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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:NRC TO EDUCATIONAL INSTITUTION
MONTHYEARML20059L5191990-09-19019 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 ML20207F3901988-08-0808 August 1988 Forwards Amend 9 to License R-87,renewing License for 20 Yrs from Date of Issuance ML20154H4751988-05-0303 May 1988 Forwards Safety Insp Repts 50-182/88-01 & 70-0152/88-01 on 880411-14.No Noncompliance Noted 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 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 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 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 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 ML20207J6821986-07-22022 July 1986 Forwards Safeguards Insp Repts 50-182/86-03 & 70-0152/86-03 on 860624-0708.No Violations Noted 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) 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 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 ML20062H2291979-05-11011 May 1979 Forwards IE Info Notice 79-12, Attempted Damage to New Fuel Assemblies ML20062F3281978-11-28028 November 1978 Forwards Amend 3 to Subj Facil Lic R-87 & Safety Eval ML20062B5161978-09-21021 September 1978 Forwards Insp Rept 50-182/78-02 on 780816-18 & Notice of Violation 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 1990-09-19
[Table view] Category:OUTGOING CORRESPONDENCE
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 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 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 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 ML20207F3901988-08-0808 August 1988 Forwards Amend 9 to License R-87,renewing License for 20 Yrs from Date of Issuance ML20154H4751988-05-0303 May 1988 Forwards Safety Insp Repts 50-182/88-01 & 70-0152/88-01 on 880411-14.No Noncompliance Noted 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 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 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 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 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 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 ML20207J6821986-07-22022 July 1986 Forwards Safeguards Insp Repts 50-182/86-03 & 70-0152/86-03 on 860624-0708.No Violations Noted 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) 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 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 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 ML20062H2291979-05-11011 May 1979 Forwards IE Info Notice 79-12, Attempted Damage to New Fuel Assemblies ML20062F3281978-11-28028 November 1978 Forwards Amend 3 to Subj Facil Lic R-87 & Safety Eval ML20062B5161978-09-21021 September 1978 Forwards Insp Rept 50-182/78-02 on 780816-18 & Notice of Violation 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 1999-05-06
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o UNITED STATES NUCLEAR REGULATORY COMMISSION
, E WASHINGTON, D. C. 20555
\...../ JUL 2 5 585 Docket No. 50-182 Mr. Eldon R. Stansberry Reector Supervisor Department of Nuclear Engineering Purdue University West La'ayette, Indiana 47907
Dear Mr. Stansberry:
SUBJECT:
RENEWAL OF OPERATING LICENSE R-87 This letter is to remind you that the Operating License No. R-87 for the Purdue University research reactor is scheduled to expire or Aucust 7, 1986, and te provide you guidance for preparing your application for a renewal of tha license. Title 10 of the Code of Federal Requietions i
(10 CFR 2.109) allows continued operation under your current license until the Nuclear Regulatory Comission (NRC) acts upon an application for renewal provided the application is received at least 30 days prior to the expiration date of your current license.
The NRC considers the renewal of a non-power reactor operating license to be equivalent to reissuina the license. Therefore, renewal is not merely a routine administrative step, but involves in-depth reviews of all documentation related to the facility, an on-site review, and publication
, in the FEDERAL REGISTER of a notice of your request that provides the opportunity for public participation, as well as a notice of the results of our review of your rpplication.
Your rene:wal application should address the requirements in applicable sections of Title 10 of the Code of Federal Regulations, and should demonstrate that the reactor can continue to be operated safely and without adverse impact on the environment or the public. For the review of your renewal application, the NRC staff will apply the cuidance contained in the NPC Division 2 Regulatory Guides for Research Rectors (Enclosure 1) and the industry standards in the American Nuclear Society ANS-15 Series for research reactors.
In order for us to perfonn an adeouate review, you are requested to include, as part of your application, all of the following documentation,
, in accordance with in CFP 50.33 and 50.34:
- 1. Updated Safety Analysis Report (SAR) i A complete updated edition of your Safety Aralysis Report (SAR) and Technical Specifications are required to be submitted with your renewal application. The SAR should include inforretion that describes 4
8500060336 DR 850725 p ADOCM 05000192 PDR
Eldon R. Stansberry the facility and all changes made during the license period; the design bases and limits on its operation; and a safety analysis of the structures, components and systems to ensure that they will be able to continue to perform their intended functions. Potential and reasonable accident scenarios and their consequences should be analyzed using the best current input data and computational techniques, and should be compared, wherever possible, with facility operating experience.
Furthermore, the SAR should include updated information and analyses on demography, meteorology, geology, seismology and other natural and unnatural phenomena.
- 2. Financial Qualifications to Continue Operation [10 CFR 50.33(f)]
This information must show that there is reasonable assurance that you will be able to obtain the funds necessary to cover estimated operating costs for the period of the requested license renewal plus the estimated costs of permanently shutting down the facility and either decomissioning it or maintaining it in a safe condition. To facilitate our review, we request that the following information be provided, appropriately certified:
- a. The most recently published annual financial statement of the University. Indicate the source of funds utilized to cover costs of operation of the reactor facility,
- b. The estimated annual cost to operate the reactor for the requested oeriod of renewal, the underlying assumptions and bases of the estimate and certification that future budgets will include these funds, and
- c. The estimated costs of eventually shutting down the reactor and safely disposing of it, a listing of what is included in these costs, the assumptions underlying these estimated costs, the type of shutdown contemplated, and the source of funds to cover these costs.
- 3. EnvironmentalReport(10CFR51)
Your Environmental Report (ER) should include sufficient operational data, analyses and discussions to provide a substantial basis for NRC to develop its environmental assessment (see enclosure for an example of an Environmental Report).
- 4. Technical Specifications The content and format for Technical Specifications should be in conformance with ANS!/ANS 15.1-1982, "The Development of Technical Specifications for Research Reactors." Any substantive changes to the
Eldon R. Stansberry -
Q current Technical Specifications should be proposed and justified at the time of the license renewal application so they can be evaluated i during the review. Note that in following the ANSI /ANS 15.1-1902 format, bases must be included to support all " specifications."
- 5. Oparator Pequalification Program (10 CFR 50.54 (1-1) and 10 CFR 55, Appendix A)
A copy of your current and inclerented operator requalification procram must be submitted to ersure that it is reviewed with your renewal application and meets current NPC reouirements for non-power reactors (guidance contained in ANS 15.4-1978).
- 6. Emeroency Plan (10 CFR 50.54(q) and (r) and 10 CFP 50, Appendix El As your revised Erergency Response Plan (ERP), dated May 10, 1984 has been approved by NRC, you need only reference those respective Purdue and NPC docunents. However, if you wish to modify your ERP, any changes nust be submitted for NRC review in accordance with the above-cited regulations.
- 7. Physical Security, Plan (10 CFR 73.67)
You have an approved Physical Security Plan on file with NRC.
Accordingly, you need only reference the license amendnent containing that dor.unentation. However, if you wish to modify your Physical Security Plan, changes should be made in accordance with the requirements of 10 CFR 50.54(p) or 10 CFR 50.90.
- 8. Filing of Application i The requirements for submitting your renewal application and all other formal docurentation relating to your license with respect to addressee, notarization, signatory and number of copies are defined in NPR Generic Letter No. 84-18, " Filing of Applications for Licenses and Amendments," from Darrell G. Eisenhut to All Non-Power Peector Licensees, dated July 6, 1984. Please follow the guidance in this letter.
For your further guidance in preparing the proper infornation to be
! includad in your license renewal application, we are enclosing a copy of a license renewal package recently issued for a reactor facility (UVA,
- Enclosure ?) similar to yours. This includes the staff's Safety Evaluation 2 Reports and Environmental Assessment, and the new license for the reactor, i Upon completion of our review and a favorable evaluation of your facility, similar documents will be issued in conjunction with renewal of your reactor operatino license. He emphasize that these enclosures, except for the Technical Specifications, were developed and issued by the staff and are provided as examples of the types of findings we must make. Your documentation 1.1ust provide the technical and descriptive information that will support our issuance of similar evaluations for your facility, i
i
Eldon R. Stansberry 1 If you have any questions, please contact Robert Carter, our project
- manager for your facility, at (301) 492-9795.
Sincerely, Gwo. &-
i Cecil 0. Thomas, Chief Standardization and Special Projects Division of Licensing
Enclosures:
As stated cc: See next page t
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- .-.-, , ., . - - . . - - -. ., , - - - - - --- -.-- -,----.. , . - - . . . - , - - - --n.-- - - . . - - . -- . .n - -
Purdue University Docket No. 50-182 cc: ifr. Arthur J. Ladow City Building West Lafayette, Indiara 46901 State Board of Health AW: Director, Rureau of Engineering 1330 k'est Michigan Street Indianapolis, Indiana 46206 Attorney General State House Indianapolis, Indiare e
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JUL 2 51985 Eldon R. Stansberry If you have any questions, please contact Robert Carter, our project manager for your facility, at (301) 492-9795.
Sincerely, Cecil 0. Thomas, Chief Standardization and Special Projects Division of Licensing
Enclosures:
As stated cc: See next page i DISTRIBUTION l
Docket FTTe=
NRC PDR SSPB Reading RCarter PAnderson HBerkow CThomas Region III l
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