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| | 'Drigham Youn University Risk Management Department |
| | 'Cranda11 House West Provo, Utah Mf>02 g ,,7 gggg |
| | .D o e t(eA 50/ A 4 L - - |
| | ~~ 8 February 5, 1991 , |
| | Bill Doach Director, Division of Itadiation Safoty and Safeguards Dear Sir In compliance with our technical specifications (5.3.) the 0.5 Curio Pu/Bo source has boon removod from the reactor. This was approved by the lladiation Safety Committoo. The source has boon stored in a rostricted area located in the Eyring Science Contor room 171. The sourco is stored behind a concrote block wall. The source was leak checked with no detectable removable contamination. |
| | (less than .001 microcuries). We have contacted the Dopartment of Energy in an attempt to return the Pu/Bo sourco however this has not mot with much success. In the event that the DOE cannot find a suitable use for the source we propose to switch control of the source to Special Nuclear Material Licenso # UT2500091. If you. |
| | have questions suggestions or concerns please give me a call at (801) 378-5779. |
| | Other than the above mentionod changes the status of the L-77 reactor (Licenso R-109) remains unchangod. |
| | There was no human exposure-to radiation associated with the reactor above background level, as measured by TLD dosimetry, over the past year. In addition there has boon no release of radioactivo offluents to the environment. |
| | The TLD monitors placed in the f acility in accordance with the Technical Specifications have recorded no measurable exposure abovo background levels. |
| | The shielding tank remains in good condition with no visible signs of leakage or significant corrosion. |
| | Sincerel,y, # |
| | v s / |
| | ( N d e l $ h '~ 7 f, 2 - |
| | Edwin F.,Jsckson Radiation Safety Officer ZEof 9102200199 910205 |
| | * l@hl}9 kp hDR ADOCK 0500 2}} |
Latest revision as of 09:53, 21 December 2020
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20129H2531996-10-29029 October 1996
Forwards Order Terminating Facility License R-109 IAW Application Dtd 900628,amend 12 to Indemnity Agreement E-50, SE & EA Associated W/Action
ML20149L7761996-07-10010 July 1996
Forwards Final Rept, Radiological Survey of Brigham Young Univ L-77 Research Reactor
ML20091K3661995-08-0707 August 1995
Informs That Environ Survey & Site Assessment Program of Licensee Has Reviewed Revised Decommissioning Plan for L-77 Research Reactor at Brigham Young Univ in Provo,Ut.Comments Encl
ML20087K5941995-08-0707 August 1995
Requests Addl Info to Improve Thoroughness & Technical Quality of Document Re Decommissioning Plan for L-77 Research Reactor.Encl Comments Offered for Consideration
ML20149F3671994-08-0505 August 1994
Requests Addl Info on Final Termination Survey of L-77 Research Reactor & Response to Orise Rept,Per
ML20149F3731994-07-25025 July 1994
Forwards Review & Comments Re Brigham Young Univ Rept on Decommissioning Survey for L-77 Research Reactor.More Info Requested to Determine True & Complete Radiological Status & Complete Radiological Status of Site
ML20029C6571994-04-15015 April 1994
Forwards Decommissioning Survey for L-77 Research Reactor Brigham Young Univ.
ML20126F9731992-12-22022 December 1992
Proposes Changing Completion Date to Complete All Phases of Decommissioning from 5 Wks to 930131
ML20125D2521992-12-0909 December 1992
Forwards Insp Rept 50-262/92-01 on 921130-1201.No Violations Noted
ML20094J9801992-03-0909 March 1992
Submits Listed Info in Response to Questions Received from NRC Dtd 910109.Advises That Statistical Repts Will Be Prepared & Maintained for NRC Review
ML20082B6421991-07-0202 July 1991
Forwards Decommissioning Plan for L-77 Research Reactor, Per NRC Request for Mod to Plan
ML20066H1771991-02-0505 February 1991
Informs of Removal of 0.5 Ci Pu/Beryllium Source from Reactor,Per Tech Spec 5.3.Source Stored Behind Concrete Block Wall.Doe Contacted in Attempt to Return Source
ML20058M9641990-08-0909 August 1990
Forwards Amend 3 to License R-109 & Safety Evaluation.Amend Replaces Title of Executive Vice President W/Title of Associate Administrative Vice President in Facility Organization in Tech Specs
ML20246B5221989-04-24024 April 1989
Forwards Tech Specs W/Alterations Per 880901 Telcon.Ltr to D Chaney Re Insp & Response Encl.W/O Ltr
ML20248F2301989-04-0505 April 1989
Forwards Insp Rept 50-262/89-01 on 890302-03.No Violations or Deviations Noted
ML20244B4971989-04-0404 April 1989
Informs That Radiation Safety Committee Met on 890322 & Approved Cutting Power to L-77 Research Reactor,To Prevent Accidental/Inadvertent Manipulation of Reactor Mechanisms, Per Insp on 890302.Power Was Cut on 890322
ML20195F5411988-11-0909 November 1988
Responds to Re Licensee Nuclear Research Reactor. NRC Working to Issue possession-only Amend to License
ML20195F5581988-09-28028 September 1988
Requests Disassembling of Nuclear Reactor at Facility & Receipt of Possession Only License.Response Requested
ML20155F1631988-06-0202 June 1988
Advises That Records Do Not Indicate Receipt of Any Parts from Wjm or PSI During 1976 to Present.Reactor Currently Secured.Fuel Shipped Offsite & Decommissioning Being Pursued,Per NRC Bulletin 88-005
ML20151C5141988-04-0101 April 1988
Forwards Info in Response to Request for Insp of Hfa Type Latching Relays Mfg by Ge,Per NRC Bulletin 88-003.Licensee Has No Subj Latchings.Reactor Fuel Removed & Shipped Off Site While Licensee Pursues Full Decommissioning
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
ML20246B1811988-03-17017 March 1988
Forwards Rewritten Tech Specs for Application for Possession Only License
ML20236G1701987-10-26026 October 1987
Advises That Jl Pellet Replacing R Cooley in Position & Duties of Section Chief of Operator Licensing Section in Div of Reactor Safety,Effective on 871025
ML20235P1031987-09-29029 September 1987
Forwards Tech Specs,Rewritten Per Ansi/Ans 15.1 - 1982,in Response to Recipient 870826 Request for Addl Info.No Detectable Gamma Radiation,Neutron Flux,Beta Contamination or Removable Alpha Contamination Found in Reactor
ML20237G5921987-08-26026 August 1987
Forwards Request for Addl Info Based on Review of 870522 Application for possession-only Amend to License R-109. Response Requested within 30 Days of Ltr Date
ML20215A4941987-06-11011 June 1987
Ack Receipt of 870408 & 0526 Ltrs Re Corrective Actions Taken Re Violations Noted in Insp Rept 50-262/87-01
ML20214N6661987-05-29029 May 1987
Forwards Insp Rept 50-262/87-02 on 870504-05.No Violations or Deviations Noted
ML20214S9181987-05-26026 May 1987
Informs That GL Jensen Licensed to Direct Licensed Activities of Licensed Operators at Brigham Young Univ Nuclear Reactor Facility,Under License SOP-873-9 & Docket 55-2453,effective 850512
ML20214S1551987-05-26026 May 1987
Responds to NRC Re Violations Noted in Insp Rept 50-262/87-01.Corrective Actions:Fuel Unloaded & Shipped Offsite & Application for Amend to License R-109 for Posssesion Only Status Requested
ML20214P0531987-05-22022 May 1987
Forwards Application for Amend to License R-109,authorizing Possession Only of 0.5-Ci Pu-Be Neutron Source in Reactor Until Source Returned to Doe.Operations at Reactor Suspended.Time Needed to Prepare Decommissioning Plan
IR 05000262/19870011987-05-0808 May 1987
Ack Receipt of Responding to Violations Noted in Insp Rept 50-262/87-01.Addl Info on Violation a Re Operational Limitations & Restrictions for Surveillances Performed Requested
ML20206S5551987-04-0808 April 1987
Responds to NRC Re Violations Noted in Insp Rept 50-262/87-01.Corrective Actions:Position of Burglar Alarm Switch Adjusted Following Insp to Allow Sys to Trigger Much Earlier than on 870203
ML20207R3931987-03-12012 March 1987
Forwards Insp Rept 50-262/87-01 on 870202-03 & Notice of Violation
ML20210J4151986-03-26026 March 1986
Lists Change in Telephone Number for R Carter,Facility Project Manager,Due to NRR Reorganization.D Tondi New Nonpower Reactors & Safeguards Licensing Section Leader. Correspondence Should Be Sent to Listed Address
ML20074A8421983-05-0909 May 1983
Requests Clarification If License Authorizes Unloading & Shipping of Fuel.Info on Procedures & Dismantling Plans to Decommission L-77 Reactors Also Requested
ML20072A9741983-01-18018 January 1983
Forwards Annual Operating Rept for 1982
ML20064F7901983-01-0303 January 1983
Notifies of Voluntary Surrender of License & Dismantling of L-77 Reactor.Requests Listed Decommissioning Info
ML20070E0401982-12-0303 December 1982
Forwards Public Version of Revised Reactor Facility Emergency Plan
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
ML20040B7441982-01-15015 January 1982
Forwards Annual Operating Rept,1981.
ML20148U2131981-02-17017 February 1981
Forwards Revised NRC Region 4 Organization Chart,Effective 810227
ML19337B1481980-08-21021 August 1980
Responds to NRC 800813 Ltr Re Violations Noted in IE Insp Rept 50-262/80-02.Corrective Actions:License Recertification Requested & Check of Operating Dates Initiated & Correctly Posted
ML20149K1911980-05-0707 May 1980
Generic Ltr 80-38 to All Nonpower Reactor Licensees Re NPR Physical Protection Requirements.Summary of Certain NPR Physical Protection Requirements Encl & Should Aid in Determining Safeguards Requirements Applicable to Facility
ML19296B7461980-02-0909 February 1980
Forwards Annual Operating Rept for 1979
ML19270G8141979-06-13013 June 1979
Forwards Executed Copy of Amend 9 to Indemnity Agreement E-50
ML19281A1921979-02-27027 February 1979
Forwards Annual Rept for 1978.
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
1996-07-10
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML20149L7761996-07-10010 July 1996
Forwards Final Rept, Radiological Survey of Brigham Young Univ L-77 Research Reactor
ML20087K5941995-08-0707 August 1995
Requests Addl Info to Improve Thoroughness & Technical Quality of Document Re Decommissioning Plan for L-77 Research Reactor.Encl Comments Offered for Consideration
ML20091K3661995-08-0707 August 1995
Informs That Environ Survey & Site Assessment Program of Licensee Has Reviewed Revised Decommissioning Plan for L-77 Research Reactor at Brigham Young Univ in Provo,Ut.Comments Encl
ML20149F3731994-07-25025 July 1994
Forwards Review & Comments Re Brigham Young Univ Rept on Decommissioning Survey for L-77 Research Reactor.More Info Requested to Determine True & Complete Radiological Status & Complete Radiological Status of Site
ML20029C6571994-04-15015 April 1994
Forwards Decommissioning Survey for L-77 Research Reactor Brigham Young Univ.
ML20126F9731992-12-22022 December 1992
Proposes Changing Completion Date to Complete All Phases of Decommissioning from 5 Wks to 930131
ML20094J9801992-03-0909 March 1992
Submits Listed Info in Response to Questions Received from NRC Dtd 910109.Advises That Statistical Repts Will Be Prepared & Maintained for NRC Review
ML20082B6421991-07-0202 July 1991
Forwards Decommissioning Plan for L-77 Research Reactor, Per NRC Request for Mod to Plan
ML20066H1771991-02-0505 February 1991
Informs of Removal of 0.5 Ci Pu/Beryllium Source from Reactor,Per Tech Spec 5.3.Source Stored Behind Concrete Block Wall.Doe Contacted in Attempt to Return Source
ML20246B5221989-04-24024 April 1989
Forwards Tech Specs W/Alterations Per 880901 Telcon.Ltr to D Chaney Re Insp & Response Encl.W/O Ltr
ML20244B4971989-04-0404 April 1989
Informs That Radiation Safety Committee Met on 890322 & Approved Cutting Power to L-77 Research Reactor,To Prevent Accidental/Inadvertent Manipulation of Reactor Mechanisms, Per Insp on 890302.Power Was Cut on 890322
ML20195F5581988-09-28028 September 1988
Requests Disassembling of Nuclear Reactor at Facility & Receipt of Possession Only License.Response Requested
ML20155F1631988-06-0202 June 1988
Advises That Records Do Not Indicate Receipt of Any Parts from Wjm or PSI During 1976 to Present.Reactor Currently Secured.Fuel Shipped Offsite & Decommissioning Being Pursued,Per NRC Bulletin 88-005
ML20151C5141988-04-0101 April 1988
Forwards Info in Response to Request for Insp of Hfa Type Latching Relays Mfg by Ge,Per NRC Bulletin 88-003.Licensee Has No Subj Latchings.Reactor Fuel Removed & Shipped Off Site While Licensee Pursues Full Decommissioning
ML20246B1811988-03-17017 March 1988
Forwards Rewritten Tech Specs for Application for Possession Only License
ML20235P1031987-09-29029 September 1987
Forwards Tech Specs,Rewritten Per Ansi/Ans 15.1 - 1982,in Response to Recipient 870826 Request for Addl Info.No Detectable Gamma Radiation,Neutron Flux,Beta Contamination or Removable Alpha Contamination Found in Reactor
ML20214S1551987-05-26026 May 1987
Responds to NRC Re Violations Noted in Insp Rept 50-262/87-01.Corrective Actions:Fuel Unloaded & Shipped Offsite & Application for Amend to License R-109 for Posssesion Only Status Requested
ML20214P0531987-05-22022 May 1987
Forwards Application for Amend to License R-109,authorizing Possession Only of 0.5-Ci Pu-Be Neutron Source in Reactor Until Source Returned to Doe.Operations at Reactor Suspended.Time Needed to Prepare Decommissioning Plan
ML20206S5551987-04-0808 April 1987
Responds to NRC Re Violations Noted in Insp Rept 50-262/87-01.Corrective Actions:Position of Burglar Alarm Switch Adjusted Following Insp to Allow Sys to Trigger Much Earlier than on 870203
ML20074A8421983-05-0909 May 1983
Requests Clarification If License Authorizes Unloading & Shipping of Fuel.Info on Procedures & Dismantling Plans to Decommission L-77 Reactors Also Requested
ML20072A9741983-01-18018 January 1983
Forwards Annual Operating Rept for 1982
ML20064F7901983-01-0303 January 1983
Notifies of Voluntary Surrender of License & Dismantling of L-77 Reactor.Requests Listed Decommissioning Info
ML20070E0401982-12-0303 December 1982
Forwards Public Version of Revised Reactor Facility Emergency Plan
ML20040B7441982-01-15015 January 1982
Forwards Annual Operating Rept,1981.
ML19337B1481980-08-21021 August 1980
Responds to NRC 800813 Ltr Re Violations Noted in IE Insp Rept 50-262/80-02.Corrective Actions:License Recertification Requested & Check of Operating Dates Initiated & Correctly Posted
ML19296B7461980-02-0909 February 1980
Forwards Annual Operating Rept for 1979
ML19270G8141979-06-13013 June 1979
Forwards Executed Copy of Amend 9 to Indemnity Agreement E-50
ML19281A1921979-02-27027 February 1979
Forwards Annual Rept for 1978.
1996-07-10
[Table view] |
Text
. *
'Drigham Youn University Risk Management Department
'Cranda11 House West Provo, Utah Mf>02 g ,,7 gggg
.D o e t(eA 50/ A 4 L - -
~~ 8 February 5, 1991 ,
Bill Doach Director, Division of Itadiation Safoty and Safeguards Dear Sir In compliance with our technical specifications (5.3.) the 0.5 Curio Pu/Bo source has boon removod from the reactor. This was approved by the lladiation Safety Committoo. The source has boon stored in a rostricted area located in the Eyring Science Contor room 171. The sourco is stored behind a concrote block wall. The source was leak checked with no detectable removable contamination.
(less than .001 microcuries). We have contacted the Dopartment of Energy in an attempt to return the Pu/Bo sourco however this has not mot with much success. In the event that the DOE cannot find a suitable use for the source we propose to switch control of the source to Special Nuclear Material Licenso # UT2500091. If you.
have questions suggestions or concerns please give me a call at (801) 378-5779.
Other than the above mentionod changes the status of the L-77 reactor (Licenso R-109) remains unchangod.
There was no human exposure-to radiation associated with the reactor above background level, as measured by TLD dosimetry, over the past year. In addition there has boon no release of radioactivo offluents to the environment.
The TLD monitors placed in the f acility in accordance with the Technical Specifications have recorded no measurable exposure abovo background levels.
The shielding tank remains in good condition with no visible signs of leakage or significant corrosion.
Sincerel,y, #
v s /
( N d e l $ h '~ 7 f, 2 -
Edwin F.,Jsckson Radiation Safety Officer ZEof 9102200199 910205
- l@hl}9 kp hDR ADOCK 0500 2