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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P7171999-10-26026 October 1999 Informs That Effective 991026,SW Holmes Will Be NRC Inspector for Facility at Dow Chemical Co,Due to Retirement of Previously Assigned Inspector ML20210P9881999-08-10010 August 1999 Forwards Insp Rept 50-264/99-201 on 990712-15.No Violations Noted.Insp Consisted of Selected Exams of Procedures & Representative Records,Interview with Personnel & Observations of Activities in Progress ML20210N3311999-08-0202 August 1999 Forwards Proprietary Details Re Loss of Communication Between Dow Emergency Services & Dow Triga Research Reactor. Details of Facility Security Plan Are Withheld Under Provisions of 10CFR2.790 ML20153B5451998-09-14014 September 1998 Forwards Proposed Modified Emergency Plan,Including Version in Form of Strikethrough Format (Deletions) or Bold Format (Additions) & Explanation for Change & Version Incorporated Into Text of Plan.With One Oversize Drawing ML20151Z4391998-07-27027 July 1998 Informs NRC That Wl Rigot Has Assumed Role of Facility Director of Dow Chemical Co Triga Nuclear Reactor,Replacing SB Butts.Sb Butts Will Replace J Roeck as Level 1 Mgt within Administration as Described in 6.1 of Facility TSs ML20203L1271998-02-26026 February 1998 Forwards Request for Addl Info Re Emergency Plan Submitted on 960708,as Supplemented on 980115.Responses Requested to Be Provided within 30 Days of Date of Ltr ML20203A0561998-02-11011 February 1998 Forwards Amend 8 to License R-108.Amend Increases Amount of Time from 30 to 60 Days That Temporary Radiation Monitor May Be Used in Place of Area Monitor ML20198P7821998-01-15015 January 1998 Forwards Proposed Modified Emergency Plan for Dow Triga Reactor & Responses to NRC ML20198B4181997-12-18018 December 1997 Forwards Insp Rept 50-264/97-201 on 971202-03.No Violations or Deviations Identified.Annual Emergency Plant Drill Acceptable Demonstration of Ability to Respond & to Mitigate Consequences of Reactor Event ML20217P3201997-08-22022 August 1997 Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transferred from Nrr.All Related Repts, Correspondence & Inquires W/Docket Number Specified Should Be Directed to Listed Address ML20210R0971997-08-19019 August 1997 Forwards Amend 7 to License R-108 & Safety Evaluation.Amend Deletes Requirement for Scram Function on Min Reactor Period,Changes Periodic Insp of Reactor Fuel Schedule, & Modifies Facility Organizational Structure ML20141C2931997-06-16016 June 1997 Forwards Response to 970417 Request for Addl Info Re Amend Request for FOL R-108.Encl Includes Changes Proposed for Amend 7 & Explanation for Question Raised in NRC Ltr ML20140E5471997-04-23023 April 1997 Forwards Insp Rept 50-264/97-01 on 970407-11.No Violations Noted ML20135C7251997-02-24024 February 1997 Forwards Response to NRC Request for Addl Info Re Amend Request for Facility Operating License R-108,ltr Dtd 961217.Encl Includes Changes Proposed for Amend 7 & Explanation for Question Raised in Ltr ML20132D2781996-12-17017 December 1996 Forwards Request for Addl Info Re License Triga Research Reactor ML20132D5511996-12-16016 December 1996 Ack Receipt of Ltr Dtd 961030,transmitting Changes to Physical Security Plan for Dow Triga Research Reactor Submitted,Per 10CFR50.54(p) ML20133G3151996-12-0909 December 1996 Informs That Rept Describing Review of Decommissioning Costs Re Dow Triga Research Reactor Will Be Available for NRC Review When on-site Insp Occurs ML20129B5951996-10-0808 October 1996 Forwards Response to RAI Re 960912 Amend Request for License R-108 ML20129H1331996-10-0202 October 1996 Requests Addl Info Re Dow Triga Research Reactor Emergency Plan Submitted on 960708 Before Review Can Be Complete ML20115E6671996-07-0808 July 1996 Forwards Proposed Modified Emergency Plan,Including Strikethrough Format (Deletion) or Bold Format (Additions) Version & Version W/Changes Incorporated in Text ML20113C3661996-06-18018 June 1996 Responds to Request for Addl Info Re Amend Request for FOL R-108 ML20101H6281996-03-18018 March 1996 Forwards Annual Rept for Triga Facility for 1995 ML20087E4011995-08-0707 August 1995 Forwards TSs in Response to RAI Re 950607 Application for Amend to License R-108 ML20078M1371995-02-0808 February 1995 Forwards Response to RAI Re 941221 Application for Amend to License R-108 ML20069J1651994-06-0606 June 1994 Notifies That Cw Kocher Has Retired from Dow Chemical Co Effective 940531,therefore,no Longer Needs Senior Operator License SOP-3922 ML20065B2231994-03-28028 March 1994 Informs That Effective 940322,WL Rigot Has Replaced Cw Kocher as Supervisor for Dow Triga Nuclear Reactor (R-108) ML20057D4511993-09-30030 September 1993 Informs That RA Wolcott Replaced Jj Havel as Chairman of Reactor Operations Committee for Dow Triga Research Reactor ML20072Q9111991-03-14014 March 1991 Advises That Power Level Increase to 300 Kw,Authorized by Amend 5 to License R-108,issued on 890508,implemented. Neutron Detectors Near Reactor Core Moved to Reflect Higher Max Power Level ML20062F7411990-11-19019 November 1990 Forwards Microprocessor-Based I&C Sys for Dow Triga Research Reactor, Containing Mods to 901015 Amend Request for License R-108 ML20058N4841990-08-0101 August 1990 Forwards Insp Rept 50-264/90-01 on 900709-11.No Violations or Deviations Identified ML20055F6901990-07-0101 July 1990 Advises That Vendor Has Not Received Part 55 Svcs from NRC & Requests That 900627 Invoice I1111 Be Corrected ML20247H7581989-09-0707 September 1989 Forwards Matl Control & Accountability Insp Rept 50-264/89-02 on 890829-30.No Violations Noted ML20247C9361989-09-0505 September 1989 Forwards Physical Security Insp Rept 50-264/89-01 on 890829- 30.No Violations Noted ML20246M6451989-05-0808 May 1989 Forwards Amend 5 to License R-108,renewing License for 20 Yrs from Issuance Date & Authorizing Power Increase from 100 to 300 Kws.Environ Assessment,Safety Evaluation,Notice of Renewal & Environ Consideration Also Encl 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 ML20207C7931988-06-29029 June 1988 Advises That Jj Havel Replaced Mb Gibbs as Chair of Reactor Operations Committee,Effective 880623 ML20154C2651988-04-29029 April 1988 Forwards Mods to Suppl Application for Renewal of License R-108,per a Adams Request ML20151X1821988-04-28028 April 1988 Ack Receipt of Describing Proposed Mods to Security Plan.Changes Consistent W/Provisions of 10CFR50.54(p) & Acceptable 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 ML20148G8991988-01-14014 January 1988 Advises That 880107 Rev to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable.Encl to Contains Proprietary Info & Being Protected Against Unauthorized Disclosure (Ref 10CFR2.790(d)) ML20237E1481987-12-23023 December 1987 Forwards Exam Rept 50-264/OLS-87-01 of Exam Administered on 871201-02 ML20236B0621987-10-0505 October 1987 Informs That 870925 Audit of Triga Research Reactor Showed Two Tasks Involving Surveillance Required by Tech Specs Not Done Per Scheduled Weekly Checklist for Wk of 870713.Failure to Complete Tasks Did Not Violate Tech Specs ML20238A0461987-08-14014 August 1987 Forwards Supplementary Info Re Renewal of License R-108 for Dow Triga Research Reactor ML20237L4351987-08-14014 August 1987 Forwards Licensed Operator Requalification Program for Facility.Program Reflects Changes Made Following Guidance of Hn Berkow ,Ansi/Ans 15.1-1977 & Changes in 10CFR55 Effective 870526 ML20238A3091987-08-13013 August 1987 Forwards Answers to Questions Posed Following Submittal of May 1987 Formal Answers,Including More Detailed Info Re fire-fighting Equipment in Reactor Room & Nearby Areas & Detailed Analysis of Temp Rise Expected in Fuel Element ML20237H3941987-08-11011 August 1987 Requests Ref Matl Listed in Encl 1 & Applications 60 Days Prior to Operator & Senior Operator Licensing Exams Scheduled for Wk of 871130.Requirements for Administering Exam & Rules & Guidance Also Encl ML20236P5661987-08-0505 August 1987 Requests Addl Info Re Vendor Revs to 870702 Triga Research Reactor Requalification Program,Submitted in Response to NRC .Program Does Not Satisfy Revs to 10CFR55 That Became Effective on 870526.Response Requested in 30 Days ML20236H1311987-07-28028 July 1987 Forwards Revised Security Plan,Per RA Erickson 870526 Request.Rev Withheld (Ref 10CFR2.790) ML20215B4931987-06-11011 June 1987 Informs of Recent Reorganization in Nrr.Organization Now Called Standardization & Non-Power Reactor Directorate Under Div of Reactor Projects Iii,Iv,V & Special Projects.Project Manager for Facility Is a Adams 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 1999-08-02
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20210N3311999-08-0202 August 1999 Forwards Proprietary Details Re Loss of Communication Between Dow Emergency Services & Dow Triga Research Reactor. Details of Facility Security Plan Are Withheld Under Provisions of 10CFR2.790 ML20153B5451998-09-14014 September 1998 Forwards Proposed Modified Emergency Plan,Including Version in Form of Strikethrough Format (Deletions) or Bold Format (Additions) & Explanation for Change & Version Incorporated Into Text of Plan.With One Oversize Drawing ML20151Z4391998-07-27027 July 1998 Informs NRC That Wl Rigot Has Assumed Role of Facility Director of Dow Chemical Co Triga Nuclear Reactor,Replacing SB Butts.Sb Butts Will Replace J Roeck as Level 1 Mgt within Administration as Described in 6.1 of Facility TSs ML20198P7821998-01-15015 January 1998 Forwards Proposed Modified Emergency Plan for Dow Triga Reactor & Responses to NRC ML20141C2931997-06-16016 June 1997 Forwards Response to 970417 Request for Addl Info Re Amend Request for FOL R-108.Encl Includes Changes Proposed for Amend 7 & Explanation for Question Raised in NRC Ltr ML20135C7251997-02-24024 February 1997 Forwards Response to NRC Request for Addl Info Re Amend Request for Facility Operating License R-108,ltr Dtd 961217.Encl Includes Changes Proposed for Amend 7 & Explanation for Question Raised in Ltr ML20133G3151996-12-0909 December 1996 Informs That Rept Describing Review of Decommissioning Costs Re Dow Triga Research Reactor Will Be Available for NRC Review When on-site Insp Occurs ML20129B5951996-10-0808 October 1996 Forwards Response to RAI Re 960912 Amend Request for License R-108 ML20115E6671996-07-0808 July 1996 Forwards Proposed Modified Emergency Plan,Including Strikethrough Format (Deletion) or Bold Format (Additions) Version & Version W/Changes Incorporated in Text ML20113C3661996-06-18018 June 1996 Responds to Request for Addl Info Re Amend Request for FOL R-108 ML20101H6281996-03-18018 March 1996 Forwards Annual Rept for Triga Facility for 1995 ML20087E4011995-08-0707 August 1995 Forwards TSs in Response to RAI Re 950607 Application for Amend to License R-108 ML20078M1371995-02-0808 February 1995 Forwards Response to RAI Re 941221 Application for Amend to License R-108 ML20069J1651994-06-0606 June 1994 Notifies That Cw Kocher Has Retired from Dow Chemical Co Effective 940531,therefore,no Longer Needs Senior Operator License SOP-3922 ML20065B2231994-03-28028 March 1994 Informs That Effective 940322,WL Rigot Has Replaced Cw Kocher as Supervisor for Dow Triga Nuclear Reactor (R-108) ML20057D4511993-09-30030 September 1993 Informs That RA Wolcott Replaced Jj Havel as Chairman of Reactor Operations Committee for Dow Triga Research Reactor ML20072Q9111991-03-14014 March 1991 Advises That Power Level Increase to 300 Kw,Authorized by Amend 5 to License R-108,issued on 890508,implemented. Neutron Detectors Near Reactor Core Moved to Reflect Higher Max Power Level ML20062F7411990-11-19019 November 1990 Forwards Microprocessor-Based I&C Sys for Dow Triga Research Reactor, Containing Mods to 901015 Amend Request for License R-108 ML20055F6901990-07-0101 July 1990 Advises That Vendor Has Not Received Part 55 Svcs from NRC & Requests That 900627 Invoice I1111 Be Corrected ML20207C7931988-06-29029 June 1988 Advises That Jj Havel Replaced Mb Gibbs as Chair of Reactor Operations Committee,Effective 880623 ML20154C2651988-04-29029 April 1988 Forwards Mods to Suppl Application for Renewal of License R-108,per a Adams Request ML20236B0621987-10-0505 October 1987 Informs That 870925 Audit of Triga Research Reactor Showed Two Tasks Involving Surveillance Required by Tech Specs Not Done Per Scheduled Weekly Checklist for Wk of 870713.Failure to Complete Tasks Did Not Violate Tech Specs ML20238A0461987-08-14014 August 1987 Forwards Supplementary Info Re Renewal of License R-108 for Dow Triga Research Reactor ML20237L4351987-08-14014 August 1987 Forwards Licensed Operator Requalification Program for Facility.Program Reflects Changes Made Following Guidance of Hn Berkow ,Ansi/Ans 15.1-1977 & Changes in 10CFR55 Effective 870526 ML20238A3091987-08-13013 August 1987 Forwards Answers to Questions Posed Following Submittal of May 1987 Formal Answers,Including More Detailed Info Re fire-fighting Equipment in Reactor Room & Nearby Areas & Detailed Analysis of Temp Rise Expected in Fuel Element ML20236H1311987-07-28028 July 1987 Forwards Revised Security Plan,Per RA Erickson 870526 Request.Rev Withheld (Ref 10CFR2.790) ML20214T0611987-06-0202 June 1987 Forwards ALARA Policy Statement,Revised Requalification Program & Tech Specs & Addl Info in Support of Application for Renewal of License R-108,per a Adams Request ML20213G8111987-05-13013 May 1987 Forwards Endorsement 60 to Nelia Policy NF-160 ML20210S5901987-02-0909 February 1987 Forwards Revised Licensed Operator Requalification Program for Facility,Per Hn Berkow Recommendation.Revised Program Follows Guidance of Ansi/Ans 156.4-1977 ML20214V5141986-12-0202 December 1986 Forwards Check Inadvertently Omitted from 861117 Reactor License Renewal Application ML20116H1641985-04-23023 April 1985 Forwards Endorsement 56 to Nelia Policy NF-160 ML20137G9971985-03-20020 March 1985 Advises of Mods to Physical Security Sys Resulting in Change to Security Plan ML20112E7091984-12-21021 December 1984 Responds to NRC Re Violations Noted in Insp. Corrective Actions:All Licensed Senior Reactor Operators Received Written Reminders of Notification Requirements ML20090F1521984-07-13013 July 1984 Notifies That,Effective 840711,emergency Plan for Dow Triga Research Reactor Implemented ML20081A0941984-03-0101 March 1984 Forwards Revised Emergency Plan ML20028F6771983-01-10010 January 1983 Forwards Public Version of Emergency Plan,Originally Submitted in Oct 1982 ML20079K2791982-12-20020 December 1982 Forwards Public Version of Corrected Pages to Emergency Plan ML20065G8111982-09-29029 September 1982 Forwards Endorsements 47 & 48 to Nelia Policy NF-160. Endorsement 47 Amends Description of Facility to Include Larkin Lab ML20137G9511982-07-13013 July 1982 Notifies That Cw Kocher Reinstated as Reactor Supervisor, Effective 820607 & Fj Knoll Replaced Jm Macki as Research Manager of Bldg 1602 & Chairman of Reactor Operations Committee,Effective 820624 ML20054F5261982-06-10010 June 1982 Forwards Endorsement 46 to Nelia Policy NF-160 ML20041C1611982-02-12012 February 1982 Forwards Endorsement 44 to ANI Policy NF-160 ML20136H4101982-01-26026 January 1982 Responds to NRC 820113 Insp Rept on 811207-10.Requests Rept Be Modified Before Placement in Pdr.No Matls Disposed of by Incineration Under License 21-00265-06 ML20137G9031981-12-11011 December 1981 Informs That Cw Kocher Will Replace Ou Anders as Reactor Supervisor.Cw Kocher Resume Encl ML20004B0951981-04-28028 April 1981 Forwards Endorsement 42 to Nelia Policy NF-160 ML20003G9351981-04-27027 April 1981 Forwards Endorsements 40 & 41 to Nelia Policy NF-160 ML20008E2091980-10-10010 October 1980 Forwards Advance Premium,Std Premium & Reserve Premium Endorsements,Effective 800101.Also Forwards Amend 10 to Indemnity Agreement B-34 ML19351C9701980-09-25025 September 1980 Informs of Adding H Emmel,W Kocher & E Bickel to Reactor Operations Committee,As of 800826.T Parsons Was Deleted from Committee.Forwards Resumes.W/O Encls ML19323J2511980-06-0909 June 1980 Responds to NRC 800507 Ltr Re Dow Chemical Co Triga Reactor Facility Nonpower Reactor Physical Protection Requirement. Response Not Received Re Dow Triga 781005 Security Plan. Security Plan Meets 790724 & 800325 Fr Rules & Regulations ML20137H0451980-02-22022 February 1980 Informs of Personnel Changes in Reactor Operations Committee.H Gill Replaced by J Macki as Committee Chairman, Norwood Replaced by T Prasons as Health Physicist & P North Replaced by J Simpson as Senior Reactor Operator ML19296D3441980-02-22022 February 1980 Informs of Recent Personnel Changes in Reactor Operations. Reactor Operations Committee Chairman H Gill Replaced by J Macki,Health Physicist s Norwood Replaced by J Parsons & Senior Reactor Operator P North Replaced by J Simpson 1999-08-02
[Table view] |
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SD-2cy 4
The Dow Chemical Company Mdand, Michgan 48667 July 8,1996 Mr. Alexander Adams, Jr., Senior Project Manager Non-Power Reactors and Decommissioning Projects Directorate Division of Project Support Office of Nuclear Reactor Regulation DeuMr. Adams Enclosed is a proposed modified emergency plan for The Dow TRIGA Reactor, Facility Operatir.g License No. R-108. I feel the changes are significant and we will not apply the proposud changes until approval by US NRC has been made. Enclosed are two versions of tne plan. One version has all changes highlighted; either in the form of strikethrsegh format (deletions) or bold format (additions); and an explanation for each change. One version has all changes incorporated into the text of the plan. If you have any questions regarding these proposed changes, please contact me at (517) 636-6584.
Regards c
Ward L. Rigot Reactor Supervisor Dow TRIGA Research Reactor Dow Chemical Company G 9607160174 960700 PDR F
ADOCK 05000264 PDR TAMMY A. ECKERD NOTARY PUBLic, BAY COUNTY, MN
^crm uaneewar.um MYCOMMISSONEXPIRESAPRL17,2000 1C3018 g-9(,
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i
. .w Page 1: a-of a : This is a correction of a misplaced word, "a".
Sciences: The Department is now known as the Analytical Sciences Laboratory.
raGeiger-Mueller4tector+ quipped-witheneir-pumpend paper filter;: This deletion is intended to improve the clarity of this sentence.
a Geiger-Mueller detector equipped with an air pump and paper filter,:
This insertion is intended to provide information about the Continuous Air Monitor.
calibrated to provide dose rate information: This insertion is intended to provide information about the Area Monitor.
up40 not exceeding: This change is intended to clarify the sentence; the reactor is not necessarily operated at power levels up to 300 kilowatts each day.
Page 2: Facilliv Director. A manager within the organization of the Analytical Sciences Department who has line management responsibility for members of the reactor staff. This new definition is designed to identify a person with specific responsibilities.
reactoredministrator- Facility Director: There is no person or function labelled
" reactor administrator"; a Facility Director is defined.
normal: This addition is intended to reflect the differences between the normal management organization and the emergency management organization.
Page 3: administrator supervisor: This change is intended to clarify the identity of the person who will initiate emergency activities; there is no reactor administrator, willwankw>f: Delete n ference to the specific rank of the member of management as this changes from time to time.
to: a grammatical change responsible for the administration of all Dow Midland location activities involving the use of radioactive materials and radiation sources including assurance of compliance with United States Nuclear Regulatory Commission (NRC) regulations. a group of knowledgeable persons-from-severalereasef-The-DowC-hemicalfompany-whielnietermines4he policiesendsafety-standards +nellsiattersemeerning+adiological+afety-at4he Midland 4ocation-andoversees4he-facilities-whichetilizefadiationand+adioactive materials: : The Radiation Safety Committee has defined itself thus.
Page 4: Safety-Goordinator-and4heRe-Entry-Teamef4he-Persons responsible for the normal Analytical Sciences Laboratory safety program Inorganie-Analysis Grouprwhieh-is4toused-: Management and organizational changes have eliminated the specific functions of Safety Coordinator and the Re-Entry team but the safety program remains. Persons working in this building are no longer an independent group within the Analytical Sciences Laboratory.
Sciences: See above.
l and-will4iaveponab'e+quipment-for4akingeir-samples: the Michigan Division ,
Industrial hygiene group does not have equipment for taking air samples. I 1
active \ working \em plan \ changes 949426 page i of vi
i l
i Page 5: or-higher-classdemergeney: There is no credible way for this facility to experience an ;
emergency classified higher than " Notification of Unusual Event".
Page 6: salaried: All Senior Reactor Operators, salaried and bargained-for, are included in the )
line of succession. l hi+any: This is intended to remove references to gender.
He-and: This is intended to remove references to gender.
Page 7: Re-entry into a previously evacuated area: This is the addition of a previously missing heading
[ radiological hazard or a potential radiological hazard. or cau= damages :c the facility cr the :;:aff which in g=:ral do ac: include re!:=e:; of+ignific=: q=ntities of radioactive ma:cria! nor ';ignific=: risk 4c the general public. Th:2 emergencies will have effects which tend :c be confined c the facility =d whichcan be corrected with the available persc=c! =d equipment.
Emergency situations within this classification would include breaches of =curi:y, tornado warning:;, prolcaged fireein *- ---^'- '- ""y, ]: The emergency classification is changed to include only radiological hazards; other hazards mentioned in the original Emergency Plan do not credibly lead to radiological hazards at this small research reactor.
snehundary Dow fence line: This is intended to identify a specific boundary. l A 1. 4
[c,\P. -.
The-Alert-class-includes :hc= even:s which+culd, through a combi = tion of failure';
of-fuel <4 adding and+xperiments, lead to a relea= cf radicactive material which could exceed-50 M"C a:4he :,ite be=dary, avemged ever 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,75 mrem whole bcdy dose-accumulated in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,-241-mrem /hr for I hour whole body de';e ra:e, cr 100 mrem-iodine dese. This class includes catastrophic-natura! =d == made events, such as tornado or uncontrolled re!== cf toxic gax';, which would =verely injure the inhabitants: There are no credible circumstances which could lead to this level of classification at this research reactor.
active \ working \em plan \ changes 949426
. page il of vi
O 2 Page 8: Alert: There is no credible combination of circumstances that could lead to an emergency classified as Alert at this facility.
9 A detailed examination of accidents is presented by S. C. Hawley and
, R. L. Kathren in " Credible Accident Analyses for TRIGA and TRIGA-Fueled Reactors" (NUREG/CR-2387 PNL-4028, April 1982). : This j reference is added to provide more information about the evaluation of hazards. !
over4he-past-16-years since 1967: This change is intended to reflect the passing of time.
i Page 9: which is sufficiently lower than that expected from a release from a 1
damaged fuel element (see July 1967) that any such event would surely be detected. At the same time this alarm level is set sufficienmtly higher than the maximum observed natural background that no alarms due to natural background are expected about-three-times the maximum-observed n atural-backgroundrIf-a-release-of-radioactive-materials-is-suspeeted;-either-by-an ,
alarm-from-the-Gontinuous-Air-Monitor-or-the-Area-Moniterr eir-sampling-will-be l initiated 4edetermine4he-magnitudeef4he-release and4hus4he<lassification-levelef4he !
emergency- l The-air-sampling-will-be-conducted to allow an estimate +f4he amount-of-iodine-141 andether-materials-released-Thisavill-consist +f-a-10-minute 40-cubic feet per minute sampleef-airmolleeted-through-a-1-inch-TEDA+harcoal411ter-eartridgeende-particulate prefilter--The-total-activity +naherharcoal-cartridge-is-assumed 4o-be-iodine 131 A G-M-pancakedetector4vith a 2% efficieney4 vill-bessed4o-monitor 4he-radioactivity-on the-charcoal-filter-The models-and-valuesfound-in4GRP-2r10-and-304mve been used to-calculate-a-count-rate-corresponding 4e+-100-mrem 4otal4hyrmd-dese, assuming-a 4-hour-exposure-ande-breathing-rateef-204iters-per-minute-Sueh+n-exposure-could only-be-possible-if-the-total-release-fraction-equilibrium-inventory of 21 mGi-tetal iodines +feachef-24-TRIGA-fuel +1ementsavas-released 4o4he-atmosphere-withinene hour-(Sutton's-formula-for-dispersion)4aking-no+reditfor-any-retentionef-iodine-in4he poolorfor-any-plate-out- i A-portable ionehamber-will-bessed4o-evaluate 4he-possible-wholebody-dose-at4he-site boundary, ;
i active \ working \em plan \ changes 949426 page iii of vi
l The reactor-room area meni:cr-fa O M de:ce:cr) ::: m: :c alarm a: 2 mrem /hr. ' This corre:;pcads to approxima::!y 3 x 10ipGi/mL, the :c:a! re!:ase fraction inventory of noble ga=s at-the equilibrium of one of the TRICA fuel elements, as:;uming perfect mixing-itHhe'-reaetor-room.--- U;ing Sutton':; formula for dispersion this amcun: cf nob!c gas would g:ve a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> average concentratien-of approximately 0.02 MM' at the neares: ';ite boundary in slightly :; table wind conditicas.: These changes have been made as a result of a review of the design basis accident (damage of one fuel element containing the maximum burden of radioactive fission products and the subsequent release of a fixed fraction of these radioactive fission fragments) as follows:
The Dow'TRIGA research reactor achieved initial criticality 6 July 1967. On 10 July 1967 the continuous air monitor alarmed after the very first operation at 100 kilowatts.
Testing indicated the presence of a leaking fuel element in the F (outer) ring which was identified and removed from the core. This event had effects far lower than the design basis accident in that the fuel element was in the outer ring (lowest fission activity) and the reactor had been operated for only a few minutes before the alarm, not the many hours necessary to approach the maximum fission product inventory.
During the testing period in 1967 the continuous air monitor background (radon daughters in the air) was about 100 counts per minute; when the reactor was operated at 100 kilowatts the monitor usually alarmed at 1000 counts per minute within about 75 seconds and leveled off at 4000-4500 counts per minute. If the present continuous air i monitor were no more sensitive that the unit used in 1967 we would expect a leaking fuel element located at the lowest neutron flux, at far from the maximum inventory of..
radioactive fission products, to register more than 10,000 counts per minute on the continuous air monitor during operation at 240 kikowatts.
For comparison the normal background from radon daughters on particulates in the air ranges from about 30-40 counts per minute on a clean day (early Spring in Midland or a north-easterly wind) to some 400-500 counts per minute (late summer in Midland or a temperature inversion).
Thus the choice of the alarm setpoint for the continuous air monitor (4000 counts per minute) is well above the normal background levels and well below the levels expected from the design basis accident.
l l
active \ working \em plan \ changes 949426 page iv of vi i
l From Table 4 (Gaseous Fission Product Activity in the TRIGA Element Containing the i Greatest Activity Following Operation at 365 MWD) of Hawley and Kathren we l choose those noble gas isotopes likely to be present after a three-hour operation, l ignoring those with half-lives too long (days or years) or too short (32 seconds). This l includes the krypton isotopes 85m,87,88, and 89, and xenon isotopes 135 and 135m.
We correct the saturation activity values for the 300-kilowatt maximum operating power of the Dow TRIGA reactor and the 78 fuel elements (rather than 50, as in Hawley and Kathren), apply the calculation for a three-hour operation, apply a low-temperature release fraction of 1.5E-5 proposed by Foushee and Peters, and assume that all of these materials are released from the water at the top of the pool as noble gases. The result is !
that we would expect the release of about 10 millicuries of noble gases, of which more l than halfis due to the 3.2-minute krypton-89 which decays to 15-minute rubidium-89, following damage of the cladding of one fuel element in the B or C rings.
The air exhaust rate in the reactor room is 1700 cubic feet per minute, which is equivilant to 6.9E10 milliliters / day. The release of radioactive materials as above would result in a concentration of about 1.4E-7 microCuries/ milliliter, averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, from the exhaust stack at the east side of the reactor room. The nearest Dow
']
fenceline is about 160 feet west of this stack, some 40 feet west of the western-most J portion of 1602 Building.
This quantity is not sufficient to warrant declaration of an emergency classified as
" Notification of Unusual Event".
In such a case, however, an emergency classified as " Notice of Unusual Event" would be declared because of the fuel damage.
Page 10: [G-M-Pancake-TEDA Charecal 2000 cpm 100 mrem dyroid (Site-Boundary) above baekground dose is pessible.
l Portable-lon-Chamber 0.6 mrem /hr 15 mrem /whole body (Site-Boundary) dese/24 hours is I
pessible.
3 mrem //hr 75-mrem'whele Scdy desel 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is-pessible]: ;
There is no credible way for these Emergency Action Levels to be attained at this facility.
5 7: The number of siren switches has been increased.
active \ working \em plan \ changes 949426 page v of vi
I . .
1 Page11: calibrated-weekly-wititeknowraource tested daily and calibrated semi-annually: The calibration and testing procedures have been changed.
Page 12: vacation 4ists: There is no longer a vacation list that can be used for accounting for j persons during emergencies.
l re-entry 4eantstaff: There is no re-entrj team; the reactor staff performs this function.. I twoportable+, elf-contained breathing-kits 4md: The breathing apparatus has been j removed from the laboratory; the Dow fire department people arrive equipped with this i type of equipment paper..... boots: The coveralls are a lightweight impermeable composite material, and the foot coverings are connected.
Page 13: (Li): Lithium-drifted detectors are no longer used. l l
LarkinLatumd-17021803: Larkin and 1702 facilities have closed; equipment is I available at 1803 Building Page 14: five: seven: The number of siren switches has been increased.
Page 15: re-entry 4eam stali: There is no longer a re-entry team; see above. l i
Page 16: annual biennial: The requalification program is now on a biennial basis.
biennial annual: Training is now a part of the annual hypothetical exercises, fire 4ighting-: Most emergency scenarios do not include fires.
annual: The requalification program is now on a biennial schedule.
l active \ working \em plan \ changes 949426 page vi of vi