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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20236S4451998-07-20020 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 ML20217H6461998-04-28028 April 1998 Forwards Insp Rept 50-225/98-201 on 980407-10.No Violations Noted ML20217H4111997-08-0505 August 1997 Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transferred from Regional Ofc to Nrr. Addresses Listed ML20148F0771997-05-29029 May 1997 Informs That Bs Craig Replaced Mn Galayda as Supervisor of RPI Reactor Critical Facility on 970516 ML20135C0821997-02-24024 February 1997 Forwards Certificate for Listed Newly Licensed Individual. W/O Encl ML20133A4721996-12-26026 December 1996 Forwards Results of Operator Initial Exam Conducted at Rensselaer Polytech Institute on 961119.W/o Encl ML20133D0691996-12-26026 December 1996 Forwards Initial Exam Rept 50-225/OL-96-01 on 961119, Administered to Employee Who Applied for License to Operate Licensee Reactor,& Exam & Answer Key.W/O Encl ML18065B2651995-07-21021 July 1995 Informs of 950711 Conversation W/S Holmes Re Change & Temporary Reduction in Radiation Safety Staffing within Past Yrs ML20058E4681993-11-26026 November 1993 Forwards Insp Repts 50-225/93-01 & 70-0920/93-01 on 931102-04.No Violations Noted ML20059J1231993-11-0303 November 1993 Discusses Telcon Arrangements Made for Administration of Operator Licensing Exam.Written & Operating Exams Scheduled for Wk of 940110 ML20092C8061991-08-16016 August 1991 Advises of Licensee Plans to Double Storage Capacity of Fuel Vault ML20077R6771991-08-0808 August 1991 Submits Results of Boric Acid Experiments on Known Core,Per Discussions W/Nrc & Univ Nuclear Safety Review Board.State Point Measurements Made Before & After Boric Acid Addition Agreed within Specified Reproducibility Errors ML20077D9561991-05-30030 May 1991 Forwards Corrected Affidavit for Withholding Supporting Matl to License Amend for RCF Critical CX-22 Facility (Ref 10CFR2.790) ML20073P8341991-05-15015 May 1991 Forwards Abb Cenp Critical Experiments in Reactor Critical Facility of Rpi ML20073G8631991-04-30030 April 1991 Forwards CE Proprietary Abb Cenp Critical Experiments in Reactor Critical Facility of Rensselaer Polytechnic Inst. Encl Withheld (Ref 10CFR2.790) ML20073G8561991-04-12012 April 1991 Forwards Addendum to Which Transmitted Presentation of Technical Info Re Calculation & Measurement of Tech Spec Parameters for Erbium Burnable Absorbers at Facility ML20070U7151991-04-0303 April 1991 Submits Decommissioning Rept,Per 10CFR50.33(k)(2),in Response to T Michaels .Assets W/Listed Market Value Deposited in Bank of New York in Mar 1991 ML20077A4371991-03-25025 March 1991 Forwards Info Re Calculation & Measurement of Tech Spec Parameters for Erbium Burnable Adsorbers at Univ Reactor Criticality Facility Developed by C-E.Info Withheld (Ref 10CFR2.790) ML20059K1611990-09-14014 September 1990 Forwards Completed Compliance Rept Re Decommissioning of Reactor,Per 900726 Request ML20059K1701990-09-13013 September 1990 Submits Decommissioning Funding Rept,Per 10CFR50.75(e)(2) ML20055H9501990-07-26026 July 1990 Advises That Submittal Re Decommissioning & Financial Assurance Will Be Sent in mid-Sept 1990 ML20247B2291989-07-19019 July 1989 Forwards Safety Insp Rept 50-225/89-01 on 890518-19.No Violations Noted ML20246A1571989-06-27027 June 1989 Advises That 881017 & 890309 & 0413 Changes to Physical Security Plan Consistent w/10CFR50.54(p) & Acceptable ML20247J1971989-05-22022 May 1989 Submits Annual Rept of Operations at RPI Reactor Critical Facility Required Under Tech Spec 6.5.1 ML20246P3331989-03-22022 March 1989 Forwards Agenda for 890418-19 Research & Test Reactor Seminars in King of Prussia,Pa Per .Updated Agenda Soon to Follow.Map of Local Area Also Encl ML20247E1771989-03-21021 March 1989 Forwards Request for Ref Matl Requirements for Reactor/ Senior Reactor Operator Licensing Exams,Scheduled for 890614-15 ML20235V7871989-02-17017 February 1989 Forwards Memo Describing Incident Which Occurred at Reactor Critical Facility.Understands That Incident Does Not Require Immediate Notification to NRC ML20206F8061988-11-0909 November 1988 Forwards Safety Insp Rept 50-225/88-04 on 880817-18 & Notice of Violation.Violations Indicate Need for Greater Mgt Oversight of & Attention to Licensed Activities ML20154R8881988-09-28028 September 1988 Forwards Safety Insp Rept 50-225/88-03 on 880812.No Violations Noted ML20246K9431988-09-16016 September 1988 Forwards BC Drobnicki Memo,Revising Memo Communicated to NRC on 880816.Encl Withheld (Ref 10CFR2.790(d)) ML20151G9851988-07-19019 July 1988 Forwards Safeguards Insp Repts 50-225/88-02 & 70-0920/88-01 on 880607-10 & Partially Withheld Notice of Violation ML20196L0361988-06-28028 June 1988 Forwards Exam Rept 50-225/88-01OL of Exam Administered During Wk of 880523.Licensee Should Describe,Within 30 Days, What Steps Will Be Taken to Assure Future License Applicants Will Possess Adequate Experience ML20150D8641988-03-18018 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 IA-87-825, Final Response to FOIA Request.Forwards App E Document.App E Document Also Available in Pdr.App F Document Partially Withheld & App G Document Completely Withheld (Ref FOIA Exemptions 4 & 5),respectively1988-03-0808 March 1988 Final Response to FOIA Request.Forwards App E Document.App E Document Also Available in Pdr.App F Document Partially Withheld & App G Document Completely Withheld (Ref FOIA Exemptions 4 & 5),respectively ML20196K1521988-03-0808 March 1988 Final Response to FOIA Request.Forwards App E Document.App E Document Also Available in Pdr.App F Document Partially Withheld & App G Document Completely Withheld (Ref FOIA Exemptions 4 & 5),respectively ML20149M6751988-02-19019 February 1988 Forwards Exam Rept 50-225/87-02(OL) of Exams Administered on 871201-02 ML20235G7921987-09-22022 September 1987 Confirms 870917 Telcon Authorizing Licensee to Proceed W/ Conversion of High to Low Enriched U ML20235F7361987-09-22022 September 1987 Ack Reciept of 870811 Comments on Changes to Reactor Staffing at Rensselaer Polytechnic Inst Critical Experiment Reactor Facility.Conversion Granted ML20234C0041987-09-10010 September 1987 Summarizes 870909 Discussion Re F Wicks Intervention Document Which Alleges That Fj Rodriguez-Vera Inappropriate Reactor Supervisor Due to Status as Student.Student Visa Permits Employment on Campus ML20238A6071987-08-31031 August 1987 Forwards Amend 8 to License CX-22 & Safety Evaluation.Amend Changes License Conditions to Reflect Approval of Revised Security Plan Submitted on 870609.Rev to Plan Reflects New Measures Used to Protect SNM of Low Strategic Significance ML20235N7951987-07-0707 July 1987 Forwards Order Modifying License CX-22 to Convert from High to Low Enriched U,Safety Evaluation,Environ Assessment & Replacement Pages for Tech Specs,In Response to 861003 Request ML20215E0411987-06-12012 June 1987 Informs That Fence Mods Around Civil Protection & Security Zones of Facility Completed on 870611.Changes Return Facility to Spirit of Situation Prior to 861230 & of New Security Plan ML20215E1111987-06-0909 June 1987 Forwards Response to Comments Re Rensselear Polytechnic Inst Reactor Critical Facility Security Plan Dtd Jan 1987. W/O Encl ML20214U6461987-05-27027 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 Re Communications Procedures Amends Encl for Review ML20214K5511987-05-18018 May 1987 Forwards Insp Rept 50-225/87-01.Licenses of Two of Three Currently Licensed Operators Will Be Reactivated Upon Proper Application & Subsequently Renewed for Use W/New Core Configuration ML20213G5191987-05-13013 May 1987 Forwards Request for Addl Info Re Security Plan on Protection of SNM of Low Strategic Significance Submitted by .Encl Withheld (Ref 10CFR2.790(d)) ML20206Q5291987-04-15015 April 1987 Forwards Reactor Operator Requalification (Ror) Program for Rensselaer Polytechnic Inst Reactor Critical Facility (Rcf). Rept Includes Section Re Requalification of Currently Licensed Senior Reactor Operators ML20214Q5951987-04-10010 April 1987 Forwards EGG-NTA-7660, Evaluation of Spert Fuel at Rensselaer Polytechnic Inst, Technical Evaluation Rept Submitted as Part of Task 3 ML20205T5541987-03-31031 March 1987 Advises That 870205 Rev to Security Plan Will Be Reviewed w/861223 Security Plan.Headquarters Will Respond Re Rev ML20207S2931987-03-12012 March 1987 Forwards Missing Pages from App 3 to Ref 5 in Addendum to 870303 Answer to Question 16 Re Difxy Computer Code 1998-07-20
[Table view] Category:EDUCATIONAL INSTITUTION TO NRC
MONTHYEARML20059K1611990-09-14014 September 1990 Forwards Completed Compliance Rept Re Decommissioning of Reactor,Per 900726 Request ML20059K1701990-09-13013 September 1990 Submits Decommissioning Funding Rept,Per 10CFR50.75(e)(2) ML20055H9501990-07-26026 July 1990 Advises That Submittal Re Decommissioning & Financial Assurance Will Be Sent in mid-Sept 1990 ML20247J1971989-05-22022 May 1989 Submits Annual Rept of Operations at RPI Reactor Critical Facility Required Under Tech Spec 6.5.1 ML20235V7871989-02-17017 February 1989 Forwards Memo Describing Incident Which Occurred at Reactor Critical Facility.Understands That Incident Does Not Require Immediate Notification to NRC ML20246K9431988-09-16016 September 1988 Forwards BC Drobnicki Memo,Revising Memo Communicated to NRC on 880816.Encl Withheld (Ref 10CFR2.790(d)) ML20234C0041987-09-10010 September 1987 Summarizes 870909 Discussion Re F Wicks Intervention Document Which Alleges That Fj Rodriguez-Vera Inappropriate Reactor Supervisor Due to Status as Student.Student Visa Permits Employment on Campus ML20215E0411987-06-12012 June 1987 Informs That Fence Mods Around Civil Protection & Security Zones of Facility Completed on 870611.Changes Return Facility to Spirit of Situation Prior to 861230 & of New Security Plan ML20215E1111987-06-0909 June 1987 Forwards Response to Comments Re Rensselear Polytechnic Inst Reactor Critical Facility Security Plan Dtd Jan 1987. W/O Encl ML20206Q5291987-04-15015 April 1987 Forwards Reactor Operator Requalification (Ror) Program for Rensselaer Polytechnic Inst Reactor Critical Facility (Rcf). Rept Includes Section Re Requalification of Currently Licensed Senior Reactor Operators ML20207S2931987-03-12012 March 1987 Forwards Missing Pages from App 3 to Ref 5 in Addendum to 870303 Answer to Question 16 Re Difxy Computer Code ML20212N3841987-03-0303 March 1987 Forwards Response to 870106 Request for Addl Info Re 861003 Proposal to Convert Reactor Critical Facility Core to Use Low Enrichment U Fuel ML20212C5821987-02-24024 February 1987 Notifies of Application of 10CFR55.31(e) to Senior Reactor Operators Licenses During Rensselaer Polytechnic Inst Highly Enriched U/Low Enriched U Core Conversion Process,Per Telcons.Listed Tasks Underway ML20212F9701986-12-23023 December 1986 Forwards Security Plan Documenting Physical & Procedural Measures to Prevent Theft of Reactor Fuel & Sabotage to Critical Facility.Plan Withheld (Ref 10CFR2.790(d) & 73.21(a)) ML20215C1481986-10-0303 October 1986 Requests Permission for Conversion of Core to Low Enriched U Fuel & Continued Operation Per Encls.Conversion Specifics Discussed ML20210H2671986-09-22022 September 1986 Advises That Fr Vera New Supervisor of Facility ML20209F5571986-08-22022 August 1986 Forwards Description of Upgraded Physical Security Sys, Including Infrared Motion Sensors & New Control Panel.W/O Encl ML20141F9231986-04-17017 April 1986 Forwards 860317 Annual Rept Ltr to Region I,Containing Addl Info Missing from 860317 Rept Ltr to Div of Licensing,Per 860414 Telcon Request ML20138N9031985-10-18018 October 1985 Forwards Answer & Consent to Commission Order to Show Cause ML20101U3981985-01-31031 January 1985 Advises That Emergency Plan for License CX-22,submitted on 841205 & Approved by NRC ,Fully Implemented ML20100L9041984-12-0505 December 1984 Forwards Proposed Emergency Plan for License CX-22 Dtd Dec 1984,superseding Proposed Emergency Plan Dtd Sept 1984. Emergency Planning Zone in Section 6 Changed to Outside Reactor Room But Inside Bldg ML20093F7711984-09-28028 September 1984 Forwards Proposed Emergency Plan, in Response to 840730 Request for Addl Info & IE Info Notice 83-66,Suppl 1.Plan Provides Addl Info in Sections 3.5 & 3.6 Re Emergency Action Levels & Emergency Planning Zones,Respectively ML20082L5631983-11-18018 November 1983 Forwards Financial Rept for Yrs Ending June 1982 & June 1983 ML20078L0891983-10-13013 October 1983 Forwards Ltr to Replace Re Tech Specs.Original Ltr Missing Signatures ML20078L1011983-10-12012 October 1983 Forwards Amended Tech Specs.W/O Encls ML20080J3471983-09-21021 September 1983 Forwards Responses to 830726 Questions from Review of Documentation Submitted in Support of Application for License Renewal ML20023C5991983-04-26026 April 1983 Forwards Revised Physical Security Plan,Replacing 820426 Plan.Plan Withheld (Ref 10CFR2.790 & 73.21) ML20070P1561983-01-21021 January 1983 Forwards Rensselaer Polytechnic Inst Critical Facility Sar ML20028D4521983-01-13013 January 1983 Submits Public Version of Opinion That Emergency Response Plan,Already Filed,Fulfills Requirements of 10CFR50.54.If Mods Necessary,Response Will Be Provided ML20052B4161982-04-26026 April 1982 Forwards Physical Security Plan Replacing Plan Submitted on 820326.Plan Withheld (Ref 10CFR2.790) ML20050B8631982-03-26026 March 1982 Forwards Physical Security Plan,Per 810302 Ltr.Plan Withheld (Ref 10CFR2.790) ML20049K0371982-03-0101 March 1982 Submits Annual Operating Rept of Activities & Experiments for License CX-22,Mar 1981-Mar 1982 ML20040G3291982-02-0808 February 1982 Informs That RPI Critical Facility Has Less than 5,000 G U-235 on Site,In Response to 820115 Telcon.Change Represents Amended Condition for Current OL & Application for Renewal ML20040F2621982-01-12012 January 1982 Responds to NRC 811104 Ltr Re Violations Noted in IE Insp Rept 50-225/81-01.Corrective Actions:New Critical Facility Supervisor Reviewed Operating Procedures ML20003D2091981-03-0101 March 1981 Submits Annual Rept of Tests & Experiments for 800301- 810301.Facility Was Utilized for Graduate Course on Reactor Experiments,Summer Course on Reactor Design & Project Work to Satisfy Degree Requirements ML19331D3201980-08-22022 August 1980 Forwards Critical Experiments Facility Security Plan.Plan Withheld (Ref 10CFR2.790).Telcon W/P Trimble Informed of Shipment of Excess SNM to Oak Ridge,Tn ML19309F6701980-03-28028 March 1980 Responds to NRC 800310 Ltr Re Violations Noted in IE Insp Rept 50-225/80-01.Corrective Actions:Personnel Monitoring Procedure Revised & TLD Records Now Computerized ML19323B3791980-03-27027 March 1980 Responds to NRC 800307 Ltr Re Violations Noted in IE Insp Rept 50-225/80-02.Corrective Actions:Telephone Extension Installed in Control Room.Students Instructed to Work in Pairs When Practicable ML19294C1931980-02-29029 February 1980 Submits Operating Rept of Tests & Experiments Conducted Mar 1979 - Mar 1980 ML19253B0261979-09-12012 September 1979 Submits Application for Renewal of License CX-22.Forwards Fsar,Eia,Revised Section 6 of Tech Specs,Emergency Plan & 790615 & 0707 Ltrs Re Emergency Procedures ML19263E3181979-06-0101 June 1979 Forwards Executed Amend 9 to Indemnity Agreement E-42 ML19270F7301979-03-0101 March 1979 Submits Rept of Tests & Experiments Conducted from 780301 to 790301.No Changes to Tech Specs & No Unreviewed Safety Questions ML20062B7501978-10-26026 October 1978 Advises That Insurance Broker Sending Advance Premium Endorsement.Indemnity Agreement Was Forwarded Earlier 1990-09-14
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20148F0771997-05-29029 May 1997 Informs That Bs Craig Replaced Mn Galayda as Supervisor of RPI Reactor Critical Facility on 970516 ML18065B2651995-07-21021 July 1995 Informs of 950711 Conversation W/S Holmes Re Change & Temporary Reduction in Radiation Safety Staffing within Past Yrs ML20077R6771991-08-0808 August 1991 Submits Results of Boric Acid Experiments on Known Core,Per Discussions W/Nrc & Univ Nuclear Safety Review Board.State Point Measurements Made Before & After Boric Acid Addition Agreed within Specified Reproducibility Errors ML20077D9561991-05-30030 May 1991 Forwards Corrected Affidavit for Withholding Supporting Matl to License Amend for RCF Critical CX-22 Facility (Ref 10CFR2.790) ML20073P8341991-05-15015 May 1991 Forwards Abb Cenp Critical Experiments in Reactor Critical Facility of Rpi ML20073G8631991-04-30030 April 1991 Forwards CE Proprietary Abb Cenp Critical Experiments in Reactor Critical Facility of Rensselaer Polytechnic Inst. Encl Withheld (Ref 10CFR2.790) ML20073G8561991-04-12012 April 1991 Forwards Addendum to Which Transmitted Presentation of Technical Info Re Calculation & Measurement of Tech Spec Parameters for Erbium Burnable Absorbers at Facility ML20070U7151991-04-0303 April 1991 Submits Decommissioning Rept,Per 10CFR50.33(k)(2),in Response to T Michaels .Assets W/Listed Market Value Deposited in Bank of New York in Mar 1991 ML20077A4371991-03-25025 March 1991 Forwards Info Re Calculation & Measurement of Tech Spec Parameters for Erbium Burnable Adsorbers at Univ Reactor Criticality Facility Developed by C-E.Info Withheld (Ref 10CFR2.790) ML20059K1611990-09-14014 September 1990 Forwards Completed Compliance Rept Re Decommissioning of Reactor,Per 900726 Request ML20059K1701990-09-13013 September 1990 Submits Decommissioning Funding Rept,Per 10CFR50.75(e)(2) ML20055H9501990-07-26026 July 1990 Advises That Submittal Re Decommissioning & Financial Assurance Will Be Sent in mid-Sept 1990 ML20247J1971989-05-22022 May 1989 Submits Annual Rept of Operations at RPI Reactor Critical Facility Required Under Tech Spec 6.5.1 ML20235V7871989-02-17017 February 1989 Forwards Memo Describing Incident Which Occurred at Reactor Critical Facility.Understands That Incident Does Not Require Immediate Notification to NRC ML20246K9431988-09-16016 September 1988 Forwards BC Drobnicki Memo,Revising Memo Communicated to NRC on 880816.Encl Withheld (Ref 10CFR2.790(d)) ML20234C0041987-09-10010 September 1987 Summarizes 870909 Discussion Re F Wicks Intervention Document Which Alleges That Fj Rodriguez-Vera Inappropriate Reactor Supervisor Due to Status as Student.Student Visa Permits Employment on Campus ML20215E0411987-06-12012 June 1987 Informs That Fence Mods Around Civil Protection & Security Zones of Facility Completed on 870611.Changes Return Facility to Spirit of Situation Prior to 861230 & of New Security Plan ML20215E1111987-06-0909 June 1987 Forwards Response to Comments Re Rensselear Polytechnic Inst Reactor Critical Facility Security Plan Dtd Jan 1987. W/O Encl ML20206Q5291987-04-15015 April 1987 Forwards Reactor Operator Requalification (Ror) Program for Rensselaer Polytechnic Inst Reactor Critical Facility (Rcf). Rept Includes Section Re Requalification of Currently Licensed Senior Reactor Operators ML20214Q5951987-04-10010 April 1987 Forwards EGG-NTA-7660, Evaluation of Spert Fuel at Rensselaer Polytechnic Inst, Technical Evaluation Rept Submitted as Part of Task 3 ML20207S2931987-03-12012 March 1987 Forwards Missing Pages from App 3 to Ref 5 in Addendum to 870303 Answer to Question 16 Re Difxy Computer Code ML20212N3841987-03-0303 March 1987 Forwards Response to 870106 Request for Addl Info Re 861003 Proposal to Convert Reactor Critical Facility Core to Use Low Enrichment U Fuel ML20212C5821987-02-24024 February 1987 Notifies of Application of 10CFR55.31(e) to Senior Reactor Operators Licenses During Rensselaer Polytechnic Inst Highly Enriched U/Low Enriched U Core Conversion Process,Per Telcons.Listed Tasks Underway ML20212F9701986-12-23023 December 1986 Forwards Security Plan Documenting Physical & Procedural Measures to Prevent Theft of Reactor Fuel & Sabotage to Critical Facility.Plan Withheld (Ref 10CFR2.790(d) & 73.21(a)) ML20215C1481986-10-0303 October 1986 Requests Permission for Conversion of Core to Low Enriched U Fuel & Continued Operation Per Encls.Conversion Specifics Discussed ML20210H2671986-09-22022 September 1986 Advises That Fr Vera New Supervisor of Facility ML20209F5571986-08-22022 August 1986 Forwards Description of Upgraded Physical Security Sys, Including Infrared Motion Sensors & New Control Panel.W/O Encl ML20141F9231986-04-17017 April 1986 Forwards 860317 Annual Rept Ltr to Region I,Containing Addl Info Missing from 860317 Rept Ltr to Div of Licensing,Per 860414 Telcon Request ML20138N9031985-10-18018 October 1985 Forwards Answer & Consent to Commission Order to Show Cause ML20101U3981985-01-31031 January 1985 Advises That Emergency Plan for License CX-22,submitted on 841205 & Approved by NRC ,Fully Implemented ML20100L9041984-12-0505 December 1984 Forwards Proposed Emergency Plan for License CX-22 Dtd Dec 1984,superseding Proposed Emergency Plan Dtd Sept 1984. Emergency Planning Zone in Section 6 Changed to Outside Reactor Room But Inside Bldg ML20093F7711984-09-28028 September 1984 Forwards Proposed Emergency Plan, in Response to 840730 Request for Addl Info & IE Info Notice 83-66,Suppl 1.Plan Provides Addl Info in Sections 3.5 & 3.6 Re Emergency Action Levels & Emergency Planning Zones,Respectively ML20082L5631983-11-18018 November 1983 Forwards Financial Rept for Yrs Ending June 1982 & June 1983 ML20078L0891983-10-13013 October 1983 Forwards Ltr to Replace Re Tech Specs.Original Ltr Missing Signatures ML20078L1011983-10-12012 October 1983 Forwards Amended Tech Specs.W/O Encls ML20080J3471983-09-21021 September 1983 Forwards Responses to 830726 Questions from Review of Documentation Submitted in Support of Application for License Renewal ML20023C5991983-04-26026 April 1983 Forwards Revised Physical Security Plan,Replacing 820426 Plan.Plan Withheld (Ref 10CFR2.790 & 73.21) ML20070P1561983-01-21021 January 1983 Forwards Rensselaer Polytechnic Inst Critical Facility Sar ML20028D4521983-01-13013 January 1983 Submits Public Version of Opinion That Emergency Response Plan,Already Filed,Fulfills Requirements of 10CFR50.54.If Mods Necessary,Response Will Be Provided ML20052B4161982-04-26026 April 1982 Forwards Physical Security Plan Replacing Plan Submitted on 820326.Plan Withheld (Ref 10CFR2.790) ML20050B8631982-03-26026 March 1982 Forwards Physical Security Plan,Per 810302 Ltr.Plan Withheld (Ref 10CFR2.790) ML20049K0371982-03-0101 March 1982 Submits Annual Operating Rept of Activities & Experiments for License CX-22,Mar 1981-Mar 1982 ML20040G3291982-02-0808 February 1982 Informs That RPI Critical Facility Has Less than 5,000 G U-235 on Site,In Response to 820115 Telcon.Change Represents Amended Condition for Current OL & Application for Renewal ML20040F2621982-01-12012 January 1982 Responds to NRC 811104 Ltr Re Violations Noted in IE Insp Rept 50-225/81-01.Corrective Actions:New Critical Facility Supervisor Reviewed Operating Procedures ML20003D2091981-03-0101 March 1981 Submits Annual Rept of Tests & Experiments for 800301- 810301.Facility Was Utilized for Graduate Course on Reactor Experiments,Summer Course on Reactor Design & Project Work to Satisfy Degree Requirements ML19331D3201980-08-22022 August 1980 Forwards Critical Experiments Facility Security Plan.Plan Withheld (Ref 10CFR2.790).Telcon W/P Trimble Informed of Shipment of Excess SNM to Oak Ridge,Tn ML19309F6701980-03-28028 March 1980 Responds to NRC 800310 Ltr Re Violations Noted in IE Insp Rept 50-225/80-01.Corrective Actions:Personnel Monitoring Procedure Revised & TLD Records Now Computerized ML19323B3791980-03-27027 March 1980 Responds to NRC 800307 Ltr Re Violations Noted in IE Insp Rept 50-225/80-02.Corrective Actions:Telephone Extension Installed in Control Room.Students Instructed to Work in Pairs When Practicable ML19294C1931980-02-29029 February 1980 Submits Operating Rept of Tests & Experiments Conducted Mar 1979 - Mar 1980 ML19253B0261979-09-12012 September 1979 Submits Application for Renewal of License CX-22.Forwards Fsar,Eia,Revised Section 6 of Tech Specs,Emergency Plan & 790615 & 0707 Ltrs Re Emergency Procedures 1997-05-29
[Table view] |
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.:O _.
Department of Nucliar Engineering a
Rensselaer Polytechnic Institute Troy, New York 12180-3590 February 24, 1987-Mr. John Dosa, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B Office- of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear John:
SUBJECT:
APPLICATION OF 10 CFR 55.31(e) TO THE SRO's LICENSES DURING RPI HEU/ LEU CORE CONVERSION.
This is to notify you about our interpretation of 10 CFR 55.31(e) in the case of our SRO licenses during the RPI HEU/ LEU Core Conversion process.
We sent you copies (attached here as well) of our memoranda to Dr. R.T.
Lahey, Jr. informing of the HEU fuel shipment from the RPI Reactor Critical Facility (RCF), and receipt and storage of the LEU fuel at the RCF (December 31, 1986). According with the first memorandum, the last time we manipulated HEU fuel was on October 27, 1986, when we removed it from the core, inventoried it and loaded it into shipping cask FBF-35. In accord with the second memorandum, the last time we handled LEU fuel was on December 31, 1986, when the LEU SPERT fuel was inventoried and stored at the RCF fuel vault.
- According to Section 5.6 of our recently amended
- Technical Specifications:
- "all fuel transfers shall be conducted under the direction of a licensed senior operator." So last time we actively performed the functions of senior reactor operators was on December 31, 1986, and therefore if we would
~
not perform the functions of SRO's before April 30, 1987, then we would have to demonstrate to the NRC that our knowledge and understanding of facility
- operation and administration are satisfactory, in compliance with 10 CFR 55.31(e). We expect to receive an NRC order for LEU fuel loading sometime in r April 1987. In the meantime we have been working in the following tasks
- Amendment No. 6 to License CX-22 effective on December 1, 1986.
070303CB21 870224 J1DR ADOCK 05000225 PDR p0go V ,}g t
=. ,
, 3 .
D.R. Harris /F. Rodriguez-Vera February 24, 1987 Page 2
- 1. Formulation of the proposed SAR and Technical Specifications for the LEU. fuel core.
- 2. ' Answer to NRC Questions regarding previous task.
- 3. Regular instruments tests and calibration according to our Internal Procedures, which should be performed even when the reactor is shut down.
- 4. Weekly inspections of stored LEU fuel in accordance with our Internal Procedures.
- 5. Biannual RPI written examinations relevant to the LEU core (completed for Harris and Rodriguez-Vera on January 16, 1987).
- 6. Modifications to our Requalification Program for SRO's in view of the HEU/ LEU core conversion.
We consider that performance of these tasks includes on-the-job training and is sufficient to maintain our operator licenses.
This written notification is a result of our phone conversations with Mr.
Joseph Buzzy (NRC Headquarters) and Mr. Doug Coe (NRC-Region I) over the last two weeks. We expect to send our new Requalification Program to these gentlemen, af ter review and approval by our Nuclear Safety Review Board (NSR3), as suggested by Mr. Buzzy.
Sincerely, t%L .
- r. Donald R. Harris Fr sco . Rodriguez-Vera Director of the RCF Supe isor of the RCF SRO License No. SOP-10360 SRO License No. SOP-10359 Enclosures Copy of memoranda to Dr. R.T. Lahey, Jr. , from D.R. Harris and F. Rodriguez dated 10/28/86, and 12/31/86.
Copy of Amendment No. 6 to License CX-22.
cc: Joseph Buzzy (NRC. Washington, DC)
Doug Coe (NRC. Region I) i i
1 t
i
n,,-. ,.
- ? { [_.i _ Depatiment of Nuclicar Engineeririg p%y ^l W
ad .
Rensselaer Polytechnic Institute Troy, New York 12180-3590 October 28, 1986 TO: Dr. R.T. Lahey, Jr.
FROM: Dr. D.R. Harris and F. Rodriguez l
/
SUBJECT:
HEU Fuel Shipping out of the RPI Critical Facility Two shipping casks, DOT 6M Type B, arrived at the RPI reactor facility on
. October 21, 1986 and were inspected. The 177 HEU fuel plates at the reactor
- facility, license CX-22, were inventoried, inspected and packed into cask FBF-10 on October 27, 1986. R.M. Ryan brought 11 HEU fuel plates fros' the RPI LINAC, license SNM-910, to the reactor facility. on October 27; we inventoried and inspected the 11 plates, and we loaded them into cask 1BF-35. The shipping casks were closed, and seal numbers 5350 and 5356 were attached to casks FBF-10 and FBF-35, respectively. The packaging, closures, and seals were inspected by us and by R.M. Ryan, Director, RPI Radiation and Nuclear Safety Office, on October 27. These operations were conducted in accord with cur " Procedures for Packaging of Licensed Haterial for Transport".
Alland sarlier, paperwork we now relevant await to this HEU fuel shipment was completed by us the SST truck. The provision of the shipping casks cad the assignment of the SST truck to pick up our fuel are responsibilities of USDOE personnel and are not at our discretion.
4 Photographs of the two sealed shipping casks, ready for, shipment, are cttached to this meno. We would like to keep these pictures in our file for the next NSRB meeting, and for the NRC inspectors to review, so please send them back to us.
/evh Attachment C/ B. Drobnicki J. Dosa (NRC)
G. Judd R. Ryan
! D. Sangrey
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FIGURE 1. Container FBF #10, Seal #5350 Containing 177 HEU Fuel Plates from l j the Critical Facility (License CK-22) i l
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FIGURE 2. Container FBF #35, Seal #5356 Containing 11 HEU Plates from the LINAC Vault (License S?ti-910) ,
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Rensselaer Polytechnic institute Troy, New York 12180-3590 December 31, 1986 TO: Dr. R.T. Lahey, Jr.
FROM: Dr. D.R. Harris F. Rodriguez
SUBJECT:
Receipt of Low-Enrichment Fuel at RFI Critical Facility
REFERENCES:
10/28/86'and 12/5/86 Ffemos J.L. Snelgrove, R.F. Domagain, and L.R. Dates, "Reqitalification of SPERT Pins for Use in liniversity Reactors,"
ANL/RERTR/TM-8, December 1986.
The new low-enrichment fuel (592 rods of 4.81 wolght parcont If215
- curi chmont-) wan recolved nt the RPI Ronctor CrItienI rnetiIiy (Rf:F) on lincombe r '10, 1986. The Inel was in9pected, loventorted, and stored in tha reconstructed RCF' fuel vault on December 30 and 3i, 1986. The empty shipping canks used to ship the new fatel will be rettirned on .Innunry I'l, 1987 to EC&G Idaho. The new fuel wa9 nubjected to nn intonnive rpini t flention investigntion by Argonne Hattonni Imborntnry innder contract: to tlin llS H O F,. The (nel was fotind to be in excellent condit ten (Snalgrove, 1986).
The tinclear Regn1ntory Commins ton han npproved (R. Crui ter, verbal commiinicat.f on, Flovember 1986) the qual.lfIcatto't of the new finet for n9e in tita RCF.
/evh C/ !). Berg K. Brown (DOE)
G. Dahl J. Donn (NRC)
B. Drobnicki G. Judd A. Maclea R. Ryan D. Sangrey
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- g UNITED STATES 8 a NUCLEAR REGULATORY COMMISSION E :
) WASHINGTON, D. C. 20555
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RENSSELAER POLYTECHNIC INSTITUTE DOCKET NO. 50-225 f
i, AMENDMENT TO FACILITY OPERATING LICENSE
' . Amendment No. 6 License No. CX-22
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
, A. The application for amendment to Facility Operating License No.
, CX-22, filed by Rensselaer Polytechnic Institute (the licensee),
dated October 17, 1986, complies with the standards and requirements
, of the Atomic Energy Act of 1954, as amended (the Act), and the
! Commission's regulations as set forth in 10 CFR Chapter I; i
B. The faciliti will operate in conformity with the amended license, the provisions of the Act, and the rules and regulations of the Commission; 1 C. There is reasonable assurance: (i) that the activities authorized L by P s amendment can be conducted without endangering the health j ai . afety of the public, and (ii) that such activities will be l conducted in compliance with the Commission's. regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and' safety of the,public; i
E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have '
been satisfied; and l F. Publication of notice of this amendment is not required since it does not involve a significant hazards consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2).
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4 2., Accordingly, Facility Operating License No. CX-22 is hereby. amended by adding paragraph B.5, which reads as follows: ,
- 5. Pursuant to the Act and 10 CFR Part 70, " Domestic Licensing of Special Nuclear Material," to receive and possest, but not to use, 21.12 kilograms of contained uranium-235 in SPERT (F-1) fuel pins.
- 3. Accordingly, the license is amended by changes to the Technical Specificatfons as indicated in the attachment to this license amendment, and paragr6ph C.2 of License No. CX-22 is hereby amended to read as
, follows:
i.
- 2. Technical Specifications The Technical Specifications contained in Appendix A, as revised
. through Amendment No. 6, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
- 4. This license amendment is effective as of its date of issuance. t FOR THE NUCLEAR REGULATORY COMMISSION 2
t/-
Herbert N. Berkow, Director Standardization and Special Projects Directorate
- Division of PWR Licensing-B
- Office of Nuclear Reactor Regulation J
Attachment:
Appendix A Technical Specifications Changes Date of Issuance: December 1, 1986 t
ATTACHMENT TO LICENSE AMENDMENT NO. 6 FACILITY OPERATING LICENSE NO. CX-22 DOCKET NO. 50-225 Revised Appendix A Technical Specifications is as follows:
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Remove Pages Add Pages 5-2 5-2 5-3 5-3 1
Changes on the revised pages are identified by marginal lines.
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- 5-2 5.4.2 Reactor Core fhe stainless steel reactor core structure is comprised of u#er, center, and lower gria p'lates. The active core is situated netween tne upper and. center gria plates and is about 22 inches in height and 22 inches in equivalent diam-eter. The core normally contains 38 stationary fuel assem-blies and 4 control rod assemblies with fuel followers. Tne entire support structure is mounted on four posts set in tne floor of the reactor tank.
5.4.3 Standard Fuel Assemoiies A. stationary fuel assembly shall be composed of a maximum of t 18 fuel plates. The box-type fuel assembifes are 2.9 X 2.9 X 22 inches in dimensions'. The center-to-center spacing of .
the fuel plates is maintained by grooved polystyrene inserts 4 at 0.163 inch. A control rod fuel follower will be of similar fuel enrichment, but*1imited to a maximum of 16 plates per assembly. For reduced loadings, plates may be omitted or dummy plates used.
5.'4.4 Control Rod Assemolles The control ' rod assembly shall consist of a control rod -
aosoreer sec't' ion and a control rod follower. Tne length of the control rod poison section is 22 inenes and is nominally
.2.619 inches square. l The poison and fuel follower are in-i serted in a stainless steel square tuce, 2.75 inches square, which passes throug,h tne core and rests in a hydraulic ouffer l
on the bottom grid. plate,q,f,the support structure.
The drive mechanism is a mo,t or and gear oox coup. led by a mag-
- netic clutch to a rack and pinion attached to the top of the rod from an overhead cantilever mount.
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5.5 Water Handling System The water handling system allows remote filling and emptying of the reactor tank. It provides for a water dump by means of a fail safe butterfly-type gate valve wnen a reactor scram is initiated. The j filling system shall be controlled by the operator who must satisfy the sequential interlock system before adding water to the tank. A pump is provided to add the moderator-reflector water from the stor-age cump tank into the reactor tank. Slow and fast fill rates of about 10 gpm and 50 gpm, respectively, are provided. A nominal six inch valve is installed in the dump line and has the capability of emptying the reactor tank on demand of the operator or wnen a reac-tor scram is initiated, unless bypassed with the approval of the
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5-3 licensed senior operator on duty. A valve is installed in the bottom drain line of the reactor tank to provide for completely emptying the reactor tank.
5.6 Fuel i
The fuel used for reactor operation is~ a plate-type, stainless steel clad, UO -SS cermet enriched to 93% U-235. Stainless steel clad, SPERT (F-1) fu$1 pins, enriched to 4.8% U-235jcan be stored in the facility, but not used for reactor operation.
5.7 Fuel Storage and Transfer When not in use, the fuel shall be stored within the storage vault located in the reactor room. The vault shall be closed by a locked door and shall be provided with a criticality monitor near the vault door. The fuel shall be stored in cadmium clad steel tubes with no more than 1 kg fuel per tube mounted on a steel wall rack. A stora tube in the storage vault can not contain more than 15 SPERT (F-1) ge fuel pins at any time. The. center-to-center spacing of the storage tubes together with the cadmium clad steel tubes assures that the infinite multiplication factor is less than 0.9 when flooded with water.
All fuel transfers shall be conducted under the direction of a licensed senior operator.
Operating personnel shall be familiar with health physics procedures and monitoring techniques and shall monitor the operation with appropriate radiation instrumentation.
For a completely unknown or untested system, fuel loading shall follow the inverse multiplication approach to criticality and, thereafter, meet Specification 4.2. Should any interruption of the loading occur (more than four days), all fuel elements except the initial loading step shall be removed from the core in reverse sequence and the operation repeated.
For a known system, up to a quadrant of elements may be removed from the core or a single stationary fuel assembly be replaced with another stationary. assembly only under the following conditions:
- 1. The net change in reactivity has been previously determined by measurement or calculation to be negative or less than $.72.
. 2. The reactor is subcritical by at least $2.86 in reactivity.
- 3. There is initially only one vacant position within the active fuel lattice.
- 4. The nuclear instrumentation is on scale and the dump valve is not bypassed.
- 5. The critical rod bank position is checked after the operation is complete.
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/ UNITED STATES 8
6 j NUCLEAR REGULATORY COMMISSION WASHINGTON, D C. 20655 -
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 6 TO FACILITY LICENSE NO. CX-22 RENSSELAER POLYTECHNIC INSTITUTE DOCKET NO. 50-225 -
^
1.0 INTRODUCTION
' Rensselaer Polytechnic Institute (RPI) submitted an application, pursuant to 10 CFR 50.90, for an amendment to the operating Ifcense for
- their 100W critical facility on October 17, 1986.
The amendment request asked for peritission to recalve and possess 600 SPERT (F-1) fuel pins containing 21.12 kilograms of contained U-235.
The fuel would be stored in the fuel storage vault with no n: ore than 15 fuel pins per storage tube. This fuel will be utilized in the reactor after fuel. the reactor's conversion to the use of Low Enriched Uranium (LEU) 2.0 EVALUATION The RPI fuel storage vault contains 81 cells composed of stainless steel l tubes, with a five inch inner diameter, surrounded by 0.015 inch of cadmium metal. These tubes are bolted to a unistrut frame in parallel rows. Each cell was designed to accommodate up to one kilogram of '
U-235. The infinite multip11 cation factor has been calculated to be less than 0.90 even if the fuel storage vault were to be entirely flooded with water. The fuel storage vault design was approved by the NRC ca December 2, 1983 1r. conjunction with RPI's license renewal.
The SPERT (F-1) fuel oins to be received and stored each contain 35.2 gm of U-235. Fifteen fuel pins in a cell would amount to 0.52 kg of U-235; an amount less than that already approved for each cell.
Forty storage tubes / cells will be used to store the SPERT (F-1) fuel pins. If RPI needs to store the fuel from its current core, there will be a sufficient nuinber of storage tubes (25 are needed) to safely accommodate these fuel plates. "
There will be no significant increase in individual or cumulative occupational radiat. ion exposure to the operating staff as a re.; ult of re elving and storing the unirradiated SPERT (F-1) fuel pins.
Radiation exposure to the public will be insignificant.
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3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves changes in the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and changes in inspection and surveillance requirements. The staff has determined that the amendment involves no significent hazards consideration (as discussed below), there is no significant change in the types or significant increase in the amcunts of any effluents that may be released offsite, and there is no significant increase in individual
, or cumulative occupational radiatiua exposure. Accordingly, this amenoment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR.51.22(b), no Environmental Impact Statement or Environmental Assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that: (1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously evaluated, or create the possibility of a new or different kind of accident from any accident previously evaluated, and does not involve a significant reduction in a margir. of safety, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed activities, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or the the health and safety of the public.
Principal Contributor: John Dosa Dated: December 1, 1986
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