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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:NRC TO EDUCATIONAL INSTITUTION
MONTHYEARML20248C3591989-08-0101 August 1989 Advises of Reactor & Senior Reactor Operator Licensing Exams Scheduled for Wk of 891030.Ref Matl Requirements, Requirements & Procedures for Administration of Written Exams & Requirements for Facility Review Encl ML20245J3411989-05-0101 May 1989 Advises That Reactor Operator Exams Scheduled for Wk of 890612.Encl Ref Matl Requested by 890512 in Order to Meet Schedule ML20154K9221988-09-20020 September 1988 Ack Receipt of & Check in Payment for Civil Penalties in Amount of $5,000.Ack Receipt of 880728 Response to Notice of Violation ML20151V0661988-08-11011 August 1988 Confirms NRC Agreement to Extend Response to 880713 Notice of Violation Until 880901,per G Sanborn 880810 Request ML20151F0291988-07-13013 July 1988 Discusses Insp Repts 50-128/88-01 & 50-128/88-03 on 880307- 09 & 0411-12 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $5,000.Violations Indicate Failure to Exercise Adequate Mgt Control ML20195C2541988-06-13013 June 1988 Forwards Insp Rept 50-128/88-03 on 880411-12.Violations Will Be Addressed in Separate Correspondence ML20195D6401988-06-10010 June 1988 Advises That Term Explosive Matls Used in Tech Specs Means Class a Explosives Per DOT Regulation 49FR Chapter 1. Matls Not Defined as Class a Explosives Must Be Reviewed Per Tech Spec Section 4.6 Prior to Being Placed in Reactor ML20153G1501988-05-0505 May 1988 Forwards Insp Rept 50-128/88-02 on 880405-07.No Violations or Deviations Noted ML20151T9401988-04-21021 April 1988 Forwards Summary of 880405 Enforcement Conference in Region 4 Ofc Re Violations Noted in Insp Rept 50-128/88-01 ML20151L6451988-03-23023 March 1988 Forwards Amend 11 to License R-83 & Safety Evaluation.Amend Modifies Title of One Position in Organizational Structure for Station ML20148J0101988-03-17017 March 1988 Confirmatory Action Ltr 88-03 Re 880316 Conversation That Listed Actions Being Taken in Response to Concerns in Insp on 880306-09.Nuclear Science Ctr Reactor Safety Committee Will Perform Detailed Review If Neutron Diffraction Studies ML20237D4161987-12-16016 December 1987 Confirms That Operator Licensing Exams Scheduled for Wk of 880229.Util Should Make Available at Site Approved Ref Matl Listed in Encl 1 by 880115.Exam Requirements Also Encl ML20236G0771987-10-26026 October 1987 Confirms That Jl Pellet Will Assume Position & Duties of Section Chief of Operator Licensing Section in Div of Reactor Safety Effective on 871025 to Replace R Cooley ML20215A7111987-06-11011 June 1987 Ack Receipt of Util 870408 & 0512 Ltrs Responding to 870311 Notice of Violation & NRC 870311 & s & Informing NRC of Corrective Actions Re Violations.One Violation Withdrawn & Second to Be Reviewed During Insp ML20215D2031987-06-11011 June 1987 Informs That T Micheal Assigned as Project Manager for Facility Due to NRR Reorganization ML20209F9761987-04-28028 April 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-128/87-01.Requests Records Substantiating That Bromine Experiment Reviewed by Nuclear Science Ctr Before Bromine Irradiated in Reactor ML20205Q6601987-03-30030 March 1987 Informs That 870224 Request to Modify Emergency Plan Changing Annual Renewal of Agreements W/Offsite Support Agencies to Multiple Yr or Open Renewal Would Decrease Effectiveness of Plan & Unacceptable ML20212P5401987-03-11011 March 1987 Forwards Insp Rept 50-128/87-01 on 870112-14 & Notice of Violation.One Unresolved Item Identified in Paragraph 4.g of Rept ML20212A1821987-02-24024 February 1987 Advises That Applications for Reactor Operator & Senior Operator Licensing Exam Scheduled for 870330 Received in Timely Manner.List of Ref Matl Requirements for Exam & Requirements for Administration of Written Exams Encl ML20214M4391986-09-0404 September 1986 Forwards Insp Rept 50-128/86-02 on 860729-30.No Violations or Deviations Noted.Status of Items Identified During Previous Insp Findings Examined ML20206Q2131986-08-27027 August 1986 Forwards Environ Assessment & Notice of Finding of No Significant Environ Impact Re 860711 Proposed Amend to License R-83 to Increase Mass for Fueled Experiments IR 05000128/19860061986-08-20020 August 1986 Grants 30-day Extension Until 860922 for Reply to 860722 Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-128/86-06 & EA-86-105,per 860811 Request ML20211Q9701986-07-22022 July 1986 Discusses Insp on 860505 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $1,250. Confirmation of Action Ltr Transmitted on 860507 & Enforcement Conference Conducted on 860521 ML20198A0661986-05-15015 May 1986 Forwards Insp Rept 50-128/86-01 on 860505 & Notice of Violation.Enforcement Conference Scheduled on 860521 to Discuss Violations,Reasons & Corrective Actions.Concern Expressed Re Lack of Discipline Exhibited by Staff ML20210H9271986-03-27027 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 ML20138N0611985-12-17017 December 1985 Discusses NRC 850927 Order to Show Cause Why All Excess High Enriched U Fuel Should Not Be Removed to Secure Facility Away from Reactor Site.Consent to Order Understood, Since Hearing Not Requested,Nor Order Contested ML20133F8751985-10-0808 October 1985 Forwards Chronology of Commission Approved Physical Security Plan for Texas A&M Univ AGN-201M Reactor Facility ML20058B4721982-07-16016 July 1982 Forwards Amend 8 to License R-83.Amend Changes Tech Specs Re Administrative Organizational Controls ML20054M4011982-07-0808 July 1982 Forwards IE Insp Rept 50-128/82-01 on 820604.No Noncompliance Noted 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 ML20137G4721971-06-23023 June 1971 Advises That Presence & Irradiation of Explosives in Reactor Must Be Evaluated Due to Potential for Damage to Reactor. Evaluation Requested Establishing Operating Restrictions,Max Quantity of Explosives Allowed in Facility & Form 1989-08-01
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20209F0171999-07-0909 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 ML20195J9881999-06-10010 June 1999 Forwards Results of Operator Initial Exam Conducted at Texas A&M Univ on 990405-06.Without Encl 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 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 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 ML20153C9791998-09-22022 September 1998 Forwards Copy of Results of Operator Initial Exam Conducted at Texas A&M Univ on 980914.Without Encl 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 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 ML20199J2841998-01-29029 January 1998 Transmits SRO License Certificate to Th Fisher.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 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 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 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 ML20137R4221997-04-0303 April 1997 Forwards Results of Operator Initial Exam Conducted at Facility on 970324.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 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 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 ML20129F0981996-09-27027 September 1996 Informs of Arrangements Made W/B Asher for Administration of Operator Licensing Exam During Wk of 961118 ML20058L3911993-12-13013 December 1993 Forwards Results for Operator Initial Exam Conducted at Facility on 931109.W/o Encl ML20058L3631993-12-0909 December 1993 Forwards Initial Exam Rept 50-128/OL-93-03 Administered During Wk of 931108 ML20058L3611993-12-0909 December 1993 Forwards Initial Exam Rept 50-128/OL-93-03 Administered During Wk of 931108.W/o Encl ML20059F9971993-10-26026 October 1993 Forwards Amend 18 to Indemnity Agreement E-12,amend 13 to License R-83 & Se.Amend Modifies License Conditions to Allow Greater Flexibility in Possession & Storage of Radioactive Matls Used to Support Research & Development ML20056E6161993-08-0909 August 1993 Requests Response to Encl Ref Matl Request for Ro/Sro Licensing Exams Scheduled for 931108.Info on Administration of Written Exams & Rules & Guidelines Also Encl ML20056C4551993-06-0808 June 1993 Forwards Initial Exam Rept 50-128/OL-93-02 on 930518 ML20056C1341993-03-23023 March 1993 Confirms Meeting Between Wd Reece & B Murray on 930428 to Discuss NRC Mgt Personnel Opportunity to Review & Discuss Performance Perspectives of Licensed Activities IR 05000128/19920021993-01-19019 January 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-128/92-02 ML20248C3591989-08-0101 August 1989 Advises of Reactor & Senior Reactor Operator Licensing Exams Scheduled for Wk of 891030.Ref Matl Requirements, Requirements & Procedures for Administration of Written Exams & Requirements for Facility Review Encl ML20245J3411989-05-0101 May 1989 Advises That Reactor Operator Exams Scheduled for Wk of 890612.Encl Ref Matl Requested by 890512 in Order to Meet Schedule ML20154K9221988-09-20020 September 1988 Ack Receipt of & Check in Payment for Civil Penalties in Amount of $5,000.Ack Receipt of 880728 Response to Notice of Violation ML20151V0661988-08-11011 August 1988 Confirms NRC Agreement to Extend Response to 880713 Notice of Violation Until 880901,per G Sanborn 880810 Request ML20151F0291988-07-13013 July 1988 Discusses Insp Repts 50-128/88-01 & 50-128/88-03 on 880307- 09 & 0411-12 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $5,000.Violations Indicate Failure to Exercise Adequate Mgt Control ML20195C2541988-06-13013 June 1988 Forwards Insp Rept 50-128/88-03 on 880411-12.Violations Will Be Addressed in Separate Correspondence ML20195D6401988-06-10010 June 1988 Advises That Term Explosive Matls Used in Tech Specs Means Class a Explosives Per DOT Regulation 49FR Chapter 1. Matls Not Defined as Class a Explosives Must Be Reviewed Per Tech Spec Section 4.6 Prior to Being Placed in Reactor 1999-07-09
[Table view] |
Text
_ - _ _ _ _ _
s e .
4 JUN l l 1987 In Reply Refer To:
Docket: 50-128/87-01 a
-1 l
1 1
Dr. Herbert H. Richardson, Director {
Texas Engineering Experiment Station l Texas A&M University ^
i College Station, Texas 77843 Gentlemen:
]
Thank you for your letters of April 8,1987, and May 12, 1987, in response to our letters of March 11, 1987, and April 28, 1987, and the Notice of Violation dated March 11, 1987. As a result of our review of the additional documents you l submitted on May 12, 1987, we are in agreement that the experiment involving the irradiation of bromophenanthrene was reviewed in accordance with the j requirements of Technical Specification 6.3.3(a) and 3.6.3(a). Therefore, j the violation (128/8701-01) concerning the failure to evaluate a reactor '
experiment is being withdrawn.
With regard to violation 128/8701-02, we have no further questions at this' l time on your proposed corrective actions. We will review the implementation 1 of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintained.
1 Sincerely, !
."4 vM Lv q of;
Lawrence A. Yandell, Chief .
Radiological Protection and Safeguards I Branch .
cc:
F. E. Vandiver, President Texas A&M University College Station, Texas 77843 M. E. McLain Radiation Safety Officer Texas A&M University )
College Station, Texas 77843 Mr. Feenan Jennings, Chairman i Reactor Safety Board Texas A&M University College Station, Texas 77843
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Texas A&M University j i
Texas State Department of Health 1100 W. 49th Street Austin, Texas 78756 i l
Texas Bureau of Radiation Control ATTN: C. Dittman, Region 6 j 1100 W. 49th Street l Austin, Texas 78756 )
bcc to DMB (IE-01) j bec distrib. by RIV:
RP8 j R. D. Martin, RA RPSB ;
D. Weiss, RM/ALF l RIV File l DRSP j RSB l MIS SYSTEM RSTS Operator Inspector j Section Chief L. A. Yandell l R. L. Bangart R. E. Hall NRR Project Inspector i l
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g TEXAS ENGINEERING EXPERIMENT STATION TEXAS A&M UNIVERSITY COLLEGE STATION, TEXAS 77843 3575 #
1 M i 12 May 1987 NUCLEAR SCIENCE CENTER 409/845-7551 j
Mr. William L. Fisher, Chief l f '
Radiological and Safeguards Programs ,
Branch E !. 3 19 9 ,' ii U.S. Nuclear Regulatory Commission ..i, O,
Region IV '
l 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011
Reference:
Docket 50-128/87-01
Dear Mr. Fisher:
This writing is in reply to your letter of 28 April 1987 requesting additional information on the irradiation of bromophenanthrcne at the Texas A&M University !
Nuclear Science Center on 18 December 1986. As stated-in our reply of 8 April I 1987 to the stated violation this routine experiment was reviewed and approved for i irradiation under blanket authorization EA-1 "In-Pool Irradiations" a copy of 1 which was previously provided. Additional information is provided to document !
review and approval of bromophenanthrene irradiations of which several have been j performed over the past six years. Modifications have been made to bromine sample i handling procedures the latest being a detailed review in August 1985. That review in the form of Staff Meeting #374 is attached. Review requirements of 50P IV-A for the irradiation of the bromine samples is also attached as is the authorization Form 514 dated 12/18/86.
Res ectfully submitted, oA_A, ( O b Do ald E. Feltz Director DEF/ym Attachments cc: H. H. Richardson, Director, Texas Eng. Experiment Station F. Jennings, Chairman, Reactor Safety Board M. E. McLain, Radiological Safety Office K. L. Peddicord, Head, Nuclear Engineering Department J. A. Reuscher, Director, Nuclear Research Reactor Programs
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Nuclear Science Center Staff Meeting #374 23 August 1985 l l
In Attendance: Feltz, Krohn, Stasny, Jeffords ,
i The purpose of the meeting was to review procedures for the production of isotopes La-140 and Br-82 for Teledyne Isotopes. This material is to be irradiated Tuesday, 27 August 1985 and prepared for delivery on the morning of 28 August i 1985. The material will be shipped on Federal Express. The irradiation involves 3 each 1.4 mC samples of La-140 powder and 3 each 20 mC Br-82 post irradiation prepared samples. Since post irradiation handling of the samples is required it is important that all personnel involved be familiar with the special handling procedures. The attached proedures were approved in the staff meeting. Tests.
were performed on the preparation of the Br-82 samples using low activity samples.
These test verified dissolving methods. During the Br-82 test it was determiend that 30 percent of sample activity will be lost to gases and residue following transfer. The Br-82 gases will be extracted and held for decay.
See attachment for detailed procedures. ,
1 Res,pectfully submitted,
, c?
Donald E. Feltz Director
. e. .
TELEDYNE IS0 TOPE PRODUCTION 3- . Handling and Loading Procedures John Krohn, 23 August 1985 . >
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In preparation for the upcoming production and loading of tracer materials for l Teledyne Isotopes, Inc., the following set of handling and loading procedures is set forth. It is requested that each person that will be involved become familiar with procedures prior to the runs which are scheduled for Tuesday, 27 August.
General Guide.ines
. All post-irradiation handling, chemistry and shipping container loading will_be !
done in the Chem Lab.
. The operation will be under the supervision of Technical Services.
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. A representative from the HP group will be present during all. handling, etc., and will have final approval of any proposed actions. '
. The operation will involve loading 6 (six) injector bombs (containers) with NSC produced radioisotope tracers. There will be 3 bombs filled with catalyst powder and 3 with a liquid solution.
. Handling time will be split between several NSC personnel to reduce any one person's exposure. ,
Specific Procedures Isotope Production Both tracer materials will be irradiated on Tuesday, 27 August. There will be "
three vials of bromophenanthrene each containing approximately 2 grams to'be run for two hours from startup and producing 34 millicuries of Br-82 and the end of l irradiation. The second material is a powder catalyst. Again there will be three vials, each containing one gram of the powder to be run for the last six hours and 24 minutes of the day's run and producing 2.63 millicuries of La-140 and 1 milli ' .s Curie of Na-24 at the end of irradation.
Handling Bromine Tracer l 1
The bromine vials will be unloaded from the long tube at 1600 on Tuesday. The-vials will be placed in the " bullet" shields used for M. D. Anderson iridium ship-i l
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l ments. These shields will be transported to the Chem Lab by placing them into a
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five gallon can and lowering them with the crane to the lower level. From there they will be carried to the Chem Lab and the shields placed in the fume hood. This ]
j transport procedure may be changed at the discretion of the Reactor Supervisor. 4 After the shields are in the Chem Lab fume hood, the bromine vials will be taken out and placed in the holes in the lead brick at the front of the fume hood. An empty syringe will be inserted into each of the vials and a suction drawn. These l
syringes will be placed into a plastic bag which will then be sealed. '
A 10 cc syringe of toluene will then be inserted into each bromine vial and the vial filled with toluene. The tops of the vials will then be covered with tape to prevent evaporation.
On Wednesday morning, 28 August, the tracer containers will be loaded. The following procedures will be repeated for each of the three bromine samples:
- 1. Prepare a tracer container as per the attached instructions.
- 2. Place the glass funnel in the top of the container.
- 3. Remove the tape from a bromine vial, take a small sample with a syringe and replace the tape.
- 4. Repeat the sampling procedure for the other two vials at this time, and Nit on assay results from Lab 4.
- 5. Cut the top off of the bromine vial with the exacto.
.. 6. Lift the vial with the holder and pour into the funnel.
- 7. Wash the funnel with clean toluene in a squirt bottle.
- 8. Close the container valve and have the HP place a bag over the valve and top of the container. t
- 9. Repack the shipping drum with the full tracer container as per the attached i instructions. ,
l The results of the assay from Lab 4 should be used to properly mark each shipping container. Great care should be taken while handling the liquid solution as toluene is very volatile. Af ter the drums are packed and marked, they should be i m removed from the Chem Lab and the remaining three drums brought in. N l
- s. l Lanthanum Tracer l The three lanthanum vials will be left in the pool overnight following their irradiation. The vials will be unloaded Wednesday morning following the loading of the bromine tracer containers. The lanthanum vials will be transported to the Chem Lab in the same manner as the bromine. After the shields containing the lanthanum vials are placed in the fume hood, the vials will be placed in the same brick as was used for the bromine vials. The following procedura rtill be followed in loading the lanthanum tracer containers:
.,3. s-
- 1. Prepare the tracer container as per the attached instructions. l
- 2. Place the glass funnel into the top of the container.
- 3. Cut the top off of a lanthanum vial.
- 4. Lift the vial with the holder and pour into the funnel.
- 5. Wash the funnel with toluene from the squirt bottle.
- 6. Close the container valve and have the HP place a bag over the valve and top of the container.
- 7. Repack the shipping drum with the full tracer container as per the attached instructions. i
- 8. . Repeat for the two remaining lanthanum vials.
Handling Personnel i The following schedule of sections responsible for performing each operation is designed to reduce the radiation exposure to any one. person and to ensure proper q handling of the tracers. Each group leader will assign the duties for that group j as he sees fit. i Operation Groups Responsible
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~, Initial bromine transfer to Chem Lab Operations, HP Transfer of bromine to brick Operations, HP Extraction of gas and addition of toluene Tech Services, HP Bromine sampling, assay, vial opening Tech Services, HP Tracer container preparation, filling, pack Tech Services, HP Initial lanthanum transfer to Chem Lab Operations, HP Lanthanum transfer to brick Operations, HP {
Lanthanum vial opening Tech Services, HP d Tracer container preparation, filling, pack Tech Services, HP l
Again, clease have everyone involved study these procedures before the operations d are .eduled. Any questions should be answered before the operations begin.
Please bring any questions to the attention of John Krohn. , l
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.> Handling Procedure for Packaging' '
Tracer Container for Shipping
- 1. Insert carrier r6ds with plate th*ough~the sleeves on the tracer container shielding.
- 2. Slide top plate on the rods and screw on the wing nuts.
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- 3. Insert the tracer container with the carrier into the inner shipping.
container and acrew cap by hand. ,
- 4. Replace absorbent in drum and insert the plywood lid.
- 5. Till the remaining void with shock absorbing packaging material. j
- 6. Close the drum with a lid, ring and bolt. -
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ea Handling Procedures for Readying Tracer Container !
for Filling or Injection of Radioactive Meterial- ,
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- 1. Remove ring and lid from the shipping drum.
- 2. Remove packing material from the drum down to the' top plywood lid.
- 3. Remove the plywood lid. A screw type cap of the inner shipping container surrounded by absorbing media should be visible.
- 4. Unscrew the cap and extract the tracer container from the inner '
shipping container by the handle with its carrier.
- 5. To remove the carrier, unscrew the wing nuts when the tracer container is in position for filling or injecting and extract' the bottom plate and rods. .
- 6. Ensure that the valves are closed and that the valve handles are removed. ,
NOTEt' Avoid excess handling of tracer containers containing radioactive .
material.
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MAX RADIATION AT $URFACE OF CONTAINER MR/HR, @ 3 FffT MA/HR MATERIAL RELEASED TO VEHICLE PLACARDED DAff RELIA $fD TIME $URVfYOR LOADED BY UNLOADED BYi co m $sahoe or/ ob u e b5n. 8Y~ G No - M ' le) u; }) .) 8,j,,sa'II:les e ,,, 1, +rans}wrul samole ha,, 4 Ha
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i STANDARD OPERATING PROCEDURES l Prepared by Subject Section Page
) JLK EXPERIMENT APPROVAL IV-A 1 j
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- 1. General i These procedures apply to the use of NSCR experimental facilities and cover the approval, irradiation,and release of a large variety of samples which are submitted in many shapes , chemical forms ,and various states. The procedures apply to all experiments associated with the operation of the reactor. No new experiment shall be implemented until:
- a. A hazards analysis has been performed and reviewed for compliance with the I limitations on experiments (Section 3 6 of Technical Specifications) by the Reactor Safety Board. Minor modifications to a reviewed and approved experiment may be made at the discretion of the SR0 upon the determination and documentation that the changes do not constitute a significantly new or different safety risk than the original approved experiment (Technical Specification 4.6(a)).
- b. The reactivity worth of an experiment has been measured. Prior to the first use of an experiment for which there is no previous reactivity worth re-corded for the current operational core and position , the worth will be measured.
Furthermore ,no experiment classified as approved by the RSB will be performed until it has been reviewed for compliance with Section 3.6.1 through 3.6.3 of the Technical Specifications by a licensed Senior Reactor Operator and a person qualfied in health physics. Approval procedure will depend on whether the service is a i routine sample irradiation or whether it is a non-routine operation. ,
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- 2. Routine Sample Irradiation Approval j l
Each experimenter requiring the irradiation of a sample will initiate action by com- '
pleting NSC Form 514--Irradiation Information Sheet (See Figure IV-A-1). This form which will be submitted with each set of samples describes the isotope needed , the activity expected,and the preferred method of release. Information concerning the method of sample preparation, details of the irradiation record,and sample disposition are completed by the Operations and Health Physics Staff as a record of the sample history. This form must be signed and approved by the Senior Reactor Operator and Health Physicist prior to irradiation.
For guidance of the individuals reviewing NSC Form 514,the sample,its encapsu-lation , the procedures for handling it , and the method of positioning it in the j reactor should satisfy the following criteria to be approved for irradiation:
- a. Encapsulation will insure sample containment to prevent contamination of the reactor pooi , handling areas,and any laboratories involved.
- b. The induced sample activity can be safely handled using available equipment.
- c. If a dimensional change of the sample is expected , adequate expansion space will be left in the irradiation capsule.
Approved: '~
udd k Dire c toryJ(SC
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EX*ERIMENTER- DEPT OR COMPANY LICENSE NO *URCHA$E ORDE' LOCATION IN CORE IRRADIATION DEVICE DATE OF lRRADIATIOF 'RRADIATION TIME ENCAPSULATION, PRIMARY $ECONDARY INSTRUCTION $ FOR RELEA$t
$ AMPLE NO.
COMPOSITION
$ AMPLE MA$$
150 TOPE ($1 ACTIVITV'
- 1f octivity is less than 10 c it is odoquote to indicole it as such.
NO. OF $AMMES IRRADIATED Measured 6p: Cold Ctitleal At Power .
1RRADIATION INFORMATION l EXP AUTH # H.P. APPROVA! $RO APPROVAL DATE lH TIME !On
DATE OU' TIME 'Oc " AGE HR$ IRRAD. I i
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CONTAMINATION OF $ HIPPING CONTAINED TYPE OF $ HIPPING CONTAINER N$C SHIELD # 'OCK # l MAX RADIATION AT $URFACE OF CONTAINER MR/HR, @ 3 FEET MR/HR i
MATERIAL RELEASED TO VEHICLE PLACARDED DATE RELEASED TIME $URVEYOR
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Prepared by STANDARD OPERATING PROCEDURES Subject Page i
Section
) JLK EXPERIMENT APPROVAL IV-A 2
- d. The expected reactivity change due to incertion and removal are within acceptable limits (See S0P II-D-6).
- e. Significant reactivity variations due to sample movement (sway , bobbing , !
or rotation) will be prevented, j
- f. The limitations on experiments as indicated in Technical Specifications :
3.6.1 through 3.6.3 must be satisfied prior to approval.
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- g. Expected activity should reflect either total activity of all samples or a per-batch amount from which total activity can be calculated. The ,
activity should be categorized according to the major contributing isotopes. !
Activity level should be that at the end of irradiation (i.e. , decay time ,
equals zero) unless the release time is known. When the time of release is !
known and the activity is calculated for such time , the time should be i noted (e.g. ,500 mci total e 1200, 10-10-83).
I 3 Approval of Non-routine Reactor Services j
This section pertains to all experiments that cannot be described as routine reactor service. The service ,which may be a single measurement or a series of experiments will be initiated by the experimenter submitting NSC Form 511--Description of Services Requested. This form is attached as Figure IV-A-2. After completion by the experi- menter the form will be reviewed by the Management and Health Physics Staff to determine if:
- a. The serv ~s requested are within the capability of the NSC.
- b. They can be performed safely.
- c. No violation of Technical Specifications would arise in performing the service.
- d. Prior RSB approval has been obtained in the form of an Experiment Authorization.
If the above conditions can be met satisfactorily the experiment may be scheduled.
If not , the experiment will be discussed in detail in a staff meeting and submitted j to the RSB for approval if necessary. q l
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Director, MC
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