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Category:CORRESPONDENCE-LETTERS
MONTHYEARIA-98-313, First Final Response to FOIA Request for Documents.Records Subj to Request Encl & Identified in App a1998-09-0404 September 1998 First Final Response to FOIA Request for Documents.Records Subj to Request Encl & Identified in App a ML20239A1371998-09-0404 September 1998 First Final Response to FOIA Request for Documents.Records Subj to Request Encl & Identified in App a ML20239A4271992-06-0404 June 1992 Forwards Proposed Survey Plan for Pathfinder Generating Station,Sioux Fall,Sd, for Approval ML20073B9901991-06-18018 June 1991 Forwards Rept Summarizing Findings of Orau Review of 59 Docket Files for Terminated Research & Test Reactors ML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 ML20151A5041988-03-30030 March 1988 Forwards Executed Amend 22 to Indemnity Agreement B-8, Terminating Agreement 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 ML20147D0271988-02-26026 February 1988 Forwards Amend 22 to Indemnity Agreement B-8,order Terminating License CX-10,safety Evaluation & Environ Assessment ML20235K2791987-09-29029 September 1987 Forwards Insp Rept 50-013/87-01 on 870917-21.No Violations or Deviations Noted.Contractor Rept, Confirmatory Radiological Survey of CX-10 Area,Bldg A,Lynchburg Research Ctr Also Encl ML20235D6541987-09-16016 September 1987 Notification of 871027-28 Nuclear Fuel Cycle Licensee Workshop in Atlanta,Ga.Map & List of Hotels Encl.W/O Stated Encls ML20215B0101987-06-11011 June 1987 Informs of Recent Reorganization of Nrr.A Adams Designated as Facility Project Manager ML20214T5451986-11-24024 November 1986 Assigns Jj Dosa as Project Manager to Facility ML20199J9421986-07-0202 July 1986 Forwards Revised Section 8 of Dismantling Plan for CX-10 Reactor.Changes Due to Reorganization ML20206L5901986-06-24024 June 1986 Forwards Replacement Table 2-1 Providing Specific Info for Final Survey Rept for License CX-10 ML20140G7021986-03-27027 March 1986 Lists Change in Telephone Number for H Bernard,Facility Project Manager,Due to NRR Reorganization.D Tondi New Nonpower Reactors & Safeguards Licensing Section Leader. Correspondence Should Be Sent to Listed Address ML20153H0171986-02-20020 February 1986 Advises That Ofc of Resource Mgt Will Be Sending Bill for 840807 Application for Decommissioning License CX-10. Discussion of 6-month Billing Process Submitted ML20138A0301985-11-27027 November 1985 Ack Receipt of 850828 & 1114 Ltrs Informing NRC of Steps Taken to Correct Violation Noted in Insp Repts 50-013/85-01 & 70-0824/85-05 IR 05000013/19850011985-10-25025 October 1985 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-013/85-01 & 70-0824/85-05.Damage to Drum Occurred During Transport & Due to Condition Normally Incident to Transportation ML20137M4981985-08-28028 August 1985 Responds to NRC Re Violations Noted in Insp Repts 50-013/85-01 & 70-0824/85-05.Corrective Actions:Shipment of Fissle Class 2 Packages Suspended Until Checklist Containing Requirements for Shipments Developed ML20133P7361985-07-29029 July 1985 Forwards Insp Repts 50-013/85-01 & 70-0824/85-05 on 850610-14 & Notice of Violation ML20116D8891985-04-17017 April 1985 Requests Info Re Authorization for B&W to Dismantle & Decontaminate Reactor Facility Near Lynchburg,Va ML20101S5501985-01-29029 January 1985 Requests That Lynchburg Research Ctr Be Granted Authorization to Proceed W/Dismantling & Decontamination of Facility.All Fuel Possessed Under License CX-10 Shipped to DOE Oak Ridge,Tn Facility ML20099D1301984-11-15015 November 1984 Forwards Responses to 841012 Questions Re 840807 Application for Dismantlement & Termination of CX-10 Facility ML20091P5301984-06-0808 June 1984 Requests Exemption from Requirements of 10CFR50.54(r) Re Emergency Plan Due to Dismantling of CX-10 Facility ML20087N3721984-03-26026 March 1984 Forwards Endorsements 108 & 109 to Nelia Policy NF-83, Endorsement 110 to Nelia Policy NF-111 & Endorsement 42 to Maelu Policy MF-84 ML20082F1031983-11-22022 November 1983 Requests Waiver of Operator Requalification Program & 10CFR55.31(e) Requirement to Permit Operators & Senior Operators to Perform Fuel Handling Functions ML20082H6541983-11-15015 November 1983 Forwards Rev 3 to Security Plan.Rev Withheld (Ref 10CFR2.790) ML20082H6651983-09-19019 September 1983 Forwards Rev 3 to Page 6-2 of Reactor Security Plan.Page Withheld ML20065G7391982-09-27027 September 1982 Details Evaluation of Discrepancy Between Electronically Simulated Reactor & Channel Periods Revealed in Calibr Test Performed on Log-N-2 Channel.No Unsafe Condition Existed & No Tech Spec Violation Occurred ML20069G4001982-09-23023 September 1982 Forwards Emergency Plan,Revision 0 ML20062D7741982-08-0303 August 1982 Forwards Amend 21 to Indemnity Agreement B-8,in Response to NRC ML20062F2781982-07-20020 July 1982 Forwards Order Terminating License R-47 in Accordance w/810723 Application & Amend 21 to Indemnity Agreement 8 ML20054M8861982-06-18018 June 1982 Forwards IE Insp Rept 50-099/82-03 on 820525-26.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 ML20052A8801982-04-23023 April 1982 Advises That Dismantling & Decontamination of Facility Have Been Completed.Nrc Verification Survey & Facility Release for Unrestricted Use Requested.Survey Results Encl ML20041C6691982-01-26026 January 1982 Forwards Revisions to Facility Security Plan.Revisions Withheld (Ref 10CFR2.790) ML20010G2441981-09-10010 September 1981 Requests That Lynchburg Research Ctr Be Granted Exemption from Requirements for Submittal of Revised Emergency Plan Per 10CFR50.47.Proposed Plan Would Not Be Implemented Until After Facility Fuel Has Been Removed ML20009B2431981-07-0909 July 1981 Forwards Rept Re Critical Experiment Program Authorized by Amend 11 to License CX-10.Experimental Measurements Verified That Core Parameters Are within Prescribed License Limits ML20004D3711981-06-0404 June 1981 Requests Meeting W/Nrc to Discuss Requirements Re Planned Dismantling of Lynchburg Pool Reactor for Termination of License R-47 ML20004D3701981-06-0303 June 1981 Forwards Updated Security Plan.Plan Withheld (Ref 10CFR2.790) ML19347F2811981-05-13013 May 1981 Forwards Endorsement 98 to Nelia Policies NF-111 & NF-83 ML20003E4401981-03-31031 March 1981 Forwards Info Re Security Plan,In Response to NRC 810302 Request.Info Withheld (Ref 10CFR2.790) ML19345B6481980-11-25025 November 1980 Discusses NRC 801106 Ltr Requesting Submittal of Names of Personnel Responsible for Emergency Planning.Nrc Should Direct Such Requests to AF Olsen ML19338E9001980-10-0101 October 1980 Forwards Executed Amend 20 to Indemnity Agreement B-8, Modifying Prefatory Language of Paragraph 5,Article I Re Transportation ML19331D6741980-08-29029 August 1980 Forwards Tech Specs Incorporating Changes Proposed by 790501-02 Ltrs & Submitted in Connection w/780303 Request for Renewal of License R-47 ML19323F5901980-05-19019 May 1980 Forwards Revised Page & App to Amended Reactor Security Plan.Encl Withheld (Ref 10CFR2.790) 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 ML19312D8631980-04-30030 April 1980 Submits Addl Info Re Equation for Effect of Uncertainty in Dp/Dt at Min Critical Moderator Height for Accident Condition ML19309E0731980-04-11011 April 1980 Submits Addl Info Re 791018 Amend Request.Describes Range of Allowable Nonmoderator to Moderator Ratio & Computer Codes Used for front-end Calculations for Analysis of Max Credible Accident ML19257B9261980-01-16016 January 1980 Forwards Page 18a for Insertion in 791023 Rept Hazards Evaluation Rept for Tightly-Packed Fuel Storage Critical Experiment Program. 1998-09-04
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20239A4271992-06-0404 June 1992 Forwards Proposed Survey Plan for Pathfinder Generating Station,Sioux Fall,Sd, for Approval ML20073B9901991-06-18018 June 1991 Forwards Rept Summarizing Findings of Orau Review of 59 Docket Files for Terminated Research & Test Reactors ML20151A5041988-03-30030 March 1988 Forwards Executed Amend 22 to Indemnity Agreement B-8, Terminating Agreement ML20199J9421986-07-0202 July 1986 Forwards Revised Section 8 of Dismantling Plan for CX-10 Reactor.Changes Due to Reorganization ML20206L5901986-06-24024 June 1986 Forwards Replacement Table 2-1 Providing Specific Info for Final Survey Rept for License CX-10 ML20137M4981985-08-28028 August 1985 Responds to NRC Re Violations Noted in Insp Repts 50-013/85-01 & 70-0824/85-05.Corrective Actions:Shipment of Fissle Class 2 Packages Suspended Until Checklist Containing Requirements for Shipments Developed ML20116D8891985-04-17017 April 1985 Requests Info Re Authorization for B&W to Dismantle & Decontaminate Reactor Facility Near Lynchburg,Va ML20101S5501985-01-29029 January 1985 Requests That Lynchburg Research Ctr Be Granted Authorization to Proceed W/Dismantling & Decontamination of Facility.All Fuel Possessed Under License CX-10 Shipped to DOE Oak Ridge,Tn Facility ML20099D1301984-11-15015 November 1984 Forwards Responses to 841012 Questions Re 840807 Application for Dismantlement & Termination of CX-10 Facility ML20091P5301984-06-0808 June 1984 Requests Exemption from Requirements of 10CFR50.54(r) Re Emergency Plan Due to Dismantling of CX-10 Facility ML20087N3721984-03-26026 March 1984 Forwards Endorsements 108 & 109 to Nelia Policy NF-83, Endorsement 110 to Nelia Policy NF-111 & Endorsement 42 to Maelu Policy MF-84 ML20082F1031983-11-22022 November 1983 Requests Waiver of Operator Requalification Program & 10CFR55.31(e) Requirement to Permit Operators & Senior Operators to Perform Fuel Handling Functions ML20082H6541983-11-15015 November 1983 Forwards Rev 3 to Security Plan.Rev Withheld (Ref 10CFR2.790) ML20082H6651983-09-19019 September 1983 Forwards Rev 3 to Page 6-2 of Reactor Security Plan.Page Withheld ML20065G7391982-09-27027 September 1982 Details Evaluation of Discrepancy Between Electronically Simulated Reactor & Channel Periods Revealed in Calibr Test Performed on Log-N-2 Channel.No Unsafe Condition Existed & No Tech Spec Violation Occurred ML20069G4001982-09-23023 September 1982 Forwards Emergency Plan,Revision 0 ML20062D7741982-08-0303 August 1982 Forwards Amend 21 to Indemnity Agreement B-8,in Response to NRC ML20052A8801982-04-23023 April 1982 Advises That Dismantling & Decontamination of Facility Have Been Completed.Nrc Verification Survey & Facility Release for Unrestricted Use Requested.Survey Results Encl ML20041C6691982-01-26026 January 1982 Forwards Revisions to Facility Security Plan.Revisions Withheld (Ref 10CFR2.790) ML20010G2441981-09-10010 September 1981 Requests That Lynchburg Research Ctr Be Granted Exemption from Requirements for Submittal of Revised Emergency Plan Per 10CFR50.47.Proposed Plan Would Not Be Implemented Until After Facility Fuel Has Been Removed ML20009B2431981-07-0909 July 1981 Forwards Rept Re Critical Experiment Program Authorized by Amend 11 to License CX-10.Experimental Measurements Verified That Core Parameters Are within Prescribed License Limits ML20004D3711981-06-0404 June 1981 Requests Meeting W/Nrc to Discuss Requirements Re Planned Dismantling of Lynchburg Pool Reactor for Termination of License R-47 ML20004D3701981-06-0303 June 1981 Forwards Updated Security Plan.Plan Withheld (Ref 10CFR2.790) ML19347F2811981-05-13013 May 1981 Forwards Endorsement 98 to Nelia Policies NF-111 & NF-83 ML20003E4401981-03-31031 March 1981 Forwards Info Re Security Plan,In Response to NRC 810302 Request.Info Withheld (Ref 10CFR2.790) ML19345B6481980-11-25025 November 1980 Discusses NRC 801106 Ltr Requesting Submittal of Names of Personnel Responsible for Emergency Planning.Nrc Should Direct Such Requests to AF Olsen ML19338E9001980-10-0101 October 1980 Forwards Executed Amend 20 to Indemnity Agreement B-8, Modifying Prefatory Language of Paragraph 5,Article I Re Transportation ML19331D6741980-08-29029 August 1980 Forwards Tech Specs Incorporating Changes Proposed by 790501-02 Ltrs & Submitted in Connection w/780303 Request for Renewal of License R-47 ML19323F5901980-05-19019 May 1980 Forwards Revised Page & App to Amended Reactor Security Plan.Encl Withheld (Ref 10CFR2.790) ML19312D8631980-04-30030 April 1980 Submits Addl Info Re Equation for Effect of Uncertainty in Dp/Dt at Min Critical Moderator Height for Accident Condition ML19309E0731980-04-11011 April 1980 Submits Addl Info Re 791018 Amend Request.Describes Range of Allowable Nonmoderator to Moderator Ratio & Computer Codes Used for front-end Calculations for Analysis of Max Credible Accident ML19257B9261980-01-16016 January 1980 Forwards Page 18a for Insertion in 791023 Rept Hazards Evaluation Rept for Tightly-Packed Fuel Storage Critical Experiment Program. ML19260B2441979-12-0303 December 1979 Submits Addl Info in Support of Request for Amend to License CX-10.Discusses Probability of Max Credible Accident & Need for Amend to Tech Specs ML19256E2251979-10-26026 October 1979 Forwards Executed Amend 20 to Indemnity Agreement B-8 & Amend 2 to Indemnity Agreement G-2 ML19254E4591979-10-18018 October 1979 Requests Amend to License CX-10 to Authorize Critical Experiments Utilizing nonmoderator-to-moderator Ratios Described in Hazards Evaluation Rept for Tightly-Packed Fuel Storage Critical Experiment Program. ML19276H0231979-08-15015 August 1979 Responds to 790730 Ltr Requesting Info from Nonpower Reactor Licensees Re Effect of Safeguards Rule.Upgrade Rule Necessitates Protection of Reactor as Category I Facility for Physical Protection Purposes ML19242A7741979-08-0101 August 1979 Forwards,Per s Ramos Request,Analyses of Design Basis Accident & Loca,In Support of Renewal of License R-47 ML19289E9111979-05-21021 May 1979 Forwards Executed Amend 1 to Indemnity Agreement G-2 & Amend 19 to Indemnity Agreement B-8 ML19305A3711979-03-0707 March 1979 Responds to 790301 Telcon Request.Forwards 1977 Form 10K, Annual Rept to Sec Supporting Renewal of License R-47. Form Is Last One Transmitted to Sec Re B&W Merger Into Jr Mcdermott Co ML19289D1831979-02-16016 February 1979 Responds to 790202 Ltr.Provides Details of Amounts & Enrichments of Snm.Agrees to Add License Condition Requiring Mod of Reactor Security Plan.Claims No Exemptions for Any SNM ML19269C5211979-01-29029 January 1979 Responds to NRC 780821 Ltr.Forwards Info Re Financial Data, Business Conducted,Organizational Structure,Radiological Monitoring,Safety Hazards & Tech Specs ML20147D7791978-12-0808 December 1978 Concurs That Inspec Rept Contains No Proprietary Info & Agrees to Placing It in NRC PDR 1992-06-04
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20151A5041988-03-30030 March 1988 Forwards Executed Amend 22 to Indemnity Agreement B-8, Terminating Agreement ML20199J9421986-07-0202 July 1986 Forwards Revised Section 8 of Dismantling Plan for CX-10 Reactor.Changes Due to Reorganization ML20206L5901986-06-24024 June 1986 Forwards Replacement Table 2-1 Providing Specific Info for Final Survey Rept for License CX-10 ML20137M4981985-08-28028 August 1985 Responds to NRC Re Violations Noted in Insp Repts 50-013/85-01 & 70-0824/85-05.Corrective Actions:Shipment of Fissle Class 2 Packages Suspended Until Checklist Containing Requirements for Shipments Developed ML20101S5501985-01-29029 January 1985 Requests That Lynchburg Research Ctr Be Granted Authorization to Proceed W/Dismantling & Decontamination of Facility.All Fuel Possessed Under License CX-10 Shipped to DOE Oak Ridge,Tn Facility ML20099D1301984-11-15015 November 1984 Forwards Responses to 841012 Questions Re 840807 Application for Dismantlement & Termination of CX-10 Facility ML20091P5301984-06-0808 June 1984 Requests Exemption from Requirements of 10CFR50.54(r) Re Emergency Plan Due to Dismantling of CX-10 Facility ML20082F1031983-11-22022 November 1983 Requests Waiver of Operator Requalification Program & 10CFR55.31(e) Requirement to Permit Operators & Senior Operators to Perform Fuel Handling Functions ML20082H6541983-11-15015 November 1983 Forwards Rev 3 to Security Plan.Rev Withheld (Ref 10CFR2.790) ML20082H6651983-09-19019 September 1983 Forwards Rev 3 to Page 6-2 of Reactor Security Plan.Page Withheld ML20065G7391982-09-27027 September 1982 Details Evaluation of Discrepancy Between Electronically Simulated Reactor & Channel Periods Revealed in Calibr Test Performed on Log-N-2 Channel.No Unsafe Condition Existed & No Tech Spec Violation Occurred ML20069G4001982-09-23023 September 1982 Forwards Emergency Plan,Revision 0 ML20062D7741982-08-0303 August 1982 Forwards Amend 21 to Indemnity Agreement B-8,in Response to NRC ML20052A8801982-04-23023 April 1982 Advises That Dismantling & Decontamination of Facility Have Been Completed.Nrc Verification Survey & Facility Release for Unrestricted Use Requested.Survey Results Encl ML20041C6691982-01-26026 January 1982 Forwards Revisions to Facility Security Plan.Revisions Withheld (Ref 10CFR2.790) ML20010G2441981-09-10010 September 1981 Requests That Lynchburg Research Ctr Be Granted Exemption from Requirements for Submittal of Revised Emergency Plan Per 10CFR50.47.Proposed Plan Would Not Be Implemented Until After Facility Fuel Has Been Removed ML20009B2431981-07-0909 July 1981 Forwards Rept Re Critical Experiment Program Authorized by Amend 11 to License CX-10.Experimental Measurements Verified That Core Parameters Are within Prescribed License Limits ML20004D3711981-06-0404 June 1981 Requests Meeting W/Nrc to Discuss Requirements Re Planned Dismantling of Lynchburg Pool Reactor for Termination of License R-47 ML20004D3701981-06-0303 June 1981 Forwards Updated Security Plan.Plan Withheld (Ref 10CFR2.790) ML20003E4401981-03-31031 March 1981 Forwards Info Re Security Plan,In Response to NRC 810302 Request.Info Withheld (Ref 10CFR2.790) ML19345B6481980-11-25025 November 1980 Discusses NRC 801106 Ltr Requesting Submittal of Names of Personnel Responsible for Emergency Planning.Nrc Should Direct Such Requests to AF Olsen ML19338E9001980-10-0101 October 1980 Forwards Executed Amend 20 to Indemnity Agreement B-8, Modifying Prefatory Language of Paragraph 5,Article I Re Transportation ML19331D6741980-08-29029 August 1980 Forwards Tech Specs Incorporating Changes Proposed by 790501-02 Ltrs & Submitted in Connection w/780303 Request for Renewal of License R-47 ML19323F5901980-05-19019 May 1980 Forwards Revised Page & App to Amended Reactor Security Plan.Encl Withheld (Ref 10CFR2.790) ML19312D8631980-04-30030 April 1980 Submits Addl Info Re Equation for Effect of Uncertainty in Dp/Dt at Min Critical Moderator Height for Accident Condition ML19309E0731980-04-11011 April 1980 Submits Addl Info Re 791018 Amend Request.Describes Range of Allowable Nonmoderator to Moderator Ratio & Computer Codes Used for front-end Calculations for Analysis of Max Credible Accident ML19257B9261980-01-16016 January 1980 Forwards Page 18a for Insertion in 791023 Rept Hazards Evaluation Rept for Tightly-Packed Fuel Storage Critical Experiment Program. ML19260B2441979-12-0303 December 1979 Submits Addl Info in Support of Request for Amend to License CX-10.Discusses Probability of Max Credible Accident & Need for Amend to Tech Specs ML19256E2251979-10-26026 October 1979 Forwards Executed Amend 20 to Indemnity Agreement B-8 & Amend 2 to Indemnity Agreement G-2 ML19254E4591979-10-18018 October 1979 Requests Amend to License CX-10 to Authorize Critical Experiments Utilizing nonmoderator-to-moderator Ratios Described in Hazards Evaluation Rept for Tightly-Packed Fuel Storage Critical Experiment Program. ML19276H0231979-08-15015 August 1979 Responds to 790730 Ltr Requesting Info from Nonpower Reactor Licensees Re Effect of Safeguards Rule.Upgrade Rule Necessitates Protection of Reactor as Category I Facility for Physical Protection Purposes ML19242A7741979-08-0101 August 1979 Forwards,Per s Ramos Request,Analyses of Design Basis Accident & Loca,In Support of Renewal of License R-47 ML19289E9111979-05-21021 May 1979 Forwards Executed Amend 1 to Indemnity Agreement G-2 & Amend 19 to Indemnity Agreement B-8 ML19305A3711979-03-0707 March 1979 Responds to 790301 Telcon Request.Forwards 1977 Form 10K, Annual Rept to Sec Supporting Renewal of License R-47. Form Is Last One Transmitted to Sec Re B&W Merger Into Jr Mcdermott Co ML19289D1831979-02-16016 February 1979 Responds to 790202 Ltr.Provides Details of Amounts & Enrichments of Snm.Agrees to Add License Condition Requiring Mod of Reactor Security Plan.Claims No Exemptions for Any SNM ML19269C5211979-01-29029 January 1979 Responds to NRC 780821 Ltr.Forwards Info Re Financial Data, Business Conducted,Organizational Structure,Radiological Monitoring,Safety Hazards & Tech Specs ML20147D7791978-12-0808 December 1978 Concurs That Inspec Rept Contains No Proprietary Info & Agrees to Placing It in NRC PDR 1988-03-30
[Table view] |
Text
- _ - -
- A Research & Development Division Babcock & Wilcox tynennora R....rch c.nier a McDermott company P. O. Box 11165 Lynchburg, Virginia 24506-1165
~
July 2,1986 l
Standardization and Special Projects Branch Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555 i
Reference:
License No. CX-10, Docket No. 50-13 1
Subject:
Organization Change Gentlemen:
My letter dated August 7,1984, forwarded the Dismantling Plan for the CX-10 Reactor, dated July,1984. Since that time there has been a re- i organization at the Lynchburg Research Center that affects the dis- l mantling plan.
A revised Section 8 of the plan is attached. Changes are indicated by '
vertical lines in the right-hand margin.
Very truly yours, l BABC0CK & WILC0X Lynchburg Research Center a010~
Arne F. Olsen Senior License Administrator Jhc Attachment I pc: NRC, Region II O
8607080465 860702 PDR "T f-' I P
ADOCK 05000013 PDR -
8.0 Administrative Requirements 8.1 Technical Specification The technical specifications for the CX-10 facility have not been designated, in as much as the facility was licensed for operation prior to January 16, 1969. As specified in 10 CFR 50.36(d)(1), the technical specifications shall be deemed to include the entire safety analysis report as technical specifi-cations. These technical specifications address the safety of the facility during operation and will no longer be applicable for the operations speci-fied in this plan. Therefore, subsequent to the removal of the fuel from the facility and transfer of the An-Be sealed sources, the technical specifi-cations shall be replaced with the requirements specified in this plan.
8.2 Organization Figure 8-1 is the organization chart for the Lynchburg Research Center (LRC) as. it applies to the CX-10 Decommissioning project. -
8.2.1 Manager, Lynchburg Technical Operations - The Manager, Lynchburg Techni-cal Operations has overall authority and responsibility for all operations at the Lynchburg Research Center. He is appointed by and reports to the Vice President, Research and Development Division.
8.2.2 Manager, Decommissioning - The Manager, Decommissioning is responsible for managing the dismantling and decontamination activities associated with the CX-10 decommissioning, retaining the necessary records, pre-paring all ' reg'uired reports and controlling the project expenses. The Manager, Decommissioning is appointed by and reports to the Vice President, Research and Development Division.
8.2.3 Manager, Facilities and Ouality Assurance - The Manager, Facilities and Quality Assurance has overall authority and responsibility for the ad-ministration of the Quality Assurance program within the Research and Development Division. He is appointed by and reports to the Vice President, Research and Development Division.
8-1
8.2.4 Manager, Quality Assurance - The Manager, Quality Assurance has the j authority and responsibility for the implementation of the Quality I Assurance program within the Research and Development Division. He is
( appointed by and reports to the Manager, Facilities and Quality l Assurance.
8.2.5 Quality Assurance Administrator - The Quality Assurance Administrator implements the Quality Assurance program at the Lynchburg Research Center. He reprts to the Manager, Quality Assurance and is independent l from all operatic's at the Lynchburg Research Center. He shall be responsible for reviewing and approving Quality Assurance program plans. .
He performs vendor audits and audits LRC projects for compliance with !
approved QA program plans. He shall administer the technical procedure l program.
8.2.6 Safety Review Committee - The Safety Review Committee (SRC) is comprised l Uf. at least five senior technical members appointed by the Manager.
Lynchburg Technical Operations. The membership shall be constituted of no nore than 75% from the LRC. There shall be one member representing l
LRC management who will act as the committee coordinator. The combined experience of the members includes reactor operations, reactor engineering, health physics radiological safety, licensed material handling and chemistry. Specialized consultants are also available to the SRC. The Facility Supervisor shall determine the items that come l
before the committee.
The following are examples of items that require SRC approval:
- a. Any change requiring a " license amendment.
- b. Any new process which involves the use of licensed naterial.
- c. Any change of a technical specification,
- d. Any change, test, or experiment pursuant to a reactor license involving an unreviewed safety question as defined in 10 CFR 50.59(c).
The Committee also has the following functions:
- a. Review general procedures for handling and using licensed material.
8-2 .
l
- b. Review procedures for the acquisition and disposal of licensed materi al . -
- c. Review procedures for maintaining an accurate inventory of licensed material ,
- d. Review procedures for the control of radiation and the protection of personnel from radiation exposure,
- e. Review procedures and proposed projects for fire safety and fire pre-vention considerations,
- f. Review any changes in the foregoing procedures that require a significant deviation from established procedures before the changes are instituted.
- g. Review abnomal occurrences as defined in appropriate reactor licenses.
- h. Review proposed experiments and tests at the reactor and critical experiment facilities which are significantly different from those previously perfomed at the facilities.
- 1. Provide the LRC with general consulting services in the field of radiation protection and radioactive materials handling.
Committee approval of new processes and practices prior to the writing of procedures will be occasionally necessary due to the experimental nature of the work perfomed at the LRC. In these instances, the Committee will review, with those responsible for the safe operation of the process or practice, the potential hazards and philosophy of operation. The l l
approval by the Committee shall constitute approval to perfom the work l without written procedures. The SRC shall meet four times annually. A quarum shall consist of a majority of the membership.
8.2.7 Facility Sdper' visor - The Facility Supervisor is appointed by and reports l to the Manager, Lynchburg Technical Operations. He shall demonstrate to Company management proficiency in the application of good principles of radiation protection, industrial safety and nuclear criticality safety as l related to activities at the LRC. He shall be responsible to the Manager, Lynchburg Technical Operations for the safe conduct of all operations at l
the LRC and for assuring that these operations are conducted in accordance with all license conditions. He shall also be responsible for reviewing and approving all area operating procedures.
8-3 i
8.2.8 Manager, Safety and Licensing - The Manager, Safety and Licensing is appointed by and reports- to the Manager, Lynchburg Technical Operations.
The Supervisor, Health and Safety, the License Administrator, and the Accountability Specialist report to him.
8.2.9 License Administrator - The License Administrator shall have a B.S. I degree in science or engineering and three year experience in nuclear i technology or an A.S. degree in science or nuclear technology and 12 year
- experience in nuclear technology. The License Administrator reports to the Manager, Safety and Licensing.
! The License Administrator shall be responsible for administering the LRC 4 licenses. He shril be the primary liaison with the NRC and other
, federal, state and local agencies regarding nuclear matters. He is the
) coordinator of the Safety Review Committee and is the management repre-j sentative on the SRC. He is the chairman of the Safety Audit Sub-I
, committee and is the Facility Supervisor. The License Administrator is the LRC's internal auditor for regulatory compliance.
4 8.2.10 Accountability Specialist - The Accountability Specialist reports to the !
Manager, Safety and Licensing. He is responsible for maintenance and re-tension of the SNM accountability records, preparing and transnitting t
required reports.
J 8.2.11 Supervisor, Health and Safety - The Supervisor, Health and Safety is appointed by and reports to the Manager, Safety and Licensing. The l supervisor"sha'll have a B.S. degree in a technical field and professional l experience in assignments involving radiation protection at a supervisory l evel . He shall have five years experience and demonstrated proficiency-
- in the application of radiation safety principles and be knowledgeable in the fields related to radiation protection.
i His duties include supervising the activities of the Industrial Safety technician and the Health Physics Engineers.
4 8-4
t 8.2.12 Health Physics Engineer - The Health Physics Engineer shall be appointed by and report to the Supervisor, Health and Safety. He shall have a B.S.
degree with course work in Health Physics. His responsibilities include:
- a. Performing area surveys.
- b. Administering the air survey program.
- c. Administering the respiratory protection program.
- d. Administering the bioassay program,
- e. Leak testing sealed sources.
- f. Supervising shipping and receiving of radioactive materials,
- g. Supervising and coordinating the waste disposal program i
- h. Assisting in personnel, equipment and facility decoatamination.
- i. Conducting radiation safety training,
- j. Providing expertise in all aspects of radiation protection.
i k. Generating, maintaining and distributing records and reports required by regulations and procedures pertinent to the group's activities.
- 1. Distributing and processing personnel monitoring equipment.
8.2.13 Survey Monitors - Survey Monitors are technicians trained in the per-formance of radiation and contamination surveys. They report to the Manager, Decommissioning for their day-to-day work assignments and administratively to the Health Physics Engineer. They shall perform surveys and generate required records.
8.2.14 Technician, Industrial Safety - The Industrial Safety Technician shall be appointed by and report to the Manager, Safety and Licensing. He shall have one year of experience in radiation and industrial safety. He shall be familiar with the codes and requirements of OSHA and NFPA. His responsibilities shall include:
- a. Administering the Industrial Safety Program,
- b. Reviewing proposed facility changes to insure fire safety,
- c. Providing expertise in fire prevention to the Facility Supervisor and Safety Review Committee,
- d. Performing tests, inspections and maintenance of fire protection, control and extinguishing equipment.
, e. Provide training for the LRC Fire and Rescue Team, t .
8-5 i
. . .. _ .. . _ - ~--.- ..-
- f. Conducting safety inspections.
8.2.15 tianager, Facilities - The Manager, Facilities shall be appointed by the l Manager, Facilities and Quality Assurance. His duties include the super-vision and direction of two groups; Office Services and Plant Engineering.
He assists in planning and coordinating work for other departments involving Facilities personnel and outside contractors.
Other responsibilities include assisting technical sections in planning and designing systems and facilities to carry out their objectives, and recommending, designing, estimating, and supervising new construction and modifications to existing structures and systems.
8.2.16 Supervisor, Plant Engineering - The Supervisor, Plant Engineering is !
appointed by and reports to the Manager, Facilities. His duties include supervising the activities of the custodians, two groups of maintenance personnel, and contractors.
8.2.17 Decommissioning Foreman - The Decommissioning Foreman is appointed by and reports to the Manager, Decommissioning. The foreman directs the day-to-day activities of the work crew. The foreman is trained and experience fil the safe handling of radioactive material.
l 8.2.18 Technical Support - The two technical laboratories provide personnel and facilities to support the decommissioning project on an as needed basis.
This support includes data interpretation, development of measurement ,
techniques, performing special measurement tasks, and report writing. .
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