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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20210G4481999-07-26026 July 1999 Discusses Arrangements Made for Administration of Operator Licensing Exam at Armed Forces Radiobiological Research Institute Reactor,Scheduled for Wk of 990913 ML20155K2881998-10-13013 October 1998 Informs That Afrri Will Conduct Annual Emergency Drill on 981105.NRC Is Invited to Attend pre-drill Meeting & Drill. Meeting for Controllers & Evaluators Will Be Conducted on 981102 ML20151X9441998-09-13013 September 1998 Forwards Certificates to Wh Baxter,Ma Ortelli,Sd Osborne & Kl Wrisley,All Newly Licensed Individuals.Certificates in Addition to Actual License ML20239A1981998-09-0303 September 1998 Forwards Initial Exam Rept 50-170/OL-98-01 Held During Week of 980810.NRC Administered Initial Exam to Employees of Applying for License to Operate Armed Forces Radiological Research Inst Reactor ML20151U9611998-09-0303 September 1998 Forwards Copy of Results of Operator Initial Exam Conducted at Afrri on 980810-11.Without Encl ML20217K8781998-04-23023 April 1998 Discusses Arrangements Made for Administration of Operator Licensing Exam at Armed Forces Radiobiological Research Inst Reactor for Wk of 980810.Requests That Listed Matls Be Furnished at Least 60 Days Prior to Exam Date ML20197A7841998-03-0303 March 1998 Forwards Insp Rept 50-170/98-201 on 980202-06.No Violations Noted ML20198E9981997-08-0505 August 1997 Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transferred from Regional Ofc to Nrr. Addresses Listed ML20149L8051996-11-12012 November 1996 Forwards SRO Certificates to Listed Individuals in Recognition of Important Role Licensed Operators Fulfill in Protecting Health & Safety of Public & Achievement Represented by Meeting NRC Requirements ML20134J9681996-11-12012 November 1996 Forwards SRO Certificates to Listed Individuals in Recognition of Important Role Licensed Operators Fulfill in Protecting Health & Safety of Public & Acheivement Represented by Meeting NRC Requirements ML20134F2751996-10-23023 October 1996 Informs That SI Miller Appointed Acting Reactor Facility Director for Armed Forces Radiobiology Research Inst (Afrri) Replacing ML Moore,Effective 961015 ML20128P2561996-10-11011 October 1996 Extends Invitation to Observe Annual Emergency Drill & Attend Functions on 961104 ML20128L5921996-10-10010 October 1996 Forwards Copy of Results of Operator Initial Exam Conducted on 960916-17.W/o Encl ML20128L5961996-10-10010 October 1996 Forwards Copy of Initial Exam Rept 50-170/OL-96-01 Conducted on 960916-17 ML20115J7911996-07-25025 July 1996 Forwards Analysis & Physical Security Plan Contain Dod Unclassified Controlled Nuclear Info.Encl Withheld,Per 10CFR2.790 ML20108A1111996-05-0202 May 1996 Forwards Corrected 1995 Annual Rept of Afrri Triga Reactor ML20096D2891995-12-0707 December 1995 Forwards Comments & Questions Re Review of Draft Application Format,Content Guidance,Review Plan & Acceptance Criteria for non-power Reactors ML20098A9821995-09-20020 September 1995 Informs That Licensee Will Conduct Annual Emergency Drill on 951115 ML20092A1231995-08-31031 August 1995 Informs That Dod Directed That Afrri Be Closed & Nuclear Reactor Be Shutdown in FY97.AFRRI Will Notify NRC & Submit Necessary Requests & Plans for Approval in Accordance W/ Federal Regulations & NRC Guidelines ML20095D3491995-02-23023 February 1995 Comments on Introduction & Chapters 1,6,8 & 9 of Draft, Format & Content for Applications for Licensing of Nonpower Reactors, & Draft, Safety Analysis Rept Review Plan & Acceptance Criteria for Nonpower Reactors ML20078E2831995-01-19019 January 1995 Informs That Captain Ee Kearsley Msc,Usn Assumed Position of Acting Director of Armed Forces Radiobiology Research Inst, Replacing Captain Rl Bumgarner,Mc,Usn ML20078C1781994-10-11011 October 1994 Informs That Licensee Will Conduct Annual Emergency Drill on 941109 ML20070R6661994-05-19019 May 1994 Forwards Armed Forces Radiobiology Research Institute & Afrri Reactor Facility Emergency Plan. List of Changes Also Encl ML20067B0871994-02-22022 February 1994 Forwards Rev 2 to Physical Security Plan,Adding Section 4.a.(6) on Page 3 to Allow Visitors Such as Tours Into Controlled Access Area & Correcting Section 5.e(7) on Page 8 to State That UPS Located in RCA Not Caa.Encl Withheld ML20059F9501994-01-12012 January 1994 Approves Return of Slightly Contaminated Soil to Original Location Since Action Does Not Constitute Disposal of Radioactive Matl Per 10CFR20.302 ML20078C0971993-12-27027 December 1993 Submits Request for Approval of Slightly Radioactive Matl Disposal Procedures.Attachment Describes Site,Counting Data, Principal Exposure Pathways & Calculations of Estimated Dose to Maximally Exposed Individual ML20058F0531993-11-24024 November 1993 Informs Nrc,Certification of Responsibility for Reactor Indemnification & Decommissioning Costs Assumed by Defense Nuclear Agency,Ref ,Is Now Assumed by Uniformed Svcs Univ of Health Sciences ML20058F0961993-11-24024 November 1993 Informs Nrc,Certification of Responsibility for Decommissioning Costs Originally Assumed by Dna on Behalf of Dod,Ref ,Are Now Assumed by Uniformed Svcs Univ of Health Sciences Re License 19-08330-02 ML20058F1051993-11-24024 November 1993 Informs NRC of Certification of Responsibility for Decommission Costs Originally Assumed by Dna of Behalf of Dod Are Now Assumed by Uniformed Svcs Univ of Health Sciences Re License 19-08330-03 ML20059G7141993-11-0404 November 1993 Forwards Modified Reactor Operator Requalification Program for Afrri Triga Reactor Facility, Adding Lecture on Plant Protection Sys & Facility Interlocks on Page 2,section VA & New Section Detailing Recovery Program at Top of Page 4 ML20059C1011993-10-29029 October 1993 Informs That Licensee Completed Changes to Improve Emergency Plan W/O Prior Commission Approval as Authorized by 10CFR50.54(q).Changes Made & Approved Under 10CFR50.59. Revised Emergency Plan Encl ML20058N5511993-09-27027 September 1993 Responds to 930804 & 0919 Ltr Re Rev 1 to Afrri Triga Reactor Physical Security Plan.Changes Consistent W/ Provisions of 10CFR50.54(p) & Acceptable ML20056H5951993-09-0909 September 1993 Forwards Rev 1 to Armed Forces Radiobiology Research Inst Reactor Facility Physical Security Plan,Per 10CFR50.54(p)(2).Plan Withheld,Per 10CFR2.790 ML20057A7071993-09-0808 September 1993 Discusses Arrangements Made for Administration of Operator Licensing Exams at Facility During Wk of 940117.Addl Info Encl ML20056E3261993-08-17017 August 1993 Forwards Safety Insp Rept 50-170/93-01 on 930720-22.No Violations Noted ML20056E6231993-08-0606 August 1993 Requests Response to Encl Ref Matl Request for Ro/Sro Licensing Exams Scheduled for 940110.Info on Administration of Written Exams & Rules & Guidelines Also Encl ML20046C4011993-08-0606 August 1993 Requests to Change Approved Reactor Operator Requalification Program for Afrri Triga Reactor Facility,Per 10CFR55.59(c) ML20046B4171993-08-0404 August 1993 Forwards Changes to Reactor Facility Physical Security Plan, Per 10CFR50.54(p)(2).Plan Withheld,Per 10CFR2.790 ML20045H5481993-07-0707 July 1993 Clarifies Resolution of Previously Expressed Concern Re Funding of Major Reactor Facility Repair.Funding Route for Specific Large Budget Repair Items Currently in Use Will Continue to Be Available ML20044E3601993-03-11011 March 1993 Forwards Dod Points of Contact on DOE Reactor Licensing or Certification Matter,Per 930301 Telcon ML20115C6011992-09-30030 September 1992 Forwards Updated TS for Afrri Reactor Facility ML20113H8851992-07-29029 July 1992 Forwards Replacement Pages iii,12,15,25,35,36,37 & 38 to Make Changes Requested in 911227 TS Submittal,Per 920729 Conversation ML20082T9961991-09-10010 September 1991 Forwards Revised Proposed Changes to Tech Specs for Afrri Facility License R-84 ML20083B4221991-09-0909 September 1991 Requests Withdrawal of Requesting Amend to License R-84.Intent of Request Was to Indicate Change of Command from Gw Irving to Captian Rl Bumgarner on 910830 ML20024H2561991-05-17017 May 1991 Forwards Response to NRC 910501 Request for Addl Info on Proposed Tech Spec Changes for License R-84 ML20024H1371991-05-0202 May 1991 Concludes That Best Answer for Question B-18 of Ro/Sro Licensing Exam Administered at Affri on 910423 Is Response D ML20073D9101991-04-26026 April 1991 Submits Comments on Reactor Operator & Senior Reactor Operator Licensing Exams Administered on 910423.Listed Corrections to Written Exam Answer Key Requested ML20070H0621991-03-0505 March 1991 Forwards TR-90-01, Max Temp Calculation & Operational Characteristics of Fuel Follower Control Rods for Afrri Triga Reactor Facility, Per NRC 910212 Request for Addl Info ML20024H1411991-02-20020 February 1991 Submits Listed Ref Matls in Response to 910130 Request.Ref Matls Include,Sar,Ts,Emergency Plan,Operating Procedures,Ref Packaging Containing Various Ref Equations,Rod Curves & Technical Data.Operator Licensing Exam Encl ML20058H7971990-11-14014 November 1990 Forwards Request for Addl Info Re 900430 Application for Amend to License R-84 1999-07-26
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20155K2881998-10-13013 October 1998 Informs That Afrri Will Conduct Annual Emergency Drill on 981105.NRC Is Invited to Attend pre-drill Meeting & Drill. Meeting for Controllers & Evaluators Will Be Conducted on 981102 ML20134F2751996-10-23023 October 1996 Informs That SI Miller Appointed Acting Reactor Facility Director for Armed Forces Radiobiology Research Inst (Afrri) Replacing ML Moore,Effective 961015 ML20128P2561996-10-11011 October 1996 Extends Invitation to Observe Annual Emergency Drill & Attend Functions on 961104 ML20115J7911996-07-25025 July 1996 Forwards Analysis & Physical Security Plan Contain Dod Unclassified Controlled Nuclear Info.Encl Withheld,Per 10CFR2.790 ML20108A1111996-05-0202 May 1996 Forwards Corrected 1995 Annual Rept of Afrri Triga Reactor ML20096D2891995-12-0707 December 1995 Forwards Comments & Questions Re Review of Draft Application Format,Content Guidance,Review Plan & Acceptance Criteria for non-power Reactors ML20098A9821995-09-20020 September 1995 Informs That Licensee Will Conduct Annual Emergency Drill on 951115 ML20092A1231995-08-31031 August 1995 Informs That Dod Directed That Afrri Be Closed & Nuclear Reactor Be Shutdown in FY97.AFRRI Will Notify NRC & Submit Necessary Requests & Plans for Approval in Accordance W/ Federal Regulations & NRC Guidelines ML20095D3491995-02-23023 February 1995 Comments on Introduction & Chapters 1,6,8 & 9 of Draft, Format & Content for Applications for Licensing of Nonpower Reactors, & Draft, Safety Analysis Rept Review Plan & Acceptance Criteria for Nonpower Reactors ML20078E2831995-01-19019 January 1995 Informs That Captain Ee Kearsley Msc,Usn Assumed Position of Acting Director of Armed Forces Radiobiology Research Inst, Replacing Captain Rl Bumgarner,Mc,Usn ML20078C1781994-10-11011 October 1994 Informs That Licensee Will Conduct Annual Emergency Drill on 941109 ML20070R6661994-05-19019 May 1994 Forwards Armed Forces Radiobiology Research Institute & Afrri Reactor Facility Emergency Plan. List of Changes Also Encl ML20067B0871994-02-22022 February 1994 Forwards Rev 2 to Physical Security Plan,Adding Section 4.a.(6) on Page 3 to Allow Visitors Such as Tours Into Controlled Access Area & Correcting Section 5.e(7) on Page 8 to State That UPS Located in RCA Not Caa.Encl Withheld ML20078C0971993-12-27027 December 1993 Submits Request for Approval of Slightly Radioactive Matl Disposal Procedures.Attachment Describes Site,Counting Data, Principal Exposure Pathways & Calculations of Estimated Dose to Maximally Exposed Individual ML20058F1051993-11-24024 November 1993 Informs NRC of Certification of Responsibility for Decommission Costs Originally Assumed by Dna of Behalf of Dod Are Now Assumed by Uniformed Svcs Univ of Health Sciences Re License 19-08330-03 ML20058F0961993-11-24024 November 1993 Informs Nrc,Certification of Responsibility for Decommissioning Costs Originally Assumed by Dna on Behalf of Dod,Ref ,Are Now Assumed by Uniformed Svcs Univ of Health Sciences Re License 19-08330-02 ML20058F0531993-11-24024 November 1993 Informs Nrc,Certification of Responsibility for Reactor Indemnification & Decommissioning Costs Assumed by Defense Nuclear Agency,Ref ,Is Now Assumed by Uniformed Svcs Univ of Health Sciences ML20059G7141993-11-0404 November 1993 Forwards Modified Reactor Operator Requalification Program for Afrri Triga Reactor Facility, Adding Lecture on Plant Protection Sys & Facility Interlocks on Page 2,section VA & New Section Detailing Recovery Program at Top of Page 4 ML20059C1011993-10-29029 October 1993 Informs That Licensee Completed Changes to Improve Emergency Plan W/O Prior Commission Approval as Authorized by 10CFR50.54(q).Changes Made & Approved Under 10CFR50.59. Revised Emergency Plan Encl ML20056H5951993-09-0909 September 1993 Forwards Rev 1 to Armed Forces Radiobiology Research Inst Reactor Facility Physical Security Plan,Per 10CFR50.54(p)(2).Plan Withheld,Per 10CFR2.790 ML20046C4011993-08-0606 August 1993 Requests to Change Approved Reactor Operator Requalification Program for Afrri Triga Reactor Facility,Per 10CFR55.59(c) ML20046B4171993-08-0404 August 1993 Forwards Changes to Reactor Facility Physical Security Plan, Per 10CFR50.54(p)(2).Plan Withheld,Per 10CFR2.790 ML20045H5481993-07-0707 July 1993 Clarifies Resolution of Previously Expressed Concern Re Funding of Major Reactor Facility Repair.Funding Route for Specific Large Budget Repair Items Currently in Use Will Continue to Be Available ML20044E3601993-03-11011 March 1993 Forwards Dod Points of Contact on DOE Reactor Licensing or Certification Matter,Per 930301 Telcon ML20115C6011992-09-30030 September 1992 Forwards Updated TS for Afrri Reactor Facility ML20113H8851992-07-29029 July 1992 Forwards Replacement Pages iii,12,15,25,35,36,37 & 38 to Make Changes Requested in 911227 TS Submittal,Per 920729 Conversation ML20082T9961991-09-10010 September 1991 Forwards Revised Proposed Changes to Tech Specs for Afrri Facility License R-84 ML20083B4221991-09-0909 September 1991 Requests Withdrawal of Requesting Amend to License R-84.Intent of Request Was to Indicate Change of Command from Gw Irving to Captian Rl Bumgarner on 910830 ML20024H2561991-05-17017 May 1991 Forwards Response to NRC 910501 Request for Addl Info on Proposed Tech Spec Changes for License R-84 ML20024H1371991-05-0202 May 1991 Concludes That Best Answer for Question B-18 of Ro/Sro Licensing Exam Administered at Affri on 910423 Is Response D ML20073D9101991-04-26026 April 1991 Submits Comments on Reactor Operator & Senior Reactor Operator Licensing Exams Administered on 910423.Listed Corrections to Written Exam Answer Key Requested ML20070H0621991-03-0505 March 1991 Forwards TR-90-01, Max Temp Calculation & Operational Characteristics of Fuel Follower Control Rods for Afrri Triga Reactor Facility, Per NRC 910212 Request for Addl Info ML20024H1411991-02-20020 February 1991 Submits Listed Ref Matls in Response to 910130 Request.Ref Matls Include,Sar,Ts,Emergency Plan,Operating Procedures,Ref Packaging Containing Various Ref Equations,Rod Curves & Technical Data.Operator Licensing Exam Encl ML20055H2141990-07-23023 July 1990 Forwards Analysis of Decommissioning Costs for Afrri Triga Reactor Facility. Method of Decommissioning Selected for Planning Purposes Is Decon Alternative.Defense Nuclear Agency Exempt from Fees,Per 10CFR170.11 ML20055G6451990-07-11011 July 1990 Forwards Replacement Pages to 900612 Physical Security Plan. W/O Encl ML20063P9211990-06-26026 June 1990 Forwards Replacement Pages 3 & 7 to Physical Security Plans, 900401,interim,Summer 1990. Guard Changed to Watchman on Each Page ML20044A4041990-06-20020 June 1990 Forwards Reformatted & Revised Emergency Plan for Armed Forces Radiobiology Research Inst (Afrri) & Afrri Reactor Facility, Incorporating NRC 900522 Comments & Afrri Emergency Response Guidebook. ML20043H0601990-06-12012 June 1990 Forwards Physical Security Plans.Paragraph 5.f of Interim Plan Amended to Reflect Fact That Only Balanced Magnetic Contacts on Internal Facility Doors Bypassed During Normal Duty Hours.W/O Encl ML20042G6551990-05-10010 May 1990 Forwards Physical Security Plan Labeled Summer 1990. Plan Contains Changes Necessitated Because of Installation on New Instrument Detection Sys to Be Implemented at Completion of Installation in Summer.Encl Withheld (Ref 10CFR2.790) ML20042F0401990-05-0303 May 1990 Forwards Comparison & Correlation of Proposed & Current Emergency Plans, Supplementing Licensee 900410 Submittal ML20042E9541990-05-0101 May 1990 Forwards Changes to Physical Security Plan,Reflecting Upgrade of Security Intrusion Detection Sys,For Review.Encl Withheld (Ref 10CFR2.790) ML20006F1861990-02-22022 February 1990 Forwards LERs for Consideration,Per 10CFR50.73 ML20248C1841989-09-21021 September 1989 Forwards Response to Request for Addl Info Re Armed Forces Radiobiology Research Institute Proposed Reactor Operator Requalification Program ML20247P2851989-09-18018 September 1989 Responds to Transmitting Order Imposing Civil Monetary Penalty in Amount of $2,500.Fee Paid ML20246D1801989-06-30030 June 1989 Forwards Emergency Plan for Triga Reactor Facility & Current Inservice Support Agreement ML20244D1721989-06-0505 June 1989 Forwards Proposed Reactor Operator Requalification Program for Armed Forces Radiology Research Inst & Triga Reactor Facility,For Review & Approval ML20246L6301989-05-0404 May 1989 Responds to Re Violations Noted in Insp Rept 50-170/88-04.Corrective Actions:Addl Specific Written Safety Analyses Immediately Performed on Both Voltmeter & Cerenkov Detector in Dec 1988.Proprietary Encl Withheld ML20246G3491989-05-0404 May 1989 Responds to NRC 890322 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $2,500.Legal Reason Why Penalty Should Not Be Imposed Discussed ML20245D0541989-04-20020 April 1989 Ack That Request for Extension Re 890322 Notice of Violation & Proposed Imposition of Penalty Granted on 890420.New Submission Date Will Be 890505 ML20245G8501989-03-29029 March 1989 Forwards Armed Forces Radiobiology Research Institute Triga MARK-F Reactor Facility Annual Rept 1988. Revised Pages 3-39,3-43,4-22,4-23 & 4-24 of SAR Also Encl 1998-10-13
[Table view] Category:OTHER U.S. GOVERNMENT AGENCY/DEPARTMENT TO NRC
MONTHYEARML20055H2141990-07-23023 July 1990 Forwards Analysis of Decommissioning Costs for Afrri Triga Reactor Facility. Method of Decommissioning Selected for Planning Purposes Is Decon Alternative.Defense Nuclear Agency Exempt from Fees,Per 10CFR170.11 ML20248C1841989-09-21021 September 1989 Forwards Response to Request for Addl Info Re Armed Forces Radiobiology Research Institute Proposed Reactor Operator Requalification Program ML20247P2851989-09-18018 September 1989 Responds to Transmitting Order Imposing Civil Monetary Penalty in Amount of $2,500.Fee Paid ML20244D1721989-06-0505 June 1989 Forwards Proposed Reactor Operator Requalification Program for Armed Forces Radiology Research Inst & Triga Reactor Facility,For Review & Approval ML20245D0541989-04-20020 April 1989 Ack That Request for Extension Re 890322 Notice of Violation & Proposed Imposition of Penalty Granted on 890420.New Submission Date Will Be 890505 ML20245G8501989-03-29029 March 1989 Forwards Armed Forces Radiobiology Research Institute Triga MARK-F Reactor Facility Annual Rept 1988. Revised Pages 3-39,3-43,4-22,4-23 & 4-24 of SAR Also Encl ML20246L4951989-03-0101 March 1989 Provides follow-up to & 890213 Site Visit, Addressing Reasons for Temporary Suspension of Operations in Reactor Facility & Basis for Intention to Resume Operations ML20244B6341989-02-14014 February 1989 Responds to NRC Re Rationale for Suspending Reactor Experimental Operations.Operators Reviewed Procedures & Identified Areas for Change & Recommended Improvements ML20237H2861987-08-0707 August 1987 Responds to NRC Re Violation Noted in Insp Rept 50-170/87-02.Corrective Actions:All Specified Waste Drums Properly Labeled Per 10CFR20.203(f) & Health Physics Procedure 6-2 Accordingly Revised.Procedure Encl ML20205N9611986-05-0707 May 1986 Forwards Changes to Physical Security Plan.Changes Withheld (Ref 10CFR2.790) ML20197H2701986-04-29029 April 1986 Responds to NRC Request Noted in Exam Rept 50-170/86-01 on 860106 to More Accurately Describe Reactor Safety Svcs & Fire Prevention Conditions.All Fire Extinguishers Checked & Housekeeping Insps Will Be Performed More Frequently ML20116M9501985-04-30030 April 1985 Forwards Reissue 2 to Armed Forces Radiobiology Research Inst Physical Security Plan.Plan Withheld (Ref 10CFR2.790) ML20108D1641985-03-0505 March 1985 Forwards Revised Armed Forces Radiobiology Research Inst Emergency Plan.Changes Reflect Correct Alarm Points as Operationally Set,Currently & Historically,On Stack Gas Monitor ML20092G5141984-06-19019 June 1984 Forwards Proposed Tech Specs Developed Per Reg Guide 2.2 & Proposed Std ANS-15.1.Requests Review of Tech Specs for Inclusion in License R-84 ML20079K6391984-01-20020 January 1984 Informs That Effective 840116,Captain CR Williamson,En,Usa, Assumed Duties of Physicist in Charge of Armed Forces Radiobiology Research Inst Reactor Facility.Appointment Order Encl ML20078L5901983-10-11011 October 1983 Submits Public Version of Notification That Oct 1982 Emergency Plan Implemented & Placed Into Effect on 831007 ML20069G3771983-03-24024 March 1983 Informs of Upcoming Planned Actions.Major Renovation of Mechanical & Electrical Sys & Replacement of Cooling Tower Among Activities Planned for FY84-85 ML20079L9811983-02-18018 February 1983 Responds to 821029 Request for Brief Summary of Events Which Transpired During 821029 Site Visit ML20028B2831982-11-24024 November 1982 Forwards Licensee Emergency Plan.Certificate of Svc Encl. Related Correspondence ML20028A6921982-11-0202 November 1982 Forwards Public Version of Emergency Plan ML20027B5361982-09-17017 September 1982 Advises of Plans for Major Renovation of Ventilation & Air Handling Sys in Approx 1.5 Yrs.Portions of Renovations Require Amend to Existing Tech Specs.Requests Exemption from Potential Tech Spec Amend ML20053E8331982-06-0909 June 1982 Forwards Revision 1 to Physical Security Plan.Revision Withheld (Ref 10CFR2.790) ML20049H7031982-02-24024 February 1982 Notifies That on 820217 Core Inspection After Pulse Operation Revealed Final Elements 3376-E & 3389-E in-core Lattice Positions F-9 & F-27,respectively,were Cocked.Cause Undetermined.Fuel Elements Returned to Lattice Positions ML20009B0041981-07-19019 July 1981 Forwards Environ Rept for Armed Forces Radiobiology Research Inst Triga Reactor Facility Under License R-84.Rept Submitted for Review & Incorporation Into Docket as Part of Research Reactor Relicensing Effort ML20009B0201981-07-10010 July 1981 Forwards Updated SAR for Review.Rept Supersedes Revised Final Safeguards Rept & All Subsequent Amends ML20004B4101981-05-14014 May 1981 Informs That No EIS Has Been Prepared for Armed Forces Radiobiology Research Institute Routine Operations ML19347F5701981-05-12012 May 1981 Forwards Info Re Security Plan,In Response to 810508 Inquiry.Info Withheld (Ref 10CFR2.790) ML19350B7991981-03-12012 March 1981 Advises That Notice of Appearance Re Triga Research Reactor Inadvertently Not Filed.Notice & Certificate of Svc Encl ML19345C8631980-12-0303 December 1980 Forwards Annual Operating Rept for Yr Ending 801001 & Safety Analysis of FSAR ML19345C8241980-12-0303 December 1980 Requests Correction of Typographical Error in Fr Notice Re Application for Renewal of Amended OL ML19338E8461980-10-0303 October 1980 Forwards Safety Analysis of FSAR for Afrri Triga Facility ML19337A6361980-09-26026 September 1980 Forwards Eia Data for Renewal of License R-84 ML19337A5201980-09-26026 September 1980 Forwards Emergency Plan ML19338D0421980-09-17017 September 1980 Forwards Proposed Reactor Operator Requalification Program for Review Per NUREG-0094 ML19331D6811980-09-0101 September 1980 Forwards Proposed Amend 17 to Tech Specs,Specifying Safety Limits & Limiting Conditions,Surveillance Requirements, Design Features & Administrative Requirements.Replaces Previous Document in Docket File ML19309H9321980-05-16016 May 1980 Forwards Physical Security Plan for AFFRI-TRIGA. Plan Withheld (Ref 10CFR2.790) ML19322E5811980-03-25025 March 1980 Forwards RO Re Illumination of Scram Indicators on Reactor Control Console ML19209D1471979-10-16016 October 1979 Forwards Amend 10 to Indemnity Agreement D-2,in Response to NRC 791010 Ltr ML19209C8781979-10-15015 October 1979 Forwards Proposed Changes to Tech Specs for License R-84 ML19207B3321979-08-15015 August 1979 Forwards Rept of Reactor Exhaust Sys Malfunction on 790809: Electrical Fire in EF-1 Cubicle of Motor Control Ctr. Caused by Power Surge Due to Failed Transformer.Motor Control Contact Replaced ML19242C4701979-08-0707 August 1979 Submits Info Requested in 790730 Ltr Re License R-84, Covering Total Inventory of U-235,fuel Loading in Core,Fuel in Storage,Ceiling for Possession & Exempted Fuel ML19247B6111979-08-0707 August 1979 Responds to 790720 Request for Resubmittal of Proposed Tech Specs.Notarized Request Was Missing Item.Signature of Military Officer Is Considered Notarized Sworn Statement ML19242C4531979-08-0101 August 1979 Forwards Deficiency Rept Re Malfunction of Fuel Element Temp Sensing Circuit ML19242C4911979-07-31031 July 1979 Forwards Amended Deficiency Rept Re Malfunction of Pool Water Level Sensing Switch,Submitted by Defense Nuclear Agency ML19241A7471979-07-0202 July 1979 Forwards Amend 17 to Tech Specs for License R-84 ML19305A0361978-11-28028 November 1978 Responds to NRC 781107 Ltr Re Deviation Noted in Insp Rept 50-170/78-04.Corrective Actions:Reactor Staffing Corrected, Fuel Assembly Displacements Will Be Reported,Operator Requalification Program Instituted & Reactor Room Sealed 1990-07-23
[Table view] |
Text
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DEFENSE NUCLEAR AGENCY
, .. ARMEC FORCES RADICBIOLOGY RESEARCH INSTITUTE B ETHESD A, M A RYL AND 20014
)**. jh 000^8 DID g og ;;0 Director Division of Reactor Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Sir:
The enclosed Environmental Impact Appraisal Data is submitted in accordance with 10 CFR Par 50.51 for USNRC Research Reactor License No. R-84, Docket No. 50-170. This information incorporates all known environmental aspects related to our facility and is submitted in accordance with USNRC guidance for licensing renewal.
Sincerely, O &
1 Enclosur,e PAUL E. TYLER as stated Captain, MC, USN Director c:
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s' ARMED FORCES RADI0 BIOLOGY RESEARCH INSTITUTE TRIGA MARK-F REACTOR ENVIRONMENTAL IMPACT APPRAISAI, DATA 1
r I. INTRODUCTION This document is provided as information, reference 10 CFR Part 51.50(c)(3). The data herein deals with those features and operating characteristics of the Armed Forces Radiobiology Research Institute (AFRRI)
TRIGA Mark F Research Reactor as related to the local environment. The AFRRI TRIGA Mark F reactor is used for bionadical research, irradiations of electrical components and radioisotope production -in support of the Institute's radiobiology research mission. Operation of the facility will generally not exceed a five (5) day week, eight (8) hour day and most operations will occur during daylight hours. The AFRRI reactor will normally I
I operate at steady state power levels not to exceed 1 MW (t,hermal) and in a pulsing mode with step reactivity insertions up to a maximum of 2.8% AK/K.
! II. SITE AFRRI, and the AFRRI TRIGA reactor is located within the confines of the National Naval Medical Center (NNMC), Bethesda, Maryland, which in turn is located approximately three miles north of Washington, D.C. The NNMC is located within an approximate area that is bounded on the north by the Beltway (I-495), on the east by Connecticut Avenue, on the south by Jones Bridge Road, and on the west by Wisconsin Avenue. AFRRI is located on the south side of the NNMC in Building 42.
III. AFRRI FACILITY DESCRIPTION The AFRRI complex consists of five phases or buildings which are designed to appear as one building or unit. The principle radiation facilities housed within AFRRI are the TRIGA Reactor Facility, the LINEAR Accelerator (LINAC) Facility, the Cobalt-60 Facility, and the Standards Laboratory, which contains a Theratron and a X-ray unit. In addition to these facilities there are included within AFRRI a Computer Center, Research !
Laboratories, a Hot Cell, Radiochemistry Laboratory, an Animal Facility, j related support areas, and office spaces. The AFRRI cc aplex consists of four I (4) separate floor levels. The first and fourth levels are the lowest and the highest levels, respectively. l IV. GENERAL DESCRIPTION ,
l A. Reactor Facility The TRIGA Reactor Facility occupies various areas on the first level, the second level, and the third level of one building of the AFRRI facility. On the first level, the facility consists of Exposure Room 1 (ERl), Exposure Room 2 (ER2), Prep Area, Room 1120, and Room 1121. The heat exchanger for the reactor coolant systems is located in Room 1121. On the second level, the Facility consists of the Hot Cell, the Radiochemistry I
Laboratory, which contains portions of the Pneumatic Transfer Systems, and
> the Equipment Room which contains reactor coolant pumps, demineralizers, and the absolute filters for the reactor heating and ventilating system. On the
- third level, , the Facility consists of the Reactor Room which contains the ,
1 l
r 1
, . _ ,, - , , _ . - , - - . . . , , , - _ . , _ . , . , . .._-,_m. - - . . . . - - -
d movable reactor core and control rod drive system, the Reactor Control Room which contains the reactor control console and the associated nuclear instrumentation, the Maintenance Shop, the Equipment Room containing the reactor air system and portions of the heating and ventilating system, and offices.
There are no exterior conduits, pipelines, electrical or mechanical structures or transmission lines attached to the reactor facility other than utility service facilities which are similar to those required for the rest of the AFRRI facility.
The AFRRI reactor is a TRIGA-Mark F that was designed and manufactured by General Atomic Company and installed at AFRRI in 1962. The thermal reactor has a movable core and is designed to operate up to one megawatt of thermal power in the steady state mode and up to 2500 megawatts in the pulse mode (10 milli-seconds FWHM). The cylindrical core consists of 87 stainless steel clad fuel elements, enriched to 20% in uranium-235, and four aluminum clad borated graphite control rods. The core moderator consists of zirconium hydride and water, and the reactor core is reflected on the top and bottom by graphite, and at the periphery by water. The cylindrical fbel elements are positioned in the core in five rings. The rings are designed as B, C, D. E, and F, and contain 6, 12, 15, 24, and 30 fuel elements, respectively. The four control rods are located in the center core position (1) and the D-ring (3).
The reactor core is positioned in the reactor tank under approximately 16 feet of demineralised water. The reactor core is cooled by the natural convection of the water in the reactor tank. The water, in turn is pumped from the tank by the primary system coolant pump, passed through a heat exchanger and demineralizer, and then retured to the tank. The ;
secondary coolant system pumps industrial raw water from the cooling tower l basin, through the heat exchanger, and returned to the cooling tower where the water is cooled by being passed down through the tower to the basin.
There are four principle experimental facilities associated with the AFRRI-TRIGA reactor and these are Exposure Room 1, Exposure Room 2, the I Pneumatic Transfer Systems, and the In-Core Experiment Tube (CET).
Experiments can also be placed in the reactor tank, but this method of irradiations is not normally used.
B. Reactor Tank The AFRRI-TRIGA reactor tank is constructed of aluminum and is embedded in concrete. Aluminum was selected as the tank material to improve long term reliability and to minimize problems of corrosion and neutron activation. The reactor tank, which is clover-leaf in shape, is approximately 19-1/2 feet deep with a diameter across the tank lobes of approximately 13 rect. The basic wall thickness of the tank is 3/8-inch, I except in two clover-leaf projections that extend into the north and south .
exposure rooms, and this wall thickness is 1/4-inch. The tank bottom and l projection shelf thickness is 1/2-inch.
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In addition to containing the reactor core-support structure, reactor core, and tank shield doors, the reactor tank contains approximately 15,000 gallons of demineralized water which serves both as the primary reactor coolant, and as a radiation shield.
C. Shield Doors Two radiation shield doors are located in the reactor pool and divide the reactor tank into two equal sections. These interlocking doors are constructed of 1/2-inch aluminum plate and 8-inch aluminum Z-sections.
The doors are approximately 19 inches thick, 5 feet high and 6 feet wide.
Each water-tight door is filled with approximately 18,000 pounds of No. 6 lead shot and approximately 90 gallons of transformer oil to provide cooling for the lead shot. The gap between the shield doors is stepped to prevent radiation streaming through the door. Each door is supported on a low-friction steel thrust bearing mounted at the bottom of the tank.
The shield doors may be rotated 90 to permit the core support carriage to move from one end of the reactor tank to the other. Rotation of the doors is accomplished using a 1/6 HP drive motor located in a small pit at the reactor top. Power for door rotation is transmitted through one 200:1 and two 10:1 reduction gears. Each shield door is connected to a reduction gear, mounted on the side of the carriage track, by a vertical shaft extending from the top of the door to the reduction gear. Operating controls for the doors are located at the control console. Approximately 3 minutes are required to fully open or close the lead shield doors.
Limit switches are used to indicate the fully opened or closed positions of the shield doors. These limit switches, located on top of the reduction gear above each door, are part of an interlock system which prevents movement of the core support carriage and denies power to the control rod magnets unless the shield doors are fully opened or fully closed.
D. Carriage and Core Support Structures A four-wheeled carriage, traveling on two tracks that span the reactor tank, is used to move the reactor core from one operating position within the tank to another. In addition to supporting the core, the carriage also serves as a support for four control rod drives, a diffuser system, and various electronic control devices.
The carriage consists of a structural steel framework enclosed with removable aluminum covers. The carriage is approximately 64 inches square by 24 inches high. Four control rod drives are attached to a mounting plate elevated above the carriage. Two wheels on one side of the carriage are grooved to match a double beveled track. Engagement of the wheels and track restrains any lateral displacement of the carriage. The two wheels on the opposite side of the carriage are flat faced and roll on a flat track.
The carriage is propelled using a two-speed electric motor, and a rack and pinion gear system. The gear rack is attached to one side of the double beveled track. The carriage is driven at two speeds,1-1/2 feet per 3
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minute, and 2-1/4 feet per minute. Low speed is used during the first and last foot of travel as the carriage moves from one extreme limit of travel to the other. The intervening distance is trdversed at the high speed.
Microswitches are employed to automatically change the drive motor's speed depending on the carriage's position on the track. Microswitches are also used to stop the carriage drive motor when the carriage has reached either of l its two extreme limits of travel. These switches are part of a facility interlock system. As a safety measure, mechanical stops are mounted at both ends of the carriage track to prevent carriage overtravel at the extreme limits. The carriage position is read on a position indicator at the reactor console. Travel time for the carriage from one extreme position in the reactor tank to the other is approximately 5 minutes.
Power, control circuit wiring, and compressed air are supplied to the carriage through a trail cable and flexible hose. The cable and hose are attached to the carriage control rod drive motor enclosure. The trail cable and hose are supported by a wall-mounted swinging boom.
The core support structure consists of an aluminum cylinder approximately 36 inches in diameter and 12 feet high, and an aluminum adapter 5 feet high and 19-1/2 inches in diameter. Both the cylinder and adapter are !
formed from 5/16-inch thick aluminum plate. The support structure connects at its top to the carriage, and at its bottom to the adapter. A vertical slot 16-inches wi.de extends the full height of the aluminum cylinder. This slot provid a access to the inside of the support structure permitting the installation and removal of fuel elements from the core without having to raise th( above the water-level.
E. Grid Plates AFRRI-TRIGA fuel elements and other in-core assemblies are spaced and supported in the core by an upper grid and a lower grid plate.
The upper grid plate is 18-3/4 inches in diameter, and contains ninety-one 1-1/2 inch diameter holes. Four of these holes receive the guide tubes for the three standard control rods and the transient rod. The three standard control rods are located ~.n positions Dl, D7, and D13 The transient rod is located in position A1. The remaining 87 holes accept in-core elements and assemblies. These holes, or grid spaces, are located in concentric rings. Each ring is designated by the letters (A through F)
I radially from the center. Spaces in each ring are identified numerically in a clockwise direction from a reference radius which points in the direction of the North Exposure Room ( ERl). One-quarter inch diameter holes in between the grid spaces will be used for in-core experiments and dosimetry.
The lower grid plate is 16-5/8 inches in diameter and is gold anodized to reduce grid plate wear and to aid light reflection in the core.
The lower grid plate contain eighty-seven 1/4-inch diameter holes to accept the fuel element end fixtures, four 1-1/2-inch diameter holes to accept the control rod guide tubes, and thirty 5/8-inch diameter holes to permit flow of l
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cooling water. Both grid plates are made from 3/4-inch thick aluminum plates. Each plate is bolted to the shroud by four captive screws. Correct positioning of the grid plates is assured by two positioning dowels on the grid plate support pads.
F. Core The core is enclosed in the aluminum shroud attached to the bottom of the adapter. The core forms a right circular cylinder consisting of a compact array of 87 cylindriical fuel-moderator elements and four control rods, all positioned vertically between two grid plates. The core is positioned within the shroud such that its horizontal center line is approximately 29 inches above the bottom of the reactor tank. Serial numbers are used to identify individual fuel elements and control rods.
G. Reactor Water Systems The water coolant systems for the AFRRI reactor consists of a primary cooling system, a secondary cooling system (with 1 MW heat exchanger and cooling tower), a demineralized water make-up system for the primary cooling system, tsnd a N-16 diffuser system.
H. Reactor Ventilation System The Reactor Room contains approximately 1800 square feet of floor space, has a ceiling height of 18 feet, and a volume of 32,400 cubic feet.
The doors and hatches leading to the Reactor Room are sealed with compressible rubber garlute to enhance confinement of the Reactor Room air when the dampers are closed. A system of double doors serves as an air lock for entry and exit of the Reactor Room. The air enters primarily through two air supply fans , is circulated then exhausted. It passes through both roughing filter and absolute filter banks before being discharged out the stack which extends approximately 35 feet above the roof of the reactor building.
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V. ENVIRONMENTAL EFFECTS OF FACILITY OPERATION I A. Thermal Effluents The AFRRI Reactor has a maximum thermal power output of 1 MW in the steady state mode. The environmental effects of thermal effluents of this order of magnitude are considered to be negligible. During prolonged ;
operations at the upper range of power levels the secondary cooling system is 1 activated and waste heat is rejected to the atmosphere through the facility's i cooling tower. The efficiency of this cc,oling tower is determined by the temperature and humidity of the outside ambient air. !
l B. Radioactive Effluents Enclosure 1 summarizes the gaseous, liquid and solid radioactive wastes for the AFRRI facility, which are considered to have minimal effect on ,
the surrounding environment. I 5
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- l C. Environmental Effects of Accidents Accidents ranging from failure of experiments to the largest core damage and fission product release considered possible result in doses of only a small fraction of 10 CFR Fart 100 guidelines and are considered negligible with respect to the environment.
VI. UNAVOIDABLE EFFECTS OF FACILITY CONSTRUCTION AND OPERATION The unavoidable effects of construction and operation involves the materials used in construction that cannot be recovered and the fissionable material used in the reactor. No adverse impact on the environment is expected from either of the unavoidable effects.
VII. ALTERNATIVES TO CONSTRUCTION AND OPERATION OF THE FACILITY There are no suitable or more economical alternatives which can accomplish the diversity of research objectives at this facility. These objectives include radiobiology research, radioisotope production, neutron accivation and irradiation of electronic equipment.
VIII. LONG TERM EFFECTS OF FACILITY CONSTRUCTION AND OPERATION The long-term effects of a research facility such as the AFRRI are considered to be beneficial as a result of the contribution to scientific and medical knowledge. This is especially true in view of the relatively low capital cost involved and the minimal impact on the envircament associated with such facilities.
IX. COST AND BENEFITS OF FACILITY AND ALTERNATIVES The cost for a facility such as the AFRRI Reactor Facility is in the order of four (4) million dollars with very little environmental impact. The benefits of this facility are in the field of biomedical research in support of our national defense posture and provide additional data and findings in the scientific and medical fields for international use. Some of the activities conducted with this facility could be accomplished using particle accelerators or radioactive sources, however, these alternatives are more costly, less efficient and cannot totally replace the existing capabilities associated with this facility. There is no reasonable alternative to the AFRRI Reactor for conducting the broad spectrum of research previously mentioned.
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i . DNOPOOITION
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. i .uitrace on onrect sv-oot susa cT
- SAF Sumary: Reactor Environmental Data THRU: SAHP "C" SAF pm 24 Sep 80 cari jT0: SSD Dr arras /bsm/50411
- 1. Sumary of Gaseous Radioeffluent,1 Jan 71 to 30 Jun 80:
- a. Total Release - Radionuclide(s):
Ar-41 N-13,0-15 I-125 Xe-133 Source of activity: Reactor LINAC Other Other
, Released activity (mC1): 1971 26900 T41T6 0 0
,' 1972 11040 3760 <1 120 1973 11310 3850 0 1380 1974 16690 20740 0 40 1975 7190 20180 <1 340 1976 2750 1040 0 2100 l 1977 2370 640 <1 1590 1
1978 9410 15840 <1 340 3 " "
1979 18930 0 <1 1280 l " "
1980( y) 1940 5 <1 260 i
i b. Dose Assessment Notes:
I
{ (1) Environmental doses from Xe-133 and I-125 are less than 10% of the doses lproceduresnotreactoroperations,andarenotevaluatedindetail.from Ar-41, N-13 and For example, the 0-1
! greatest single annual releases and the corresporiding calculated environmental i concentrations are (from HPP 2-5, Xmax 7 0.12 Q/U oyez ~ 3E-4Q):
(a) I-125, 342 pCi, 3.3 E-15 C1/m3, (4E-5 x MPC).
j (b) Xe-133, 2100 mC1, 2.0 E-11 Ci/m3 (IE-4 x MPC).
I (2) Doses from Ar-41, N-13 and 0-15 are assessed by the concentric cyiinder j set model, as given in HPP 2-5; this is a departure from the unrealistic semi-infinite cloud model used in previous years. Highest average (annual) unrestricted area exposure rates corresponding to given releases are:
I Radionuclide(s): Ar-41 N-13,0-15 Xe-133 Average mR/h, with Q=1 C1/s*: 4.1 4.3 0.5
Enclosure 1 DAi47.,2496
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SAF 24 Sep 80
SUBJECT:
Sumary: Reactor Environmental Data
- c. Based upon the above the dose assessment for the above annual releases is:
Year: 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 Ar-41 Ci/s: 8.5E-7 3.5E-7 3.6E-7 5.3E-7 2.3E-7 8.7E-8 7.5E-8 3.0E-7 6.0E-7 1.2E-7 mR/h: 3.5E-6 1.4E-6 1.5E-6 2.2E-6 9.3E-7 3.6E-7 3.1E-7 1.2E-6 2.5E-6 5.1E-7 mrem: 0.031 0.012 0.013 0.019 0.008 0.003 0.003 0.011 0.022 .002 N,0 Ci/s: 4.6E-8 1.2E-7 1.2 E-7 6.5E-7 6.4E-7 3.3E-8 2.0E-8 5.0E-7 0
" 1.6E-1@
mR/h: 2.0E-7 5.2E-7 5.2E-7 2.8E-6 2.8E-6 1.4 E-7 8.6E-8 2.2E-6 0 7E-mrem: 0.002 0.005 0.005 0.024 0.024 0.002 0.001 0.019 0 10~j0
- 2. Environmental Film Dosimeters: 1971-1980.
- a. This is a summary of environmental dosimetry data representing possible reactor-produced radioeffluent doses to the environment. Statistical analyses of these results show no correlation to AFRRI operations or meteorological conditions. These results are judged to reflect normal variation in ambient background and the statistical uncertainty of the dosimetry.
- b. Sumary (all doses in millirem):
Year Envir. Dosimeter Avg.* Highest Dosimeter Reading
~1973 1.7 12 1974 2.2 10 1975 2.4 14 1976 0.3 13 1977 3.3 20 1978 1.5 30 1979 5.1 9 1980(y) -2.5 All are net readings, with background station doses (located miles from AFRRI) subtracted. Individual dosimeter readings have 2a uncertainties of 8 millirem.
- 3. Liquid Effluent: 1971-1980.
- a. During this period there were no measurable releases of radioactive liquids j
from the reactor; in fact there were no releases of water to the environment from the reactor, in any measurable quantities. J
- b. Radioactivity was released to the sanitary sewerage system, from the AFRRI waste tanks, but the amount was well below all aoplicable limits of 10 CFR 20. The sources of liquid radioeffluent are-l (1) Radionuclide laboratory low-level liquid waste, and l (2) Animal care facility excreta, including those injected with radionuclides due to biomedical experiments. l 2
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SAF 24 Sep 80
SUBJECT:
Summary: Reactor Environmental Data .
- 4. Solid Waste Disposal: 1971-1980.
- a. With the exceptions noted below, there are no solid waste shipments of reactor-produced materials.
- b. Low-level solid waste from reactor operations, including possible contaminated paper, gloves, disposable smocks, and animal bedding constitute a volume of 1-5 55 gallon drums (depending on workload), with less than 1 mci per year, essentially all short-lived radionuclides; e.g., Na-24, Mn-56, Cu-64.
- c. Reactor resins, and cuno filters are changed at intervals of 6 to 18 months.
These are disposed of as solid waste. Typical activities observed in these materials in the past have been:
Cr-51 up to 7.6 pCi, Co-60 " "
8.1 "
Co-58 "
" 25.7 "
X-40 7.6 "
Mn-56 " "
1.8 "
Zn-65 4.1 ,
Na-24 " "
1.4 "
, and smaller amounts of other radionuclides
- 5. Environmental Sampling: 1971-1980.
- a. Quarterly environmental samples are taken of water, soil and vegetation. All l sample results have been below action levels specified in Health Physics Procedure 2-5 and in fact generally are indistinguishable from normal environmental background activity levels.
. ~r; LE TER A. SLABACK, Jr.
Head, Radiation Safety Department cf-DNA/BA0 l RRFSC j l
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