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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N3581999-10-25025 October 1999 Ack Receipt of Ref Author Ltr of 990720, Transmitting Changes to Fixed Site & Transportation Plan for Protection of Special Nuclear Matl of Moderate & Low Strategic Significance.Nrc Approval Not Required ML20217C4981999-10-0101 October 1999 Informs That Based on NRC Review of General Atomics Info Concerning Decommissioning Cost Estimates.Nrc Has Determined That Submittal Listed Should Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211L9961999-08-27027 August 1999 Forwards Semiannual Effluent Rept Required for Period 990101-990630.All Airborne & Liquid Effluent Releases Were Well within Allowable State of CA & NRC 10CFR20 Limits ML20216G7361999-08-16016 August 1999 Identifies Listed Revs Which Impact Portion of Physical Protection Plan Applying to Mark I And/Or Mark F Triga Reactors,To Assist in Review of Jul 1999 Version of Plan ML20210Q8571999-08-12012 August 1999 Forwards Amends 36 & 45 to Licenses R-38 & R-67,respectively & Se.Amends Approve Decommissioning Plan for Ga Triga Mark 1 & F Research Reactors & Authorized Approved Decommissioning Plan to Be Included as Suppl to SAR ML20210G2371999-07-29029 July 1999 Forwards EA Re Issuance of Amend 36 to Amended Facility License R-38 & Amend 45 to Amended Facility License R-67 for General Atomics ML20216G7161999-07-26026 July 1999 Documents That Changes Applicable to Two Triga Reactors Have Been Made Per 10CFR50.54 Re Revised Fixed Site & Transportation Plan for Protection of Special Nuclear Matl of Moderate & Low Strategic Significance ML20212H5571999-07-20020 July 1999 Forwards Proprietary Revised Fixed Site & Transportation Plan for Protection of Special Nuclear Matl of Moderate & Low Strategic Significance. Encl Withheld,Per 10CFR2.790 ML20196F2361999-06-22022 June 1999 Forwards Pages with Revised Organization Chart for Proposed Revised Tech Specs & for Decommissioning Plan ML20206S0341999-05-12012 May 1999 Responds to NRC 990414 RAI Re Licensee Submittal of Decommissioning Plan & Request for Termination of Triga Mark I & Mark F non-power Reactor Licenses R-38 & R-67.Revised Triga Ts,Encl,For Review & Approval ML20217B6491999-05-0707 May 1999 Informs of Staff Determination That Document Re Decommissioning Cost Estimates Should Be Withheld from Public Disclosure in Response to & Affidavit,Per 10CFR2.790 ML20206F4141999-05-0303 May 1999 Responds to Recent RAI Re Submittal of Decommissioning Plan & Request for Termination of Triga Mark & Mark F non-power Reactor Licenses R-38 & R-67.Decommissioning Plan,Encl ML20205S1981999-04-22022 April 1999 Responds to NRC 990414 RAI Re General Atomics Submittal of Decommissioning Plan & Request for Termination of Triga Mark I & Mark F non-power Reactor Licenses R-38 & R-67 ML20205P4251999-04-14014 April 1999 Discusses Continuing Review of Amend Request for Amended Facility License Numbers R-38 & R-67 Submitted 970418. Forwards Rai.Response Requested within 30 Days of Date of Ltr ML20195E6471999-04-14014 April 1999 Forwards Triga Mark I 1998 Annual Rept. Sections of Rept Are Numbered Consistent with Items of Info Referred to in Section 9.6e of TSs for Mark I Triga Reactor ML20205D6181999-03-31031 March 1999 Forwards Proprietary Rept on Agreed Upon Procedures & Rept & Consolidated Financial Statements Re Financial Assurance for Decommissioning.Encls Withheld,Per 10CFR2.790 ML20203D7261999-02-11011 February 1999 Ack Receipt of Which Transmitted Changes to General Atomic Radiological Contingency Plan Submitted Under Provisions of 10CFR50.54(q).Informs That NRC Approval Not Needed Since Changes Do Not Decrease Plan Effectiveness ML20203C4571999-02-0303 February 1999 Forwards Issue a to QAPD-9009-2, Triga Reactor Facility Decommissioning QA Program Document ML20202C6241999-01-28028 January 1999 Responds to NRC 980116 RAI Re Decommissioning Plan & Request for Termination of Triga Mark I & Mark F non-power Reactor Licenses R-38 & R-67 ML20202A6821999-01-25025 January 1999 Ack Receipt of Which Transmitted Changes to Ga Radiological Contingency Plan Submitted,Per 10CFR50.54(q). NRC Approval Not Required ML20198K8811998-12-21021 December 1998 Informs That 981120 Affidavit of Jr Edwards & Listed Investment Statement of Account,Marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of Aea,As Amended ML20196F5371998-12-0101 December 1998 Informs That from General Atomics Technologies Corp Will Be Withheld from Public Disclosure,Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20195H3721998-11-20020 November 1998 Responds to RAI Re Submittal of Decommissioning Plan & Request for Termination of Triga Mark I & Mark F non-power Reactor Licenses R-38 & R-67.Item 6 Addressed Separately as It Contains Proprietary Info.Proprietary Encl Withheld ML20155H0921998-11-0505 November 1998 Forwards Bracketed Version of Proprietary Re Financial Assurance for Decommissioning,As Requested in NRC .Pdr Copy of Subject Ltr,Encl.Proprietary Info Withheld ML20154M3191998-10-0909 October 1998 Forwards Revised Pages 10-1 & 10-2 to Licensee NRC Approved Radiological Contingency Plan.Pages Were Revised to Require Radiation Safety Training for Triga Reactor Personnel Annually,Per NRC ML20154M3021998-10-0909 October 1998 Forwards Revised Pages 10-1 & 10-2 of Licensee NRC Approved Radiological Contingency Plan.Pages Were Revised to Require Radiation Safety Training for Triga Reactor Personnel Annually,Per NRC ML20154G9531998-10-0101 October 1998 Submits Reissued ,Forwarding Signed License Amend 44,which Replaces Criticality Safeguards Committee with Criticality & Radiation Safety Committee & Decreasing Frequency of Audits from Quarterly to Annually ML20154B4661998-10-0101 October 1998 Forwards Amend 44 to License R-67 & Safety Evaluation.Amend Replaces Criticality Safeguards Committee with Criticality & Radiation Safety Committee & Decreases Frequency of Audits from Quarterly to Annually ML20153C2831998-09-18018 September 1998 Ack Receipt of Transmitting Changes to Licensee Fixed Site & Transportation Plan for Protection of Special Nuclear Matls of Moderate & Low Strategic Significance ML20239A2661998-08-24024 August 1998 Forwards Proprietary Revised Pp 4-7 & 4-8 of Licensee Radiological Contingency Plan. Revs Update Selected Names & Telephone Numbers of Licensee Emergency Response Personnel.Proprietary Info Withheld NUREG-0849, Informs That General Atomics Radiological Contingency Plan for Training & Familiarization Onsite for Offsite Response Organizations Acceptable & Approved by Nrc.Changes Were Revised Using NUREG-08491998-08-24024 August 1998 Informs That General Atomics Radiological Contingency Plan for Training & Familiarization Onsite for Offsite Response Organizations Acceptable & Approved by Nrc.Changes Were Revised Using NUREG-0849 ML20237D0591998-08-20020 August 1998 Forwards Revised Pp 4-7 & 4-8 of Licensee Radiological Contingency Plan. Revs Update Selected Names & Telephone Numbers of Ga Emergency Response Personnel.Changes Do Not Represent Decrease in Effectiveness of Plan ML20238E7581998-08-20020 August 1998 Forwards Semiannual Effluent Rept for Jan-Jun 1998, IAW 10CFR70.59.Attachment a to Rept Provides Detailed Info Concerning Triga Ar-41 releases,Kr-85 & XE-133 Releases & Stack Sample Results Over Reported Period ML20237A2741998-08-11011 August 1998 Forwards Certificate to Js Greenwood Newly Licensed Individual at General Atomics.W/O Encl ML20236Y4551998-08-0707 August 1998 Responds to 980730 Request for Info,Providing Justification for Reducing Training Frequency ML20236V5411998-07-30030 July 1998 Informs That NRC Has Completed Review of Changes to General Atomics Radiological Contingency Plan Submitted on 971010 ML20236U2461998-07-27027 July 1998 Informs That Effective 980731,J Greenwood Will Be Replacing J Razvi as Physicist-in-charge for Licensee Triga Mark I & Mark F Reactors ML20236U7321998-07-22022 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-089/98-202 & 50-163/98-202 Issued on 980611 ML20236R5601998-07-20020 July 1998 Informs That J Greenwood Submitted Applications to Be Licensed for Both non-power Reactors Mark I & Mark F,But Has Only Received License for Mark I.Ga Would Appreciate Nrc'S Help in Correcting Oversight ML20236N0121998-07-10010 July 1998 Responds to NRC Re Violations Noted in Insp Repts 50-089/98-202 & 50-163/98-202.Corrective Actions:Discussed Violation W/Health Physics Technician Responsible for Drill & Distributed Memo Re Criticality Warning Alarm Sys Drills ML20249A8481998-06-17017 June 1998 Informs of Arrangements Made W/J Razvi for Administration of OL Exams at General Atomics Mark I/Mark F Reactor During Week of 980706.Requests Matl Listed in Encl 1 as Soon as Possible ML20249A6821998-06-12012 June 1998 Advises NRC of Licensee Plans for Portion of Bldg That Houses Some of Offices & Bathrooms Near Mark I Triga Reactor.Security & Emergency Plans Will Be Revised to Show New Entrance ML20249A6971998-06-11011 June 1998 Forwards Insp Repts 50-089/98-202 & 50-163/98-202 on 980504- 07 & Notice of Violation.Various Aspects of Safety & Security Programs Inspected ML20216B6761998-05-12012 May 1998 Informs That 980331 Submittal Re Affidavit of Je Jones, Secretary & Treasurer of General Atomics Technologies Corp, Will Be Withheld Per 10CFR2.790 & Section 103(b) of AEC Act of 1954 ML20217H7541998-04-28028 April 1998 Forwards Proprietary New Parent Company Guarantee to Replace 920909 Guarantee,To Be Consistent W/Agreed Upon Alternative Method.Encl Withheld ML20217F8601998-04-24024 April 1998 Advises NRC That as Licensee Recently Discussed by Telcon, Need Addl Time to Prepare Appropriate & Complete Responses ML20216G0621998-04-14014 April 1998 Forwards Triga Mark I Reactor Annual Rept CY97, Per Applicable Ts.Sections of Rept Are Numbered Consistent W/ Items of Info Referred in Licensee TS Section 9.6e ML20217J3081998-03-31031 March 1998 Forwards Proprietary Revised Financial Documents for 1997 Re Financial Assurance for Decommissioning.Proprietary Encls Withheld ML20217C2101998-03-18018 March 1998 Forwards Insp Repts 50-089/98-201 & 50-163/98-201 on 980217- 18.No Violations Noted ML20197B7351998-03-0303 March 1998 Concludes That General Atomics Triga Reactors Facility Reactor Operator Requalification Program Meet Requirements of Regulations & Acceptable,Per 971216 Submittal & Suppl, 1999-08-27
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217N3581999-10-25025 October 1999 Ack Receipt of Ref Author Ltr of 990720, Transmitting Changes to Fixed Site & Transportation Plan for Protection of Special Nuclear Matl of Moderate & Low Strategic Significance.Nrc Approval Not Required ML20217C4981999-10-0101 October 1999 Informs That Based on NRC Review of General Atomics Info Concerning Decommissioning Cost Estimates.Nrc Has Determined That Submittal Listed Should Be Withheld from Public Disclosure,Per 10CFR2.790 ML20210Q8571999-08-12012 August 1999 Forwards Amends 36 & 45 to Licenses R-38 & R-67,respectively & Se.Amends Approve Decommissioning Plan for Ga Triga Mark 1 & F Research Reactors & Authorized Approved Decommissioning Plan to Be Included as Suppl to SAR ML20210G2371999-07-29029 July 1999 Forwards EA Re Issuance of Amend 36 to Amended Facility License R-38 & Amend 45 to Amended Facility License R-67 for General Atomics ML20217B6491999-05-0707 May 1999 Informs of Staff Determination That Document Re Decommissioning Cost Estimates Should Be Withheld from Public Disclosure in Response to & Affidavit,Per 10CFR2.790 ML20205P4251999-04-14014 April 1999 Discusses Continuing Review of Amend Request for Amended Facility License Numbers R-38 & R-67 Submitted 970418. Forwards Rai.Response Requested within 30 Days of Date of Ltr ML20203D7261999-02-11011 February 1999 Ack Receipt of Which Transmitted Changes to General Atomic Radiological Contingency Plan Submitted Under Provisions of 10CFR50.54(q).Informs That NRC Approval Not Needed Since Changes Do Not Decrease Plan Effectiveness ML20202A6821999-01-25025 January 1999 Ack Receipt of Which Transmitted Changes to Ga Radiological Contingency Plan Submitted,Per 10CFR50.54(q). NRC Approval Not Required ML20198K8811998-12-21021 December 1998 Informs That 981120 Affidavit of Jr Edwards & Listed Investment Statement of Account,Marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of Aea,As Amended ML20196F5371998-12-0101 December 1998 Informs That from General Atomics Technologies Corp Will Be Withheld from Public Disclosure,Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20154B4661998-10-0101 October 1998 Forwards Amend 44 to License R-67 & Safety Evaluation.Amend Replaces Criticality Safeguards Committee with Criticality & Radiation Safety Committee & Decreases Frequency of Audits from Quarterly to Annually ML20154G9531998-10-0101 October 1998 Submits Reissued ,Forwarding Signed License Amend 44,which Replaces Criticality Safeguards Committee with Criticality & Radiation Safety Committee & Decreasing Frequency of Audits from Quarterly to Annually ML20153C2831998-09-18018 September 1998 Ack Receipt of Transmitting Changes to Licensee Fixed Site & Transportation Plan for Protection of Special Nuclear Matls of Moderate & Low Strategic Significance NUREG-0849, Informs That General Atomics Radiological Contingency Plan for Training & Familiarization Onsite for Offsite Response Organizations Acceptable & Approved by Nrc.Changes Were Revised Using NUREG-08491998-08-24024 August 1998 Informs That General Atomics Radiological Contingency Plan for Training & Familiarization Onsite for Offsite Response Organizations Acceptable & Approved by Nrc.Changes Were Revised Using NUREG-0849 ML20237A2741998-08-11011 August 1998 Forwards Certificate to Js Greenwood Newly Licensed Individual at General Atomics.W/O Encl ML20236V5411998-07-30030 July 1998 Informs That NRC Has Completed Review of Changes to General Atomics Radiological Contingency Plan Submitted on 971010 ML20236U7321998-07-22022 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-089/98-202 & 50-163/98-202 Issued on 980611 ML20249A8481998-06-17017 June 1998 Informs of Arrangements Made W/J Razvi for Administration of OL Exams at General Atomics Mark I/Mark F Reactor During Week of 980706.Requests Matl Listed in Encl 1 as Soon as Possible ML20249A6971998-06-11011 June 1998 Forwards Insp Repts 50-089/98-202 & 50-163/98-202 on 980504- 07 & Notice of Violation.Various Aspects of Safety & Security Programs Inspected ML20216B6761998-05-12012 May 1998 Informs That 980331 Submittal Re Affidavit of Je Jones, Secretary & Treasurer of General Atomics Technologies Corp, Will Be Withheld Per 10CFR2.790 & Section 103(b) of AEC Act of 1954 ML20217C2101998-03-18018 March 1998 Forwards Insp Repts 50-089/98-201 & 50-163/98-201 on 980217- 18.No Violations Noted ML20197B7351998-03-0303 March 1998 Concludes That General Atomics Triga Reactors Facility Reactor Operator Requalification Program Meet Requirements of Regulations & Acceptable,Per 971216 Submittal & Suppl, ML20198S8061998-01-16016 January 1998 Forwards Request for Addl Info Re Licensee 970418 Request for Amends to Licenses R-38 & R-67.Response Requested within 90 Days of Ltr Date ML20198H5161998-01-0505 January 1998 Forwards RAI Re Revised Reactor Operator Requalification Program.Response Requested within 60 Days of Date of Ltr ML20212G4031997-10-29029 October 1997 Forwards Amend 35 to License R-38 & Safety Evaluation.Amend Removes Authority from License to Operate Reactor,Authorizes Possession Only of Reactor & Changes TS to Remove Operational Requirements Not Needed for Possessions Only ML20211P3211997-10-0909 October 1997 Forwards Amend 34 to License R-38 & Se.Amend Changes Requirements for Calibration of Power Measuring Channels to Require Calibrations Only If Reactor Could Achieve Criticality ML20137C8621997-03-20020 March 1997 Forwards RAI Re Review of 961217 Amend Request for Facility OL R-38 for Triga Mark I Research Reactor.Response to Be Provided within 30 Days ML20128Q1121996-10-10010 October 1996 Final Response to FOIA Request for Documents.Records in App a Encl & Will Be Available in Pdr.App B Records Withheld in Part (Ref FOIA Exemptions 4 & 5) & App C Records Completely Withheld (Ref FOIA Exemptions 4 & 5) ML20134E6471996-07-0909 July 1996 Partially Deleted Ltr Responding to Re Financial Assurance for Funding Decommissioning of Facilities Located in San Diego ML20057C4761993-09-0101 September 1993 Forwards Insp Repts 50-089/93-01,50-163/93-01 & 70-0734/93-04 on 930803-06.Non-cited Violations Identified. Insp Rept Partially Withheld Ref 10CFR2.790(d) ML20062G2801990-11-0808 November 1990 Forwards Exam Rept 50-089/OL-90-01 on 901023-24 IR 05000089/19900011990-08-15015 August 1990 Forwards Safeguards Insp Repts 50-089/90-01 & 50-163/90-01 on 900710-27.No Violations or Deviations Noted.Rept Withheld (Ref 10CFR2.790(d)) ML20248D5031989-09-28028 September 1989 Advises That Reactor Operator & Senior Reactor Operator Written Exams Rescheduled for 891031 & Operating Exams Rescheduled for 891101-03 ML20247H5911989-07-24024 July 1989 Advises That Senior Operator Licensing Written Exams & Operating Exams Scheduled for 891024 & 25-27,respectively. Ref Matls Listed on Encl Should Be Provided by 890825.W/o Encl ML20247G1531989-03-24024 March 1989 Forwards Insp Rept 50-089/OL-89-01 on 890314-16.No Items of Noncompliance Noted ML20206J2691988-11-18018 November 1988 Forwards Amend 40 to License R-67 & Safety Evaluation. Amend Adds Requirements for Site Boundary,Allowing Reactor Bldg Air Leakage & Verification Thereof & Installation, Availability & Surveillance of Operability of Reactor Room ML20205T6961988-11-0303 November 1988 Notifies of 890110 Meeting W/Region V in San Francisco,Ca to Discuss NRC Reactor Operator Licensing Program in Region ML20151U6711988-08-11011 August 1988 Informs of NRC Interpretation of Section 10CFR50.74(a) Re Changes in Operator or Senior Operator Status.Notification of NRC Required When Operator Reassigned to Nonlicensed Position W/No Intent to Return to Licensed Position ML20154P1081988-05-25025 May 1988 Forwards Request for Addl Info Re 871222 Application for Amend to License R-67.Response Requested within 30 Days of Ltr Date 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 ML20195J1611988-01-0808 January 1988 Forwards Insp Rept 50-089/87-03 on 871217.No Noncompliance Noted ML20234F2731987-12-24024 December 1987 Forwards Exam Repts 50-089/OL-87-03 & 50-163/OL-87-03 of Exams Administered on 871214 ML20236L3601987-11-0303 November 1987 Informs That Written Senior Operator Licensing Exams Scheduled for 871214.Facility Mgt Responsible for Providing Adequate Space & Facilities for Exams. Requirements for Administration of Written Exams Encl ML20238A6461987-08-28028 August 1987 Forwards Amend 39 to License R-67 & Safety Evaluation.Amend Adds Triga Fuel Containing Max U Content of 30 Weight Percent W/Enrichment of Less than 20% to Category of Std Triga Fuel.W/O Evaluation ML20238D6041987-08-26026 August 1987 Forwards Exam Rept 50-089/OL-87-02 of Exam Administered on 870804-05 ML20236D5271987-07-16016 July 1987 Documents Previous Discussions W/Whittemore & Furnishes Addl Info Re 870804 Visit of Representatives from China to Observe Administration of Written Exam to Personnel ML20235E8901987-07-0606 July 1987 Forwards Amend 38 to License R-67 & Safety Evaluation.Amend Authorizes Increase in Irradiation Time for Fueled Incore Thermionic Direct Conversion Devices W/Irradiation Time Not to Exceed 40,000 H for One Fueled Incore Thermionic Device ML20234E1631987-06-18018 June 1987 Forwards Exam Rept 50-089/OL-87-01 of Exams Administered on 870519 & 20.Results of Exams Found Two Reactor Operator Candidates Meeting Min Qualification Requirements for Licensing.Personal Privacy Info Withheld (10CFR9.5(a)(6)) ML20215A3881987-06-11011 June 1987 Informs of Recent Reorganization of Nrr.A Adams Designated as Facility Project Manager ML20209C4051987-04-14014 April 1987 Forwards Amend 27 to License R-38 & Safety Evaluation.Amend Changes License & Tech Specs to Include Max Reactivity Insertion Allowed in Pulsing Mode & Eliminates Inconsistency Between License Condition for Max Power Level 1999-08-12
[Table view] |
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1 January 16,'-1998 Dr. Keith E. Asmussen, Director "s
Licensing, Safety and Nuclear Compliance General Atomics P.O. Box 85608 San Diego, Cellfornia 92186 9784
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (TAC NOS, M98498 AND M98499)
Dear Dr. Asmussen:
We are continuing our review of your amendment request for Amended Facility License Nos. R 38 and R 67 for the General Atomics TRIGA Mark I and Mark F Research Reactorc which you submitted on April 18,1997. Durirg our review of your amendment request. ,3 questions have arisen for which we require additionalinformation and clarification. Please provide responses to the enclosed request for additionalinformation within 90 days of the date of this letter, in accordance witti 10 CFR 50.30(b), your response must be executed in a signed original under oath or affirmation. Followir.g receipt of the additionalinformation, we will continue our evaluation of your amendment request.
If you have any questions regarding this review, please contact me at (301) 415-1127. i Sincerely, ORIGINAL SIGNED BY:
Alexander Adams, Jr., Senior Project Miinager Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Rogulation Docket Nos. 50-89 and 50-163
Enclosure:
As stated .
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See next page h'h. g}
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- 4. . . . . /
Dr. Keith E. Asmussen, Director -
Licensing, Safety and Nuclear Compliance General Atomics P.O. Box 85608 San Diego, California 92186-9784
$UBJECT: REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. M98498 AND M98499)
Dear Dr. Asmussen:
- We are continuing our review of your amendment request for Amended Facility License Nos. R-38 and R-67 for the General Atomics TRIGA Mark I and Mark F Rusearch Reactors which you submitted on April 18,1997. During our review of your amendment request, questions have arisen for which we require additionalinformation and clarification. Please provide responses to the enclosed request for additionalInformation within 90 days of the date of this letter, in accordance with 10 CFR 50.30(b), your response must be executed in a signed original under oath or affirmation. Following receipt of the additional information, we will continue our evaluation of your amendnient request.
If you have any questions regarding this review, please contact me at (301) 415-1127.
Sincerely, Alexander Adams, Jr., Senior Project Manager Non-Power Reactors and Decommissioning Project Directoiate Division of Reactor Progrem Management Office of Nuclear Reactor Regulation Docket Nos. 50-89 and 50-163
Enclosure:
- As stated.
cc w/ enclosure:
See next page s
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Gen 9tal Atomics Docket Nos. 50-89/163 cc:
Califo nia Department of Health ATTA. Chief, Environmental Radiation Control Unit Radiologic Health Section 714 P Street, Room 498 Sacramento, California 95814
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION GENERAL ATOMICS TRIGA MARK l AND MARK F RESEARCH REACTORS DOCKET NOS. 50-89 AND 50-163
- 1. Section 1.2. On Figures 13 and 1-4 please show the boundaries of the Mark I, Mark F and Star., of California licenses.
- 2. Section 1.2.1. Because it is not Ilcensed by the NRC, the NRC cannot approve decommissioning of the remaining components of the Mark til reactor Please describe what steps, if any, have been take^ with the State of California to decommission the Mark Ill and terminate that license.
- 3. Sections 1.2.1 and 2.3. It appears from your decommissioning plan (DP) that you propose to cortpletely demolish the reactor building. Your termination survey and
, NRC's confirmatory survey would be of the site. NRC normally approves DPs that propose complate demolition of structures when removing the activated and contaminated material threatens the structuralintegrity of the building and could have an impact on non-radiological safety. However, section 2.2.2 cf your DP shows that the radioactive portions of the f acility are confined to the reactor internals and biological shield. Also section 3.3 appears to show a decommissioning process where the radioactive materialis removad without jeopardizing the structuralintegrity of the reactor t,ailding. Please jastify demolition of the reactor building before the confirmatory survey is requested from NRC or revise your DP to show the conduct of the termination and confirmatory surveys on the decontaminated and dismantled building. Please revise other portions of your DP as needed.
- 4. Section 1.2.2, What oart of the '.otal cost shnwn in the table is related to the decommissioning of the Mark I and Mark F reactors?
- 5. Section 1.2.2. It is mentioned that removal and shipment of fuel are not coasidered decommissioning tasks. However, pcssession, on-site handimg, and transportation must comply with NRC regulations and may require NRC authorizations. Explain how these functions are to be managed whenever fuelis on site before and during actual dismantlement and decontamination of the TRIGA reactor facilities.
- 6. Section 1.2.3. Please provide information that shows that General Atomics Technologies Corporation has been meeting the terms and conditions of their external sinking fund discussed in your submittal of May 20,1996 (Reference 10,5). If the sinking fund does not contain sufficient funds to carry out decommissioning, where wil' actual funding come from for decommissioning activ! ties?
- 7. Sestion 1.2.4. Please provide a copy of the Quality Assurance Program Document T prepared for decommissioning of the reactors.
2
- 8. Table 21. Does the information in this table consider the activation of reactor structure and components such as the reactor tank, concrete and soil surrounding the reactor? For example, Europium-152 is a common isotope from the irradiation c) concrete, but according to your table, is not an expected radionuclide. Do your calculations show that soil was activated by operation of the reactor? If so, what volume of sollis activated?
- 9. Sections 2.2.3 and 4. Please discuss the difference between criteria to release the site and structures for unrestricted use at the end of decommissioning activities and the criteria to dispose or remove potentially contamin ed materials from the site during the decommissioning process.
- a. Please clearly discuss criteria for release of the site, structures and components for unrestricted use at the time of license termination. Address both contamination and radiation fields. Please see the new Subpart E of 10 CFR Part 20, " Radiological Criteria for License Termination." Because, as discussed in 10 CFR 20.1401(b)(3), you have subml(ted your DP before August 20,1998, the release criteria applicable to your application are the appropriate sections of
" Cleanup Criteria" for reactor licensees in the " Action Plan to Ensure Timely Cleanup of Site Decommissioning Management Plan Sites" dated April 16,1992 (57 FR 13389). Please note that some guidance in th!s document is for materials licensees and may not be appdcable to your situation,
- b. Please discuss your plans for disposal of radioactive material created by decommissioning activities. This question refers to material that will not be released for unrestricted use by termliation of the reactor licenses.
- 10. Section 2.3.1 Table 2-4. The items in this list are normally considered facility components that are removable only after the decommissioning amendment is approved. For the NRC licensed reactors please commit to not removing these components until the decommissionin'g amendment is issued or provide justification for removing th-
- components under the possession only amendment. If removal of these components will occur under the decommissioning amendment, please revise the DP accordingly.
- 11. Section 2.3. Under 10 CFR 50.82(b), an amendment to existing reactor licenses will be issued by NRC to authorize dismantlement and decommissioning. These amended licenses will include relevant Technical Specifications (TSs) and other features, including applicable Pnysical Protection and Emergency Plans. Please submit proposed documents for our review and evaluation. If you wish to use the existing documents please state this. You may want to censider developing these documents to address relevant issues both while any fuel is on site, and after fuel removal.
- 12. Section 2.3 Use of a localized fine mist of water is mentioned. How will the contaminated water be disposed of ?
- 13. Section 3.1.2. The DP refers to approved procedures. Please explain the approval process and its relatic'1 ship to the reactor TSs.
. - . . ., . . . - , - .. -.. -- . - . . . ~. - . - - . . . - .
- ge 4 ..
d-4 114.' Section 3.1.3. Please discuss a dose estimate to members of the pubic from decommissioning activities.
- 15. Table 3-2. Please revise this table to clearly show the collective dose from - ,
decommissioning the NRC licensed reactors separate from the State of California -
licensed material. . l o 16. Section 3.3: Please discuss the potentist consequences to the public and the workers, ,
assuming's pool leak while fuel is still on the site, perhaps initiated by nearby. 1 dismantlement activities, or even by a seismic event. . '
- 17. Figure 4-3. Please discuss the use of the sampling system depicted in this figure.
1
' 18. Section 6. Please discuss continued compliance with Parts 50 and 73 for your
, physical security pian, t
- 19. Section 9. -Your definition of unreviewed safety question is different from that in 10 CFR 50.59. Amendments to the regulations in August 1996 extended the application of 10 CFR 50.59 to NPRs whose licenses no longer authorize operation of ,
the reactor. Please amend this section of your DP to be in accordance with the regulLtions.
- 20. Appendix A. With tne change in license status of the Mark I to possession-only, do you plan to conduct additional chara::terization measurements if so, please desci ;;,e
- the results of those measurements, or if not yet conducted, described the planned measurements.
- 21. - Appendix B,-Section 2.2, page 8 8: Please give best estimates for the schedule for fuel shipme.nt off-site, and for submitting the request to NRC for license terminations.
' 2 2. Appendix B, Suction 3.1.2. Are any of the hazardous materials discussed in this #
section activated or contaminated? Please discuss types and quantities of any mixed wastes that result from decommissioning.
- 23. - Appendix B, Section 4.1.2, page B 19: Please discuss further your bases for
- estimating zero potential exposures to the public after license termination. What release criteria are assumed?' Should NRC consider this to be GA commitment?-
- 24. . Sectiom4.1.3, page 0 20: . Please discuss the basis for the number of truck trips for
~ her.ordous and radiologicht waste.- What total quantities of these materials are assumed to be involveJ? How many trips will be required to transfer all irradiated vTRIGA fuel off the site?:
11, 125.' cSection 4.2.3, page B-20: Please give the basis and best estimates of quantities of
- - ' uncontaminated co..struction debris to be trucked off the site, 4
?26.1 Section 4.8, page.B-22:: Please d!scuss human health effects on decommissioning y workers; ' Please give best estimate.(and explanation) of internal doses to the public.
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