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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20073B9901991-06-18018 June 1991 Forwards Rept Summarizing Findings of Orau Review of 59 Docket Files for Terminated Research & Test Reactors ML20045A7891990-03-0808 March 1990 Forwards Final Rept Orau 90/A-69, Confirmatory Radiological Survey of Triga Reactor Facility,Michigan State Univ,East Lansing,Mi. ML20045A7841990-01-29029 January 1990 Advises That Actions Taken to Resolve Concern Re Elevated Gamma Level,Detected on Clean Waste Dumpster,Adequate to Resolve Concern & Documentation Accurately Describes Final Radiological Status of Remaining Waste as Acceptable ML19332C8761989-11-21021 November 1989 Forwards Revised Summary Page to Termination Radiation Survey Summary & Final Rept.Results of Survey for Loose Surface Contamination at Max Point in Room 192 Incorrect ML19325F1851989-11-0606 November 1989 Forwards Termination Radiation Survey Summary & Final Rept, Per Order.Scheduling of Insp of Facility Requested ML20245H5601989-08-11011 August 1989 Forwards Safety Insp 50-294/89-01 on 890719-21.No Violations Noted ML20246G3581989-07-11011 July 1989 Forwards Order Authorizing Dismantling of Facility & Disposition of Component Parts for License R-114,per 890120 Application.Environ Assessment & Finding of No Significant Impact & Safety Evaluation Also Encl ML20244D2431989-06-0707 June 1989 Forwards Amend 7 to License R-114 & Safety Evaluation. Amend Converts License to Possession Only Status ML20246F3411989-05-0404 May 1989 Forwards Response to Request for Addl Info Re Decommissioning of Triga Reactor ML20247M8271989-03-30030 March 1989 Discusses Licensee Requests for Changes to Requalification Program.Requests Include Extension of Max Time Period of 24 Months for Requalification Cycle to Account for Changes in Outage Schedules & Reorganization of Training Programs ML20247B5371989-03-21021 March 1989 Forwards Request for Addl Info to Complete Review of Decommissioning Plan for Michigan State Univ ML20235N6251989-02-23023 February 1989 Forwards Fr Notice of Proposed Issuance of Orders Authorizing Disposition of Component Parts & Terminating License R-114 ML20154R0451988-09-12012 September 1988 Responds to 880616 Request for Approval of Route to Be Used for Transport of Spent Reactor Fuel.Route from East Lansing, Mi to Idaho Falls,Id Judged to Meet Requirements of 10CFR73.37.Data Re Arrangements & Approved Route Encl ML20150D8641988-03-18018 March 1988 Informs of Relocation of NRR to Rockville,Md.Official Mailing Address Still Remains Same & Project Managers Have New Locations & Phone Numbers.Ts Michaels Still Lead Project Manager for Facility & a Adams Will Serve as Backup ML20147B6991988-02-25025 February 1988 Forwards Amend 6 to License R-114 & Safety Evaluation.Amend Changes Tech Specs to Delete Semiannual Pulse & Annual Power Calibrs & to Restrict Licensee to Subcritical Mode ML20215C3491987-06-11011 June 1987 Informs of Recent NRR Reorganization.Designates T Michaels Project Manager for Facility ML20214U9841987-06-0303 June 1987 Forwards Revised NRC Form 398,personal Qualifications statement-licensee & NRC Form 396,certification of Medical Exam by Facility Licensee.Forms Revised to Reflect Changes to 10CFR55 Effective on 870526.W/o Encls ML20212E2011986-12-29029 December 1986 Forwards Notice of Violation from Insp on 860619-26.Notice Result of NRC Review of Listed Responses to Unresolved Item Re Discrepancies in Area Radiation Monitor Calibr Records. Corrective Actions Will Be Reviewed.No Reply Necessary ML20214P0271986-11-21021 November 1986 Advises That Addl Investigations & Tests Since Have Been Carried Out,Per 1983-84 Area Monitor Results. Anomalies Discovered That Were Not Readily Apparent During 1983-84 Calibr Tests.Instrument Returned to Mfg for Repair ML20211K0191986-10-31031 October 1986 Responds to 861003 Request for Further Info Re Discrepancies in Calibr of Radiation Monitoring Instrumentation for Triga Nuclear Reactor.Prior to 1985,calibr Carried Out by Moving Portable Source Into Reactor Room & Conducting Tests ML20215E5931986-10-0303 October 1986 Requests Addl Info Re 860805 & 0908 Responses to Discrepancies Noted in Insp of License R-114 on 860619-20, Including Assurance That Radiation Monitor Calibr Calculations Performed within 30 Days of Ltr Date ML20214N5951986-08-0505 August 1986 Responds to Questions Re Radiation Calibr of Area Radiation Monitor Raised in Insp Rept 50-294/86-01 on 860619-26.Ion Chamber Calibr Results Encl ML20207F2471986-07-15015 July 1986 Forwards Safety Insp Rept 50-294/86-01 on 860619-26.No Violations Noted.Unresolved Item Identified in Section 12 of Rept Will Be Reviewed for Potential Enforcement Action ML20198T2011986-06-0303 June 1986 Requests Listed Addl Info Re Decommissioning of Research Reactor,Including Possibility of Sealing Off Reactor Tank Top & Releasing Remainder of Room for Nonresearch Activities.Meeting to Discuss Concerns Requested ML20203J2481986-04-24024 April 1986 Forwards Rev 1 to Guidance & Discussion of Requirements for Application to Terminate Nonpower Reactor Facility OL & Reg Guide 1.86, Termination of OLs for Nuclear Reactors, Per 860414 Telcon Re Decommissioning of Facility.W/O Encls ML20199L0401986-03-31031 March 1986 Advises That Rev 4 to Emergency Plan Will Be Implemented as of 860401,per NRC 860318 Request ML20140F3381986-03-26026 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 ML20137S5081986-02-11011 February 1986 Forwards Revised NRC Form 398 Requiring All Info to Be Completed in Total W/Each new,renewal,upgrade,multi-unit & Reapplication Operator License Submittal.W/O Encls IA-85-754, Responds to FOIA Request for Procedures Re Univ of Michigan Nuclear Reactor.Licensee Not Required to Submit Procedures to Nrc.Complete Set of Current Procedures Available at Univ of Michigan for Insp1985-11-27027 November 1985 Responds to FOIA Request for Procedures Re Univ of Michigan Nuclear Reactor.Licensee Not Required to Submit Procedures to Nrc.Complete Set of Current Procedures Available at Univ of Michigan for Insp ML20138G0651985-11-27027 November 1985 Responds to FOIA Request for Procedures Re Univ of Michigan Nuclear Reactor.Licensee Not Required to Submit Procedures to Nrc.Complete Set of Current Procedures Available at Univ of Michigan for Insp ML20138S0711985-11-13013 November 1985 Informs That 851017 Proposed Changes to Emergency Plan Do Not Meet Requirements for Annual Onsite Emergency Drills. Plan Should Be Revised within 60 Days of Ltr Date ML20138G0801985-11-10010 November 1985 FOIA Request for Procedures Re Univ of Michigan Nuclear Reactor ML20129J4021985-07-10010 July 1985 Forwards Rev 3 to Emergency Plan,In Response to Co Thomas 850613 Request for More Detailed Description of Annual Onsite Emergency Drills ML20127D4371985-06-13013 June 1985 Forwards Emergency Plan Evaluation Rept. Plan Meets Requirements Except That Onsite Emergency Drills Should Be Conducted as Action Drills.Requests Mod of Plan to Reflect Change within 120 Days.Plan Should Be Implemented ML20205A7221985-04-22022 April 1985 Forwards Rev 2 to Emergency Plan.Plan Became Detached in Processing of Author ML20099D5641985-02-20020 February 1985 Forwards ,Revised Pages to Rev 2 & Revised Pages 17,18 & 22 to Rev 1 to Emergency Plan.W/O Revised Pages to Rev 2 ML20094E2861984-07-24024 July 1984 Forwards Rev 4 to Requalification Program for Licensed Operators, in Response to 840711 Generic Ltr 83-12A ML20093A1231984-06-26026 June 1984 Forwards Rev 1 to SAR for Triga Reactor,In Connection W/ Application for Renewal of License R-114 ML20091R6001984-06-11011 June 1984 Forwards Replies to Questions Re Relicensing of Michigan State Univ Reactor,License R-114 ML20091M8691984-06-0404 June 1984 Forwards Rev 3 to Requalification Program for Licensed Operators ML20099D5831984-05-21021 May 1984 Forwards Pages 17,18 & 22 to Rev 1 to Emergency Plan ML20078A4301983-09-19019 September 1983 Advises of Delay in Transferring Triga Reactor to Air Force. Univ Will Continue to Operate Reactor for at Least 1 Yr.If Transfer Authorized,Operation Will Be Continued No Longer than 2 Yrs ML20079S1031983-06-15015 June 1983 Forwards Public Version of Request for Extension Until 831101 to Submit Required Changes to Emergency Plan,Per .Changes Unnecessary If Reactor Transfer to Mcclellan Air Force Base Authorized ML20071A8291983-02-18018 February 1983 Requests Licensing Exams Be Administered to MW Mitchell & M Heinzmann.Exams Should Be Conducted During Wk of 830320 or 26 ML20071A8311983-02-18018 February 1983 Requests Exam for Senior Reactor Operator License ML20071A8341983-02-18018 February 1983 Requests Exam for Reactor Operator License ML20065U3711982-10-0606 October 1982 Forwards Public Version of Revised Emergency Plan,Per NRC 820616 Generic Ltr ML20062D1871982-07-29029 July 1982 Forwards Response to IE Bulletin 82-02 Re Bolted Connections.Visual or Surface Exams Not Typically Performed on Bolting in RCS Unless Requested.No Trend of Leakage Recurrence Detected ML20055A5401982-07-12012 July 1982 Submits Annual Operating Rept for 1981 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 1991-06-18
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20073B9901991-06-18018 June 1991 Forwards Rept Summarizing Findings of Orau Review of 59 Docket Files for Terminated Research & Test Reactors ML20045A7891990-03-0808 March 1990 Forwards Final Rept Orau 90/A-69, Confirmatory Radiological Survey of Triga Reactor Facility,Michigan State Univ,East Lansing,Mi. ML20045A7841990-01-29029 January 1990 Advises That Actions Taken to Resolve Concern Re Elevated Gamma Level,Detected on Clean Waste Dumpster,Adequate to Resolve Concern & Documentation Accurately Describes Final Radiological Status of Remaining Waste as Acceptable ML19332C8761989-11-21021 November 1989 Forwards Revised Summary Page to Termination Radiation Survey Summary & Final Rept.Results of Survey for Loose Surface Contamination at Max Point in Room 192 Incorrect ML19325F1851989-11-0606 November 1989 Forwards Termination Radiation Survey Summary & Final Rept, Per Order.Scheduling of Insp of Facility Requested ML20246F3411989-05-0404 May 1989 Forwards Response to Request for Addl Info Re Decommissioning of Triga Reactor ML20214P0271986-11-21021 November 1986 Advises That Addl Investigations & Tests Since Have Been Carried Out,Per 1983-84 Area Monitor Results. Anomalies Discovered That Were Not Readily Apparent During 1983-84 Calibr Tests.Instrument Returned to Mfg for Repair ML20211K0191986-10-31031 October 1986 Responds to 861003 Request for Further Info Re Discrepancies in Calibr of Radiation Monitoring Instrumentation for Triga Nuclear Reactor.Prior to 1985,calibr Carried Out by Moving Portable Source Into Reactor Room & Conducting Tests ML20214N5951986-08-0505 August 1986 Responds to Questions Re Radiation Calibr of Area Radiation Monitor Raised in Insp Rept 50-294/86-01 on 860619-26.Ion Chamber Calibr Results Encl ML20198T2011986-06-0303 June 1986 Requests Listed Addl Info Re Decommissioning of Research Reactor,Including Possibility of Sealing Off Reactor Tank Top & Releasing Remainder of Room for Nonresearch Activities.Meeting to Discuss Concerns Requested ML20199L0401986-03-31031 March 1986 Advises That Rev 4 to Emergency Plan Will Be Implemented as of 860401,per NRC 860318 Request ML20138G0801985-11-10010 November 1985 FOIA Request for Procedures Re Univ of Michigan Nuclear Reactor ML20129J4021985-07-10010 July 1985 Forwards Rev 3 to Emergency Plan,In Response to Co Thomas 850613 Request for More Detailed Description of Annual Onsite Emergency Drills ML20205A7221985-04-22022 April 1985 Forwards Rev 2 to Emergency Plan.Plan Became Detached in Processing of Author ML20099D5641985-02-20020 February 1985 Forwards ,Revised Pages to Rev 2 & Revised Pages 17,18 & 22 to Rev 1 to Emergency Plan.W/O Revised Pages to Rev 2 ML20094E2861984-07-24024 July 1984 Forwards Rev 4 to Requalification Program for Licensed Operators, in Response to 840711 Generic Ltr 83-12A ML20093A1231984-06-26026 June 1984 Forwards Rev 1 to SAR for Triga Reactor,In Connection W/ Application for Renewal of License R-114 ML20091R6001984-06-11011 June 1984 Forwards Replies to Questions Re Relicensing of Michigan State Univ Reactor,License R-114 ML20091M8691984-06-0404 June 1984 Forwards Rev 3 to Requalification Program for Licensed Operators ML20099D5831984-05-21021 May 1984 Forwards Pages 17,18 & 22 to Rev 1 to Emergency Plan ML20078A4301983-09-19019 September 1983 Advises of Delay in Transferring Triga Reactor to Air Force. Univ Will Continue to Operate Reactor for at Least 1 Yr.If Transfer Authorized,Operation Will Be Continued No Longer than 2 Yrs ML20079S1031983-06-15015 June 1983 Forwards Public Version of Request for Extension Until 831101 to Submit Required Changes to Emergency Plan,Per .Changes Unnecessary If Reactor Transfer to Mcclellan Air Force Base Authorized ML20071A8341983-02-18018 February 1983 Requests Exam for Reactor Operator License ML20071A8291983-02-18018 February 1983 Requests Licensing Exams Be Administered to MW Mitchell & M Heinzmann.Exams Should Be Conducted During Wk of 830320 or 26 ML20071A8311983-02-18018 February 1983 Requests Exam for Senior Reactor Operator License ML20065U3711982-10-0606 October 1982 Forwards Public Version of Revised Emergency Plan,Per NRC 820616 Generic Ltr ML20062D1871982-07-29029 July 1982 Forwards Response to IE Bulletin 82-02 Re Bolted Connections.Visual or Surface Exams Not Typically Performed on Bolting in RCS Unless Requested.No Trend of Leakage Recurrence Detected ML20055A5401982-07-12012 July 1982 Submits Annual Operating Rept for 1981 ML20010H5501981-09-21021 September 1981 Forwards Updated Safety Analysis Matl & Requalification Program,In Support of Renewal of License R-114 ML19347F8271981-05-14014 May 1981 Forwards Annual Financial Rept 1980.Estimate Costs of Shutdown Per Reg Guide 1.86 Requirements Provided ML19347E1781981-04-15015 April 1981 Submits Reactor Operating Rept for 1980 ML19347D6061981-03-13013 March 1981 Forwards Revised Physical Security Plan.Plan Withheld (Ref 10CFR2.790) ML19347C9901981-03-0404 March 1981 Requests Copy of NRC 780713 Ltr Requesting Financial Considerations About Continuing Operations of Facility ML19347C1511980-09-22022 September 1980 Responds to NRC 800829 Ltr Re Violations Noted in IE Insp on 800811-13.Corrective Actions:Reactor Safety Committee Will Audit Maint Records to Ensure That Testing & Surveillance Procedures Are Performed in Timely Manner ML19312E7701980-05-0101 May 1980 Responds to Item of Noncompliance Noted in NRC 800426 Ltr. Corrective Actions:Reactor Safety Committee Meetings Have Been Timely Since 791119 ML19309A7421980-03-11011 March 1980 Forwards Tech Specs,Amended to Comply W/New Format Requirements,For Renewal of License R-114 ML19290C2431980-01-0202 January 1980 Forwards Revision 3 to Physical Security Plan. Plan Withheld (Ref 10CFR2.790) ML19291B9271979-12-10010 December 1979 Forwards Executed Amend 10 to Indemnity Agreement E-51 Defining in Course of Transportation. ML19210C0181979-10-19019 October 1979 Responds to IE Bulletin 79-19.No Liquid Low Level Waste Is Generated.From Jan 1978-June 1979,three Radwaste Shipments Made,Consisting Mainly of Plastic Gloves,Bags & Vials ML19269E6691979-06-22022 June 1979 Advises of Incident on 790613:fuel Temp Indication Dropped to Zero During Full Power Operation.Caused by Failure of Thermocouples in B5 Serial Number 7833 Fuel Element.Meter Connected to Other Fuel Element ML19246C3351979-05-18018 May 1979 Responds to NRC 790430 Ltr Re Violation Noted in IE Insp Rept.Corrective Actions Withheld (Ref 10CFR2.790) ML19247A4691979-05-0101 May 1979 Ack Receipt of NRC 790404 Ltr Re Univ of Mi Pilot Testing Program of Personnel Dosimeters.Reviews Results of Nbs Insp of Irradation Facilities,Irradation Geometries Examinations, Calibr Procedures & Recordkeeping Plans ML19247A4711979-04-0606 April 1979 Discusses Interagency Policy Committee of Personnel Radiation Monitoring Activities Re Univ of Mi Test Program of Personnel Dosimetry Which Shows Large Numbers of Dosimetry Processors Are Not Able to Meet New Std ML19263D0631979-03-0202 March 1979 Advises That Log N Channel of Control Console Strip Recorder Is Repaired.Due to Subsequent Start Up Channel & Linear Channel Problems,Reactor Was Not Pulsed Until 790216 1991-06-18
[Table view] |
Text
' ' ' ~
j 1
Oak Ridge Energy / j Associated Post Office Bcx t 1 ' Enwonment i Universities Oak Ridge. Tennessee 37831-0117 Systems Division l
January 29, 1990 l l
Mr. Paul Pelke Nuclear Regulatory Commission ,
Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
Subject:
DUMPSTERS OF " CLEAN" WASTE FROM MSU TRIGA >
REACTOR DECOMMISSIONING i
Dear Mr. Pelke:
ORAU has reviewed the documentation developed by Michigan State University (see !
attached), describing the actions taken to resolve the concern regarding an. >
elevated gamma level, detected on one of the " clean" waste dumpsters'during our confirmatory survey visit. Both dumpsters were emptied and the waste monitored i item-by-item. The source of the elevated gamma level was identified as a small- :
metal washer; no other items were found to have associated residual radiation or contamination above ambient background levels. On the basis of the !
agreement between ORAU and MSU (Chem-Nuclear Systems, Inc.) data on the other ,
portions of the confirmatory survey, it is our opinion that the actions were .;
adequate to resolve the concern and that the documentation accurately describes ;
the final radiological status of the remaining waste as being acceptable for disposal without restrictions.
If you have any questions, I may be reached at FTS- 626-3305.
Sincerely, r
" iAWf James D. Berger, Director Environmental Survey and Site Assessment Program JDB:jls l l
Enclosures j cc: C. Sjoblom, NRC/6H3 G. LaRoche, NRC/6H3 i D. Tiktinsky, NRC/6A4 i CYTMid pe7YNRC/6A47 i
160137 p0 0 !
%~
9306140227 900129 PDR ADOCK 05000294 i p PDR ,
~ ; ,
MICHIGAN STATE UNIVERSITY COL 11.GE OF ENGINEERING EAST LANSING + MICHIGAN
DEPARTMENT Or CHEMICAL ENGINEERING
$17/355 3155 FAX: 517/3361105
.t January 4, 1990 Mr. Jim Berger Oak Ridge Associated Universities Oak Ridge, Tennessee 37830 RE: Resolution of the dumpster contamination question at Michigan State University ,
Dear Mr. Berger:
Attached is a summary to recap the events that occurred during the recent inspection that you and your team conducted here at Michigan State !
University in support of the TRIGA Reactor Decommissioning and ultimate termination of our NRC Reactor License. Also attached are the results of the surveys conducted on the vaste dumpsters after your team demobilized.
As you will recall, there was a question concerning potential radioactive content of the waterial (" clean" waste from the dismantlement operations) stored in these dumpsters located outside the Engineering Building. To resolve this problem, we had decided that the dumpsters should be unloaded and the contents re-surveyed in order to identify the source of the elevated radiation readings.
This operation has been completed on both dumpsters and, as shown in the attachments, the " source" was located and identified. It has since been removed, packaged, and will be properly disposed of as radioactive waste.
Please review the enclosed information and let us know if you have any further questions. We sincerely appreciate your cooperation in this matter.
1 can be reached at (517)355-3444 or 355-5135.
Cordially yourg, b- _-,_
Bruce Wilkinson Reactor Supervisor M5Liu en Affseneatnw Actson Equalopportunstvinststotuon
.. . . . - . . . - - . . .-. . ~ - -. . .. .-
N'* - .' ; e- y
[
MIC111GAN STATE UNIVERSITY .
I college OF ENGINEEUNG EAST LANSING
'{
DEPARTMETR OT OEMICAL ENGIMIUNG {
517/)151135 FAX: 517/3361103 i ' January 4, 1990 l(
ADDITIONAL INFORMATION TO SUPPORT TIIE VERIFICATION SURVEY / INSPECTION OF Tile MICllICAN STATE UNIVERSITY TRICA REACTOR FACILITY
_(Docket 50-294 License R-115) ;
i.
On December 18, 1989 the NRC contractor (Oak Ridge Associated Universities - !
ORAU) cond'n ted a verification survey / inspection of the Michigan State University TRIGA Reactor Facility as required for License termination j following dismantlement / decommissioning operations. During the survey, MSU 4
personnel and the MSU contractor's (Chem-Nuclear Systems, Inc. - CNSI) l Project Manager were on-site to observe and assist as necessary. This }
proved to be helpful since not all areas associated with the reactor facility were immediately obvious / accessible. The secondary pump station :
and various pipe and conduit penetrations located in the basement (machine !
shop and services tunnel) and elsewhere about the Engineering Building were made available to the chief inspector, and were included as part of the inspection / survey. i V
Based on preliminary results conveyed to the licensee by. the inspection team, all areas of the Facility are in compliance with the criteria for release; no corrective action was required.
In addition to the surveys in the " remote" locations of the Facility as mentioned above, one other area was expected to be included in the Final .
Inspection. As discussed in Section 6.2 of the " Termination Radiation !
Survey Summary and Final Report", " clean" (non-radioactive) waste generated j during the dismantlement operations was collected and stored in (2) metal' i dumpsters located outside the Engineering Building (see Attachment 1). '
Since this was donc as a final step in maintaining positive con *.rol of all '
waste from the Project site, it was anticipated that these dumpsters should ,
be surveyed / inspected by the NRC prior to releasing them for disposal in a '
local landfill.
Results of the verification survey (see Attachment 2) indicated that one of ,
the dumpsters (shown as "dumpster No. 1") probably contained radioactive '
material above the limits for release. The other dumpster ("No. 2") ,
exhibited no detectable radiation above background as reported by the i inspector and verified by MSU.
In order to identify the cause of the elevated readings, it was necessary to I unload the dumpster. It was decided that the Licensee (MSU) and contractor would unload and re-survey the entire dumpster (No. 1). In addition, the same operation would be performed on dumpster No. 2 since, although the external survey results were satisfactory, it too was now suspect. A written report of the results was to be forwarded to the chief inspector who would incorporate it into his report to the NRC. This decision was relayed to the NRC Region III office. Results of this task / survey is provided as Attachment 3.
AlW ss an Afhrmatus Aitew f:qn.at oppneruness lossstateon
-- . - .. - - - - .. .+-
i ^O - ;. .
The unloading, surveying, and repackaging was conducted on December 19 & 20,. i 1989. Materials, mostly contained in plastic trash bags, were removed in a. ;
controlled manner and surveyed with a sensitive gamma-scintillometer -
instruments. As indicated in the survey results, the source of the-elevated ;
readings on dumpster No. 1 was determined to be from a small (1/2"-dia.) !
steel washer that somehow got into the " clean" waste stream. The radioactivity associated with this item was induced Cobalt-60 which -
exhibited approximately 5 mR/hr on contact and is estimated to contain 5 to .
10 micro-Curies of activity. Although a detailed investigation has been made and several explanations formulated, the true cause for the oversight ;
can only be speculated. Fortunately, the waste had been retained for this ;
final evaluation, the mistake was identified, and recovery was made.
The radioactive material has been properly packaged and will be disposed of I as radioactive waste. The dumpsters have been reloaded and will be released to a local sanitary landfill upon notification of License termination'from the NRC.
D i
r 2The survey instrument used was a Ludlum Model 3 ratemeter with a 2" x 2" sodium-iodide (NaI) detector (Ludlum model 44-10)
LON tout *d4 Tron /MSDICTION ft tmYt cuavsv atrow lo .- Dec 19-20,1989 Yet 5'^"'
0945 Twt cm (Ie/20) 1]QQ roc _1_ oF 2 to ~,
wc^' Mich State University MSU:
st%c*
R* assin
- wo o o* u o M. ffit chell J,L 8 conTAwsAnos ANo
- o RaotA1 .suavev Dumpster S torage Area 3.W.Wilkinson CNSI M. Mr.nning covut~rs
,, g Allowable limits are NRC Rec. Guian 1_ M rne c,v r South of Engineering Bldg .
"Attachmcnt 3" Contamination and 5 micro r/hr exposure rate e n avessa r tivrts opence em* AirH A cscA maEA co~taat s tuts demnCO cm* *LPH4 O ovsta release limits) as specified in the MSU decommissioning p'lan (St E CCuutNT$1 comnco cm* 9( TA-O Auun ec*M00 cm' BE Ta.Gauus O No acT.cN aEco CCNt au'N AT CN ' ALN4 BET A-oA pua Eberline FMIT)
SouaCt CHtCK DAT A CONT A u.NaTcN sunwETS ,Nstavu m "' m ano m aA DI ATION W/HP-210 probe #274 At ru. eE,Ac.uu. etT cAuua a ^g','TgN NEUTaON i; BETA 4AuuAludlum MOdel 3 sovactio 99 *5'""" "' "w n. ~ W/44-10_2x2 crystal Tc sovace sTarncTw com 91,019 em 2.2x10" "^oco*"EVEW M. R. Manning, CNSI e,T, 1/2/90
.Nsf avutat aEsao~st 0.17x16hn
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cra 24K == ^'""^ 8E'^G^*"" "***". O "0'* ** **
~ sw-u eETA-cauur O neu Efficiency 26.4% O 7 i.- O racee ""- ' "- sevTaoN O toc %,cN
" * ~
cicxcacuNo c,m 20 com 150&
- cpm raoIE Em- Ee's s'co cm""< e w 0 AEASON FOR SURVEY O raocrovaE-No C3 srtciat Re-survey of " clean" waste stored in " ! I D aoutiNE dumpsters from the Rx dismantlement. !
- ALPHA BET A-G auu a m,.mn. O " I I sWWE/ B ET A-G auu n O m
EQUav ._._ EoVW , on n g raose NeutacN O toc ^"o" NO enms com> ever cent enope too cm a racee ico em mier, aw O (on contaet) 23 l l t -
l ( 2x Bk'g (5 Materials from Dump uter # 1 (exhept . tem 21- was ler) 2 l l < 5 mr/hr 1/2 inch steel wash e r 2Trem Damhster #1 !
3 I ( 2x Bkh ( 5 Materials from Dump nt rr #2 l l 4
l l 2 l I s I i 2.
I i 6' All Materials ekhibited less tha n twice
l l 7 ba c k},round levels after washer was removed 30 l l om e fromlDumpster #l. Dumpster #2 did not demonstrate s' l l gp 9 overltwice backi;round radiation / contamination levels, u l l
]"oo to l l 33 l l o
11 l l u l l N
x.
(D gy l ll ,g l l
- o 13 For [udlum 2x2 hetector, 5 micr a r/hr 38 I l gy .,, in ejuivalent tp 3000 cpm (Cs 13 7) 37 l [
s=
NO 15 3" OM l l l DX 16 -l l 39 l l ir <a i l l i i
- THE RNom4G a wtLLFUL RECOADING CF FALSE. FICTICIOUS.Om FaauDULENT $7Aff u(NTS OR ENTR8t$ ON THis DOCUuf MT W AT BE PUNISMA8tt AS A FELONT UNDER FEOtaAL STATUTES.
NO . Not Deteophie r
< - - - - - - - - . _ _ - - - - - - - - , - - _ _ . - - _ - - - - - , --- - - , - - - . , - . , , , . , ,,-., - -- :.w.- - , -
focalian of Tican~ waste _Dumpsters foufside, Sonib_ cad.ct_cid ihrineerig RatZding)
(PwkPg Ares /kWHng Roed)
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CLEAN WASTE #
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i Michigan State University .
O-- TRIGA Reactor Decommissioning Project '
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July - August,1989 e
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ATTACHMENT 2 METAL "DUMPSTERS" USED TO COLLECT / STORE " CLEAN" WASTE (1) from the MSU TRIGA Reactor Dismantlement / Decommissioning Project Capacity: Approx. 8 Cubic Yards Number of Dumpsters used: 2 (See Attachment i for actual location of the dumpsters at ACCESS / LOADING DOORS the Project Site)
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Verification Survey Results(2):
(conducted on 18 Dec 89 by ORAU)
Dumpster No.1: All Background readings except as noted above Dumpster No. 2: All Background readings (satisfactory)
A'OTN-(1) " Clean" waste conshted of mheeHaneous construction debns and routhe/daHy trash generated ,
1 durkg the dhmanuement operations. Refer to Secuon 62 of the MSUDecommbsionmg Plan and/or Thal Report 'for further hjormation.
(2) - SurveyInstrument Used Portable Count-rate Meter w/2"r 2"Na/ Detector 4
P 19 & 20 DEC 89 !-
RE-SURVEY OF Tile MSU CLEAN WASTE DUMPSTERS (No.1 & No. 2) f (Surveys conducted following NRC verfication survey on 19 Dec - see Attachment 2) ']
Trash & trash bags were unloaded from the dumpsters & surveyed (1) , ,
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hll . "1l (Yaste Dumpslers - 'q; k j l ,
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see Attachment I for actuallocation on h
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\ Ei RADIOACTIVITY ESTIMATE /EVALUATIOR i Gamma Spectroscopy Performed; ;
- Major Isotope Identified - Cobalt-00 -
Using a Co60 Check Source of known Activity, the a livity of the Washer was estimated as follows:
1/2" Flat Steel Washer Found in check Source Dumpster Activity - 0.5 uCi Number 1 Source Strength' - 0.35 mR/hr gg, b:
Washer ).
(1) - Survey Instruments Used: Radiation Level' - approx. 5 mR/hr i" Estimated Activity 10 uCi p' Ludlum Model 3 w/model 44-10 probe (2"x 2" Nal) & .
0.5uci Eberline PRM-6 w/ IIP-210 probe (thin-window GM lube) x SmR/hr = 7uci 0.35mR/hr g Results were all " background" after the steel washer was removed - i
- - as measured on contact w/an Eberline ?.
lon ChamberInstrument (