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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P7141999-10-26026 October 1999 Informs That Effective 991026,CH Bassett Will Be NRC Inspector for Facility at Purdue Univ,Due to Retirement of Previously Assigned Inspector ML20217L0371999-10-21021 October 1999 Informs That Arrangements Were Made Between P Doyle & R Bean for Administration of Operator Licensing Exam at Purdue Univ Reactor.Exam Scheduled for Wk of 991206.Requests That Listed Matl Be Furnished,In Order to Meet Schedule ML20206K7951999-05-0606 May 1999 Forwards Insp Rept 50-182/99-201 on 990412-15.No Violations Identified ML20199E1781998-12-17017 December 1998 Forwards Revised Emergency Plan for Purdue Univ Reactor PUR-1,which Involves Updating of Names of Organizations on Campus & Clarifying Chain of Command in Event of Emergency ML20199C0261997-11-13013 November 1997 Forwards Certificate Issued to Rs Bean for Becoming Newly Licensed at Univ as Ro.W/O Encl ML20212G8371997-10-31031 October 1997 Forwards Results of Operator Initial Exam Conducted at Purdue Univ on 970929.W/o Encl ML20217E8201997-09-24024 September 1997 Confirms Arrangements Made to Administer Operator Licensing Retake Exam at Purdue Univ Reactor.Exam Scheduled for Wk of 970929 ML20217D6711997-09-24024 September 1997 Forwards Reactor License Exam for R Bean & Copy of NRC Guidance for Proctoring Exams.W/O Encls 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 ML20141A4201997-06-18018 June 1997 Forwards Results of Operator Initial Exam Conducted at Purdue Univ on 970602-03.W/o Encl ML20140C3211997-03-31031 March 1997 Requests That Listed Matl in Encl Be Furnished in Order to Meet Schedule for Written & Operating Exam for Wk of 970604 ML20133F3831997-01-10010 January 1997 Forwards Insp Repts 50-182/96-01 & 70-0152/96-01 on 961216- 19.No Violations Noted ML20132H0131996-12-20020 December 1996 Forwards Annual Repts for Purdue Univ in West Lafayette,In ML20070S0831991-03-18018 March 1991 Forwards Addl Pages to Complete Submissions for Amend for Field Study,Per 901220 Request ML20070S0881991-03-0404 March 1991 Forwards Addl Matl to Support 901220 Amend Request for Field Study ML20059L5191990-09-19019 September 1990 Requests Util Provide Ref Matls Listed in Encl 1, Ref Matl Requirements, for Exam Scheduled for Wk of 901112. Requirements for Administration & Review of & NRC Rules & Guidelines for Written Exams Encl ML20043B9061990-05-17017 May 1990 Requests Finalization of Revs to Emergency Plan for Reactor Re Type & Frequency of Drills,Per Section 9.2, Conduct of Drills & Exercises. ML20012E2351990-03-19019 March 1990 Submits Annual Update to Proposed Schedule for Conversion from High Enriched U to Low Enriched U,Per 10CFR50.64 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 ML20247D0911989-03-23023 March 1989 Provides Annual Update of Proposed Schedule for Conversion from High Enriched U to Low Enriched U.Univ Started Final Design of Core & Reflector & Thermal Hydraulics.Listed Schedule Proposed for Completion of Project ML20207F3901988-08-0808 August 1988 Forwards Amend 9 to License R-87,renewing License for 20 Yrs from Date of Issuance ML20154E6741988-05-13013 May 1988 Forwards PUR-1 Tech Specs Incorporating Changes Discussed in Recent Telcon & Grammatical & Typo Corrections ML20154H4751988-05-0303 May 1988 Forwards Safety Insp Repts 50-182/88-01 & 70-0152/88-01 on 880411-14.No Noncompliance Noted ML20148J1911988-03-23023 March 1988 Provides Annual Update to Proposed Schedule for Conversion from Highly Enriched U to Low Enriched U 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 ML20196C8121988-02-12012 February 1988 Forwards Revised Operator Requalification Program in Response to 880114 Request for Addl Info.Program re-written to Comply W/Ansi/Ans 15.4 & 10CFR55.59 ML20148E8891988-01-14014 January 1988 Forwards Request for Addl Info Re Facility Operator Requalification Program,Per Application for Renewal of R-87.Info Requested within 30 Days of Ltr Date ML20215A7561987-06-11011 June 1987 Informs of Recent Reorganization of Nrr.Ofc Now Standardization & Non-Power Reactor Project Directorate, Under Div of Reactor Projects Iii,Iv,V & Special Projects, NRR 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 ML20216B6511987-05-27027 May 1987 Forwards Final EGG-NTA-7527, Technical Evaluation Rept for Renewal of OL for Purdue Univ Reactor ML20206M8341987-04-14014 April 1987 Ack Receipt of Proposed Schedule for Conversion of Reactor from High Enriched U to Low Enriched U,Per 10CFR50.64 ML20204B2891987-03-17017 March 1987 Advises of Proposed Listed Schedule for Conversion from High Enriched U to Low Enriched U ML20205C1251987-03-13013 March 1987 Notifies of 870416 Public Meeting W/Nrr & Region III Representatives in Rosemont,Il to Discuss Rev to 10CFR55, Operators Licenses & Implementation of Rev.Meeting Agenda Encl ML20214T0631986-12-0202 December 1986 Forwards Response to 861107 Request for Addl Info Re Application for Renewal of License.Encl 2 Includes Missing Page from Original Sar,Per Question 1.Revised Operator Requalification Program Also Encl,Per Question 26 ML20213G4081986-11-0707 November 1986 Forwards Request for Addl Info in Order to Continue Review of Documentation Submitted in Support of Application for Renewal of License R-87.Responses Should Be Provided by 861121 ML20210J4211986-09-25025 September 1986 Forwards Preliminary Questions & Comments for Discussion During 861007 Site Visit Re License Renewal Application ML20214P9711986-09-19019 September 1986 Forwards Revised Operator Requalification Program in Support of Application for Renewal of License R-87 & Request for Exemptions from Portions of Revised Program ML20214P9991986-09-19019 September 1986 Requests Exemptions for Two Licensed Senior Operators from Parts a & B & Portion of Part E Dealing W/Records of 1986 Rev to Operator Requalification Program.Operators Presently Teach Matl Covered in Lectures ML20212M5031986-08-19019 August 1986 Forwards Notice of Consideration of Application for Renewal of License R-87.License Will Not Expire Until Application Finally Determined ML20206N9321986-08-0101 August 1986 Forwards Response to NRC Re Noncompliance Noted in Insp of Licenses R-87 & SNM-142.Response Withheld (Ref 10CFR2.790) ML20207J6821986-07-22022 July 1986 Forwards Safeguards Insp Repts 50-182/86-03 & 70-0152/86-03 on 860624-0708.No Violations Noted ML20207F3651986-07-17017 July 1986 Advises That Tech Specs Submitted w/860630 Ltr Should Be Considered as Part of Application to Renew License R-87 & Not as Separate Item IR 05000182/19860021986-07-15015 July 1986 Forwards Proprietary Safeguards Insp Repts 50-182/86-02 & 70-0152/86-02 on 860624-26 & Notice of Violation.Encls Withheld (Ref 10CFR2.790) ML20199K5251986-06-30030 June 1986 Forwards Rev IV to Tech Specs for License R-87,for Consideration & Approval.Description of Changes Encl ML20206S6781986-06-20020 June 1986 Forwards Safety Insp Repts 50-182/86-01 & 70-0152/86-01 on 860604-05.No Noncompliance Noted ML20210J5521986-03-26026 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 ML20137S4801986-02-11011 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 ML20138N0161985-12-17017 December 1985 Discusses NRC 850927 Order to Show Cause Why All Excess High Enriched U Fuel Should Not Be Removed to Secure Facility Away from Reactor Site.Consent to Order Understood,Since Hearing Not Requested,Nor Order Contested ML20133C0471985-07-25025 July 1985 Advises That License R-87 Scheduled to Expire on 860807. Guidance for Preparing Renewal Application Provided.Requests Supporting Documentation,Including Updated Sar,Operator Requalification Program & Physical Security Plan ML20106C4171985-02-0707 February 1985 Responds to Re Emergency Plan for Facility.Plan Implemented W/Exception of Section 9.2 Re Conduct of Drills & Exercises & Section 9.3 Re Critiques of Drills & Exercises.Full Scenario Will Be Conducted by 860822 1999-05-06
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20199E1781998-12-17017 December 1998 Forwards Revised Emergency Plan for Purdue Univ Reactor PUR-1,which Involves Updating of Names of Organizations on Campus & Clarifying Chain of Command in Event of Emergency ML20132H0131996-12-20020 December 1996 Forwards Annual Repts for Purdue Univ in West Lafayette,In ML20070S0831991-03-18018 March 1991 Forwards Addl Pages to Complete Submissions for Amend for Field Study,Per 901220 Request ML20070S0881991-03-0404 March 1991 Forwards Addl Matl to Support 901220 Amend Request for Field Study ML20043B9061990-05-17017 May 1990 Requests Finalization of Revs to Emergency Plan for Reactor Re Type & Frequency of Drills,Per Section 9.2, Conduct of Drills & Exercises. ML20012E2351990-03-19019 March 1990 Submits Annual Update to Proposed Schedule for Conversion from High Enriched U to Low Enriched U,Per 10CFR50.64 ML20247D0911989-03-23023 March 1989 Provides Annual Update of Proposed Schedule for Conversion from High Enriched U to Low Enriched U.Univ Started Final Design of Core & Reflector & Thermal Hydraulics.Listed Schedule Proposed for Completion of Project ML20154E6741988-05-13013 May 1988 Forwards PUR-1 Tech Specs Incorporating Changes Discussed in Recent Telcon & Grammatical & Typo Corrections ML20148J1911988-03-23023 March 1988 Provides Annual Update to Proposed Schedule for Conversion from Highly Enriched U to Low Enriched U ML20196C8121988-02-12012 February 1988 Forwards Revised Operator Requalification Program in Response to 880114 Request for Addl Info.Program re-written to Comply W/Ansi/Ans 15.4 & 10CFR55.59 ML20216B6511987-05-27027 May 1987 Forwards Final EGG-NTA-7527, Technical Evaluation Rept for Renewal of OL for Purdue Univ Reactor ML20204B2891987-03-17017 March 1987 Advises of Proposed Listed Schedule for Conversion from High Enriched U to Low Enriched U ML20214T0631986-12-0202 December 1986 Forwards Response to 861107 Request for Addl Info Re Application for Renewal of License.Encl 2 Includes Missing Page from Original Sar,Per Question 1.Revised Operator Requalification Program Also Encl,Per Question 26 ML20214P9991986-09-19019 September 1986 Requests Exemptions for Two Licensed Senior Operators from Parts a & B & Portion of Part E Dealing W/Records of 1986 Rev to Operator Requalification Program.Operators Presently Teach Matl Covered in Lectures ML20214P9711986-09-19019 September 1986 Forwards Revised Operator Requalification Program in Support of Application for Renewal of License R-87 & Request for Exemptions from Portions of Revised Program ML20206N9321986-08-0101 August 1986 Forwards Response to NRC Re Noncompliance Noted in Insp of Licenses R-87 & SNM-142.Response Withheld (Ref 10CFR2.790) ML20207F3651986-07-17017 July 1986 Advises That Tech Specs Submitted w/860630 Ltr Should Be Considered as Part of Application to Renew License R-87 & Not as Separate Item ML20199K5251986-06-30030 June 1986 Forwards Rev IV to Tech Specs for License R-87,for Consideration & Approval.Description of Changes Encl ML20106C4171985-02-0707 February 1985 Responds to Re Emergency Plan for Facility.Plan Implemented W/Exception of Section 9.2 Re Conduct of Drills & Exercises & Section 9.3 Re Critiques of Drills & Exercises.Full Scenario Will Be Conducted by 860822 ML20084M3301984-05-11011 May 1984 Responds to Re Emergency Plan Not Adequately Addressing 10CFR50,App E Requirements.Possibility of Fire Remote,Therefore,Alarm Unwarranted.Forwards Rev 1 to Page 34 of Emergency Plan,Changing Internal Drills to Annual ML20028C3811982-12-10010 December 1982 Forwards Public Version of Amended Emergency Plan ML20028A6381982-11-0303 November 1982 Forwards Public Version of Emergency Plan ML20066D5871982-10-20020 October 1982 Submits Public Version of Request for Extension to 821231 to Submit Revised Emergency Plan ML20063A5901982-08-16016 August 1982 Provides Addl Info for Change 1 to Tech Specs Re Reactivity Limits,As Requested in ML20009E4341981-07-20020 July 1981 Requests Exception to Parts A,B & E of Operator Requalification Program for Two Senior Operators.Both Operators Are Members of Committee on Reactor Operations ML20004F0231981-06-0909 June 1981 Forwards 810608 Followup Ltr to 810602 Telegram Re Reactor Scram Times Exceeding Tech Specs ML20003H3991981-04-0909 April 1981 Responds to NRC 810318 Ltr Re Violations Noted in IE Insp Rept 50-182/81-02.Corrective Actions:Reminder Will Be Put on Surveillance Status Board 5 Months After Last Coro Meeting ML19253C4431979-11-21021 November 1979 Forwards Executed Amend 10 to Indemnity Agreement E-6, Modifying Prefatory Language Re Course of Transportation. ML19270G5201979-06-0505 June 1979 Forwards Modified Physical Security Plan.Plan Withheld (Ref 10CFR2.790) 1998-12-17
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PURDUE U N IVE RSITY
s i
DEPARTMENT OF 4
R Aoiotoolc AL AND i
E.NvlRoNMENTAL M AN AoE Mi.HT March 18, 1991 l
i l U. S. Nuclear Regulatory Commission Materials Licensing Section 799 Roosevelt Road Glen Ellyn, Illinois 60137 1
Gentlemen:
Please find enclosed four additional pages to complete the submissions request was for an filed amendment for a field study. The original in a letter dated Supplemental information was filed on March December 4, 1991.
20, 1990.
Complete j
copies have also been submitted to Dr. Donna-Beth Howe, NMSS, Washington.
If there should be any questions please call me at Since the 317-494-2350.
first nesting period is expected to begin any day and valuable data may be lost, we would appreciate expedited handling of this request.
this matter. Thank you in advance for your consideration of Sincerely, p,1l$f /, ' #
v names P. Schweitzer Ph.D.
Radiation Safety Officer i
i P l' l Enclosures JN/tn 9104020122 91031G 7 -x nsoog
._ civit cnoistcaino suitomo. ein + wrer t-Avent,IN mo? .
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Watersheds and Drinking Water Two watersheds drain the NWSCC property. The extreite northern portion of the site is drained by Lake Greenwood which flows into First Creek. This watershed empties into the west fork of the White River, the Wabash River a.nd ultimately' the Ohio River.
Flow in First Creek is less than 5 cubic feet per second (1.6 million callons per day).
Lake Greenwood.
This flow is 0.06% af the capacity of Any tritium released in this watershed would b mixed thoroughly and be at a concentration of less than 2 x 10 -0 microcuries/mL as previously discussed. Dose calculations have been previously shown for drinking three liters of water per day from this source.
The east majority fork of the of the siteRl',er White is rerved (3.3by x cbeeks 10 gallons that empty into the per day) . The creeks: Little sulphur, Sulphur, Turkey and Seed Tick all have flows of less than 1.6 million gallons per day. Boggs Creek (central portion of the site) has a flow of 3-6 million gallons gheer day. In one case miximum daily rate)(allthe theconcentration tritium released to Boggs would be 1.2Creek x 10- g.
miccccuries/mL _'
l.5 mil 11 curies 3 x 106 gallons x 3785 mL/ gallon= 1.2 x 10 11 uCi/mL j This is one billionth of the MPC of 3 x 10-3 uCi/mL. To approach MPC on any given day, the flow rate of a creek would need to be less than 132 gallons per day.
) 1.5 millicuries 132 gallons x 3785 mL/ gallon = 3 x 10~3 uC1/r.1 There in depth are seven from 100-225 wellsfeet.
in the southern portion of the site ranging These wells serve the rest facility and are r.ot a prime /y source of drinking water. -Lake Greenwood is the primary drinking wat er source and calculations for dose from ingestion have been per 'ormed.
Access Access t.o the site is strictly controlled however no fences would prohibit site personnel from entry into areas where the bird population nests.
The roads are patrolled 24-hours a day and any unauthorized personnel are required to return to the industrial and residential area. Researchers must notify security te advise them of their presence in these areas outside of the industrial complex. Approximately 60 children may live la the rasidential area at one time. The same methods as above are used to prevent entry of the children into these areas.
I
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Miscellaneous Gardens may be present only at the residential areas. Due-to the prolific deer population it is difficult to grow vegetables since they are consumed by the deer. Therefore a small percentage of food intake would be from gardens.
.The recreation activities are limited to fishing in- Lake Greenwood and hunting - deer during the season (October 10 - -
December 31).
The procedure described by Nagy includes pipetting by mouth. The researcher is prohibited from- mouth pipetting as are all researchers at Purdue.
.ake Greenwood is approximately 820 acres and the dimensions are 3.5 miles by 0.5 miles.
The instructions to people on base will inclua; the phone number of the Command Duty Of ficer which is manned-24 hours / day. Tho.
notice will also include: "If sick, wounded or dead birds are found, they should not be handled." The Command Duty Officer will be given instructions describing. -procedures .if birds are found.
- l'
v In original documents submitted regarding the release of tritium to the environment some assumptions were made. All the assumptions were very conservative and in all instances illustrated the worst possible case. Many of the assumptions were also mutually exclusive which could lead to an overestimation in exposure by at least a factor of two.
Some of the factors that need clarifice. tion and reconsideration are below:
Deposition and Uptake oLIrit.iura The model assumes total deposition of all tritium on plants or uptake into plants such that consumption of all plants within a given area would result in the ingestion of all the tritium released In reality many factors would prevent this from occurring.
- 1. Rainfall and subsequent runoff would remove up to 30 percent of the tritium deposited (NCRP).
- 2. Much of the water vapor respired by the birds would actually never be deposited on the ground. A small percentage would enter into the groundwater cycle and essentially be lost from circulation. Up to 60 percent may be lost by evapo-tanspiration to the atmosphere
(!!CRP) .
- 3. In addition concentration by plants would not exceed 0.5 of tue amount present in the environment.
Taking these factors into account the amount available from plants in the garden scenario and deer consumption scenario wculd be one-fourth.
0.5 (concentration by plants) x 0.5 (loss from environment by evapo-transpiration) = 0.25 reduction Bioelimination The model also assumed no biological elimination by deer or plants. If a hc l ?-life of 5 days ir the door (maximum probable) is ar.sumed from the Ir.e t release (August 15) to the beginning of deer seaso.. IOctober 6) three half-lives would pass. This could cesult in a reduction by one-eighth in the amount of tritium present.
In addition, most deer would graze outside the 25 square mile nesting area and not have a diet that consists solely of tritiated plants.
0.125 redNtion
.i -
i a-Bird Density The concentration of birds in the environment is also likely to be -less than -- the 10 . birds per square . mile - as originally stated.-
approximately 25 square The miles. ' habitats "to be- studied cover (See_ map provided) With a maximum of eighty birds the average density would-be 3.2 birds per. square mile.
which excrete up to 0.25 millicuries If this -is rounded to' 5 btrds -
the theoretical maximum would be 1.25 millicuries oor square-mile.
0.5 reduction .
Conclusiong T1.e scenarios regarding garden ingestion- and- deer consumption would change-if these more realistic = factors are considered.
1.
For the garden ingestion the-dose would be reduced by 0.25 (Deposition and uptake of tritium)'x 0.5 (Bird Density)'= 0;125 0.125 x .25-millirem = .-031 millirem
- 2. For the deer consumption scenario _the dose would be reduced by 0.25 (Deposition ' and uptake of = tritium): x 0.5 (Bird Density)l x--0 125- (Bioelimination) '= .016- .
0.016-x 3 millirem-= .048 millirem Again. these estimates. would . pertain to- the maximally _.
exposed indiv_idual and-- are ; not' likely~ tot- be reached- =in: -
normal circumstances.
Reference:
llational Council' on -Radiation- Protection :and
- Measurernents, Report No. 62 March 9,-1979 c
f.
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