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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20196L2741999-05-20020 May 1999 Informs That Univ of Wa Did Not Receive Project Funding from State of Wa Legislature for Upcoming Biennium,Which Is from 1999 to 2001.University Intends to Leave Reactor in Current stand-by Status Until Addl Funding Received ML20155E0941998-10-20020 October 1998 Confirms Conference Call of 981013 & 980923 Meetings Re Univ of Washington Research Reactor Decommissioning Project Budget Status.Decommissioning Plan Will Be Amended.Amend Will Be Submitted Prior to Start of First Phase ML20248M2831998-06-11011 June 1998 Forwards Insp Rept 50-139/98-201 on 980514.No Violations Noted.Various Aspects of Safety Program Were Inspected Including Selective Exams of Procedures & Representative Records,Interviews W/Personnel & Observation of Facility ML20059M3931990-09-26026 September 1990 Ack Receipt of Transmitting Change to Physical Security Plan.Nrc Considers Security Plan to Be Withdrawn. Ltr Withheld (Ref 10CFR2.790) ML20056A5371990-07-31031 July 1990 Responds to 900706 Request for Addl Info Re Decommissioning Univ of Washington Argonaut Reactor.Items Refer to Sections 1.3 & 2.1 of Razebld Decommissioning Plan ML20055E4501990-07-0606 July 1990 Forwards Second Request for Addl Info Re Razebld Decommissioning Plan ML20055C3411990-02-0808 February 1990 Forwards Insp Rept 50-139/90-02 on 900111.No Violations Noted ML20246P0111989-08-29029 August 1989 Submits Statement of Intent Re Financial Assurance for Decommissioning Reactor.During First Phase of Decommissioning,Reactor Will Be Defueled & Fuel Shipped to DOE Facility.State of Wa Funds Will Be Requested ML20246F3601989-08-23023 August 1989 Forwards Tech Specs for Possession Only License,Revising Tech Specs Transmitted w/890803 Application.Tech Specs Will Go Into Effect When Fuel Removed from Site.Application Requests Security Plan Exemption ML20245G4841989-08-10010 August 1989 Advises That 890803 Application for Amend to License R-73 Should Be Considered as Application for Possession Only,That Tech Specs Be Considered New & Not Revised & That Emergency Plan Be Emergency Plan for Possession Only License ML20248B7081989-08-0303 August 1989 Forwards Application for Proposed Amend 15 to License R-73, Terminating Security Plan & Amended Security Plan.Reactor Defueled & Fuel in Storage Tubes at Univ ML20247G5671989-05-19019 May 1989 Provides Procedure Outline for Decommissioning Reactor to Convert Facility Housing to Subcritical Assembly.Application Should Include Decommissioning Plan Which Discusses Radioactivity Levels Prior to Installation of Assembly ML20247M6121989-03-23023 March 1989 Requests That Nuclear Reactor No Longer Required to Meet 10CFR50.64 Requirements Due to Decommissioning Plans & Disposal of High Enrichment Fuel ML20195H0451988-11-18018 November 1988 Forwards Amend 14 to License R-73 & Safety Evaluation.Amend Allows Certain Surveillance Requirements Associated W/ Operation of Reactor to Be Suspended If No Fuel in Core ML20205T6921988-11-0303 November 1988 Notifies of 890110 Meeting W/Region V in San Francisco,Ca to Discuss Policies & Procedures for Operator Licensing Activity in Region V.Agenda Encl ML20155F0961988-10-0606 October 1988 Forwards Application for Amend to License R-73,removing Surveillance of Rod Drop Times,Shutdown Margin,Reactivity Insertion Rate of Control Rods & Power Calibr of Safety Channels ML20151U7541988-08-11011 August 1988 Informs of NRC Interpretation of Section 10CFR50.74(a) Re Changes in Operator or Senior Operator Status 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 ML20153B3061988-03-17017 March 1988 Forwards Doe,Ofc of Energy Research,Div of Univ & Industry Programs Notifying That Funds for Conversion of Reactor from Highly Enriched U to Low Enriched U Will Not Be Available During FY88 ML20148G6761988-03-10010 March 1988 Forwards Insp Rept 50-139/88-01 on 880111.No Violations or Deviations Noted ML20147D0421988-02-29029 February 1988 Requests That Recipient Resubmit Proposal to Convert to Low Enriched U Fuel to Meet 10CFR50.64(6)(2) or (3) Requirements by 880327.Identical Ltrs Sent to Listed Dockets ML20149M3561988-02-24024 February 1988 Forwards Amend 13 to License R-73.Amend Modifies Tech Specs to Change Permissible Rod Drop Time of Shim Rod 3 to 3 s, Increases Surveillance Frequency for All Control Rods & Reduces Core Excess Reactivity to 1.9% Delta K/K ML20147G9681988-01-14014 January 1988 Notifies of Plan to Amend Tech Specs,Changing Drop Time Limit for Shim Rod 3 to 2 Seconds.Change Will Be Requested Due to Gradual Loss of Excess Reactively Caused by Leakage of Water from Fuel Box Gasket & 880104 Event IR 05000139/19870021987-12-0404 December 1987 Forwards Matl Control & Accounting Safeguards Insp Rept 50-139/87-02 on 871116 & 17.No Violations or Deviations Noted.Rept Withheld (Ref 10CFR2.790(d)) ML20235U1941987-10-0606 October 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-139/87-01.Periodic Measurement of Rod 3 Drop Time Following Reactor Operation Expected Based on 870930 Telcon ML20235J9721987-09-25025 September 1987 Extends Invitation to Attend 871110 Meeting W/Region V in San Francisco,Ca to Discuss Policies & Procedures for Operator Licensing Activity in Region V & NRC Policy & Developments ML20235U2151987-09-22022 September 1987 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-139/87-01.Corrective Actions:Consultation W/Univ Police Dept Has Led to Improvement in Coordination.New Video Cassette Recorder Being Prepared ML20238D7511987-08-28028 August 1987 Forwards Insp Rept 50-139/87-01 on 870727-28 & Notice of Violation ML20215C6351987-06-11011 June 1987 Informs of Recent NRR Reorganization.Current Ofc Now Called Standardization & Non-Power Reactor Directorate,Under Div of Reactor Projects Iii,Iv,V & Special Projects,Nrr.T Michaels Project Manager for Facility ML20204B8371987-03-18018 March 1987 Advises That,Per Encl DOE to Univ,Availability of Funding for FY87 for Conversion of highly-enriched U to low- Enriched U Withdrawn ML20206R6801986-06-27027 June 1986 Forwards Safeguards Insp Repts 50-139/86-01 & 50-139/86-02 on 860602-03.No Violation Noted ML20140G7111986-03-27027 March 1986 Lists Change in Telephone Number for H Bernard,Facility Project Manager,Due to NRR Reorganization.D Tondi New Nonpower Reactor & Safeguards Licensing Section Leader. Correspondence Should Be Sent to Listed Address ML20136F8091985-11-18018 November 1985 Informs That Excess Unirradiated Highly Enriched U Can Be Removed from Facility within 120 Days of Effective Date of Show Cause Order ML20136A9181985-11-14014 November 1985 Responds to 851023 Request for Guidance on Any Requirement Re Use of N Stamped Equipment in Reactor Thermal Hydraulic Circuits.No Stamping Requirements Contained in 10CFR or in Manuals or Guides ML20133P6471985-10-23023 October 1985 Requests Confirmation of Interpretation That Training Reactor Not Required to Have N Stamped Equipment Installed in Thermalhydraulic Circuits.Univ Planning Major Reactor Refurbishing ML20138G6971985-10-14014 October 1985 Ack Receipt of Show Cause Order to Dispose of Highly Enriched U Fuel.Requests Extension Beyond 120 Days,Until DOE Richland Operations Ofc Can Assume Possession ML20138A0801985-10-0404 October 1985 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp on 850717-19 ML20138A0991985-09-26026 September 1985 Responds to NRC Re Violations Noted in Insp on 850717-19.Corrective Actions:Evacuation Drills Will Be Held Annually & Written Operator Exams Will Be Held During Last Quarter 1985 ML20135F9711985-09-0404 September 1985 Forwards Insp Rept 50-139/85-01 on 850717-19 & Notice of Violation ML20129E9971985-05-0909 May 1985 Responds to FOIA Request for Compilations of Results of Operator Licensing & Requalification Exams.App a Documents Placed in Pdr.App B Documents Already in PDR ML20127M3791985-05-0606 May 1985 Advises That 850205 & 0424 Changes to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20127P1151985-04-24024 April 1985 Forwards Exam Rept 50-139/OL-85-01 on 850325-26 ML20197H1651984-06-12012 June 1984 Forwards IE Safeguards Insp Rept 50-139/84-01 on 840424 & Notice of Violation ML20140C0351984-03-24024 March 1984 FOIA Request for All Physical & Safeguards Insp Repts from 1979 to Present at Ucla,Univ of Washington,Univ of Florida, Virginia Polytechnic Inst & Iowa State Univ IR 05000139/19820021982-07-29029 July 1982 Forwards IE Safeguards Insp Rept 50-139/82-02 on 820722.No Noncompliance Noted ML20054L6971982-06-23023 June 1982 Forwards IE Insp Rept 50-139/82-01 on 820608-11.No Noncompliance Noted 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 ML20126M2231981-06-0404 June 1981 Forwards Amend 11 to License R-73 & Safety Evaluation.Amend Reduces Possession Limit of SNM to 4.4 Kg U-235 & Authorizes Offsite Storage of 3.5 Kg of U-235 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 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 1999-05-20
[Table view] Category:NRC TO EDUCATIONAL INSTITUTION
MONTHYEARML20059M3931990-09-26026 September 1990 Ack Receipt of Transmitting Change to Physical Security Plan.Nrc Considers Security Plan to Be Withdrawn. Ltr Withheld (Ref 10CFR2.790) ML20055E4501990-07-0606 July 1990 Forwards Second Request for Addl Info Re Razebld Decommissioning Plan ML20055C3411990-02-0808 February 1990 Forwards Insp Rept 50-139/90-02 on 900111.No Violations Noted ML20247G5671989-05-19019 May 1989 Provides Procedure Outline for Decommissioning Reactor to Convert Facility Housing to Subcritical Assembly.Application Should Include Decommissioning Plan Which Discusses Radioactivity Levels Prior to Installation of Assembly ML20195H0451988-11-18018 November 1988 Forwards Amend 14 to License R-73 & Safety Evaluation.Amend Allows Certain Surveillance Requirements Associated W/ Operation of Reactor to Be Suspended If No Fuel in Core ML20205T6921988-11-0303 November 1988 Notifies of 890110 Meeting W/Region V in San Francisco,Ca to Discuss Policies & Procedures for Operator Licensing Activity in Region V.Agenda Encl ML20151U7541988-08-11011 August 1988 Informs of NRC Interpretation of Section 10CFR50.74(a) Re Changes in Operator or Senior Operator Status ML20148G6761988-03-10010 March 1988 Forwards Insp Rept 50-139/88-01 on 880111.No Violations or Deviations Noted ML20147D0421988-02-29029 February 1988 Requests That Recipient Resubmit Proposal to Convert to Low Enriched U Fuel to Meet 10CFR50.64(6)(2) or (3) Requirements by 880327.Identical Ltrs Sent to Listed Dockets ML20149M3561988-02-24024 February 1988 Forwards Amend 13 to License R-73.Amend Modifies Tech Specs to Change Permissible Rod Drop Time of Shim Rod 3 to 3 s, Increases Surveillance Frequency for All Control Rods & Reduces Core Excess Reactivity to 1.9% Delta K/K IR 05000139/19870021987-12-0404 December 1987 Forwards Matl Control & Accounting Safeguards Insp Rept 50-139/87-02 on 871116 & 17.No Violations or Deviations Noted.Rept Withheld (Ref 10CFR2.790(d)) ML20235U1941987-10-0606 October 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-139/87-01.Periodic Measurement of Rod 3 Drop Time Following Reactor Operation Expected Based on 870930 Telcon ML20235J9721987-09-25025 September 1987 Extends Invitation to Attend 871110 Meeting W/Region V in San Francisco,Ca to Discuss Policies & Procedures for Operator Licensing Activity in Region V & NRC Policy & Developments ML20238D7511987-08-28028 August 1987 Forwards Insp Rept 50-139/87-01 on 870727-28 & Notice of Violation ML20215C6351987-06-11011 June 1987 Informs of Recent NRR Reorganization.Current Ofc Now Called Standardization & Non-Power Reactor Directorate,Under Div of Reactor Projects Iii,Iv,V & Special Projects,Nrr.T Michaels Project Manager for Facility ML20206R6801986-06-27027 June 1986 Forwards Safeguards Insp Repts 50-139/86-01 & 50-139/86-02 on 860602-03.No Violation Noted ML20140G7111986-03-27027 March 1986 Lists Change in Telephone Number for H Bernard,Facility Project Manager,Due to NRR Reorganization.D Tondi New Nonpower Reactor & Safeguards Licensing Section Leader. Correspondence Should Be Sent to Listed Address ML20136F8091985-11-18018 November 1985 Informs That Excess Unirradiated Highly Enriched U Can Be Removed from Facility within 120 Days of Effective Date of Show Cause Order ML20136A9181985-11-14014 November 1985 Responds to 851023 Request for Guidance on Any Requirement Re Use of N Stamped Equipment in Reactor Thermal Hydraulic Circuits.No Stamping Requirements Contained in 10CFR or in Manuals or Guides ML20138A0801985-10-0404 October 1985 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp on 850717-19 ML20135F9711985-09-0404 September 1985 Forwards Insp Rept 50-139/85-01 on 850717-19 & Notice of Violation ML20127M3791985-05-0606 May 1985 Advises That 850205 & 0424 Changes to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20127P1151985-04-24024 April 1985 Forwards Exam Rept 50-139/OL-85-01 on 850325-26 ML20197H1651984-06-12012 June 1984 Forwards IE Safeguards Insp Rept 50-139/84-01 on 840424 & Notice of Violation IR 05000139/19820021982-07-29029 July 1982 Forwards IE Safeguards Insp Rept 50-139/82-02 on 820722.No Noncompliance Noted ML20054L6971982-06-23023 June 1982 Forwards IE Insp Rept 50-139/82-01 on 820608-11.No Noncompliance Noted 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 ML20126M2231981-06-0404 June 1981 Forwards Amend 11 to License R-73 & Safety Evaluation.Amend Reduces Possession Limit of SNM to 4.4 Kg U-235 & Authorizes Offsite Storage of 3.5 Kg of U-235 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 1990-09-26
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20248M2831998-06-11011 June 1998 Forwards Insp Rept 50-139/98-201 on 980514.No Violations Noted.Various Aspects of Safety Program Were Inspected Including Selective Exams of Procedures & Representative Records,Interviews W/Personnel & Observation of Facility ML20059M3931990-09-26026 September 1990 Ack Receipt of Transmitting Change to Physical Security Plan.Nrc Considers Security Plan to Be Withdrawn. Ltr Withheld (Ref 10CFR2.790) ML20055E4501990-07-0606 July 1990 Forwards Second Request for Addl Info Re Razebld Decommissioning Plan ML20055C3411990-02-0808 February 1990 Forwards Insp Rept 50-139/90-02 on 900111.No Violations Noted ML20247G5671989-05-19019 May 1989 Provides Procedure Outline for Decommissioning Reactor to Convert Facility Housing to Subcritical Assembly.Application Should Include Decommissioning Plan Which Discusses Radioactivity Levels Prior to Installation of Assembly ML20195H0451988-11-18018 November 1988 Forwards Amend 14 to License R-73 & Safety Evaluation.Amend Allows Certain Surveillance Requirements Associated W/ Operation of Reactor to Be Suspended If No Fuel in Core ML20205T6921988-11-0303 November 1988 Notifies of 890110 Meeting W/Region V in San Francisco,Ca to Discuss Policies & Procedures for Operator Licensing Activity in Region V.Agenda Encl ML20151U7541988-08-11011 August 1988 Informs of NRC Interpretation of Section 10CFR50.74(a) Re Changes in Operator or Senior Operator Status 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 ML20148G6761988-03-10010 March 1988 Forwards Insp Rept 50-139/88-01 on 880111.No Violations or Deviations Noted ML20147D0421988-02-29029 February 1988 Requests That Recipient Resubmit Proposal to Convert to Low Enriched U Fuel to Meet 10CFR50.64(6)(2) or (3) Requirements by 880327.Identical Ltrs Sent to Listed Dockets ML20149M3561988-02-24024 February 1988 Forwards Amend 13 to License R-73.Amend Modifies Tech Specs to Change Permissible Rod Drop Time of Shim Rod 3 to 3 s, Increases Surveillance Frequency for All Control Rods & Reduces Core Excess Reactivity to 1.9% Delta K/K IR 05000139/19870021987-12-0404 December 1987 Forwards Matl Control & Accounting Safeguards Insp Rept 50-139/87-02 on 871116 & 17.No Violations or Deviations Noted.Rept Withheld (Ref 10CFR2.790(d)) ML20235U1941987-10-0606 October 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-139/87-01.Periodic Measurement of Rod 3 Drop Time Following Reactor Operation Expected Based on 870930 Telcon ML20235J9721987-09-25025 September 1987 Extends Invitation to Attend 871110 Meeting W/Region V in San Francisco,Ca to Discuss Policies & Procedures for Operator Licensing Activity in Region V & NRC Policy & Developments ML20238D7511987-08-28028 August 1987 Forwards Insp Rept 50-139/87-01 on 870727-28 & Notice of Violation ML20215C6351987-06-11011 June 1987 Informs of Recent NRR Reorganization.Current Ofc Now Called Standardization & Non-Power Reactor Directorate,Under Div of Reactor Projects Iii,Iv,V & Special Projects,Nrr.T Michaels Project Manager for Facility ML20206R6801986-06-27027 June 1986 Forwards Safeguards Insp Repts 50-139/86-01 & 50-139/86-02 on 860602-03.No Violation Noted ML20140G7111986-03-27027 March 1986 Lists Change in Telephone Number for H Bernard,Facility Project Manager,Due to NRR Reorganization.D Tondi New Nonpower Reactor & Safeguards Licensing Section Leader. Correspondence Should Be Sent to Listed Address ML20136F8091985-11-18018 November 1985 Informs That Excess Unirradiated Highly Enriched U Can Be Removed from Facility within 120 Days of Effective Date of Show Cause Order ML20136A9181985-11-14014 November 1985 Responds to 851023 Request for Guidance on Any Requirement Re Use of N Stamped Equipment in Reactor Thermal Hydraulic Circuits.No Stamping Requirements Contained in 10CFR or in Manuals or Guides ML20138A0801985-10-0404 October 1985 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp on 850717-19 ML20135F9711985-09-0404 September 1985 Forwards Insp Rept 50-139/85-01 on 850717-19 & Notice of Violation ML20129E9971985-05-0909 May 1985 Responds to FOIA Request for Compilations of Results of Operator Licensing & Requalification Exams.App a Documents Placed in Pdr.App B Documents Already in PDR ML20127M3791985-05-0606 May 1985 Advises That 850205 & 0424 Changes to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20127P1151985-04-24024 April 1985 Forwards Exam Rept 50-139/OL-85-01 on 850325-26 ML20197H1651984-06-12012 June 1984 Forwards IE Safeguards Insp Rept 50-139/84-01 on 840424 & Notice of Violation IR 05000139/19820021982-07-29029 July 1982 Forwards IE Safeguards Insp Rept 50-139/82-02 on 820722.No Noncompliance Noted ML20054L6971982-06-23023 June 1982 Forwards IE Insp Rept 50-139/82-01 on 820608-11.No Noncompliance Noted 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 ML20126M2231981-06-0404 June 1981 Forwards Amend 11 to License R-73 & Safety Evaluation.Amend Reduces Possession Limit of SNM to 4.4 Kg U-235 & Authorizes Offsite Storage of 3.5 Kg of U-235 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 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 1998-06-11
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' UNITED STATES NOCLEAR REGULATORY COMMISSION
,g WASHINGTON, D. C. 20555 May 19, 1989
\.....l* -
Docket No. 50-139 D'r. Maurice A. 'Robkin, Director Nuclear Engineering Laboratories University 'of Washington Seattle,~ Washington 98195
Dear Dr. Robkin:
SUBJECT:
DECOMMISSIONING 0F THE UNIVERSITY OF WASHINGTON ARGONAUT REACTOR In accordance with your request for guidance on the approach to be'taken, from a licensing standpoint, to convert the facility housing the reactor to a facility' housing a subtritical assembly, the following procedure as outlined below will be followed.
The application for terraination should include the following provisions:
- a. A decommissioning plan which discusses what will be dismantled and the expected residual radioactivity levels prior to instal-lation of the subcritical assembly.
- b. The decommissioning plan should also discuss the ultimate dis-position of this facility for use as an unrestricted area. Thus, if you plan to hold a possession-only license under 10 CFR Part 50, to possess the residual byproduct material and to house the subcrit-
~
ical assembly for 20 years, then you should discuss how the facility will be dismantled, and the expected residual radioactivity levels at that time,
- c. A request to extend the license termination date to a point in time where you expect to ultimately decommission. This date should not be more than 40 years. The decommissioning rule (10 CFR 50.82 copy enclosed) permits this to occur. That is, the license remains in effect until the facility is ultimately decomiaission64. However, a statement to the effect that your license should be extended to a particular date to accommodate ultimate decommissioning is appropriate,
- d. As required by 10 CFR 50.75(e) (copy enclosed from Federal Register Notice 53 FR 24050, June 27, 1988), financial assurance for ultimate decommissioning needs to be provided. Specifically, for your facility any of the subparagraphs of 10 CFR 50.75(e)(2) that apply to your facility should be addressed.
Of*I I \
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8905310011 890519 PDP ADOCK 05000139 1
P PDC
I l
. l
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. i Dr. Mabrice A. Robkin May 19, 1989
- e. Concurrently, you should file an application for a separate ]
license under Part 70 to operate a subtritical assembly. 1 After review of the application, the staff, if appropriate, will amend the '
current license to permit possession of the contaminated facility and authorize decontamination and decommissioning of the reactor. Also, after review and if appropriate a Part 70 license will be issued.
Should you decide not to proceed with the subcritical assembly, then you l should submit a decommissioning plan for release of the facility as an unrestricted area.
l Since your license expires on October 13,1989, the decommissioning plan in I either of the above cases should be submitted as soon as possib.le, but in no I case later than September 13, 1989.
Please feel free to call me at 301-492-1102 if you have any questions regarding this approach.
Sincerely, 5, '
Theodore S. Michaels, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosures:
As stated cc: See next page I
i
Univer'sity of Washington Docket No.59-139 cc: Mayor of City of Seattle Seattle, Washington 98104 1
1 1
50.81 t d l 50.91(a)
PART 50 0 DOMEST'C UCENSING OF PRODUCTION AND UTILIZATION FACILITIES (m\
l an> creditor secured by such mort. f21 A description of controls and hmits 1 50.90 Appr, cation for amendment of
, gaee, pledge or llen, any purchazer of on procedures and equipment to protect license or construction permit, g such faellsty at the sale thereof upon occupational and public health and Wheneser a holder of a license or
- foreclosure of such mortrage. pledge, a
- or tien or upon exercise of any poser safeth.. R construction pe mit desires to amend
- (H A descnption of the planned fmal ? the license or permit. application for an
[ofstrnee sale ofcontained therein, or any a.s.
any such purchaser. radiation survey: a amendment must be filed with the (4) An updated cost estimate for the I Commission. as specified in 150 4. fully 1 60 s2 Applicat6on for terrr; nation of chosen alternative for decommissionmg.
- describing the changes desired. and beenu. comparison of that estimate with following as far as applicable, the form (a) Any licensee may apply to the present funds set aside for prescribed for original applications.
Commission for authonty to surrender a decommissionmg. and plan for assunng license voluntarily and to decommission the asailabihty of adequate funds for 6cM Noaca for pdec cerament; Ssata the facility. For a facihty that completion of decommissioning. conauftatkan.
permanently ceases operation after July (5) A desenption of technical The Commanha wdl uaa the 27.198& this apphcation must be made specifications. quahty assurance O following procedras en an appbcation within two ears following permanent provisions and physical security plan " requestag an asaendment to an cessation o operations. and in no case provisions in place dunng sp,,g%,e ler a lealMy lioroced la'er than one year prior to expiration of decommissionmg under i &QJ4b) se 130.22 er for a the operating bcense. Each appbcation (c) Decommissionmg plans which testmg facikty:
for termination of hcense must be propose an alternative that delays -
accompanied. or preceded, by a completion of decommissioning by proposed decommissioning plan. For a includmg a period of storage or long- { MbMWCMA8WNM S the time a licensee requests an facihty which has permanently ceased term surveillance must provide that-operation pnor to luly 27.1988' (1) Funds needed to romplete j amendment. it must provide to the requirements for contents of the . Commission, in accordance with the decommissioning be placed into an a decommissionira plan as specified in 6 distribution requirements specified in account segregated from hcensee assets paragraphs (b) thrrugh (d) of this section ; I 50 t its analysis about the issue of no and outside the hcensee's ma) be modified with approsal of the admmistrative control durmg the storage significant hazards consideration usmg Commission to reflect the fact that the or surseillante period. or a surety the standards in ! $0.92.
decommissionmg process has been method or fund statement of intent be E initiated previousib .
. mamtamed in accordance with the (2)(i) The Canaissioni may publish in (b) The proposed decommissiomng cntena of i 50.75(e). and b Fede al Ragmaar under l 2J(5 an (2) Means be included for adjusting individnal acbce of propesed action for 11 ch ce o[the alternative for . an amendmmt for wtid at makaa a decommissiomng with a description of g cost estimees and associated funding a
- lesels oser the storage or surveillance . pposed determaretim that no 1 ed sigtifa n* hazards cmarbtion la 5 (i) r n e ectnc utihty bcensee, an period 1 (d) For decommissiomng plans in
{a tavcdved er. at leaaJ ance every 30 days.
-
- lternatn a e is acceptable if it provides I for completien of decommissioning ' which the maior dismantlement i publieb a penodic Federal Register actinties are delay ed by first placing e nobce of pryosed actions wtuts 7 withm 60 years Consideration will be ideDtIFau cad SEr endment la6Ued and given to a'n alternatne which proudes the facihty in storage. plannmg for these delayed actinties may be less detailed each amendment pr70 sed to be lesned l for completien of decommissionmg sina the la st seca periodie notice. er 61 beyond 60 years only when necessary to Updated detailed plans must be submitted and approsed pnor to the snay publish both sad no6ces.
protect the pubhc heal'.h and safety. (ii) For coch amendment proposed to Factors to be considered in evaluatmg start of these actinties an abernatn e w hich praides for le} lf the decommissionmg plan completion of decommusionmg beyond demonstrates that the decommissionmg 60 years are set out in paragraph will be performed m accordance with (b)(1)(ni) of this section ~ the regulations in this chapter and will In) For a hcensee other than an not be mimical to the common defense electnc utilit), an alternatn e is and security or to the health and safety r acceptable if it proudes for completion of the pubhc. and after notice to of decommissionmg without sigmficant mterested persons. the Commission will delay Consideration will be gn en to an approse the plan subject to such alternetis e which provides for delayed conditions and hmitations as it deems completion of decommissioning only appropnate and necessary and issue an when necessar) in protect the pubhc order authonzing the decommissioning health and safety Factors to be (f) The Commission will terminate the considered in evaluating an alternatne bcense if it determines that-which proudes for dela> ed completion (1) The decommissioning has been of decommissiomng are set out in performed in accordance with the paragraph (b)(1)Dii) of this section. approsed decommissioning plan and the order authorizing decommissioning; and (iii) Factors to be considered in (2)The terminal radiation survey and making the evaluations required by paragraphs (b)(1)(i) and (bl(1)(ii) of this associated documentation demonstrates section include unavailability of waste that the facihty and site are suitable for disposal capacity and other site specific _ release for unrestncted use.
factors affectmF the hcensee's
- capabihty to carry out decommissionmg AurNoutNT or Liernst on CoNsT*oc.
safely,includmg presence of other T!op PERMIT AT RicWzsT or Hoteca l
nuclear fecihties at the site.
i l
November 30,1988 50 50 t
27, 1988 / Rules and Regulations .
=
j,,f Regist:r / Vcl. 53, No.1:3 / Monday, June indi !
(2) An adjustment factor atleast equal be renewed automatically unless 90 - I 1 r
to 0.65 L + 0.13 E + 0.22 B is to be used ' days or more prior to the renewal date.
%,on, graphs
. Funding for (b). (c). (e), and where L and E are escalation factors for the issuer notifies the Commission, t!!e
,,c, gr) beneficiary, and the licensee ofits i,,ioning of electric utilities labor is and energy.respectively, and are intention not to renew.The surety or ^f, year p, d",g,,ct to the st Energy regulation Department Regulatory of agencies to be taken from regional data of U.S.
of Labor Bureau of Labor insurance must also provide that the full deci g' mission (FERC) and State Public Stdtistics and B is an escalation factor face amount be paid to the beneficiary ,,gi, .
t/tility Cornmissions) having jurisdiction for waste burial and is to be taken from automatically prior to the expiration t get rate reguladon. The -requirements without proof of forfeiture if the !icensee I, up gct.
NRC report NUREG-1307, Report on ef this section,in particular paragraph ' Waste Burial Charges." fails to provide a replacement j,~ p,lar (cl.cre in addition to, and not (d) Each non-electric utility applicant acceptable to the Commission within 30 / go1 substitulloo for, other requirements, and cre not intended to be used, by for or holder of an operating license for days after receipt of notification of i infi a production or utilization facility shull , cancellation. / (? l themselves, by other agencies to (B)he surety or insurance must be i ant submit a decommissioning report as cstablish rates. required by i 50.33(k) of this part payable to a trust established for freq l (b) Each electric utility applicant for. containing a cost estimate for decommissioning costs.%e trustee and C cot cr brider of an operating license for a decommissioning the facility, an trusi must be acceptable to the 5 (.
production or utilization facility of the Commission. An acceptable trustee to r indication of which method or methods type cod power level specified in desenbed in paragraph (e) of this includes an appropriate State or Federal (
paragraph (c) of this section shall submit secti n as acceptable to the Commission government agency or an entity which
- to o o decommissioning report, as required has the authority to act as a trustee and , rad i will be used to provide funds for, ('
by i 50.33(k) of this part containing a decommissioning, and a description of whese trust operations are regulated g certification that financial assurance for the means of ed usting the cost estimate and examined by a Federal or State g (- j f co decommissioning will be provided in an and associated undinglevel agency.
cmount which may be rnore but not less periodically over the life of the facility. (C) he surety method or insurance i enI than the amount stated in the bble in d(e)(1) As provided in paragraphs (e) must remain in effect until the g int Commission has terminated the license.
4g fur paragraph (c)(1)of this section, adjusted- (2)and(3)of this section, financial annually using a rate at least equal to assurance is to be provided by the . (2) For a licensei, other than an that stated in paragraph (c)(2) of this f 11 wing methods: ehetric utility, acceptable methods of $; yas de section, by one or more of the methods 8 (i) Prepayment. Prepayment l's the providing financial assurance for described in paragraph (e) of this section as acceptable to the deposit prior to the start of operation decommissioning are- a
(
y j int an account segregated from licensee (i) Prepayment; ;
Commission.The amount stated in the assets and outside the bcensee s (ii) An external sinking fund,in which g cpplicant's or licensee's certificatica ,
administrauve control of cash or liquid deposits are made at least annually, d' may be based on a cost estimate for assets such that the amount of funds coupled with a surety method or g decommissioning the facility. As part of would be sufficient to pay insurance, the value of which may the certification, a copy of the financial dec mmissioning costs. Prepayment decrease by the amount being instrument obtained to satisfy the may be in the form of a trust. escrow . accurculated in the sinking fund. p g, requirements of paragraph (e) of this account, government fund, certificate of (iU) A surety rnethod,insurarjee,or section is to be submitted to NRC. deposit, or deposit of government other guarantee method. A parent g- In securities. company guarantee of funds for I" (c) Table of minimu'm amounta .
(January 1966 dollars) required to (ii) External sinking fund. An external decommissioning costs based on a .E.
demonstrate reasonable assurance of sinking fund is a fund established and financial test may be used if the i*-
funds for decommissioning by reactor maintained by setting funds aside guarantee and test are as contained in
type and power level. P (in MWt): periodically in an account segregated Appendix A of10 CFR Part 30. A parent '
~
company guarantee may not be used in adjustment factor.' from licensee assets and outside the licensee's administrative controlin combination with other financial {[p 1 mas which the total amount of funds would methods to satisfy the requirements of ; ,
be sufficient to pay decommissioning this section. . j. , .
(1)(t) For a PWR: costs at the time termination of (iv)In the case of Federal. State, or ,. p greater than or equal to local government licensees, a statement 3400 M Ws $105 operation is expected. An extemal l twtween 12b0 MWt and 3400 MWt (yor a PWR sinking fund may be in the form of a trust. escrow account, government fund.
ofintent containing a cost estimate for decommissioning, and Indicating that
+ funds for decommissioning will be y'
r g,
I .,
of less than 12o0 MWt. ce.tificate of deposit. or deposit of use P=1200 MWt) $PS +,0.0088PJ government securities, obtained when necessary. Y' (iii) A surety method. insurance.or (3) For an ' electric utility. acceptable. g.
g eater tha or equal to other guarantee method.nese methods methods of providing financial ,
3400 M Wt _.. 3135 assurance for decommissioning are-Fuarantee that decommissioning costs between 1200 MWs and will be paid should the licensee default. (i) Prepayment: .t 3400 MWt (For a BWR A surety method may be in the form of a (ii) An external sinking fund in which ,
of less than 1200 MWt. deposits are made at least annually: r use P=1200 MWt) $(104 + 0.009P) surely bond. letter of credit. of line of (iii) A surety method or insurance; y :
credit. Any surety method or insurance used to provide financialinsurance for and i decommissioning must contain the (iv)in the case of Federal government <
1 umounts .re twnd on .cwtice retved to the Iicensees, a stetcment ofintent e dehndson of " Decommission"in i so.2 of thispart (olloWlng Conditions:
' (A) The surety method or insurance containing a cost estimate for p l ripen $OtYof ronrs$nci$e*sNIuNa'$'ff"1 must be open-ended or,if written for a decommissioning or an amount based - , l rr. men.t. tie 3and thai neceuery to urminate the on paragraph (c) of this section, and 4.cenu.
specified term, such as five years, must y.
g
_ _ _ - _ _ ._ _ _ _ _ _- _=
\
i Dr. 'Maurice A. Robkin May 19, 1989 i
i
- e. Concurrently, you should file an application for a separate ifcense under Part 70 to operate a subcritical assembly.
After ' review of the application, the staff, if appropriate, will amend the current license to permit possession of the contaminated facility and authorize decontamination and decommissioning of the reactor. Also, after review and if appropriate a Part 70 license will be issued.
Should you decide not to proceed with the subcritical assembly, then you should submit a decommissioning plan for release of the facility as an unrestricted area.
Since your license expires on October 13, 1989, the decommissioning plan in either of the above cases should be submitted as soon as possible, but in no case later than September 13, 1989.
Please feel free to call me at 301-492-1102 if you have any questions regarding this approach.
Sincerely,
/s/
Theodore S. Michaels, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosures:
As stated cc: See next page DISTRIBUTION:s
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