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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20211Q4001999-09-0707 September 1999 Forwards Final Version of Nuclear Science Ctr TS Pending Official Approval from Nrc.Revised TS Simply Incorporates Changes That Were Proposed in Previous Ltrs with Exception of Minor Mod ML20209F0171999-07-0909 July 1999 Forwards Insp Rept 50-128/99-201 on 990608-10.No Safety or Noncompliance Concerns Identified.Various Aspects of Reactor Health Physics & Safeguards Programs Inspected ML20195J4391999-06-10010 June 1999 Forwards Initial Exam Rept 50-128/OL-99-01 Administered During Wk of 990405 to Employees of Facility Who Had Applied for License to Operate Texas A&M Univ Reactor ML20195J9881999-06-10010 June 1999 Forwards Results of Operator Initial Exam Conducted at Texas A&M Univ on 990405-06.Without Encl ML20205R2391999-04-14014 April 1999 Informs That DOE Was Unable to Fund Conversion of Tx A&M Univ Nuclear Science Center Reactor to Low Enrichment U Fuel in FY98 ML20202J6071999-02-0404 February 1999 Advises of Arrangements Made with a Sanchez for Administration of Operator Licensing Exam Wk of 990329. Forwards Ref Matl for RSO & RO Licensing Exam,Administration of Written Exam & Procedures for Administration of Exam ML20197H0921998-12-0808 December 1998 Forwards Insp Rept 50-128/97-201 on 971103-05 & 981102-05.No Significant Safety Issues Were Identified & No Reply Required ML20155A4221998-10-22022 October 1998 Forwards Comment on Rev to Nuclear Science Center Physical Security Plan Submitted by Ltr Dtd 980916.Use Guidance Provided in Reg Guide 5.59 to Address Development of Rev to Security Plan in Response to Comments ML20154L2231998-10-14014 October 1998 Forwards RO License Certificate for CM Lemons,Newly Licensed Individual at Texas A&M Univ ML20153C9791998-09-22022 September 1998 Forwards Copy of Results of Operator Initial Exam Conducted at Texas A&M Univ on 980914.Without Encl ML20154F5391998-09-22022 September 1998 Forwards Inital Exam Rept 50-128/OL-98-02 Administered During Week of 980914 to Employee of Facility Who Applied for License to Operate Texas A&M Univ Reactor ML20153B7501998-09-16016 September 1998 Informs That Nuclear Science Ctr Has Reviewed & Revised Physical Security Plan to Fully Implement NRC Comments & Recommendations,With Exception of One General Comment. Encl Withheld ML20237D6541998-08-20020 August 1998 Discusses Arrangements Made W/A Sanchez,For Administration of Operating Licensing Exams at Texas A&M Univ During Wk of 980914.Matl Furnished for Exam Administered in May 1998 Will Be Used ML20236Q3181998-07-0909 July 1998 Forwards Comments Re Rev to Nuclear Science Ctr Physical Security Plan.Comments Requested to Be Included in Rev to Plan ML20236N0041998-06-22022 June 1998 Forwards SRO Certificates to B Correll,P Pratt & J Stone. W/O Encls ML20249A6291998-06-12012 June 1998 Forwards Copy of Results of Operator Initial Exam Conducted at Texas A&M Univ on 980526-28.W/o Encl ML20249A6101998-06-12012 June 1998 Informs That During Week of 980525,NRC Administered Initial Exam to Employees of Facility Who Applied for License to Operate Texas A&M University Reactor ML20249A6081998-06-11011 June 1998 Forwards Request for Addl Info Re 980126 Application for Amend to Texas A&M Triga Research Reactor License Dealing W/Production of I-125 ML20217M7531998-03-30030 March 1998 Informs That DOE Will Be Unable to Fund Conversion of Texas A&M Univ Nuclear Science Ctr Reactor to Low Enrichment U Fuel in FY97,IAW 10CFR50.64 ML20217F1801998-03-24024 March 1998 Informs That Ltr Submitted W/Nuclear Science Reactor Physical Security Plan Failed to Mention That Changes to Plan Do Not Reduce Effectiveness of Plan & Plan Submitted IAW 10CFR50.90 ML20217Q0831998-03-0202 March 1998 Forwards Nuclear Science Ctr Physical Security Plan.Changes on Copy Designated by Black Vertical Lines in Right Margin. Encl Withheld ML20203J0521998-02-25025 February 1998 Informs That Data Contained in Pages 2,3 & 4 of License Amend Application Submitted by Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20202G2151998-02-0808 February 1998 Requests That Specific Parts of SE Accompanying 980126 Request for Amend to TS Be Withheld from Public Disclosure Per 10CFR9.17 & 10CFR2.790 ML20199J2841998-01-29029 January 1998 Transmits SRO License Certificate to Th Fisher.W/O Encl ML20199K5241998-01-29029 January 1998 Forwards Revised Ts,Including Minor Changes Made to Sections 3.5.2,6.6.1.f.1 & 6.6.2 ML20199D7801998-01-23023 January 1998 Forwards Revised Safeguard Contingency Plan for Nuclear Science Ctr at Tx A&M Univ,Per 10CFR50.54(p).Changes Do Not Reduce Effectiveness of Security Plan.W/O Encl ML20199C1941997-11-13013 November 1997 Forwards Senior Reactor Operator License Certificates to AB Caldwell & Bk Correll.W/O Encl ML20199B2141997-11-0303 November 1997 Confirms Arrangements Between W Eresian & a Sanchez for Administration of Operator Licensing Exam.Final Applications Certifying Training Must Be Completed & Submitted at Least 14 Days Before First Exam Date ML20211A7141997-09-17017 September 1997 Forwards Signed Amend 19 to Indemnity Agreement E-12 ML20216E9741997-09-0404 September 1997 Forwards Results of Operators Initial Exam Conducted at Facility on 970825-26.W/o Encl IR 05000128/19970011997-08-11011 August 1997 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-128/97-01 on 970317-21.Revised NOV Re Violation E,Concerning Failure to Survey Encl ML20149F3461997-07-15015 July 1997 Forwards Amend 19 to Indemnity Agreement E12,amend 14 to License R-83 & Se.Amend Modifies License Conditions to Allow Greater Flexibility in Possession & Storage of Radioactive Matls Used to Support Research & Development within Site ML20141C6271997-06-16016 June 1997 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-128/97-01 on 970317-21.Corrective Actions:Requalification Program Implementation Responsibility Has Been Assigned to Individual Designated as Reactor Administrative Assistant ML20140D2811997-06-0404 June 1997 Informs of Arrangements Made for Administration of Operator Licensing Exams for Wk of 970825.Ref Matls for Exam,Facility Review of Written Exams,Administration of Written Exams & Procedures for Administration of Written Exams Encl ML20148F1151997-05-29029 May 1997 Forwards Insp Rept 50-128/97-01 on 970317-21 & Notice of Violation.Nrc Will Use Facility Response to Determine Whether Further Enforcement Action Will Be Needed.Mgt Meeting W/Nrc Scheduled for 970619 to Discuss Insp Findings ML20138C8741997-04-25025 April 1997 Informs That DOE Will Be Unable to Fund Conversion of Texas A&M Univ Nuclear Science Ctr Reactor to Low Enrichment U Fuel in FY97 ML20137Y0301997-04-16016 April 1997 Forwards Rev 4 to Nuclear Science Center Senior Reactor Operator & Reactor Operator Requalification Program ML20137T9251997-04-11011 April 1997 Forwards Reactor Operator License Certificate to Dj Beckel, Newly Licensed Individual at Texas Engineering Experiment Station Reactor.W/O Encl ML20137L3321997-04-0303 April 1997 Forwards Retaken Exam Rept 50-128/OL-97-01 on 970324.Exam Administered to Employee,To Operated Texas A&M Triga Reactor ML20137R4221997-04-0303 April 1997 Forwards Results of Operator Initial Exam Conducted at Facility on 970324.W/o Encl ML20137C9001997-03-19019 March 1997 Forwards Reactor Operator License Exam,Category B,To Be Administered to D Beckel on 970324.Pre-exam & post-exam Security Agreement Also Encl for Signature & to Be Returned W/Exam Matls ML20135D5391997-02-25025 February 1997 Requests That Indemnity Agreement E-12 Be Changed as Listed ML20147E2351997-02-13013 February 1997 Forwards Reactor Operator License Certificates to Listed Individuals.W/O Encl ML20135E9411996-12-0909 December 1996 Forwards Initial Exam Rept 50-128/OL-96-02 Administered to Employees Who Had Applied for License to Operate Texas A&M Reactor During Wk of 961118 ML20135D8671996-12-0606 December 1996 Forwards Results of Operator Initial Exam Conducted on 961119-21.W/o Encl ML20135E1591996-12-0505 December 1996 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp of License R-83 ML20134M7061996-11-21021 November 1996 Forwards Request for Addl Info,In Order to Complete Review of 960715 Application to Increase Power Level of Texas A&M Univ Sys Nuclear Science Center Reactor Up to 1,500 Kilowatts ML20134L6851996-11-18018 November 1996 Forwards Certificates to Two Newly Licensed Individuals at Texas A&M University System.W/O Encls ML20129A8591996-10-17017 October 1996 Informs NRC of Reportable Occurrence Re Violation of Tech Specs LCO on 961015.Automatic Ventilation Sys Shutdown Bypassed During Air Monitor Check Prior to Reactor Startup ML20129F0981996-09-27027 September 1996 Informs of Arrangements Made W/B Asher for Administration of Operator Licensing Exam During Wk of 961118 1999-09-07
[Table view] Category:EDUCATIONAL INSTITUTION TO NRC
MONTHYEARML20058L5081990-07-24024 July 1990 Forwards Kr Hall Re Availability of Funds for Any Future Decommissioning of Nuclear Science Ctr Reactor, Per 10CFR50.33(k),for Filing ML20058L5161990-07-0909 July 1990 Advises That Request Will Be Made to State of Tx Legislature for Appropriation of Funds for Decommissioning & Decontamination of Nuclear Science Ctr Reactor After Future Decision for Final Shut Down Made ML20043E2581990-06-0404 June 1990 Forwards Proposed Change to Reactor Operator & Senior Reactor Operator Requalification Program.Proposed Change Makes Written Exams Administered to Operators on Physical Security Plan Part of Operator Requalification Program ML20043B1521990-05-11011 May 1990 Responds to Violations Noted in Insp Rept 50-128/90-01 on 900221-23.Corrective Actions:Program for Review of Users License Established & Responsibility for Radiation Protection Program Transferred to Licensee ML20012C5491990-03-0909 March 1990 Responds to Violation Noted in Insp Rept 50-128/90-01 on 900110-12.Corrective Actions:Emergency Preparedness & Physical Security Designated as Next Scheduled Operator Requalification Program Topic for Lecture ML20012A0671990-02-28028 February 1990 Advises That Federal Govt Funding Not Available for Conversion of Nuclear Science Ctr Triga Reactor from High Enriched U to Low Enriched U Fuel During FY90.Reactor Does Not Have Further Plans for Conversion in 1990 ML19327B2891989-10-24024 October 1989 Requests That Licensee on License R-83 Be Officially Designated as Texas Engineering Experiment Station,Texas A&M Univ Sys,Per 890904 License Amend Request ML19325C8391989-10-13013 October 1989 Forwards 801020 Ltr Documenting Change of Licensee for Nuclear Science Ctr Reactor,Agreement Ltr Re Occupational Safety Advice & Revised Tech Spec Page 46 ML20247F9171989-09-0808 September 1989 Forwards Addl Info Re Nuclear Science Ctr Reactor Organizational Structure.New Organizational Structure Will Improve Communications,Streamline Mgt Functions & Establish Responsive Radiation Protection Program ML20151V9311988-08-10010 August 1988 Requests Extension to 880901 Be Granted for Response Deadline to 880713 Notice of Violation & Proposed Imposition of Civil Penalty.Addl Time Needed to Obtain Final Approval & Signitures of Individuals Presently on Vacation ML20151Y8821988-07-28028 July 1988 Responds to Notice of Violation & Proposed Imposition of Civil Penalty on 880713 in Amount of $5,000.Corrective Actions:Dosimeters Issued to Current NSC Employees Reviewed & Updated ML20151H5171988-07-21021 July 1988 Forwards Payment in Amount of $5,000 for 880713 Order Imposing Civil Monetary Penalty ML20155C9201988-06-0707 June 1988 Forwards Minutes of Reactor Safety Board Subcommitee for Review of Nuclear Science Ctr Experiment & Radiological Control 880530 Meeting ML20155A7511988-05-10010 May 1988 Forwards Summary of Rsb Subcommittee for Review of NSC Experiments & Radiological Control 880520 Meeting ML20196F0231988-02-23023 February 1988 Submits Info to Correct Addressed to Berkow Re Change in Adminstration of Nuclear Science Ctr Reactor. Effective Date for Change Is 880201 ML20149H0451988-02-0808 February 1988 Submits Change to Facility Emergency Preparedness Plan.Ref in Plan to Support Agreement W/St Joseph Hosp,Bryan,Tx to Be Replaced W/Support Agreement W/Humana Hosp,College Station, Tx ML20214D9111987-05-12012 May 1987 Responds to 870428 Request for Addl Info Re 861218 Violation on Irradiation of Bromophenanthrene.Bromine Sample Handling Procedures Have Been Modified.Minutes of Staff Meeting 374 Encl ML20214H1381987-05-12012 May 1987 Requests That Recipient Advise Appropriate Ofcs & Region IV of Request That Correspondence Re Nuclear Science Ctr Reactor Be Distributed as Listed.Fe Vandiver Removed from Distribution List Re Reactor ML20206G5991987-04-0808 April 1987 Responds to NRC Re Violations Noted in Insp Rept 50-128/87-01.Corrective Actions:New Handling Procedures Will Be Developed for Process of bromo-phenanthrene & Addition to SOPs Re Isotopic Max Curie Content Values Under Evaluation ML20205R0011987-03-30030 March 1987 Forwards Twenty-Third Progress Rept of Texas A&M Univ, Nuclear Science Ctr for 1986, Per Tech Spec 6.6.1 Reporting Requirements ML20212C4731987-02-24024 February 1987 Requests Mod to Approved Emergency Preparedness Plan to Permit Nuclear Science Ctr & Offsite Support Agencies to Enter Into Emergency Support Agreements Having Annual, Multiple Year or Open Renewal ML20210K9671987-01-28028 January 1987 Responds to 870122 & 23 Telcons Re Documented Evaluations of Irradiations of Bromo-Phenanthrene (Powder Form) for Production of Br-82 Against Tech Spec 3.6.3 for Accidental Release of Generated Bromine Gas During Irradiation ML20209B3671987-01-27027 January 1987 Notifies That No Federal Funds Available for Conversion of Plant from Use of Highly Enriched U to Low Enriched U Fuel During FY87,per 10CFR50.64.RE Stephens Stating That DOE Funds Unavailable Encl ML20212Q9761987-01-19019 January 1987 Remits Payment in Response to 870112 Order Imposing Civil Monetary Penalty in Amount of $833 ML20214P5871986-09-18018 September 1986 Submits Position in Support of Request for Removal of $1,250 Civil Penalty Proposed on 860722 for Violations Re 860310 & 0501 Incidents Concerning Experiment Handling.Violations Should Be Classified as Severity Level V,Not III ML20214P5801986-09-18018 September 1986 Responds to NRC 860722 Notice of Violation & Proposed Imposition of Civil Penalty.Corrective Actions:Training Provided on Experiment Handling & Reactivity Measurements. Reevaluation of Violation Re 860310 & 0501 Events Requested ML20205E0111986-08-11011 August 1986 Responds to NRC 860722 Notice of Violation & Proposed Imposition of Civil Penalty from Insp Rept 50-128/86-01. Extension of Response Until 860922 Requested ML20138L8971985-10-22022 October 1985 Requests That Univ President & Nuclear Engineering Dept Head Be Included in Distribution List.Author Should Also Be Included in Future Correspondence ML20117J4501985-05-0606 May 1985 Discusses Need for Progress in Area of Evacuation Time Estimate Studies Re Current Technology & Idynev.Proposal for Development of NRC Capability Re Idynev Provided ML20100L8271985-04-10010 April 1985 Notifies That Wa Porter Replaced by Hh Richardson as Interim Director of Texas Engineering Experimental Station.Address Correction Provided ML20113C6011985-03-25025 March 1985 Forwards 21st Progress Rept of Texas A&M Univ Nuclear Science Ctr,1984 ML20134N8911985-02-14014 February 1985 Informs That First Name of Hh Richardson,Director of Univ of Texas Engineering Experiment Station,Misspelled in ML20113D5021985-01-28028 January 1985 Informs of 841231 Resignation of Wa Porter as Director of Facility & Appointment of Hh Richardson as Director & Licensee,Effective 841231 ML20092P6501984-03-27027 March 1984 Forwards Twentieth Progress Rept of Texas A&M Univ Nuclear Science Ctr,1983, Per Tech Spec 6.6.1 Reporting Requirements ML20080B9981984-01-30030 January 1984 Advises That Requirements of Category III Physical Security Met Following Shipment & Transfer of 1,106 G U-235,in Form of Triga Flip Elements,To Idaho Falls,Id.Shipment Completed in Aug 1983 ML20082S9841983-10-28028 October 1983 Memorializes 831027 Telcon Re 1-day Extension for Final Rept of RO on 831006.Final Rept Will Be Mailed on 831028 ML20078P0061983-10-28028 October 1983 Forwards Final Rept of RO on 831004 Re Possible Operation in Excess of Licensed Power Level ML20078N9941983-10-28028 October 1983 Forwards Final Rept of RO on 831004 Re Possible Operation in Excess of Licensed Power Level ML20086P8621983-10-17017 October 1983 Confirms 831013 Telcon Requesting That Due Date of Final Rept Re 831006 Occurrence Be Extended to 831027 ML20077C7211983-07-22022 July 1983 Describes Procedure Change for Shipment of Irradiated Triga Fuel from Facility to Anl/West.Responsibility for Fuel & Inventory Transfer Will Occur When Fuel Is in Cask & Cask Is Ready for Closure ML20077D3811983-07-20020 July 1983 Advises of Scheduled Transfer of Irradiated Triga Fuel to Anl West Triga Facility in Idaho Falls,Id During Wk of 830822.Description of Fuel Loading for Each Shipping Package Submitted ML20080B6541983-07-14014 July 1983 Advises That Irradiated Reactor Fuel Will Be Transported to Anl in Two GE-T2 F Casks ML20024D9771983-06-21021 June 1983 Forwards Public Version of Summary Evaluation of Evacuation Time Estimates.Adverse Weather Conditions (Rain) Should Be Considered for Summer Scenario ML20023D9741983-05-30030 May 1983 Forwards Revised Page 29 of Tech Specs Correcting Error in Item 3.8 Re Primary Coolant Conditions ML20076E7741983-05-0909 May 1983 Requests Copy of Region IV Organization Chart ML20023B6491983-04-29029 April 1983 Forwards Completion & Results of Phase I of Nscr Post-Damage Pulse Test Program for Full Flip Triga Core. ML20076E9431983-04-29029 April 1983 Forwards Completion & Results of Phase I of Nuclear Science Ctr Reactor Post-Damage Pulse Test Program for Full Flip Triga Core. Pulse Test Planned at Phase I Level to Study Fuel Characteristics ML20023B9051983-04-12012 April 1983 Responds to NRC 830316 Ltr Re Violations Noted in IE Insp Rept 50-128/82-03.Corrective Actions:Training Sessions Conducted for Reactor Operations Personnel to Demonstrate Proper Preparation of Ice Bath ML20071E4001983-03-0808 March 1983 Informs That DE Feltz Has Accepted Position of Director of Nuclear Science Ctr ML20064M2311983-02-0404 February 1983 Forwards Nuclear Science Ctr Reactor Post-Damage Pulse Test for Full Flip Triga Core, for Review.Plan Approved W/Minor Changes by Reactor Safety Board on 830128 1990-07-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20211Q4001999-09-0707 September 1999 Forwards Final Version of Nuclear Science Ctr TS Pending Official Approval from Nrc.Revised TS Simply Incorporates Changes That Were Proposed in Previous Ltrs with Exception of Minor Mod ML20205R2391999-04-14014 April 1999 Informs That DOE Was Unable to Fund Conversion of Tx A&M Univ Nuclear Science Center Reactor to Low Enrichment U Fuel in FY98 ML20153B7501998-09-16016 September 1998 Informs That Nuclear Science Ctr Has Reviewed & Revised Physical Security Plan to Fully Implement NRC Comments & Recommendations,With Exception of One General Comment. Encl Withheld ML20217M7531998-03-30030 March 1998 Informs That DOE Will Be Unable to Fund Conversion of Texas A&M Univ Nuclear Science Ctr Reactor to Low Enrichment U Fuel in FY97,IAW 10CFR50.64 ML20217F1801998-03-24024 March 1998 Informs That Ltr Submitted W/Nuclear Science Reactor Physical Security Plan Failed to Mention That Changes to Plan Do Not Reduce Effectiveness of Plan & Plan Submitted IAW 10CFR50.90 ML20217Q0831998-03-0202 March 1998 Forwards Nuclear Science Ctr Physical Security Plan.Changes on Copy Designated by Black Vertical Lines in Right Margin. Encl Withheld ML20202G2151998-02-0808 February 1998 Requests That Specific Parts of SE Accompanying 980126 Request for Amend to TS Be Withheld from Public Disclosure Per 10CFR9.17 & 10CFR2.790 ML20199K5241998-01-29029 January 1998 Forwards Revised Ts,Including Minor Changes Made to Sections 3.5.2,6.6.1.f.1 & 6.6.2 ML20199D7801998-01-23023 January 1998 Forwards Revised Safeguard Contingency Plan for Nuclear Science Ctr at Tx A&M Univ,Per 10CFR50.54(p).Changes Do Not Reduce Effectiveness of Security Plan.W/O Encl ML20211A7141997-09-17017 September 1997 Forwards Signed Amend 19 to Indemnity Agreement E-12 ML20141C6271997-06-16016 June 1997 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-128/97-01 on 970317-21.Corrective Actions:Requalification Program Implementation Responsibility Has Been Assigned to Individual Designated as Reactor Administrative Assistant ML20138C8741997-04-25025 April 1997 Informs That DOE Will Be Unable to Fund Conversion of Texas A&M Univ Nuclear Science Ctr Reactor to Low Enrichment U Fuel in FY97 ML20137Y0301997-04-16016 April 1997 Forwards Rev 4 to Nuclear Science Center Senior Reactor Operator & Reactor Operator Requalification Program ML20135D5391997-02-25025 February 1997 Requests That Indemnity Agreement E-12 Be Changed as Listed ML20129A8591996-10-17017 October 1996 Informs NRC of Reportable Occurrence Re Violation of Tech Specs LCO on 961015.Automatic Ventilation Sys Shutdown Bypassed During Air Monitor Check Prior to Reactor Startup ML20115D0351996-07-0808 July 1996 Informs NRC That Name of Level 1 Licensee for Tx A&M Univ Sys/Tx Engineering Experiment Station Nuclear Science Ctr, Now Bd Russell,Effective 960701 ML20101N0281996-04-0303 April 1996 Informs That DOE Unable to Fund Conversion of Licensee Reactor to LEU Fuel in FY96,in Accordance w/10CFR50.64, Limitations on Use of HEU in Domestic Non-Power Reactors ML20093C2371995-10-0606 October 1995 Forwards Rev to Emergency Preparedness Plan for Nuclear Science Ctr Tx A&M Univ Sys. Change Increases Required Time for Emergency Class Event from Minutes to Hours ML20087G3531995-03-20020 March 1995 Informs That Nuclear Science Ctr Has Completed Preliminary Amend to SAR to Include Conversion to LEU Fuel ML20081F4871995-03-10010 March 1995 Advises That Nuclear Science Ctr Has Revised Safeguards Contingency Plan.Plan Withheld ML20078F5131995-01-13013 January 1995 Confirms 950113 Telcon Re Interpretation of Licensee FOL R-83,section (B(3)) Re Use of Byproduct Matl at Facility ML20078E1301994-11-0404 November 1994 Forwards Safeguards Contingency Plan,Per 10CFR50.54(p). Revised Plan Provides Better Agreement Between Working Plan & Regulations Requiring Plan.Encl Withheld ML20024J3741994-10-0707 October 1994 Forwards Rev of Emergency Preparedness Plan for Nuclear Science Ctr Tx A&M Univ Sys. Plan Rewritten to Correct Weakness Identified by Previous NRC Insp at Facility (NRC Insp Rept 50-128/93-01) & Changes Desired by Licensee ML20071L4851994-07-27027 July 1994 Responds to NRC Re Violation Noted in Insp Rept 50-128/94-01.Corrective Action:Audit Program Has Been Expanded Under Mop to Include Reactor Operations Records & Experimental Facilities/Experiments/Records ML20069A4231994-05-0606 May 1994 Advises of Issuance of Grant to Perform Core & Safety Analysis Covering Conversion of Nuclear Science Ctr Reactor to Low Enrichment U Fuel.Amend to SAR Will Be Submitted by 941231 ML20044D0221993-05-0707 May 1993 Responds to Emergency Planning Program Weaknesses Noted in Insp Rept 50-128/93-01.Corrective Actions:Addl Changes Made to Emergency Plan to Ensure Info Consistent W/Actual Events at Time of Declaration of Emergency Class ML20045H0321993-03-25025 March 1993 Forwards Proposed Amend 13 to License R-83,allowing Greater Flexibility Re Possession of Radioactive Matls for Supporting Research & Development Functions.Justification for Requested Amend Encl Also ML20126B2301992-12-0707 December 1992 Responds to Violations Noted in Insp Rept 50-128/92-02. Corrective Actions:Mgt Overview Program Database Created for Tracing Biennial,Annual & Semiannual Routes to Ensure Timely Completion & Limited Access Badge Documentation Upgraded ML20137Z0521992-10-23023 October 1992 Informs That Licensee Continues to Review Licensing Jurisdiction Situation W/Re to Radioactive Matl Used in & Around Texas A&M Univ Nuclear Science Ctr in College Station,Tx ML20115G6331992-08-28028 August 1992 Reviews Written Exam Administered at Faclity on 920824 & Found No Questions Causing Applicants Problems ML20096B9201992-04-27027 April 1992 Responds to NRC Re Violations Noted in Insp Rept 50-128/92-01.Corrective Actions:Amend to State of Tx License Requested ML20091R2031992-01-22022 January 1992 Comments on Listed Questions Re Operator Licensing Exam ML20070G8841991-03-0606 March 1991 Notifies That Federal Govt Funding Not Available for Conversion of NSCR from Use of HEU Fuel to LEU Fuel,Per 10CFR50-64,c,(2)(ii).Will Notify Commission by 920327 If Funds Have Been Made Available in FY92 for Conversion ML20058L5081990-07-24024 July 1990 Forwards Kr Hall Re Availability of Funds for Any Future Decommissioning of Nuclear Science Ctr Reactor, Per 10CFR50.33(k),for Filing ML20058L5161990-07-0909 July 1990 Advises That Request Will Be Made to State of Tx Legislature for Appropriation of Funds for Decommissioning & Decontamination of Nuclear Science Ctr Reactor After Future Decision for Final Shut Down Made ML20043E2581990-06-0404 June 1990 Forwards Proposed Change to Reactor Operator & Senior Reactor Operator Requalification Program.Proposed Change Makes Written Exams Administered to Operators on Physical Security Plan Part of Operator Requalification Program ML20043B1521990-05-11011 May 1990 Responds to Violations Noted in Insp Rept 50-128/90-01 on 900221-23.Corrective Actions:Program for Review of Users License Established & Responsibility for Radiation Protection Program Transferred to Licensee ML20012C5491990-03-0909 March 1990 Responds to Violation Noted in Insp Rept 50-128/90-01 on 900110-12.Corrective Actions:Emergency Preparedness & Physical Security Designated as Next Scheduled Operator Requalification Program Topic for Lecture ML20012A0671990-02-28028 February 1990 Advises That Federal Govt Funding Not Available for Conversion of Nuclear Science Ctr Triga Reactor from High Enriched U to Low Enriched U Fuel During FY90.Reactor Does Not Have Further Plans for Conversion in 1990 ML19327B2891989-10-24024 October 1989 Requests That Licensee on License R-83 Be Officially Designated as Texas Engineering Experiment Station,Texas A&M Univ Sys,Per 890904 License Amend Request ML19325C8391989-10-13013 October 1989 Forwards 801020 Ltr Documenting Change of Licensee for Nuclear Science Ctr Reactor,Agreement Ltr Re Occupational Safety Advice & Revised Tech Spec Page 46 ML20247F9171989-09-0808 September 1989 Forwards Addl Info Re Nuclear Science Ctr Reactor Organizational Structure.New Organizational Structure Will Improve Communications,Streamline Mgt Functions & Establish Responsive Radiation Protection Program ML20151V9311988-08-10010 August 1988 Requests Extension to 880901 Be Granted for Response Deadline to 880713 Notice of Violation & Proposed Imposition of Civil Penalty.Addl Time Needed to Obtain Final Approval & Signitures of Individuals Presently on Vacation ML20151Y8821988-07-28028 July 1988 Responds to Notice of Violation & Proposed Imposition of Civil Penalty on 880713 in Amount of $5,000.Corrective Actions:Dosimeters Issued to Current NSC Employees Reviewed & Updated ML20151H5171988-07-21021 July 1988 Forwards Payment in Amount of $5,000 for 880713 Order Imposing Civil Monetary Penalty ML20155C9201988-06-0707 June 1988 Forwards Minutes of Reactor Safety Board Subcommitee for Review of Nuclear Science Ctr Experiment & Radiological Control 880530 Meeting ML20155A7511988-05-10010 May 1988 Forwards Summary of Rsb Subcommittee for Review of NSC Experiments & Radiological Control 880520 Meeting ML20151U7551988-03-31031 March 1988 Forwards ORO-4207-20, Twenty-Fourth Progress Rept of Texas A&M Univ Nuclear Science Ctr,1987, Per Tech Spec 6.6.1 ML20196F0231988-02-23023 February 1988 Submits Info to Correct Addressed to Berkow Re Change in Adminstration of Nuclear Science Ctr Reactor. Effective Date for Change Is 880201 ML20149H0451988-02-0808 February 1988 Submits Change to Facility Emergency Preparedness Plan.Ref in Plan to Support Agreement W/St Joseph Hosp,Bryan,Tx to Be Replaced W/Support Agreement W/Humana Hosp,College Station, Tx 1999-09-07
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Texas A&M University College Station, Texas 77843 713/845 1811 Office of University Research 6 February 1979 Director of Iluclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Ref: Docket Number 50-128 License R-83 Dear Sir-It is proposed to make a change to the Technical Specifications for the Nuclear Science Center Reactor (NSCR) of Texas A6M University. The September 1978 inspection of the NSCR by Region IV of the Office of Inspection and Enforce-ment resulted in a request that radiography of explosive material in excess of the limits specified in the Technical Specifications of 3.6.c be terminated until further review by the Commission. At the time of the inspection, explosives had been radiographed in a neutron radiography facility that was constructed external to the reactor pool. By NRC letter dated June 23, 1971 radiography of explosives in research and testing reactor facilities is considered an unreviewed safety question. This letter was discussed over the phone with your personnel and it was their conclusion that a change to the Technical Specifications was not necessary for radiography of explosives in an experimental facility external to the reactor pool structure. Since this view is no longer held we are submitting this request for a change. The proposed change and safety evaluation which is attached has been reviewed and approved by our Reactor Safety Board. For your information we have enclosed a copy of the approved SOP's governing use of the neutron radiography facility.
Since the inspection by I & E we have lost income by having to turn away radiography business. Since income is critical to us we request that this a mendmen t receive prompt review. Your cooperation and assistance in con-sidering this Technical Specification change is sincerely appreciated.
Very truly yours, c
Q(( \=: n--~
Robert R. Berg, Chairman Reactor Safety Board Texas AEM University
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Enclosures : Safety Analysis for Amendment No. 7 to License R-83 S0P IV-F Neutron Radiography Beam Port No. 4 CC: Dr. John D. Randall, Director, NSC T Mr. Harry E. Whitmore, Associate Director, TEES Yl 3 7902136/76
\
Texas Af,M University Nuclear Science Center Safety Analysis for Amendment No. 7 to License R-83 February , 1979 College Station, Texas
Introluction It is proposed to modify the Technical Specifications to Facility License No. R-83 to permit the radiography of up to five pounds of explosive uaterials in a radiography f acility associated with the Nuclear Science Center ^:wtor.
Specification Change It is proposed that Section J. o . c r'd as follow?
3.6 Limitations on Experiments
- c. Explosive raterials in quantities greater than 5 pounds shall not be allowed within the reactor building. Irradiation of explosive materials shall be restricted as follows:
(1) Explosive materials in quantities greater than 25 milli-grama shall not be irradiated in the reactor pool. Ex-plosive materials in quantities less than 25 milli-grams may be irradiated provided the pressure produced upon detonation of the explosive has been c21culated and/
or experimentally demonstrated to be less than the design pressure of the container.
(2) Explosive caterials in quantities greater than 25 milli-grams shall be restricted from the upper research level, demineralizer room, cooling equipment room and the interior of the pool containment structure.
(3) Explosive materials in quantities greater than 5 pounds shall not be irradiated in experimental facilities.
(4) Cumulative exposures for explosive materials in quantities greater than 25 milligrams shall not exceed 10 12 n/cm 2 fgp neutrons or 25 roentgen for gamma exposures.
bases C. This specification is intended to prevent damage to the reactor or reactor safety systems resulting from failure of an experiment involving explosive naterials.
- 1. This specification is intended to prevent damage to the reactor core and safety related reactor components located within the reactor pool in the event of failure of an experiment involving the irradiation of explosive materials. Limited quantities of less than 25 milligrams and proper containment of such experiments provide the required safety for in pool irradiation.
- 2. This specification is intended to prevent damage to vital equip-ment by restricting the quantity and location of explosive materials within the reactor building. Explosives in quantitiec exceeding 25 milligrams are restricted from areas containing the reactor bridge, reactor console, pool water coolant and purification systems and reactor safety related equipment.
(1)
- 3. The f ailure of an experiment involving the irradiation of up to S lbs of explosive material in an experimental facility located external to the reactcr pool structure will not result in damage to the r eactor or the reactor pool containment structure.
- 4. This specification is intended to prevent any increase in the sensitivity of explosive materials due to radiation damage during exposures .
Safety Analysis The proposed changes to Specification 3.6.c are intended to provide for the radiography of explosive materials within the beam port 4 facility. Located en the north side of the lower research level, the facility consicts of a concrete block structure installed adjacent to the pool shield wall to contain and shield a thermal neutron L ar extracted from beam port 4 (see figure 1).
The cave structure is designed for remote positioning of samples with the beam port in operation. A hydraulic operated shield door is raised to shield the neutron beam during ;oading of a sample, then lowered for the exposure. Since the specification restricts explosive materials from areas where the reactor safety systems would be endangered, the most serious accident involves the detonation of a charge while it is being radiographed. The beam port is exposed at this time and its rupture could result in loss of pool water. The analysis will therefore center on predicting the pressure developed on the weakest part of the beam port.
Emperical studies are available concerning the prediction of peak pressures within a vented or unvented structure. 1,2 The quantities involved in this calculation are the ratio of the amount of explosive (W, in pounds equivalent TNT) to the volume of the containment structure (V, in ft 3) and the vent area through which the pressure may be released. For a more conservative analysis the vent area wi]i be assumed to be zero, i.e.,
the entire blast is contained within the radiograph, facility. This ignores two open door ways with a combined surface area of 2' Jt*. The quantity of explosive will be considered to be the maximum of 5 pounds allowed in the facility. For a containment volume of 270 ft (see 3 figure 1),
W 5 lb 7= 270 ft' '
3 From figure 2 the peak pressure (Pqg) is 100 psi. Using the conservative assumption that this maximum pressure will be transmitted through shields and collimators, the force exerted upon the end of the beam port is, 100 psi x A BP
= 2000 lb g.
(A BP
=
the cross sectional area of the beam port).
(2)
The rupture strength of the beam port is determined by the fillet weld between the beam tube and end plate (see figure 3). The area of the shear plane is, A = ni (D - t )
where, t = weld thickness = .25 in d = t ube 0. D . = 6. 7 5 in A = n (0.25) (6.75 - .25)
= 5.1 in 2 Gince the yield strength is 20,000 pai for 6061 alwalnum, RS = 5.1 (20,000) = 100,000 lb Applying a safety factor of 4, RS = 100,000 = 25,000 lb f
4 A comparison of the peak blast pressure developed 2500 lbg , with the rupture strength of the beam port extensicn, 25,000 lb reveals a wide margin of safety. Inaddition,theentireanalysishasbe,enbasedonsomevery conservative assumptions;
- 1. 27 square feet of vent areas were ignored.
T. Collimators and shielding present which would serve to dampen the blast were ignored.
- 3. A maximum of 5 pounds of explosive naterials within the facility was considered. Nornal quantities will be substantially less than this limit.
- 4. A safety tactor of 4 was used in calculating the rupture strength of the beam port extension.
In conclusion, the analysis indicates there will not be a rupture of the beam port for detonation of a 5 pound explosive charge during radiography.
liawever, should a rupture occur there is no unreviewed safety question presented, since the analysis for the loss of pool water has already been performed in Amendment II to the Safety Analysis Report. Thus, radiography of explosive materials within the specifications set fcrth presents no danger to the general public.
References
- 1. Kingery , C . M. , Schumacher , R. N . , and Ewing, W. O. , Jr . (1975), "In-ternal Pressures from Explosions in Suppressive Structures", BRL Interim Memorandum Report No. 403, Aberdeen Proving Ground, Maryland, June 1975.
(3)
- 2. Sewell, R. G. S. and Kinney G. I' . (1974), " Internal Explosions in Vented and Unvented Char.bers", Minutes of 14th Explosives Safety Seminar.
h.;w Orleans, 8-10 Nover.ber 1973, Department of "efense Explosives Safety Board, pp. 87-98.
- 3. Biker, W. E., (1978), " Inter nal Blast Loading", A Short Course on Explosion llazards Evaluation, Southwest Research Institute, pp. 3-16 to 3-34.
(4)
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NSCR NEUTRON RADIOGRAPHY BEAM PORT EXTENSION
yg*o Form 112 Nuclear Science Center 1-73 STANDARD OPERATING PROCEDURES Prepared by Subject Section Page J PT Neutron Radiography Beam Fort No. 4 IV-F 1
- 1. Ceneral This procedure pertains to the use of the neutron radiography facility including the beam port #4 area, darkroom and laboratory #3.
- 2. Description of Neutron Radiography Facility The facility is located on the lower research level as shown in Figure IV-F-1. A concrete block structure is located adjacent to the pool shield wall to con;ain and shield a thermal neutron beam extracted from beam port No. 4 (see figure IV-F-2).
The cave structure is designed for remote positioning of camples with the beam port in operation. A hydraulic chutter at the beam port exit may be raised to shield the neutron beam between exposures. bab 3 and the cark room are located on the lower research level and are insediately accessible from the sample loading area.
The darkroom is available for loading and unloading cassettes and film processing caly. Laboratory 3 is designated as a sample storage area where cabinets are available for the safe storage of samples for neutron radiography.
- 3. Personnel Control Personnel control for the radiography facility is maintained via "C-2" entry devices which alarm in the reactor control room upon entry and provide a flashing red light signal visible to the person entering.
- a. The following areas, shown in Figure (IV-F-1), are controlled by the "C-2" entry devices. The " Inner / Outer" switch on the Reactor Console switches between the inner and outer control areas so that one of these circuits is always active. The "C-2" and scram circuit switch on the shield door is always active.
(1) Inner Controlled Area The sample preparation room is designated as the inner control area.
The "C-2" device controlling this area is locateu on the' access door.
This circuit is normally deactivated during beam port operation.
(2) Outer Control Area The outer control area includes the entire lower research level. The "C-2" devices are located on the down ramp door and the stairwell door.
This circuit is normally activated only during beam port operation.
(3) Radiography Cave The "C-2" entry device on the cave entry door is designed to cause a scram if the reactor is near the radiography reflector and the door is opened. The bridge rail stop, which restricts moving the reactor any closer than 18 inches from the reflector, must be in place for reactor operation when the cave entry door is open. The keys to the bridge rail stop and the cave entry door are to be kept on a single key ring and personnel entering the cave will maintain possession of the key ring while in the cave.
- b. The keys to the Radiography Facility will be issued by the SR0 only.
- c. When leaving the radiography facility, the experimenter will lock the door and return the keys to the SRO. If the experimenter has any special instructions concerning his experiment , he will relay this information to the SRO at this time.
Approved: ( d- ,
l /~v7 k g Director, NSC Chairman, RSB / Date
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