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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 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 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 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 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 ML20199J2841998-01-29029 January 1998 Transmits SRO License Certificate to Th Fisher.W/O Encl 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 $5,000 for 880713 Order Imposing Civil Monetary Penalty ML20155C9201988-06-0707 June 1988 Forwards Minutes of Reactor Safety Board Subcommitee for Review of Nuclear Science Ctr Experiment & Radiological Control 880530 Meeting ML20155A7511988-05-10010 May 1988 Forwards Summary of Rsb Subcommittee for Review of NSC Experiments & Radiological Control 880520 Meeting ML20151U7551988-03-31031 March 1988 Forwards ORO-4207-20, Twenty-Fourth Progress Rept of Texas A&M Univ Nuclear Science Ctr,1987, Per Tech Spec 6.6.1 ML20196F0231988-02-23023 February 1988 Submits Info to Correct Addressed to Berkow Re Change in Adminstration of Nuclear Science Ctr Reactor. Effective Date for Change Is 880201 ML20149H0451988-02-0808 February 1988 Submits Change to Facility Emergency Preparedness Plan.Ref in Plan to Support Agreement W/St Joseph Hosp,Bryan,Tx to Be Replaced W/Support Agreement W/Humana Hosp,College Station, Tx 1999-09-07
[Table view] |
Text
P S*'W TEXAS ENGINEEllING EXPERIM ENT STATIO THE TEXAS A&M UNIVERSITY SYSTEM
~
COLLEGE STATION, TEXAS 77843 p' '
A s -
NUCLEAR SCIENCE CENTER 4 February 1983 713/845-7551 Y$h f! l
@-S E ! l Mr. John T. Collins .
Regional Administrator USNRC, Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011
Dear Mr. Collins:
I have enclosed a final copy of the "NSCR Post Damage Pulse Test Program" for your review. The plan was approved with only minor changes by the Reactor Safety Board on 28 January 1983, These included minor wording changes and sentence restructuring (primarily in Section V) for clarity. If there are any questions or additional comments, please let us know.
Sincerely yours, Ih r.. .
Dale Rogerb Manager Reactor Operations DR/ym Enclosure t
n e
, [
-' /
f 8304040032 830204 PDR ADOCK 05000128 P PDR RESEARCH AND DEVELOPMENT FOR MANKIND
m
. NSCR' POST DAMAGE PULSE TEST PROGRAM I
For i
A FULL FLIP TRIGA CORE f
i
, January 1983 RSB Review and Approval: -
, R. L. Watson, Acting Chainnan Reactor Safety Board
/NB' Date
?
e N *
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NSCR POST DAMAGE PULSE TEST PROGRAM FOR A FULL FLIP TRIGA CORE I. Introduction Pulsing operations of the Nuclear Science Center Reactor (NSCR) were terminated in September 1976 following the discovery of three damaged fuel elements. A detailed operating history of NSCR cores since the discovery is provided in Appendix A. Based on the completion and approval of a final fuel element damage reportI and submittal of material to the USNRC, dated 16 April 1982, a three phase post damage pulse test program has been developed for the resumption of pulsing of the NSCR. A full FLIP core loading designated as Core VIII has been selected for the pulse test program (seeFigure1). <
In this program peak core temperature values will be determined for stepwise increased pulse reactivity insertions. These values will be obtained by applying calculated peaking factors to observed fuel thermo-couple temperatures, and, in addition, core pulse energy will be determined by the foil act.ivation method for a given reactivity insertion. The pulse data obtained will be extrapolated to determine the maximum allowable reactivity insertion to produce a peak core temperature of 830 C and to predict the maximum core temperature for the accidental insertion of the full worth of the transient rod. It should also be noted that in this program requirements have been established for the periodic inspection of fuel elements expected to experience the highest core temperatures. The program will progress by phases, and local review and approval by the Reactor Safety Board will be completed prior to entering each phase.
II. Objectives The pulse test program for the resumption of pulsing of the NSCR is designed to meet the following objectives:
(1) Assure that the maximum core temperature will not exceed 830 0C (1526U F) during pulsing operation, 1" Interpretation of Damage to the FLIP Fuel During Operation of the Nuclear Science Center Reactor at Texas A&M University", M. T. Simnad, G. B. West, J. D. Randall, W. T. Richards and D. Stahl, General Atomic Company, GA-A16613, December 1981.
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(2) Establish limiting pulsing parameters for a given core.
(3) Obtain calibrations so that the peak core temperature and core pulse energy are known for a given reactivity insertion.
(4) Provide surveillance to detect fuel damage resulting from pulsing should damage occur.
III. Ini_tial Condit_ ions Core VIII was established in December 1982 at which time the transient rod was installed and verified operational for steady state. In addition, the associated electronics have been successfully checked in the steady state mode of operation. For operation in the pulse mode all electronics and maintenance checks associated with the pulse measuring channel instrumentation and transient rod system will be completed and documented prior to entering the pulse test program. As a prelude to entering the test program certain high temperature elements designated to be monitored during the pulse program were removed from the core in January 1983 for visual inspection and measurement. It was at this time that a damaged element from past pulsing operations was discovered; therefore, the entire core was unloaded and inspected. A second damaged element was found, and both have been removed from the present Core VIII configuration.
.IV. Code Calcul_ations_
The Exterminator-2 reactor code is used to determine the location of maximum pulse temperature fuel elements. Calculations have been completed for Core VIII, and based on this information the location of the peak core temperature has been determined, and the peaking factors between the IF thermocouple location and the peak core temperature location are known.
This aids in establishing the IF temperature corresponding to core Tmax "
830 C (1526 F) as the operational pulsing limit. Any future core loading will require calculation of maximum temperature locations and peaking factors to be followed by a pulse program of stepwise pulse reactivity insertion to establish pulsing parameters and limitations.
V. Fuel Element Inspection In this program two methods of fuel inspection will be used independently or jointly as needed. One method of inspection is to visually observe the m
condition of fuel elements in a bundle assembly without breaking down the bundle. The second inspection method requires the measurement of elongation and bowing of individual elements.
Fuel bundles in grid positions E-5, D-4, and C-5 and their associated fuel elements have been selected for inspection at various stages of the pulse test program (see Core VIII, Figure 1). These bundle positions are east, south, and west of the transient rod bundle. These three grid position bundles selected for inspection contain six high temperature elements. Two are adjacent to the transient rod and four are adjacent to water filled flux traps. These grid locations also contain three of the five element positions where damaged fuel was discovered. These pot.itions are C-5(SE),
D-4(NW), and E-5(NW). Positions where the two other damaged elements were located, D-5(SE) and D-6(SE), will experience flux and temperature conditions almost identical to positions C-5(SE) and E-5(NW), respectively.
Therefore, it is not essential to inspect the latter two positions at each inspection. However, they will be inspected at selected points in the program.
The instrumented elements in D-6(SW) and E-5(SW) will not be inspected due to potential loss of thermocouples during handling. The handling of elements in the transient rod bundle D-5 and the instrumented element bundle D-6 will be minimized as the handling of these bundles could result in damage to the transient rod and potential failure of the thermocouples in the instrumented element. It is essential to reactor operations that the IF in D-6(SW) is protected against damage due to handling.
The frequency selected for fuel inspections in the program is based primarily on the history of pulse operations of Core III-A prior to discovery of damaged fuel. During that period there were 455 pulses of $2.00 value, 54 pulses of $2.70 value, and 30 pulses between $2.00 and $2.70. Due to the absence of fuel inspections during operation of Core III-A there is insufficient data to establish the onset of fuel damage due to high temperature pulsing. However, it is reasonable to assume that the core was safely operated with damaged fuel for a long period and clearly without fuel element clad failure. (No fission products were released from any of the damaged elements.) It is also known that the two damaged elenents discovered in January 1983 were in the core and operating at high power since termination of pulsing in September 1976. This has been a significant
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y demonstration of fuel integrity considering that the NSCR operates approxi-mately 100 megawatt days per year.
Based on the above discussion it is clear that reactor safety would not be compromised even with an inspection program that allowed large numbers of energetic (> $2,00) pulses between inspections. However, in the first two phases of the test program the' inspection intervals (see Sections VI and VII) involve numbers of pulses more than an order of magnitude less than the number of $2.00 and $2.70 pulses experienced by Core III-A. The goal is to perform frequent, selected inspections of the fuel to establish the onset of pulse damage should it occur. The inspection of fuel following the establishment of $2.00 pulsing will provide base data for future inspections.
The increased frequency-of inspections at the higher pulse temperatures are required as these are the pulses that would most likely damage the fuel.
The inspection of fuel after maximum pulse insertion has been estbalished will provide monitoring of the long term effect of pulsing in conjunction with normal steady state operation.
VI. Pha_se I of Full FLIP P_ulse Test Program In this initial pulse test program phase the reactor will be pulsed in stepwise increased pulse reactivity insertions of $0.25 increments from
$1.00 up to and including $2.00. Fuel element inspections are included in this phase. When $2.00 is reached the following will be performed:
- 1. Determine by extrapolation the reactivity insertion value to produce a U
peak core temperature of 830 C (T max = 1526 F).
- 2. Determine by extrapolation the pulse energy in MW-sec for the maximum pulse reactivity insertion required to produce a peak core temperature U
of 830 C (Tmax = 1526 F).
- 3. Execute ten (10) pulses of $2,00 insertion and compare observed temperatures and energy for reproducibility.
! 4. Halt pulsing and inspect the fuel elements of interest by visual and measurement methods (.see Section V).
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- 5. Prepare a report of the $2.00 pulsing results for presentation to the RSB for review and approval to proceed to Phase II of the pulse test program, i
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- 6. Provide a copy of the results of Phase I to the USNRC (Washington and Region IV) follow'ing review and approval by the RSB.
Note: Following Phase I fuel inspection and during the review and approval process period, the core may be pulsed at
$2.00 maximum reactivity insertion (assuming no damage was detected) for purposes of measurement of pulse ny and nyt and neutron flux mapping of experimental facilities.
VII. Phase II of the Full FLIP Pulse Test Program In this phase the pulse reactivity insertion to produce a near maximum allowable core temperature (1326 F < T core < 1526 F) will be determined.
Fuel element inspections are included in this phase of the pulse program.
- 1. From the extrapolated results of Phase I select the extrapolated value of the pulse reactivity insertion predicted to lie half-way between
$2.00 and the maximum allowable pulse insertion. (i.e.,thepulse required to reach Tech Spec limits).
- 2. Pulse the reactor at the value obtained above and immediately inspect visually the fuel elements of interest (see Section V).
- 3. Af ter reassembly of the core select a pulse reactivity insertion of near maximum allowable value. The selection should result in a maximum pulse core temperature between the limits of 1326 F and 1526 F.
- 4. Pulse the reactor at the near maximum' allowable pulse insertion and immediately inspect visually the fuel elements of interest (see l Section V).
- 5. Execute five (5) near maximum pulses and compare observed temperature and energy for reproducibility.
- 6. Halt pulsing and imediately inspect fuel by visual means and direct measurement of elongation and bowing. In addition to the fuel elements previously inspected during the pulse test program, the elements in the instrumented and transient rod bundles will be inspected.
- 7. Prepare a report of the near maximum pulsing results for presentation to the RSB for review and approval to proceed to Phase III of the pulse test program.
- 8. Provide a copy of the results of Phase II to the USNRC (Washington and Region IV) following review and approval by the RSB.
Note: The reactor may be pulsed during the review and approval period of Phase II assuming no damage was detected. Pulse insertion values will be limited to one-half the value between $2,00 and maximum allowable insertion.
VIII. Phase III of the Full _ FLIP Pulse Test Program This phase of the program represents continued surveillance of fuel for pulse damage should it occur. This phase is designed to complement the proposed fuel surveillance requirements of the Technical Specifications for
. renewal of License R-83. The new Technical Specifications will require an annual fuel inspection program. This phase will require the following fuel inspections:
- 1. The elements of interest as described in Section V will be inspected as follows: ,
(a) Visual inspection following each 25 pulses of reactivity insertion value equal to or less than the value lying half-way between $2,00 and the maximum allowable reactivity insertion, and (b) Visual and measured inspection following each 15 pulses of reactivity greater. than the largest value described in (a) above.
(c) Inspection annually of fuel in accordance with Technical Specification requirements.
- 2. This inspection program will continue as follows:
(a) Until the total number of pulses of 1(a) has reached 75, or (b) Until the total number of pulses of 1(b) has reached 45, whichever comes first.
(Note that this will extend beyond the total equivalent pulsing of Core III-A).
(c) Following completion of the requirements of 2(a,b) the elements in the instrumented and transient rod bundles will be inspected by visual and measurenent methods.
(d) Annual inspection of fuel will be performed in accordance with Technical Specification requirements.
APPENDIX A OPERATING HISTORY AND CORE CONFIGURATIONS FOR THE NSCR FROM SEPTEMBER 1976 TO PRESENT Following the initir.1 discovery of fuel element damage in September,1976 the NSCR continued to operate in the steady state mode using the Core III-A configuration for approx imately three months, Figures showing Core III-A and all core loadings used since that time are attached in this appendix.
Reactor core loading IV-A of 59 FLIP TRIGA elements and 39 standard TRIGA elements became oper6tional on 10 January 1977. The new core loading was placed into service as part of the continuing upgrade program toward a full FLIP core loading. Core loading IV-B which became operational on 13 June 1977 differs from IV-A only by removal of the transient control rod from the core.
The NSCR continued to operate in the steady state mode using a mixed core configuration until November 1979. At that time Core V was established and contained 83 FLIP elements with a total excess reactivity of $2.90. Since this was not sufficient excess reactivity to maintain an operational core and meet utilization requirements, the loading was modified by the addition of 4 FLIP elements. This loading was designated Core VI and was established in November 1979. It contained 87 FLIP elements with a total excess reactivity of $5.73.
Increased utilization was achieved by providing irradiation positions (flux traps) on the periphery of the core. These positions are vacant fuel bundle locations approximately 3" x 3" in cross sectional area.
In an effort to increase the availability of neutrons on the east face of the reactor Core VI was modified to Core VI-A in December 1980 by moving the fuel bundle from D-7 to F-5. Tests confirmed not only an increase in the east face neutron flux but a flattened flux shape as well. This core was only operated as needed for neutron radiography, and through April, 1981 Core VI continued to be the primary core loading. At that time Core VII was established by adding an additional fuel bundle in F-2 to the Core VI-A design. In addition the neutron source was repositioned to the D-2/E-2 grid locations. Core VII was established to flatten the east face flux available to the multiple rotisserie irradiation device (MRID) and operated until January 1982 at which time Core VII-A was established. As seen in the attached figures this minor change to Core VII included the installation of an additional pneumatic receiver l
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Core VII-A continued to operate through December,1982 at which time the transient rod was. installed in D-5 and Core VIII was established. This core was loaded in preparation for reentering the pulse mode of operation and has operated satisfactorily in the steady state mode since being loaded. Up to the present time there has been approximately 650 megawatt days of steady state operation since the discovery of fuel element damage in September,1976.
Table I has been provided to summarize the operating history of various configurations used since September, 1976 TABLE I Approximate Core Date MW-Days III-A September '76 - January '77 32 IV-A, IV-B January '77 - November '79 265 -
IV November '79 2 VI, VI-A November '79 - April '81 125 VII, VII-A April '81 - December '82 220 VIII December '82 - Present 10 i
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