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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20073B9901991-06-18018 June 1991 Forwards Rept Summarizing Findings of Orau Review of 59 Docket Files for Terminated Research & Test Reactors ML19327B1471989-10-12012 October 1989 Advises That Matls Containing Residual Radioactivity Transferred for Disposal Via Low Level Waste Sys IR 05000112/19890011989-09-13013 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-112/89-01 ML20247B0711989-08-31031 August 1989 Responds to Violations Noted in Insp Rept 50-112/89-01 on 890525-26.Corrective Action:Training Program for Radiation Safety & Facility Emergency Procedures for Norman Fire Dept Being Initiated by Radiation Safety Ofc ML20246E0941989-08-18018 August 1989 Forwards Insp Rept 50-112/89-01 on 890525-26 & Notice of Violation.Recognizes That Receipt of Licensee possession- Only License Resulted in Greatly Reduced NRC Requirements Re Reactor Facility ML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 ML20244D2041989-06-0505 June 1989 Forwards Order Authorizing Dismantling of Facility & Disposition of Component Parts in Response to 881025 Application.Environ Assessment & Finding of No Significant Impact & Safety Evaluation Also Encl ML20235Z5661989-03-0909 March 1989 Forwards Addl Info Re Licensee Plan for Decommissioning,Per Request.Biographical Sketch of Author Included ML20205L2151988-10-25025 October 1988 Forwards Application for Amend to License R-53 to Approve Encl Physical Security Plan.W/O Encl 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 ML20196J3701988-03-0808 March 1988 Forwards Amend 12 to License R-53 & Safety Evaluation.Amend Authorizes Possession,But Not Operation,Of Univ of Ok AGN-211P Research Reactor & Includes Tech Spec Changes Requested in Application ML20149L6531988-02-18018 February 1988 Advises That Licensee in Process of Transferring Fuel Back to DOE Possession,Per Telcon.Work Should Be Completed by End of May,Depending on Speed of Paper Work ML20148K3151988-01-21021 January 1988 Forwards Revised Security Plan in Response to D Carlson Request ML20236S2451987-11-19019 November 1987 Forwards Updated Tech Specs for Ou Agn 211-P Reactor Per Conversation W/Nrc.Requests That Facility Be Exempt from 10CFR50.54 (R) Since No Critical Operations Will Be Allowed & Exempt from Maintaining Requalification Program ML20236F6621987-10-26026 October 1987 Informs That J Pellet Replacing R Cooley as Section Chief of Operator Licensing Section in Div of Reactor Safety, Effective 871025 IR 05000112/19870011987-09-0303 September 1987 Ack Receipt of 870414,0529 & 0720 Ltrs Informing NRC of Steps Taken to Correct Violtaions Noted in Insp Rept 50-112/87-01.Addl Info Re Violation a Provided in Adequate to Resolve Concerns,Per 870617 Telcon ML20237J5141987-07-20020 July 1987 Responds to Violation a Noted in Insp Rept 50-112/87-01. Updated Lab Survey Rept Showing LSC Efficiencies for H-3 & C-14 Encl Per Telcon W/Baer.Understands That Response to Violations B & C Acceptable ML20215C2591987-06-11011 June 1987 Advises That Standardization & Non-Power Reactor Project Directorate Now Under Div of Reactor Projects Iii,Iv & V & Special Projects,Ofc of NRR Due to Recent Organization of NRR ML20214W1981987-05-29029 May 1987 Responds to NRC Re Violations Noted in Insp Rept 50-112/87-01.Corrective Actions:Ltr from Norman Region Hosp Obtained & Sent w/ Which Indicates That Emergency Need Will Be Responded to ML20214H0441987-05-20020 May 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-112/87-01.Requests Addl Info Re Listed Violation from 870316 Notice of Violation ML20209D2621987-04-14014 April 1987 Responds to NRC Re Violations Noted in Insp Rept 50-112/87-01.Corrective Actions:Application for Mod of Tech Specs to Be Completed & Sent to NRC by 870901,including Request for Mod or Deletion of Emergency Plan ML20207S7041987-03-16016 March 1987 Forwards Insp Rept 50-112/87-01 on 870126-30 & Notice of Violation ML20202J1121986-04-0101 April 1986 Forwards Matls Balance Rept for Oct 1985 - Mar 1986 ML20210H9041986-03-27027 March 1986 Lists Change in Telephone Number for H Bernard,Facility Project Manager,Due to NRR Reorganization.D Tondi New Nonpower Reactors & Safeguards Licensing Section Leader. Correspondence Should Be Sent to Listed Address ML20136G3971985-08-12012 August 1985 Informs That 850516 Request for Amend of Requalification Training Program Unacceptable,Per 10CFR55,App a & Generic Ltr 83-12A.New Request Should Be Submitted Addressing Listed Required Conditions IR 05000112/19850011985-07-25025 July 1985 Forwards Safety Insp Rept 50-112/85-01 on 850430-0602.No Violations or Deviations Noted ML20100B4081984-11-30030 November 1984 Informs That Emergency Plan Fully Implemented,Emergency Procedures Written & Approved & Training Program W/Fire & Police Personnel Initiated ML20093P2001984-07-24024 July 1984 Ack Receipt of Ltr Approving Emergency Plan.Plan Implementation Begun.Requests Extension for Completion Until 841130 ML20082M7781983-12-0101 December 1983 Submits List of Errors Noted During Review of NUREG-0996. Errors Do Not Affect Conclusions Reached in SER ML20072G6171983-06-20020 June 1983 Forwards Revised SAR Update & Review, & Tech Specs for 20-yr Renewal of License R-53 ML20077D1391983-06-17017 June 1983 Advises That Univ Operating Under Approved Rev to Reactor Operator Requalification Program,Per NRC ML20072N0481983-05-27027 May 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-112/83-01.Corrective Actions:Check of Flow Rate for Water Purification Sys Procedure Reviewed for Relevance & Implementation ML20071H7871983-05-16016 May 1983 Informs of C Jensen Appointment as Director of Facility ML20079M2451983-02-17017 February 1983 Advises That C Jensen Has Been Appointed as Interim Director of Univ Nuclear Reactor ML20079L4081983-02-14014 February 1983 Advises That All Future Correspondence Re License R-53 Should Be Directed to D Egle ML20071C2061983-02-14014 February 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-112/82-01.Corrective Actions:Copies of Reactor Safety Committee (RCS) New Charter Will Be Forwarded to Region Iv.Rcs Audit Function Redefined ML20064F8811983-01-0404 January 1983 Forwards Revised Operator Requalification Program,To Be Substituted for Mar 1982 Submittal ML20070N4241982-12-15015 December 1982 Forwards Procedures to Suppl Responding to Notice of Violation for IE Insp Rept 50-112/82-01 ML20070N4171982-12-10010 December 1982 Responds to NRC Re Violations Noted in IE Insp Rept 50-112/82-01.Corrective Actions:Change in Sprocket on Safety Rod Drive Will Be Treated as Unreviewed Safety Question & Requalification Program Will Be Revised ML20069M4301982-10-27027 October 1982 Submits Public Version of Status of Emergency Plan,Due 821103.Plan Submitted on 820420 Complies W/Requirements.No New Plan Need Be Developed or Submitted ML20067B5721982-10-11011 October 1982 Forwards Requalification Program for Univ of Ok,For Approval ML20054L3881982-06-16016 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 ML20051J8631982-05-0606 May 1982 Forwards Final Segment of SAR Required to Obtain Renewal of License R-53 ML20052D5851982-04-20020 April 1982 Forwards Public Version of Emergency Plan,In Support of 20-yr Renewal of License R-53 for AGN-211 P Reactor ML20042B8321982-03-28028 March 1982 Forwards Addl Info Re Application for 20-yr Renewal of License R-53 for AGN-211P Reactor ML20042C0581982-03-24024 March 1982 Forwards Eia Supporting Renewal of License R-53 ML20052G2631982-03-23023 March 1982 Forwards Requalification Program for Univ of Ok AGN-211P Reactor ML20049J3711982-03-12012 March 1982 Forwards Incomplete Application for 20-yr Renewal of License R-53.Remaining Matls to Be Submitted in 2 Wks.Security Plan Withheld (Ref 10CFR2.790) ML20040H4831982-01-0404 January 1982 Responds to NRC 811207 Ltr Re Violations Noted in IE Insp Rept 50-112/81-01.Corrective Actions:Clarified Procedure Requiring All Exploratory Changes in Sys Be Reviewed by Reactor Safety Committee Prior to Evaluation ML20009C7261981-06-15015 June 1981 Submits Annual Rept for Jul 1980-June 1981 for License R-53 1991-06-18
[Table view] Category:EDUCATIONAL INSTITUTION TO NRC
MONTHYEARML20247B0711989-08-31031 August 1989 Responds to Violations Noted in Insp Rept 50-112/89-01 on 890525-26.Corrective Action:Training Program for Radiation Safety & Facility Emergency Procedures for Norman Fire Dept Being Initiated by Radiation Safety Ofc ML20235Z5661989-03-0909 March 1989 Forwards Addl Info Re Licensee Plan for Decommissioning,Per Request.Biographical Sketch of Author Included ML20205L2151988-10-25025 October 1988 Forwards Application for Amend to License R-53 to Approve Encl Physical Security Plan.W/O Encl ML20149L6531988-02-18018 February 1988 Advises That Licensee in Process of Transferring Fuel Back to DOE Possession,Per Telcon.Work Should Be Completed by End of May,Depending on Speed of Paper Work ML20148K3151988-01-21021 January 1988 Forwards Revised Security Plan in Response to D Carlson Request ML20236S2451987-11-19019 November 1987 Forwards Updated Tech Specs for Ou Agn 211-P Reactor Per Conversation W/Nrc.Requests That Facility Be Exempt from 10CFR50.54 (R) Since No Critical Operations Will Be Allowed & Exempt from Maintaining Requalification Program ML20237J5141987-07-20020 July 1987 Responds to Violation a Noted in Insp Rept 50-112/87-01. Updated Lab Survey Rept Showing LSC Efficiencies for H-3 & C-14 Encl Per Telcon W/Baer.Understands That Response to Violations B & C Acceptable ML20214W1981987-05-29029 May 1987 Responds to NRC Re Violations Noted in Insp Rept 50-112/87-01.Corrective Actions:Ltr from Norman Region Hosp Obtained & Sent w/ Which Indicates That Emergency Need Will Be Responded to ML20209D2621987-04-14014 April 1987 Responds to NRC Re Violations Noted in Insp Rept 50-112/87-01.Corrective Actions:Application for Mod of Tech Specs to Be Completed & Sent to NRC by 870901,including Request for Mod or Deletion of Emergency Plan ML20100B4081984-11-30030 November 1984 Informs That Emergency Plan Fully Implemented,Emergency Procedures Written & Approved & Training Program W/Fire & Police Personnel Initiated ML20093P2001984-07-24024 July 1984 Ack Receipt of Ltr Approving Emergency Plan.Plan Implementation Begun.Requests Extension for Completion Until 841130 ML20082M7781983-12-0101 December 1983 Submits List of Errors Noted During Review of NUREG-0996. Errors Do Not Affect Conclusions Reached in SER ML20072G6171983-06-20020 June 1983 Forwards Revised SAR Update & Review, & Tech Specs for 20-yr Renewal of License R-53 ML20077D1391983-06-17017 June 1983 Advises That Univ Operating Under Approved Rev to Reactor Operator Requalification Program,Per NRC ML20072N0481983-05-27027 May 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-112/83-01.Corrective Actions:Check of Flow Rate for Water Purification Sys Procedure Reviewed for Relevance & Implementation ML20071H7871983-05-16016 May 1983 Informs of C Jensen Appointment as Director of Facility ML20079M2451983-02-17017 February 1983 Advises That C Jensen Has Been Appointed as Interim Director of Univ Nuclear Reactor ML20071C2061983-02-14014 February 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-112/82-01.Corrective Actions:Copies of Reactor Safety Committee (RCS) New Charter Will Be Forwarded to Region Iv.Rcs Audit Function Redefined ML20079L4081983-02-14014 February 1983 Advises That All Future Correspondence Re License R-53 Should Be Directed to D Egle ML20064F8811983-01-0404 January 1983 Forwards Revised Operator Requalification Program,To Be Substituted for Mar 1982 Submittal ML20070N4241982-12-15015 December 1982 Forwards Procedures to Suppl Responding to Notice of Violation for IE Insp Rept 50-112/82-01 ML20070N4171982-12-10010 December 1982 Responds to NRC Re Violations Noted in IE Insp Rept 50-112/82-01.Corrective Actions:Change in Sprocket on Safety Rod Drive Will Be Treated as Unreviewed Safety Question & Requalification Program Will Be Revised ML20069M4301982-10-27027 October 1982 Submits Public Version of Status of Emergency Plan,Due 821103.Plan Submitted on 820420 Complies W/Requirements.No New Plan Need Be Developed or Submitted ML20067B5721982-10-11011 October 1982 Forwards Requalification Program for Univ of Ok,For Approval ML20051J8631982-05-0606 May 1982 Forwards Final Segment of SAR Required to Obtain Renewal of License R-53 ML20052D5851982-04-20020 April 1982 Forwards Public Version of Emergency Plan,In Support of 20-yr Renewal of License R-53 for AGN-211 P Reactor ML20042B8321982-03-28028 March 1982 Forwards Addl Info Re Application for 20-yr Renewal of License R-53 for AGN-211P Reactor ML20042C0581982-03-24024 March 1982 Forwards Eia Supporting Renewal of License R-53 ML20052G2631982-03-23023 March 1982 Forwards Requalification Program for Univ of Ok AGN-211P Reactor ML20049J3711982-03-12012 March 1982 Forwards Incomplete Application for 20-yr Renewal of License R-53.Remaining Matls to Be Submitted in 2 Wks.Security Plan Withheld (Ref 10CFR2.790) ML20040H4831982-01-0404 January 1982 Responds to NRC 811207 Ltr Re Violations Noted in IE Insp Rept 50-112/81-01.Corrective Actions:Clarified Procedure Requiring All Exploratory Changes in Sys Be Reviewed by Reactor Safety Committee Prior to Evaluation ML20009C7261981-06-15015 June 1981 Submits Annual Rept for Jul 1980-June 1981 for License R-53 ML19332B2881980-09-0202 September 1980 Submits Annual Rept for Jul 1979-June 1980 ML19262B9141980-01-0808 January 1980 Notifies That Cw Terrell Has Been Director of Univ of Ok Reactor Since 780901 ML19259A7031979-01-0505 January 1979 Forwards Amended Copy of App a to Tech Specs.Major Amend Contains Request for Power Increase from 15 Watts to 100 Watts ML20064B8561978-10-0606 October 1978 Requests 20-year Extension/Renewal of NRC Lic R-53. Will Furnish Documentation by mid-Nov. 1978 1989-08-31
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20073B9901991-06-18018 June 1991 Forwards Rept Summarizing Findings of Orau Review of 59 Docket Files for Terminated Research & Test Reactors ML19327B1471989-10-12012 October 1989 Advises That Matls Containing Residual Radioactivity Transferred for Disposal Via Low Level Waste Sys ML20247B0711989-08-31031 August 1989 Responds to Violations Noted in Insp Rept 50-112/89-01 on 890525-26.Corrective Action:Training Program for Radiation Safety & Facility Emergency Procedures for Norman Fire Dept Being Initiated by Radiation Safety Ofc ML20235Z5661989-03-0909 March 1989 Forwards Addl Info Re Licensee Plan for Decommissioning,Per Request.Biographical Sketch of Author Included ML20205L2151988-10-25025 October 1988 Forwards Application for Amend to License R-53 to Approve Encl Physical Security Plan.W/O Encl ML20149L6531988-02-18018 February 1988 Advises That Licensee in Process of Transferring Fuel Back to DOE Possession,Per Telcon.Work Should Be Completed by End of May,Depending on Speed of Paper Work ML20148K3151988-01-21021 January 1988 Forwards Revised Security Plan in Response to D Carlson Request ML20236S2451987-11-19019 November 1987 Forwards Updated Tech Specs for Ou Agn 211-P Reactor Per Conversation W/Nrc.Requests That Facility Be Exempt from 10CFR50.54 (R) Since No Critical Operations Will Be Allowed & Exempt from Maintaining Requalification Program ML20237J5141987-07-20020 July 1987 Responds to Violation a Noted in Insp Rept 50-112/87-01. Updated Lab Survey Rept Showing LSC Efficiencies for H-3 & C-14 Encl Per Telcon W/Baer.Understands That Response to Violations B & C Acceptable ML20214W1981987-05-29029 May 1987 Responds to NRC Re Violations Noted in Insp Rept 50-112/87-01.Corrective Actions:Ltr from Norman Region Hosp Obtained & Sent w/ Which Indicates That Emergency Need Will Be Responded to ML20209D2621987-04-14014 April 1987 Responds to NRC Re Violations Noted in Insp Rept 50-112/87-01.Corrective Actions:Application for Mod of Tech Specs to Be Completed & Sent to NRC by 870901,including Request for Mod or Deletion of Emergency Plan ML20100B4081984-11-30030 November 1984 Informs That Emergency Plan Fully Implemented,Emergency Procedures Written & Approved & Training Program W/Fire & Police Personnel Initiated ML20093P2001984-07-24024 July 1984 Ack Receipt of Ltr Approving Emergency Plan.Plan Implementation Begun.Requests Extension for Completion Until 841130 ML20082M7781983-12-0101 December 1983 Submits List of Errors Noted During Review of NUREG-0996. Errors Do Not Affect Conclusions Reached in SER ML20072G6171983-06-20020 June 1983 Forwards Revised SAR Update & Review, & Tech Specs for 20-yr Renewal of License R-53 ML20077D1391983-06-17017 June 1983 Advises That Univ Operating Under Approved Rev to Reactor Operator Requalification Program,Per NRC ML20072N0481983-05-27027 May 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-112/83-01.Corrective Actions:Check of Flow Rate for Water Purification Sys Procedure Reviewed for Relevance & Implementation ML20071H7871983-05-16016 May 1983 Informs of C Jensen Appointment as Director of Facility ML20079M2451983-02-17017 February 1983 Advises That C Jensen Has Been Appointed as Interim Director of Univ Nuclear Reactor ML20071C2061983-02-14014 February 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-112/82-01.Corrective Actions:Copies of Reactor Safety Committee (RCS) New Charter Will Be Forwarded to Region Iv.Rcs Audit Function Redefined ML20079L4081983-02-14014 February 1983 Advises That All Future Correspondence Re License R-53 Should Be Directed to D Egle ML20064F8811983-01-0404 January 1983 Forwards Revised Operator Requalification Program,To Be Substituted for Mar 1982 Submittal ML20070N4241982-12-15015 December 1982 Forwards Procedures to Suppl Responding to Notice of Violation for IE Insp Rept 50-112/82-01 ML20070N4171982-12-10010 December 1982 Responds to NRC Re Violations Noted in IE Insp Rept 50-112/82-01.Corrective Actions:Change in Sprocket on Safety Rod Drive Will Be Treated as Unreviewed Safety Question & Requalification Program Will Be Revised ML20069M4301982-10-27027 October 1982 Submits Public Version of Status of Emergency Plan,Due 821103.Plan Submitted on 820420 Complies W/Requirements.No New Plan Need Be Developed or Submitted ML20067B5721982-10-11011 October 1982 Forwards Requalification Program for Univ of Ok,For Approval ML20051J8631982-05-0606 May 1982 Forwards Final Segment of SAR Required to Obtain Renewal of License R-53 ML20052D5851982-04-20020 April 1982 Forwards Public Version of Emergency Plan,In Support of 20-yr Renewal of License R-53 for AGN-211 P Reactor ML20042B8321982-03-28028 March 1982 Forwards Addl Info Re Application for 20-yr Renewal of License R-53 for AGN-211P Reactor ML20042C0581982-03-24024 March 1982 Forwards Eia Supporting Renewal of License R-53 ML20052G2631982-03-23023 March 1982 Forwards Requalification Program for Univ of Ok AGN-211P Reactor ML20049J3711982-03-12012 March 1982 Forwards Incomplete Application for 20-yr Renewal of License R-53.Remaining Matls to Be Submitted in 2 Wks.Security Plan Withheld (Ref 10CFR2.790) ML20040H4831982-01-0404 January 1982 Responds to NRC 811207 Ltr Re Violations Noted in IE Insp Rept 50-112/81-01.Corrective Actions:Clarified Procedure Requiring All Exploratory Changes in Sys Be Reviewed by Reactor Safety Committee Prior to Evaluation ML20009C7261981-06-15015 June 1981 Submits Annual Rept for Jul 1980-June 1981 for License R-53 ML19332B2881980-09-0202 September 1980 Submits Annual Rept for Jul 1979-June 1980 ML19262B9141980-01-0808 January 1980 Notifies That Cw Terrell Has Been Director of Univ of Ok Reactor Since 780901 ML19259A7031979-01-0505 January 1979 Forwards Amended Copy of App a to Tech Specs.Major Amend Contains Request for Power Increase from 15 Watts to 100 Watts ML20064B8561978-10-0606 October 1978 Requests 20-year Extension/Renewal of NRC Lic R-53. Will Furnish Documentation by mid-Nov. 1978 1991-06-18
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University ofOklalioma SCHOOL OF AEROSPACE, MECHANICAL AND NUCLEAR ENGINEERING CO 865 Asp Avenue Room 212 ,\ 43 Nonnan, Oklahoma 73019 F March 24, 1982 (405) 325-50?1 Qlf A3 4 4
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_! io g r2 Mr. James R. Miller dC 6',g' /
Chief Standardization and Special Projects Branch '
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s Division of Licensing 'h'%.
Nuclear Regulatory Conmission M i i 9. . v' Washington, DC 20555
Reference:
Docket 50-112 Subj ect: Resubmission of Renewal of License R-53
Dear Mr. .'4 iller:
We are enclosing additional material (Environmental Impact Analysis) required to obtain a twenty year renewal of Reactor License R-53 for the AGN-211-P operated by the University of Oklahoma. We are in the process of finishing the Emergency Plan which will follow in the next few days.
Very truly yours, 6 h/ /
C. W. Terrell Director University of Oklahoma Nuclear Reactor CWT /tdg Enclosure cc Dr. Davis Egle, Director AMNE Dr. D. G. Lindstrom, Chairman of Reactor Safety Commission ,
Dr. M. Jischke, Dean of College of Engineering Dr. A. Elbert, V.P. Administrative Affairs f0}O ,
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l i 8203300121 820324 PDR ADOCK 05000112 P PDR
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e ENVIRONMENTAL IMPACT APPRAISAL UNIVERSITY OF OKLAHOMA AGN-211P LICENSE R-53 DOCKET 50-112 3/24/82
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ENVIRONMENTAL IMPACT APPRAISAL (EIA)
I. INTRODUCTION This section discusses the environmental effects of the operatisn of the University of Oklahoma AGN-211P, swimming pool type reactor. The reactor was originally licensed in 1958 and began operation in 1959. The core consists of a rectangular parallelepiped made up of 12 fuel elements surrounded by a graphite reflector and positioned nece the bottom of an 800 gallon pool of distilled water. The reactor has operated at a maximum licensed power 15 watts. Total fuel consumption is slightly less than 1 mg of U-235 since 1959.
The reactor operates, on average, about two to four hours per week.
The reactor serves to apport the Nuclear Engineering Program which of fers the B.S., M.S., and Ph.D. degrees in Nuclear Engineering. Under-graduates examine and measure the characteristics of the reactor (neutron flux, temperature coefficient, excess reactivity, control rod worths, etc.),
graduate students and faculty use the facility for research consistent with the available thermal flux.
The license renewal requests authorization to raise the power from 15 watts to 100 watts and that a flux trap core configuration also be approved.
II. FACILITY The reactor was purchased from the Aerojet General Nucleonics Corporation in 1958 and was installed by Aerojet personnel. The reactor is housed on the first floor of the Nuclear Engineering Laboratory Building (NEL), an old brick building. The second floor houses part of the University's Personnel Department. Installation of the reactor in 1958 had no obvious impact on the environment or the inmmediate terrain. No pipelines, electrical or mechanical structures or any other form of device connects the reactor the the outside environment. The reactor needs no external cooling and emits no effluents, 1
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liquids or gas. The flux is too low to produce a measurable amount of Ar-41.
Any liquid or solid wastes from experiments are appropriately packaged and disposed of through the University's regular radioactive waste program.
At a power level of 100 watts the reactor will operate exactly the same as at 15 watts. No cooling will be required. A new gas monitor has been installed to sample the air directly over the surface of the pool for Ar-41.
Estimates made indicate that 'o Ar-41 will be measurable.
Finally, no changes in the beilding or the area immediately external to the building are required or are planned as a result of the increase to 100 watts.
l III. ENVIRONMENTAL EFFECTS FROM OPERATIONS Operation of the reactor at 15 watts in the past and at 100 watts in the l
future has no discernable impact on the environment. Radiation levels at the surface of the pool will not exceed 100 mr/hr. The reactor operator sits at a console about 15 feet from the center of the pool. At 100 watts the gamma-ray background is estimated to be.about 0.3 mr/hr at this position. All personnal in the reactor room are reguired to wear either a pocket ionization chamber (visitors, students) or a TLD (reactor staff). In 23 years of operation, no member of the staff has received a radiation dose which violates Federal Regulations. We note also that the neutron flux in water is too low to produce any trituim through neutron capture by deuterium in the water.
IV. ENVIRONMENTAL EFFECTS DUE TO ACCIDENTS We consider two potential events to be the most serious:
- a. A maniac shoots his way into the reactor room and throws a stick of dynamite into the pool. Such an event would damage the core but not necessarily release any significant amount of fission products since the fuel elements are unciad, sealed polyethylene encased U02 particles with a fission product inventory characteristic of 100 watts of power. The reactor room has a volume of about 60,000 cubic feet and a separate air handling unit. .We rely on physical security to avoid this incident.
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- b. The reactor is limited to an excess reactivity of 0.6% to ensure against a prompt period. Assuming, somehow, a percent or two could be introduced, the large negative temperature coefficient would terminate the power rise near 10kw. However, radiation levels in the room immediately above (on the 2nd floor) the reactor pool could exceed occupational levels. Therefore, the room is used as storage only and is required to be locked before reactor startup.
We, therefore, see no credible, serious, impact on the environment due to normal or abnormal operations of the reactor.
V. COSTS AND BENEFITS OF,THE FACULTY Several hundred thousand dollars has been invested in the reactor and the section of the building in which the reactor is housed over a period of years.
The entire reactor and associated nuclear labs have just undergone a major renovation. There are currently no plans to move or otherwise substantively revise the reactor facility.
The University considers the benefits of the reactor facility to be numerous. Our laboratory courses are very greatly aided by the reactor.
Research is underway which could not be done without a reactor. Increased flux levels (at 100 watts) will allow a further expansion of research.
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