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| Line 2: |
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| | number = ML20062D774 | | | number = ML20062D774 |
| | issue date = 08/03/1982 | | | issue date = 08/03/1982 |
| | title = Forwards Amend 21 to Indemnity Agreement B-8,in Response to NRC 820720 Ltr | | | title = Forwards Amend 21 to Indemnity Agreement B-8,in Response to NRC |
| | author name = Olsen A | | | author name = Olsen A |
| | author affiliation = BABCOCK & WILCOX CO. | | | author affiliation = BABCOCK & WILCOX CO. |
| Line 11: |
Line 11: |
| | contact person = | | | contact person = |
| | document report number = NUDOCS 8208060217 | | | document report number = NUDOCS 8208060217 |
| | | title reference date = 07-20-1982 |
| | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, VENDOR/MANUFACTURER TO NRC | | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, VENDOR/MANUFACTURER TO NRC |
| | page count = 2 | | | page count = 2 |
Latest revision as of 14:53, 1 June 2023
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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
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____ -_
Y Research & Development Division Babcock & Wilcox Lynchburg Research Center a McDermott company P.O. Box 239 Lynchburg, Virginia 24505 August 3, 1982 (804) 384-5111 Director Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555
Reference:
License Termination R-47, Docket 50-99 Gentlemen:
In response to Darrell G. Eisenhut's letter to me dated July 20, 1982, I am enclosing a signed copy of Amendment 21 to Indemnity
. Agreement No. B-8.
Very truly yours, BABCOCK & WILCOX I
Lynchburg Research Center W -
Arne F. Olsen Senior License Administrator AF0/jhc Enclosure I o>o ri 8208060217 820803 PDR ADOCK 05000099 d PDR
e I, +j8%
, k UNITED STATES f% ,
5 NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
%, ..... f .
Docket No. 50-99 AMENDMENT TO INDEMNITY AGREEMENT N0. B-8 AMENDMENT NO. 21 Effective NL 2.0 1952 , Indemnity Agreement No. B-8 between Babcock and Wilcox Company and the Atomic Energy Commission, dated December 8, 1961, as amended, is hereby further amended as follows:
Item 3 of the Attachment to the indemnity agreement is deleted in its entirety and the following substituted therefor:
Item 3 - License number or numbers CX-1 (From 12:01 a.m. , September 26, 1957 to 12 midnight, May 31, 1973, inclusive)
CX-10 (From 12:01 a.m. , January 22, 1958)
CX-12 (From 12:01 a.m. , September 24, 1958 to 12 midnight, February 13, 1972 inclusive)
CX-19 (From 12:01 a.m. , May 14,1962, to 12 midnight, May 31, 1973 inclusive)
R-47 (From 12:01 a.m. , September 5,1958 to 12 midnight GUL 2:0 lb&-
inclusive)
TR-4 (From 12:01 a.m. , January 25, 1964 to 12 midnight, February 28, 1973 inclusive)
FOR THE UNITED STATES NUCLEAR REGULATORY C0hEISSION fkYW
' Jerome Saltzman, As'sistant Dir'ector State and Licensee Relations Office of State' Programs l
ACCEPTED [3 1982 BY b j BABC0CK & WILCOX COMPANY l
L.