ML20082F103
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| ML20082F103 | |
| Person / Time | |
|---|---|
| Site: | Lynchburg Research Center |
| Issue date: | 11/22/1983 |
| From: | Olsen A BABCOCK & WILCOX CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8311280430 | |
| Download: ML20082F103 (1) | |
Similar Documents at Lynchburg Research Center | |
|---|---|
Category:CORRESPONDENCE-LETTERS
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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 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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 Category:INCOMING CORRESPONDENCE MONTHYEARML20239A4271992-06-0404 June 1992
[Table view]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 Category:VENDOR/MANUFACTURER TO NRC MONTHYEARML20151A5041988-03-30030 March 1988
[Table view]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 |
Text
Research & Development Division Babcock & Wilcox tynennor R.s..ren c.ni.,
a McDermott company P.O. Box 239 Lynchburg, Virginia 24505
@ 4)s22 m November 22, 1983 Standardization and Special Projects Branch Division of Licensing NRR U. S. Nuclear Regulatory Commission Washington, D. C. 20555 License: CX-10, Docket 50-13 Gentlemen:
The CX-10 reactor has been shut down and its fuel placed in storage since mid-September, and no further operations are planned. The Lynchburg Research Center is developing plans that will lead to shipping the fuel off site, dismantlement of the facility and termination of the license.
During the period between the facility's final shutdown and comple-tion of the fuel shipments, properly qualified reactor operators and senior operators must be available for the fuel handling. Under the present circumstances, it is not possible for the personnel to perform the functions of an operator as required by 10 CFR 55.31(e). 1 therefore request that a waiver be granted that will permit our operators and senior operators to perform fuel handling functions,notwithstanding the fact that they have not met the 55.31(e) requirement.
I further request that the continued implementation of the Operator Requalification Program, which was approved for this facility on April 2, 1974, be waived.
If you have questions regarding these requests, please call me.
Very truly yours, BABC0CK & WILCOX Lynchburg Research Center
.- 206~
Arne F. Olsen Senior License Administrator AF0/sfp R O gR$
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