns or Violations Noted ML20128E7271993-01-28028 January 1993 Advises That 921130 & 930107 Revs 4 & 5,respectively,to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20127H2611993-01-13013 January 1993 Forwards Revised Pages to Sar,Rev 1,addressing Issues Discussed in 930131 Telcon Re Amended Facility License,Leu Reactor Startup Plan,Reactor Core & Control Elements,Safety Sys Settings & Beryllium Lifetime ML20126F4461992-12-22022 December 1992 Forwards Rev 1 to SAR for Low Enriched Fuel Conversion of Ri Nuclear Science Ctr Research Reactor, Incorporating Questions Forwarded by NRC 920914 & 1102 Ltrs & Original & Revised Tech Specs,Per ANSI N378-1974 ML20116L3711992-11-0202 November 1992 Advises That Listed Multiple Choice Question B 016 from 921027 Initial/Requalification Exam Had Two Possible Answers.All Other Questions/Answers Resolved Satisfactorily at Exit Meeting ML20099A6181992-07-23023 July 1992 Forwards Rev 1 to SAR for Low Enriched Fuel of Rhode Island Nuclear Science Ctr Research Reactor, Per Telcon W/M Mendonca.Rev Updates Analysis of LOCA to Reflect Beamport Operational & Design Considerations 1999-04-07
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20155G4431998-10-14014 October 1998 Confirms 981014 Telcon That T Tehan Will Take Two Year re- Qualification Exam at Same Time SRO License Will Be Changed from Inactive to Active Status ML20211J0081997-10-0202 October 1997 Forwards Corrected Copy of Page 29 of Amend 24 of TS Re Change Made by Amend 20 ML20196G8941997-05-30030 May 1997 Informs of Error in ,Concerning Changes to Riaec License.Ts Page 63 Correct ML20135E3531996-12-0505 December 1996 Requests One Time Extension to Allow Safety Blade Testing & Reactivity Calculations as Outlined Per Encl.One Month Extension Requested to Allow Testing to Be Done in Jan 1997 ML20134K4811996-11-13013 November 1996 Informs That B Smith,SOP-10724-1,has Retired & No Longer Needs to Maintain License ML20117A8001996-08-20020 August 1996 Forwards Info Which Constitutes Second Annual Rept Required by Rev One to TS ML20096D4081996-01-12012 January 1996 Provides Answers to Concerning Rev of Rhode Island Nuclear Science Ctr TS to Combine Radiation Safety Committee & Reactor Utilization Committee Into Single Committee Called Nuclear & Radiation Safety Committee ML20083M5121995-05-12012 May 1995 Forwards Second Rev to ECCS for Facility.Rev Incorporates Comments from Design Review Conducted by Anl ML20082S0001995-04-18018 April 1995 Advises That Shipment Id R95-030995B Made Successful Transit from Point of Origin to Destination on Schedule ML20082R9971995-04-0505 April 1995 Advises That 10CFR73 Shipment Id R95-030995A Successfully Transported from Point of Origin to Destination on Schedule ML20081J0781995-03-20020 March 1995 Forwards Rev of TS to Combine Radiation Safety Committee Reactor Utilization Committee Into Single Committee Called Nuclear & Radiation Safety Committee ML20078R3571994-12-16016 December 1994 Notifies of stand-down of Shipment W/Id Numbers R95-111894A, R95-111894B & Rescheduling of Shipment.Nrc to Be Notified of New Shipment Dates & New Id Numbers to Be Assigned ML20078R5861994-12-14014 December 1994 Proposes Rev of TS to Require Sampling of Secondary Coolant Sys for Radioactivity (TS 4.3.b) on Weekly Basis & Deletion of Requirement for Secondary Radiation Detector,Per Discussion W/Nrc.Revised TS Page 42 Encl ML20080B1411994-11-17017 November 1994 Advises That for Purposes of Completion of Notification Requirements Under 10CFR73.72,original Enrichment of Sf Assemblies Was 93%,appropriate Governors Notified According to NRC Requirements & Armed Escorts Will Be Provided ML20078B6241994-10-0707 October 1994 Forwards Ri Nuclear Science Ctr Proposed 3 MW or Higher ECCS Plan ML20072M6941994-08-24024 August 1994 Forwards Change to Physical Security Plan,Per 10CFR50.54(p)(2).Encl Withheld ML20072S2751994-08-24024 August 1994 Proposed That Section 3.7.1 of TS Be Changed as Listed, Concerning Rev of TS to More Clearly Define Allowed Reactor Operation W/O Particulate or Gaseous Stack Effluent Monitor in Svc ML19346J0111994-08-24024 August 1994 Informs That Annual Rept for 1993-1994 Would Be Administrative Burden than Technical Value.Full Rept Will Be Submitted for 1994-1995 ML20071G1801994-07-0505 July 1994 Notifies That Ef Spring Retired as Employee of Riaec & No Longer Has Need to Maintain Operators License at Facility Effective 940628.Spring RO License OP-2365-11 Should Be Expired,Per 10CFR50.74(b) ML20069H4681994-06-0101 June 1994 Forwards Rhode Island Nuclear Science Ctr Proposed 3 MW or Higher Emergency Core Cooling Sys Plan ML20069J6041994-05-17017 May 1994 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-193/94-01.Corrective Actions:Revision of Procedures & Radiation Safety Guide Has Started Which Would Be Completed by 940731 Rather than 940701 Due to Delays ML20070N7331994-04-13013 April 1994 Informs That 10CFR20 Training Requirements Fulfilled Re New Requirements Issued on 940223 Per Insp Rept 50-193/94-01 ML20063K7901994-02-18018 February 1994 Forwards Preliminary Rept on Ri Nuclear Science Ctr Conversion from HEU to LEU Fuel ML20063G0961994-01-31031 January 1994 Forwards Rev 1 to Tech Specs,Including Revs Resulting from Review Process to Date ML20058G8291993-12-0303 December 1993 Submits Change to Ri Atomic Energy Commission Physical Security Plan.Change Withheld ML20058A6551993-11-17017 November 1993 Forwards Revised Copy of Proposed TSs for License R-95, Incorporating Questions Received from NRC to Date ML20056H3101993-09-0202 September 1993 Forwards Revised Emergency Plan,Reflecting Comments from Recent NRC Region I Review of Plan.Copy of Old Plan Also Encl ML20127H2611993-01-13013 January 1993 Forwards Revised Pages to Sar,Rev 1,addressing Issues Discussed in 930131 Telcon Re Amended Facility License,Leu Reactor Startup Plan,Reactor Core & Control Elements,Safety Sys Settings & Beryllium Lifetime ML20126F4461992-12-22022 December 1992 Forwards Rev 1 to SAR for Low Enriched Fuel Conversion of Ri Nuclear Science Ctr Research Reactor, Incorporating Questions Forwarded by NRC 920914 & 1102 Ltrs & Original & Revised Tech Specs,Per ANSI N378-1974 ML20116L3711992-11-0202 November 1992 Advises That Listed Multiple Choice Question B 016 from 921027 Initial/Requalification Exam Had Two Possible Answers.All Other Questions/Answers Resolved Satisfactorily at Exit Meeting ML20099A6181992-07-23023 July 1992 Forwards Rev 1 to SAR for Low Enriched Fuel of Rhode Island Nuclear Science Ctr Research Reactor, Per Telcon W/M Mendonca.Rev Updates Analysis of LOCA to Reflect Beamport Operational & Design Considerations ML20101U1911992-07-17017 July 1992 Forwards SAR for Low Enriched Fuel Conversion of Rhode Island Nuclear Science Ctr Research Reactor ML20091Q3981992-01-23023 January 1992 Forwards Executed Amendment to Indemnity Agreement E-25 & 14 ML19337F4991992-01-22022 January 1992 Forwards Rev to Physical Security Plan.Rev Withheld ML20091K9801992-01-22022 January 1992 Responds to NRC Re Violations Noted in Insp Rept of License R-95.Corrective Actions:Security Plan Rev Submitted for Review ML20086E4051991-11-18018 November 1991 Forwards Safety Analysis Rept for Low Enriched Fuel Conversion of Ri Nuclear Science Ctr Research Reactor ML20086D2051991-11-18018 November 1991 Forwards SAR for Low Enriched Fuel Conversion of Rhode Island Nuclear Science Ctr Research Reactor ML20067B2931991-01-23023 January 1991 Confirms 910116 Telcon Rept Re Complete Loss of Telephone Svcs,Including Both Voice & Burglar/Supervisory Alarm Sys. Caused by Telephone Lines Cut Through While Installing Phone Poles.Contact Verified Using two-way Radios ML20066C2801990-12-26026 December 1990 Advises That SAR Re Conversion of Reactor from High to Low Enriched U Fuel Will Be Submitted by 910401.Employee Retirement Incentive Programs Resulted in Retirement of Assistant Director for Reactor Operations ML20055H1281990-07-17017 July 1990 Submits Financial Info in Response to Decommissioning Rule (10CFR50.75) ML20012D5741990-03-22022 March 1990 Forwards Changes to Physical Security Plan.Encl Withheld ML20245J4271989-02-22022 February 1989 Requests Date for Submittal of SAR for Conversion of Reactor from Use of High Enriched U to Low Enriched U Fuel Extended from 890301 to 890901 ML20195H7901988-06-23023 June 1988 Requests That Date for Submission of Low Enriched U Conversion Application Be Extended to 890306.Extension Required to Do Remaining Work for Selection & Validation of Low Enriched Core for Facility ML20155B9011988-05-19019 May 1988 Responds to NRC Re Violations Noted in Insp Rept 50-193/88-01.Corrective Action:Full Compliance W/Tech Specs Achieved & Calculations Will Be Performed at Least Quarterly ML20151K5291988-04-12012 April 1988 Requests Concurrence in Subj Design Criteria So as Not to Interfere W/Operation of Reactor Facility Exhaust Stack ML20151U6351988-02-25025 February 1988 Provides Description of Servo Regulating Element Contained in Tech Specs,Per 880208 Telcon.During Review of Retyped Specs,Possible Discrepancy in Description Noted ML20237A3251987-12-0808 December 1987 Requests That Expected Date for Submitting Application to Convert from High to Low Enriched U Be Extended from 880104 to 880705,per 870323 Submittal of Proposed Schedule.Delay Due to Difficulties in Converting Re Use of Std Fuel Plate ML20236P9771987-11-0909 November 1987 Responds to NRC Re Amend 15 to License R-95.EPZ Will Not Be Modified During Const & After Completion of Ctr for Atmospheric Chemistry Studies Bldg.Provisions Made to Notify Workers During Const in Event of Emergency ML20236J3611987-08-0303 August 1987 Forwards Revised Emergency Plan for State of Ri Nuclear Science Ctr.Rev Corrects Spelling to Incorporate Name Change for Support Agency & Correct Refs ML20205C9111987-03-23023 March 1987 Submits Info to Meet Requirements of Highly Enriched U-low Enriched U (HEU-LEU) Conversion Rule.Schedule of Completion Dates Encl for After Conversion Approval 1998-10-14
[Table view] Category:STATE/LOCAL GOVERNMENT TO NRC
MONTHYEARML20055H1281990-07-17017 July 1990 Submits Financial Info in Response to Decommissioning Rule (10CFR50.75) ML20012D5741990-03-22022 March 1990 Forwards Changes to Physical Security Plan.Encl Withheld ML20245J4271989-02-22022 February 1989 Requests Date for Submittal of SAR for Conversion of Reactor from Use of High Enriched U to Low Enriched U Fuel Extended from 890301 to 890901 ML20195H7901988-06-23023 June 1988 Requests That Date for Submission of Low Enriched U Conversion Application Be Extended to 890306.Extension Required to Do Remaining Work for Selection & Validation of Low Enriched Core for Facility ML20155B9011988-05-19019 May 1988 Responds to NRC Re Violations Noted in Insp Rept 50-193/88-01.Corrective Action:Full Compliance W/Tech Specs Achieved & Calculations Will Be Performed at Least Quarterly ML20151K5291988-04-12012 April 1988 Requests Concurrence in Subj Design Criteria So as Not to Interfere W/Operation of Reactor Facility Exhaust Stack ML20151U6351988-02-25025 February 1988 Provides Description of Servo Regulating Element Contained in Tech Specs,Per 880208 Telcon.During Review of Retyped Specs,Possible Discrepancy in Description Noted ML20237A3251987-12-0808 December 1987 Requests That Expected Date for Submitting Application to Convert from High to Low Enriched U Be Extended from 880104 to 880705,per 870323 Submittal of Proposed Schedule.Delay Due to Difficulties in Converting Re Use of Std Fuel Plate ML20236P9771987-11-0909 November 1987 Responds to NRC Re Amend 15 to License R-95.EPZ Will Not Be Modified During Const & After Completion of Ctr for Atmospheric Chemistry Studies Bldg.Provisions Made to Notify Workers During Const in Event of Emergency ML20236J3611987-08-0303 August 1987 Forwards Revised Emergency Plan for State of Ri Nuclear Science Ctr.Rev Corrects Spelling to Incorporate Name Change for Support Agency & Correct Refs ML20205C9111987-03-23023 March 1987 Submits Info to Meet Requirements of Highly Enriched U-low Enriched U (HEU-LEU) Conversion Rule.Schedule of Completion Dates Encl for After Conversion Approval ML20140A4081986-03-0303 March 1986 Responds to 850927 Order to Show Cause Re Amount of Unirradiated High Enriched U Fuel Onsite.Normal Compliment of Unirradiated High Enriched U Fuel Consists of Three Elements,Containing Total of 372 G ML20135F0981985-09-0606 September 1985 Responds to NRC Re Violation Noted in Insp Rept 50-193/85-02 on 850611-12.Corrective Actions:Filters Tested in Place on 850813 by B&B Testing Co & Better Record Retention Sys Initiated ML20115F1101985-04-0808 April 1985 Suppls Response to NRC Re Violations Noted in Insp Rept 50-193/84-02.Hand-held Radio Communication Capability Will Not Be Available Until 850615 Due to Equipment Ordering & Delivery Delays ML20111C2111985-02-0707 February 1985 Responds to NRC-identified Improvement Areas Noted in Insp Rept 50-193/84-02.Corrective Actions:Development of Training Matrix for Emergency Director & Emergency Coordinator Initiated ML20096F9891984-09-0606 September 1984 Advises That Complete Implementation of Emergency Plan Approval Will Be Achieved by 840917 ML20028F4631983-01-0303 January 1983 Responds to NRC 821215 Ltr Re Violations Noted in IE Insp Rept 50-193/82-02.Corrective Actions:Storage Area Monitor Modified to Provide Clearly Audible Alarm Signal If Accidental Criticality Occurs ML20069F3451982-09-0101 September 1982 Forwards Public Version of Revised Emergency Plan for State of Ri Nuclear Science Ctr ML20069F3491982-08-31031 August 1982 Forwards Public Version of Revised Emergency Plan for State of Ri Nuclear Science Ctr.Apps 3.1-3.11 Contain Agreements Reached W/Offsite Agencies ML20041F2661982-03-0909 March 1982 Notifies That Records Should Be Changed to Show Jj Garrahy Designation as Governor of Ri & New Dept of Atty General Location ML20041E1911982-02-0505 February 1982 Forwards Operating Statistics,Jul 1980-June 1981. ML20040D6101982-01-22022 January 1982 Requests Changes to Wording of Tech Spec Sections K.3.C.(3) & (4) Re Makeup & Cleanup Sys,Respectively.Actual Operating Limits Contained in K.3.C.(5) & (6).No Change Requested for Limits ML20003H9531981-05-0606 May 1981 Forwards Proposed Revisions to Security Plan.Revisions Withheld (Ref 10CFR2.790) ML19347E0771981-04-13013 April 1981 Forwards Replacement Pages for Proposed Physical Security Plan.Pages Withheld (Ref 10CFR2.790) ML20002C0891980-12-0404 December 1980 Requests Route Change for Shipment of Spent Fuel from Narragansett,Ri to Aiken,Sc.Police Escort Arranged for Area Near Harrisburg,Pa ML20003D5661980-10-27027 October 1980 Provides Alternate Route from Narragansett,Ri to Aiken,Sc, Updating 800610 Proposal.Use of Private Grounds Is Not Anticipated ML20008E2991980-10-0606 October 1980 Notifies That Amend 10 to Indemnity Agreement E-43 Was Mailed to NRC on 791024,in Response to NRC 800924 Ltr ML19320B0861980-07-0101 July 1980 Advises NRC That Rept Re Nonpower Reactor Physical Protection Upgrade Requirements Will Be Submitted to NRC by 800801 ML19323F7461980-05-22022 May 1980 Ack Receipt of NRC 800507 Notice Re Nonpower Reactor Physical Protection Requirements.Plan Will Be Forwarded as Soon as Possible ML19256F6261979-12-0707 December 1979 Notifies of Error in 791203 Ltr Re RO 50-193/79-03.Date in First Line of Second Paragraph Should Read 791129 ML19254D9261979-10-26026 October 1979 Forwards Executed Amend 10 to Indemnity Agreement E-43.New Chairman of Ri AEC Is G Seidel of Brown Univ ML19249C5461979-09-0505 September 1979 Requests Amend of License R-95 to Permit Use of U Aluminide or U Oxide Fuel Elements ML19207C4381979-09-0404 September 1979 Reports Failure of Auxiliary Electrical Power Generator During 790830 Routine Test.Caused by Weak Battery. Battery Cell Specific Gravity Will Be Tested Weekly ML19276H0501979-08-17017 August 1979 Responds to 790730 Ltr.Upgrade Rule Will Not Imply Significant Changes in Ri Atomic Energy Commission Nuclear Science Ctr.Operating Data for Jul 1977-June 1978 Encl ML20207D5281963-04-16016 April 1963 Submits,For Approval,Info to Establish Atmospheric Dilution Factor for Determining Permissible Average Concentration of Radioactive Effluent from Reactor Effluent Disposal Stack 1990-07-17
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] kj STATE OF RHODE ISLAND AND PROVIDENCE PLANTATIONS Rhode Island Atomic Energy Commission NUCLEAR S,CIENCE CENTER South Ferry Ro,.d Narragansett, R. I. 02882 August 17, 1979 00u-c7 Co-l93 U. S. Nuclear Regulatory Ccrmission Washingtcn, D. C. 20555 Attenticn: Jares R. Miller, Acting Asst. Director for Site and Safeguards Gentlemen:
Please refer to your letter of July 30, 1979 concerning the effect of the upgrade rule on the R. I. Nuclear Science Center. We have already been visited by a team from NRC and New Mexico.
Based on the discussicns with the team and our existirg security arrangerents, we do not believe that significant changes in cur facility will-be necessary to met the requirements of the uppade rule. We also do not believe that sigr.ificant charges in cur secu-rity pmcedures will be necessary. 'Ihis is because, althcugh we are licensed for greater than 5000 grams of U-235, the arount of fuel that is not self pmtecting is always less than 5000 gms.
In additicn, since the reactor cperates at 2M4, we do not antic-ipate prcblems in maintaining the fuel in the swirrdng pool at the self protection limit. To do this, hcwever, may require N-cycling into the reacter, fuel eierents which otherdise wculd have been allcwed to decay until shiprent to reprocessing.
The impact of 1 :plementing the SafeW2 upgrade rule will not be great enough for us to censider closing the facility. We do not have an estirnte of the ecst of shutting down the facility or the cost of maintaining pcssession cnly status.
The arnual budget for crerating is abcut $360,000. This dces not include the funded meearch pregame which approximately arcunt to an additional $1,0C0,000.
?96 272 g 6k1 7908310 63 3
Enclosed is a ccpy of our annual report for the 77/78 fiscal year.
Pages 12 thru 19 will provide the kinds of infor ation m;ested in your letter.
The follcwing am the answers to your specific questions:
- 1. Mintral
- 2. Minkal 3 Miniral
- 4. No data available 5 No data available
- 6. 'Ihe less to industry will be through the loss of trained personnel with advanced degrees. The reactor is used for research in master and doctoral programs. We do not train cperators for pcwer react-ors.
7 We have two research programs with applicaticns in the medical area.
We do not produce medical isotcpes.
- 8. Based en NRC facility visit, minimal.
9 Yes
- 10. 'Ihere are about 25 faculty merters who use the facility and about 25 advanced degree students. There are about 40 publications an-nually resulting from the work.
- 11. Eleven. No
- 12. We do not mn a training mactor 13 'Nenty-five . Yes
- 14. $360,000 15 Yes, by recycling back in M reactor. However, fuel decay of 90 days prior to shipment to reprocessing may present a problem.
Assuning no problem with shipping to reprocessing, the financial 1: Tact will be minirnl.
- 16. About 19. However, some involve cnly a couple of hours at the facility. 'Ihey will not be cut.
Based cn our operating experience, we see two potential prcblems, bcth ccncerning spent fuel. 'Ihe first is the decay tLT required by the reprocessing plant ce the decay heat limits en the shipping cask and the availability of transportation companies who meet the re-quirements of 73 37 Since we received your letter en August 14, 1979, we have not, as yet, checked these items.
We will be pleased to provide nore infomation, if necessary.
Very truly yours, 3
VYs i
,~ m T< ,M6 273 A. Francis DDieglio Directcr AFD:ag
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