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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20210Q7171999-08-0202 August 1999 Provides Rept of Violation of Surveillance TS TS4.2.4, Reactor Instrumentation Sys. Calorimetric Calibr of Reactor Power Instrument Channels Was Not Done in Necessary Annual Period.No Immediate Corrective Actions Necessary ML20206K7271999-05-0606 May 1999 Informs That MG Krause Will Be Reactor Supervisor & Assume Daily Supervisory Duties Previously Performed by T Bauer. T Bauer Will Continue as Assistant Director Concentrating Efforts on Extended Time Activities ML20206B1071999-04-21021 April 1999 Informs That Activities at Nuclear Engineering Teaching Lab, Continuing to Improve.Nuclear & Radiation Engineering Program Continues to Have Support from All Levels of Univ Administration - Dept,College & Institutional ML20205J2571999-03-26026 March 1999 Forwards Copy of Results of Operator Initial Exam Conducted at Univ of Texas at Austin on 990315-16.Without Encl ML20207B4341999-03-0202 March 1999 Forwards Insp Rept 50-602/98-201 on 981207-11.No Violations Noted ML20198S3041999-01-0606 January 1999 Discusses Telcon Between W Eresian & T Bauer Re Exam at Univ of Texas.Exam Scheduled During Month of Feb 1999. Rules & Guidelines That Will Be in Effect During Administration of Written Exam Encl ML20248F4661998-05-22022 May 1998 Notifies NRC That Licensee Intend to Reconstitute Committee Immediately,Rather than Wait Until Next Academic Yr ML20217M2201998-04-28028 April 1998 Forwards Replacement Page 3-13 to Univ of Tx 1997 Annual Rept.Corrections to Page Consists of Several Transcription Errors Incorrectly Categorizing Several of Tabulated Doses IR 05000602/19972011998-01-0909 January 1998 Forwards Insp Rept 50-602/97-201 on 970929-1003.No Violations Noted.Previous Level IV Violation Was Closed ML20113A1021996-06-0606 June 1996 Notifies of Change of Name of Balcones Research Ctr to Pickle Research Campus & Addition of Two Annotations for Interlock Requirements of TS W/Rcs Interlocks,Section 3.2.2, Per Conversation W/Nrc.Amended TS Pages 14 & 24 Encl ML20107K5251996-04-16016 April 1996 Forwards Response to NRC 960325 Rai,Supplementing Response Made on 951111 & Original Amend Request to Correct Lanquage in Ts.Affected TS Page Also Encl ML20094G5401995-11-11011 November 1995 Submits Response to Request for Addl Info Re NRC Ltr & Original Amend Requested .No Change to Reactor Operating Conditions Being Proposed ML20085M4361995-06-21021 June 1995 Submits Info Re Control of Access to Radiation in Beams ML20084A9671995-05-24024 May 1995 Forwards Response to NRC Ltr Re Violations Noted in Insp Rept 50-602/95-01.Corrective Actions:Review of Reactor Committee Minutes Was Done by Facility Director for Period 1/92 to 4/95 ML20056C3161993-05-0404 May 1993 Forwards Proprietary Response to NRC Ltr Re Violations Noted in Insp Rept 50-602/93-01 on 930317-18.Encl Withheld,Per 10CFR2.790 ML20056C1471993-03-23023 March 1993 Confirms Arrangements Made on 930304 to Hold Meeting on 930429 to Discuss Performance Perspectives of Licensed Activities at Nuclear Engineering Teaching Lab.Proposed Meeting Agenda Encl ML20127M9821993-01-21021 January 1993 Forwards Correction to License R-129,changing Wording on Page 7-12 ML20126L0801993-01-0505 January 1993 Forwards Insp Repts 50-192/92-02 & 50-602/92-02 on 921207-11.No Violations or Deviations Noted ML20095L8181992-04-15015 April 1992 Advises That Assembly Error Made at Triga Fabrication Facility in That Two Wires on Potentiometer on CRD Mechanisms Reversed,Per 920311 Telcon ML20091Q3981992-01-23023 January 1992 Forwards Executed Amendment to Indemnity Agreement E-25 & 14 ML20085D1821991-10-0404 October 1991 Forwards Univ SAR Amend Pages for Rev 1.01 Dtd May 1991 ML20083D3691991-09-24024 September 1991 Submits Info Re Availability of Funds for Future Decommissioning of Reactor,Per 10CFR50.33 & 10CFR50.75 ML20073R0131991-05-24024 May 1991 Requests Extension of CP CPRR-123 for Four Addl Months to Provide Time for Review of NRC Questions.Current Expiration 910630.Final Response & Amended SAR Being Sent by Separate Ltr ML20073R1061991-05-24024 May 1991 Forwards Rev 1.01 to Sar,Response to NRC Questions,Per 910222 Request for Addl Info & List of Matl Subj to License Request ML20073E6891991-04-15015 April 1991 Forwards Rev 1 to PLAN-O, Call & Notification & PLAN-E, Emergency Response, QA Plan & Pages 12,20 & 21 of Emergency Response Plan ML20066J3141991-02-12012 February 1991 Forwards Rev 1 to Tech Specs.Changes Made by Discussion & Concurrence W/Nrc ML20066E2641991-01-11011 January 1991 Forwards Rev 1 to Emergency Response Plan. Annotated Copy Also Encl to Assist Review Process Due to Editorial Changes Made to Reword Sentences ML20065Q3231990-12-11011 December 1990 Informs That Extension Date Incorrectly Stated as 900630 in .Correct Extension Date Should Read 910630 ML20062H0371990-11-26026 November 1990 Submits List of Matl Required to Complete Evaluation for Issuance of OL Including Updated Emergency & Operator Requalification Plans & Final Tech Specs & Bases.Three Open Items identifed,602/8904-05,602/8904-06 & 602/9003-01 ML20065S1391990-11-21021 November 1990 Forwards Rev 0 to QA Plan ML20056B2541990-08-13013 August 1990 Forwards Rev 1 to Physical Security Plan.Encl Withheld ML20055D0401990-06-18018 June 1990 Updates Status of Items from Past Insps for Cp.Efforts to Reasonably Complete Items within Constraints of No Matl License Complete ML20043G6341990-06-0606 June 1990 Forwards Physical Security Plan.Plan Withheld ML20006E2981990-02-0909 February 1990 Forwards J Cox 891218 Ltr for Consideration & Compliance,If Possible ML20245G8181989-06-19019 June 1989 Informs of Bw Wehring Appointment as Director of Nuclear Engineering Teaching Lab at Univ of Texas,At Austin,Per License R-92,Tech Spec 6.2c3 & 6.2.2a.Curriculum Vitae of Wehring Encl ML20235Y3541989-02-24024 February 1989 Forwards Order Extending Const Completion Date of Triga Mark II Reactor to 891231,safety Evaluation & Environ Assessment & Finding of No Significant Impact,Per 881017 Request ML20204G2111988-10-17017 October 1988 Forwards Insp Rept 50-602/88-05 on 880922-23.No Violations or Deviations Noted ML20206E5261988-10-17017 October 1988 Requests Extension of Final Completion Date by 4 Months to 890430 for CP CPRR-123.Termination of General Contractor of Record Effective 881013 Requires Assumption of Project Responsibility by Continental Insurance Co IR 05000192/19880021988-09-0202 September 1988 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-192/88-02 & 50-602/88-02 IR 05000192/19880011988-06-0808 June 1988 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-192/88-01 & 50-602/88-01.Based on Listed Understanding of Util Response, Per 880516 Telcon,Actions Responsive to NRC Concerns ML20150F3181988-04-22022 April 1988 Responds to NRC Re Violations Noted in Insp Rept on 880324.Corrective Actions:Immediate Check of Review Dates on All Procedures & List Made of All Mods of Any Type ML20150D9721988-03-18018 March 1988 Informs of NRC Relocation to Stated Address.Mailing Address Unchanged.A Adams Project Manager & TS Michaels back-up Project Manager ML20236Q9571987-11-0606 November 1987 Advises That NETL Project Progress Continues W/Projected Completion Date of 880610.Present Figures Indicate 46% Completion by mid-Oct.Key Items & Date Estimates Listed ML20236F7581987-10-26026 October 1987 Informs That Effective 871025,JL Pellet Will Replace R Cooley as Section Chief of Operator Licensing Section in Div of Reactor Safety ML20212E3451987-02-20020 February 1987 Advises of Correction to Project Completion Date Noted in .Completion Date in Sentence Two Corrected to June 1988 ML20211B3191987-02-0606 February 1987 Informs That Bids for Docket 50-602 Project Opened on 861021 W/Award of General Contract on 861204.Dismantling Activities of Docket 50-192 License Projected to Commense in Aug or Sept 1988.Submits Info to Suppl 850503 Decommissioning Plan ML20207N0351986-12-0808 December 1986 Forwards Notice of 861215 Preconstruction Conference in Austin,Tx to Discuss Const Schedule Available from Cit,Inc of Texas.Set of Plans & Specs Should Be Sent by 851208 from Ws Martin ML20203C0911986-07-10010 July 1986 Informs That Bid Advertisement for Completion of Docket 50-602 & Dismantling of Docket 50-192 Scheduled for 860817 W/Bid Openings Planned for 860916 ML20210Q1481986-05-0606 May 1986 Forwards Evaluation of 841217 & 850814 Physical Security Plans.Plans Satisfy Physical Protection Requirements of 10CFR73.67(f) & Acceptable ML20140F3181986-03-26026 March 1986 Advises of NRR Reorganization.Telephone Number of J Dosa Changed.D Tondi New Section Leader for Nonpower Reactors & Safeguards Licensing Section.Correspondence Should Be Addressed to Nrc,Attention Document Control Desk 1999-08-02
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20210Q7171999-08-0202 August 1999 Provides Rept of Violation of Surveillance TS TS4.2.4, Reactor Instrumentation Sys. Calorimetric Calibr of Reactor Power Instrument Channels Was Not Done in Necessary Annual Period.No Immediate Corrective Actions Necessary ML20206K7271999-05-0606 May 1999 Informs That MG Krause Will Be Reactor Supervisor & Assume Daily Supervisory Duties Previously Performed by T Bauer. T Bauer Will Continue as Assistant Director Concentrating Efforts on Extended Time Activities ML20206B1071999-04-21021 April 1999 Informs That Activities at Nuclear Engineering Teaching Lab, Continuing to Improve.Nuclear & Radiation Engineering Program Continues to Have Support from All Levels of Univ Administration - Dept,College & Institutional ML20248F4661998-05-22022 May 1998 Notifies NRC That Licensee Intend to Reconstitute Committee Immediately,Rather than Wait Until Next Academic Yr ML20217M2201998-04-28028 April 1998 Forwards Replacement Page 3-13 to Univ of Tx 1997 Annual Rept.Corrections to Page Consists of Several Transcription Errors Incorrectly Categorizing Several of Tabulated Doses ML20113A1021996-06-0606 June 1996 Notifies of Change of Name of Balcones Research Ctr to Pickle Research Campus & Addition of Two Annotations for Interlock Requirements of TS W/Rcs Interlocks,Section 3.2.2, Per Conversation W/Nrc.Amended TS Pages 14 & 24 Encl ML20107K5251996-04-16016 April 1996 Forwards Response to NRC 960325 Rai,Supplementing Response Made on 951111 & Original Amend Request to Correct Lanquage in Ts.Affected TS Page Also Encl ML20094G5401995-11-11011 November 1995 Submits Response to Request for Addl Info Re NRC Ltr & Original Amend Requested .No Change to Reactor Operating Conditions Being Proposed ML20085M4361995-06-21021 June 1995 Submits Info Re Control of Access to Radiation in Beams ML20084A9671995-05-24024 May 1995 Forwards Response to NRC Ltr Re Violations Noted in Insp Rept 50-602/95-01.Corrective Actions:Review of Reactor Committee Minutes Was Done by Facility Director for Period 1/92 to 4/95 ML20056C3161993-05-0404 May 1993 Forwards Proprietary Response to NRC Ltr Re Violations Noted in Insp Rept 50-602/93-01 on 930317-18.Encl Withheld,Per 10CFR2.790 ML20095L8181992-04-15015 April 1992 Advises That Assembly Error Made at Triga Fabrication Facility in That Two Wires on Potentiometer on CRD Mechanisms Reversed,Per 920311 Telcon ML20091Q3981992-01-23023 January 1992 Forwards Executed Amendment to Indemnity Agreement E-25 & 14 ML20085D1821991-10-0404 October 1991 Forwards Univ SAR Amend Pages for Rev 1.01 Dtd May 1991 ML20083D3691991-09-24024 September 1991 Submits Info Re Availability of Funds for Future Decommissioning of Reactor,Per 10CFR50.33 & 10CFR50.75 ML20073R1061991-05-24024 May 1991 Forwards Rev 1.01 to Sar,Response to NRC Questions,Per 910222 Request for Addl Info & List of Matl Subj to License Request ML20073R0131991-05-24024 May 1991 Requests Extension of CP CPRR-123 for Four Addl Months to Provide Time for Review of NRC Questions.Current Expiration 910630.Final Response & Amended SAR Being Sent by Separate Ltr ML20073E6891991-04-15015 April 1991 Forwards Rev 1 to PLAN-O, Call & Notification & PLAN-E, Emergency Response, QA Plan & Pages 12,20 & 21 of Emergency Response Plan ML20066J3141991-02-12012 February 1991 Forwards Rev 1 to Tech Specs.Changes Made by Discussion & Concurrence W/Nrc ML20066E2641991-01-11011 January 1991 Forwards Rev 1 to Emergency Response Plan. Annotated Copy Also Encl to Assist Review Process Due to Editorial Changes Made to Reword Sentences ML20065Q3231990-12-11011 December 1990 Informs That Extension Date Incorrectly Stated as 900630 in .Correct Extension Date Should Read 910630 ML20065S1391990-11-21021 November 1990 Forwards Rev 0 to QA Plan ML20056B2541990-08-13013 August 1990 Forwards Rev 1 to Physical Security Plan.Encl Withheld ML20055D0401990-06-18018 June 1990 Updates Status of Items from Past Insps for Cp.Efforts to Reasonably Complete Items within Constraints of No Matl License Complete ML20043G6341990-06-0606 June 1990 Forwards Physical Security Plan.Plan Withheld ML20006E2981990-02-0909 February 1990 Forwards J Cox 891218 Ltr for Consideration & Compliance,If Possible ML20245G8181989-06-19019 June 1989 Informs of Bw Wehring Appointment as Director of Nuclear Engineering Teaching Lab at Univ of Texas,At Austin,Per License R-92,Tech Spec 6.2c3 & 6.2.2a.Curriculum Vitae of Wehring Encl ML20206E5261988-10-17017 October 1988 Requests Extension of Final Completion Date by 4 Months to 890430 for CP CPRR-123.Termination of General Contractor of Record Effective 881013 Requires Assumption of Project Responsibility by Continental Insurance Co ML20150F3181988-04-22022 April 1988 Responds to NRC Re Violations Noted in Insp Rept on 880324.Corrective Actions:Immediate Check of Review Dates on All Procedures & List Made of All Mods of Any Type ML20236Q9571987-11-0606 November 1987 Advises That NETL Project Progress Continues W/Projected Completion Date of 880610.Present Figures Indicate 46% Completion by mid-Oct.Key Items & Date Estimates Listed ML20212E3451987-02-20020 February 1987 Advises of Correction to Project Completion Date Noted in .Completion Date in Sentence Two Corrected to June 1988 ML20211B3191987-02-0606 February 1987 Informs That Bids for Docket 50-602 Project Opened on 861021 W/Award of General Contract on 861204.Dismantling Activities of Docket 50-192 License Projected to Commense in Aug or Sept 1988.Submits Info to Suppl 850503 Decommissioning Plan ML20207N0351986-12-0808 December 1986 Forwards Notice of 861215 Preconstruction Conference in Austin,Tx to Discuss Const Schedule Available from Cit,Inc of Texas.Set of Plans & Specs Should Be Sent by 851208 from Ws Martin ML20203C0911986-07-10010 July 1986 Informs That Bid Advertisement for Completion of Docket 50-602 & Dismantling of Docket 50-192 Scheduled for 860817 W/Bid Openings Planned for 860916 ML20133G8491985-10-0909 October 1985 Forwards Revised Tech Specs for License Submittal.Revs Include Changes in Form,Per NRC Request ML20134E3431985-08-14014 August 1985 Forwards Revised Tech Specs to Suppl 841109 License Application.Revs Include Most Recent Info Available & Changes Per Telcons W/Nrc ML20133H1471985-08-14014 August 1985 Forwards Revised Security Plan,Per 850313 & 29 Telcons. Plan Withheld (Ref 10CFR73.21 & 2.790) ML20128N6691985-07-0909 July 1985 Requests Univ of Texas 841109 Application for CP & OL & Environ Assessment ML20132D2421985-07-0101 July 1985 Requests Application for CP Operating Permit & Environ Assessment for Research Reactor Be Forwarded to Author at Listed Address ML20117P1741985-05-14014 May 1985 Advises That Should Be Amended to Request Latest Facility Completion Date of 881231.Previous Date of 871231 Should Be Supplemented by Encl Latest Date,Per Telcon W/Nrc ML20116N7891985-05-0303 May 1985 Forwards Amended Application for Cp,Relocating Site 130 Meters from Original Location ML20116D4761985-04-22022 April 1985 Forwards Revised Tech Specs,Incorporating Changes in Response to Discussions During 850122 Site Visit & Telcons W/Nrc ML20115J1821985-04-15015 April 1985 Provides Financial Info as Amend to Paragraph (F) of General Info Submitted in 831109 License Application & Subsequent Submittals.Funding Approval for Major Changes in Physical Plant Is Responsibility of Board of Regents ML20113C7311985-04-0404 April 1985 Forwards Responses to NRC Questions Generated by Review of QA Program Submitted by 841109 ltr.Q-list for Structures,Sys & Components Encl ML20099H4271985-03-14014 March 1985 Forwards Supplemental Info in Support of 841109 Application & Subsequent 850227 Amend.Info Concerns Control Rods,Hvac Sys,Control Room Annunciator & Scram Channels ML20099H7501985-03-14014 March 1985 Forwards Response to Questions Re Reactor Operator Requalification Program Based on NRC Review of 841109 Application for License ML20099A2011985-02-28028 February 1985 Requests Extension Until 850315 to Respond to Request for Addl Info Re Operator Qualification & Requalification Portion of 841109 License Submittal ML20107M6161985-02-27027 February 1985 Forwards Response & Supplemental Response to Final Questions Re Initial Review & Site Visit to Proposed Reactor Facility, Per 841109 Application for License ML20107M6271985-02-27027 February 1985 Forwards Figure 1.0, Organizational Block Diagram & List of Titles of Emergency Procedures & Guidance Documents to Be Written in Support of Maintaining Emergency Preparedness,Per NRC 841109 Request ML20113E2821985-01-14014 January 1985 Certifies That Application for Cp/Ol Delivered to Governor M White,County Judge,M Renfro & Mayor R Mullen on 850114 1999-08-02
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. DEPARTMENT OF MECHANICAL ENGINEERING
.- x, 1 L R!, A-THE UNIVERSITY OF TEXAS AT AUSTIN ,
R ,jpl$ NuclearEnginaring TeachingLaboratory-(512)471-5787 FAX (512)471-4589 June:21, 1995
. United States Nuclear Regulatory Commission ATTN: Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Project Support Office-of Nuclear Reactor Regulation Washington, D.C. 20555-0001
SUBJECT:
Control of Access to Radiation in Beams Docket No. 50-602 l 1
Dear Mr. Weiss:
'1 he Nuclear Engineering Teaching Laboratory (NETL) submits the following in response to your letter of June 5, 1995. We currently have several neutron beam port experiments operating, and planning is underway for other experiments which will utilize additional neutron beam ports in the near future.
i Measurements of the dose rates /fluences encountered from the various beam lines indicated that these beams, although small in area, had dose rates which could be deemed High or Very High Radiation Areas. Hence the facility management imposed the access controls and posting requirements of 10_CFR 20.1601, 20.1602, and 20.1902. These requirements are incorporated into the shielding design criteria for each experimental setup utilizing a beam port.
The imposition of these requirements adds proportionately to the time (man hours) required to get an experiment "up and running,"
and also increases the overall cost of an experimental setup (i.e. ,
door interlocks and alarms). Notwithstanding, NETL does not regard these requirements as unduly burdensome to our operations.
With referenca to your request for detailed suggestions on how to l assure worker safety around radiation beams, we can offer specifics !
relating to one of our permanent beam experiments as an example. !
This is not to suggest that our measures would suffice for every facility (not a "one size fits all" situation) . However, the exchange of information is oftentimes very useful. We plan to submit a paper for the April 1996 Radiation Protection and Shielding Division Topical Meeting, Advancements and Applications in-Radiation Protection and Shielding, which would provide further details and a broader forum for dissemination of this information.
28CC83 S, rut Addrns:10100 Burnet Road Au,,in. Tm,, um Mnf wrns: Balconn Rnrarch Center Bldg.159 Austin, Texas 78712 9506290186 950621 PDR ADOCK 05000602 p PDR
Seymour H. Weiss June 21, 1995 Page Two Information on the measures we undertook for control of access to the beam port utilized for experiments in Neutron Depth Profili'ng is enclosed as attachment 1.
Should you have any questions on this matter, please feel free to call me at (512) 471-5787.
Cordially, h a vJ. W Bernard W. Wehring t Director of the Nuclear Engineering Teaching Laboratory Professor, Mechanical Engineering enclosure: Attachment 1 l
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4 Attachment 1 Control of Access to Radiation Beams A Case Study: Neutron Depth Profiling at the Nuclear Engineering Teaching Laboratory, The University of Texas at Austin Prepared for: Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate
Attachment 1 Page 1 The nondestructive technique of Neutron Depth Profiling (NDP) is used to determine the concentration versus depth for specific impurity elements in various substrates of a host sample. The NETL-NDP utilizes thermal neutrons from a tangential beam port of the 1-MW TRIGA Mark II research reactor. This report presents a brief overview of the engineered controls and administrative procedures in effect at NETL for the NDP experimental area as relates to personnel access to the neutron beam. For detailed ,
information on the NDP experimental setup, i.e. , design aspects of the thermal neutron beam and NDP sample chamber, see references [1]
and [2].
The NDP experimental area described herein is considered a routine, permanent neutron beam experiment. A neutron b_gAnl experiment is an experiment utilizing an open beam port with the sample located outside the biological shield. A routine neutron beam experiment is a neutron beam experiment which uses a standard collimator/ filter assembly or an empty beam port. A cermanent neutron beam experiment is a neutron beam experiment which has a concrete shielding wall (or equivalent) surrounding the sample.
The operation requirements of the NDP facility comply with - the general limitations and procedures of the Permanent Neutron Beam Experiment (Experiment Review and Authorization documents) . These li.nitations and procedures are as follows:
- 1. A concrete shielding wall (or equivalent) shall be built around the sample such that no individual can receive an effective dose equivalent of 5 mrem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for a reactor power of 1 MW if that individual stays outside the concrete shielding wall.
- 2. The concrete shielding wall shall have entryways that are locked, except during periods when access to the sample is required. An RWP [ Radiation Work Permit] shall be required to authorize personnel to enter the shielding-wall area. All limitations on personnel movement inside the shielding wall shall be given in the RWP.
- 3. The entryways shall have interlocks that energize a conspicuous visible or audible alarm a) when an entryway is unlocked with the reactor key switch on, or b) when the reactor key switch is turned on with an entryway unlocked. Tne alarm shall inform both the individual in the confines of the concrete shielding wall and the reactor operator.
c.; .
Attachment 1 Page 2
- 4. The reactor shall be shut down at the time of an unanticipated alarm.
- 5. In place of the controls required by 1., 2., 3., and 4.,
direct supervision by the reactor health physicist shall be required for the initial setup of the experiment, any changes in boundaries or shielding, and any significant changes to the sample. Dose rate measurements will be taken, recorded, and filed by the reactor health physicist in order to verify that the limitations in 1.,
2., and 3. are satisfied.
- 6. At the conclusion of a permanent routine neutron beam experiment, i.e., shielding wall removed, the special beam port shielding, i.e. , inner plug, outer plug, etc. ,
shall be replaced and secured.
The limitations on personnel movement inside the shielding wall are given in Reguirements for Operation of NDP Faci 1.ity, which is a part of the Radiation Work Permit (RWP). Ender Area Access, the RWP states, "No personnel shall be inside the area when the reactor control rods are up and the shutter is open and the steel rod plug is out. The key to the access point is in control of the Senior Reactor Operator (SRO) or the Beam Port Manager." The RWP also requires that the beam stop must be secured in place any time the control rods are up. Temporary removal of the beam stop is allowed if conditions 1) and 2) of the Area Entry requirements given below are met, and either the Health Physicist or the SRO and Beam Port Manager are notified of and approve the relocation.
The Area Entry provisions allow the experimenter to enter the enclosed area after the control rods are down, with the knowledge of the SRO and the Beam Port Manager. Sample changes or target chamber or component removal requires the following:
- 1) Dose rate must be less than 100 mrem /hr in any accessible area.
- 2) Steel rod plug in place at the aperture of the beam.
- 3) Shutter closed.
Access Requirements Durina Reactor ODerations allows the experimenter access during other reactor operations if conditions 1), 2), and 3) in Area Entry above are mot, the RO and Beam Port Manager acknowledge the entry, a By and neutron survey instrument (s) are used during the entry, and the dose rate is less than 100 mrem /hr in the accessed areas. However, the RWP explicitly states, "UNDER NO CIRCUMSTANCES SHALL ANY PERSON, AT ANY TIME, WALK THROUGH THE BEAN LINE IN FRONT OF THE BEAM CATCHER WHEN THE REACTOR IS OPERATING ABOVE 1 kW." This restriction applies even in the case of shutter closed, steel rod plug inserted.
. l d
Attachment 1 Page 3 A photograph of the Neutron Depth Profiling experimental area is presented in figure 1. Figure 2 is a line drawing of a top view of the NDP area. That is, if one stood on the biological shield (area behind the blue fence at the far left, figure 1) and looked down, the arrangement in figure 2 would be observed. The view shown in figure 1 is identical to that which is observed by the control room personnel using closed-circuit television for visual surveillance of the beam port experimental areas during reactor operations.
Note the location of the Very High Radiation - Neutron Beam sign between the sample chamber and the inner concrete shield wall in figure 1. This sign is required to be in place during reactor operations.
Supplementing the camera surveillance, a magnetic read switch is wired to a digital input scanner which provides visual and audible warnings on the reactor control console panel upon entry. To provide the experimenter with an audible entry alarm, the gate is fitted with a door motion sensor (Radio Shack Safe House @ Model Cat. No.49-419) which cannot be switched off from the fence exterior. The chain link fence gate is also placarded [RWP Required for Entry).
The exterior concrete block walls are 39.5 cm (15.6 inches) thick and 188 cm (74 inches) in height; the chain link fence and gate are 182.8 cm (72 inches) in height. The beam stop is a standard 55 gallon drum comprised of 400 pounds of paraf fin, 20 pounds of boric acid, boral and lead.
An area radiation monitor is mounted on the exterior perimeter of the chain link fence to continuously monitor the dose rate in the vicinity of the NDP area. Dose rates (combined neutron and gamma) outside the enclosed NDP area are at or less than 5 mrem /hr during 1 MW operations.
. . 1 REFERENCES
[1] K. Unlu and B. Wehring, " Neutron Depth Profiling at the University of Texas," Nucl. Instr. and Meth, Phys. Res. A 3Jlil, 402-405 (1994).
[2] K. Unlu and B. Wehring, " Neutron Depth Profiling at the University of Texas Research Reactor," Trans. Am. Nucl. Soc. fj, 163 (1994).
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