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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20210T9861999-08-12012 August 1999 Forwards Amend 7 to License SNM-1067,changing Name of License to ABB Combustion Engineering Nuclear Power & Incorporating Into License Date of 990618 for Decommissioning Financial Assurance.Ser,Encl ML20210F6891999-07-29029 July 1999 Forwards Amended Application Pages Which Reflect Change in New Organization.Effective Date of Transfer from Combustion Engineering,Inc to ABB Combustion Engineering Nuclear Power, Inc Was 990629 ML20195D3871999-06-0303 June 1999 Forwards Application for Amend to License SNM-1067 to Transfer All Assets & Liabilities Related to NRC Licensed Activities of Combustion Engineering,Inc to ABB Combustion Engineering Nuclear Power,Inc ML20196J1571998-12-0202 December 1998 Forwards Insp Rept 70-1100/98-01 on 981116-18.No Violations Noted.Insp Consisted of Selective Exams of Procedures & Representative Records,Interviews with Personnel & Observations by Inspector ML20198A9731997-12-10010 December 1997 Forwards Insp Rept 70-1100/97-02 on 971118-20.No Violations Noted.Licensee Maintained Effective Control of Radioactive Matl in Storage & Control of Facility Activities to Maintain Worker Radiation Protection ML20198R0191997-10-29029 October 1997 Forwards Amend 5 to License SNM-1067 & Ser,Including Categorical Exclusion Determination.Amend Removes Bldg 21 & Immediate Environs as Authorized Place for Use of Licensed Matl.License Conditions 6.B,7.B & 8.B,deleted ML20211H7711997-09-30030 September 1997 Forwards Amend 4 to License SNM-1067,deleting Listed Authorized Possession Limits,Ref to All Bldgs Except Bldg 21 & Authorization for All Activities Except Those Related to Decommissioning of Bldg 21 ML20211E0781997-09-19019 September 1997 Requests Further Changes Which Delete Request for Authorization to Possess SNM in Bldg 21.No Source Matl or SNM Has Been Possessed in or Around Bldg 21 Since 960208. Change Pages,Encl ML20217Q3001997-08-21021 August 1997 Submits Response to Questions on Amend Request to Downgrade License SNM-1067.Description of Revs to Submittal in ,List of Pages of Ltr to Be Replaced,Listing of Resulting Effective Pages of Pending Application & Changes,Encl ML20140G6601997-06-10010 June 1997 Forwards Insp Rept 70-1100/97-01 on 970414-17.No Violations Noted.Within Scope of Insp,No Radioactive Contamination or Radiation Levels Above Background Were Measured ML20137D9361997-03-21021 March 1997 Responds to Requesting FY97 Annual Fee for License SNM-1067 Be Assessed Pursuant to Fee Category 14 Rather than Any Other Category.Nrc Agrees That License SNM-1067 Not Subj to Annual Fees for FY97 ML20133A9251996-12-24024 December 1996 Forwards Amend 3 to License SNM-1067 & Safety Evaluation Extending Interim Storage Period of Packaged low-level Radwaste from 5 to 10 Yrs L-96-505, Responds to NRC Request in Ltr Re Amend Request from Combustion Engineering to Downgrade License SNM-1067,1996-12-20020 December 1996 Responds to NRC Request in Ltr Re Amend Request from Combustion Engineering to Downgrade License SNM-1067, ML20132D8131996-12-17017 December 1996 Forwards Amend 2 to License SNM-1067 by Including Methods for Determination of Action Levels for Environ Monitoring Data.Ser Attached ML20135F7471996-12-10010 December 1996 Informs That Mf Weber Branch Chief for Fuel Cyle Licensing Branch,Effective 961118 ML20135E9681996-12-0404 December 1996 Forwards Insp Rept 70-1100/96-02 on 961118-21.No Violations Noted ML20149L7391996-11-0808 November 1996 Informs of Addl Info Needed Before Final Action Can Be Taken on Request for Amend to Delete Windsor Lab Bldgs & Operations,Reduce SNM Possession Limits & Delay Decommissioning Underway on Bldg 17 L-96-504, Requests Extension to Interim Storage Period by Increasing Time from 5 Yrs to 10 Yrs1996-10-31031 October 1996 Requests Extension to Interim Storage Period by Increasing Time from 5 Yrs to 10 Yrs ML20128P3991996-10-15015 October 1996 Ack Receipt of Ltr Dtd 960930,requesting Elimination of Annual License Fees L-96-503, Requests That Annual Fees for FY97 for SNM-1067 Be Assessed Per 10CFR171.16-1,Category 141996-09-30030 September 1996 Requests That Annual Fees for FY97 for SNM-1067 Be Assessed Per 10CFR171.16-1,Category 14 ML20129A7231996-09-0303 September 1996 Notifies NRC That Address of C-E Changed by Town of Windsor, Without Any Change in Physical Location of Facility ML20129A7001996-07-29029 July 1996 Forwards NRC Comments on DOE Draft Rept, Derivation of Guidelines for Cobalt-60,Ni-63 & U Residual Radioactive Matl in Soil at Combustion Engineering Site,Windsor,Ct. Submitted Per 960322 Request L-93-062, Requests Extension on Completion Date for Next Assessment from 940117 to 0315 Re Fundamental Nuclear Matl Control Plan Due to Extraordinary Workloads of Qualified Independent Individuals Intended to Perform Assessment1993-12-22022 December 1993 Requests Extension on Completion Date for Next Assessment from 940117 to 0315 Re Fundamental Nuclear Matl Control Plan Due to Extraordinary Workloads of Qualified Independent Individuals Intended to Perform Assessment L-93-059, Forwards Proprietary Response to Violations Noted in Insp Rept 70-1100/93-201 Re Matl Control & Accounting Program. Encl Withheld Per 10CFR2.7901993-12-15015 December 1993 Forwards Proprietary Response to Violations Noted in Insp Rept 70-1100/93-201 Re Matl Control & Accounting Program. Encl Withheld Per 10CFR2.790 ML20059M9231993-11-18018 November 1993 Forwards Insp Rept 70-1100/93-201 on 931025-29 & Notice of Violation.Details of Insp Rept & Notice of Violation Withheld,Per 10CFR2.790(d) L-93-052, Provides Request for Addl Info Re Decommissioning Funding Plan Submitted on 9207021993-11-10010 November 1993 Provides Request for Addl Info Re Decommissioning Funding Plan Submitted on 920702 ML20059C3661993-10-29029 October 1993 Forwards Amend 28 to License SNM-1067 & Ser.Amend Decreases Possession Limits & Removes Authorization to Conduct U Bearing Nuclear Fuel Mfg Operations at Facility L-93-045, Provides Revised Organization Chart for License SNM-1067 W/Description for Each Key Position to Safety1993-10-26026 October 1993 Provides Revised Organization Chart for License SNM-1067 W/Description for Each Key Position to Safety ML20059C1801993-10-23023 October 1993 Forwards Insp Rept 70-1100/93-03 on 930915-17.No Violations Noted L-93-040, Informs That Licensee Believes Response to NRC Bulletin 91-001,Suppl 1,is No Longer Required Due to Windsor Facility No Longer Being Fuel Fabrication Facility1993-10-0707 October 1993 Informs That Licensee Believes Response to NRC Bulletin 91-001,Suppl 1,is No Longer Required Due to Windsor Facility No Longer Being Fuel Fabrication Facility L-93-039, Confirms Termination of Nuclear Fuel Mfg Activities at Facility,Per Commitment Made in1993-09-30030 September 1993 Confirms Termination of Nuclear Fuel Mfg Activities at Facility,Per Commitment Made in ML20057C9881993-09-29029 September 1993 Forwards List of Personnel to Be Granted Unescorted Access to Facility ML20057B8921993-09-23023 September 1993 Accepts Proposed Date of 931008 Re NRC Bulletin 91-001,Suppl 1 ML20057C2111993-09-23023 September 1993 Ack Receipt of 930915 Notification of Decision to Terminate, by 930930,commercial Nuclear Fuel Mfg Operations at Windsor Facility.Understands That C-E Plans to Submit Amend Request Reflecting Listed Changes in Sept 1993 RA-93-016, Notifies That C-E Will Terminate,By 930930,commercial Nuclear Fuel Mfg Operations at Windsor Facility.Subj Termination Will Consist of Cessation of Mfg of U Bearing Fuel & Removal of All Inventoried SNM in Bldgs 17 & 211993-09-15015 September 1993 Notifies That C-E Will Terminate,By 930930,commercial Nuclear Fuel Mfg Operations at Windsor Facility.Subj Termination Will Consist of Cessation of Mfg of U Bearing Fuel & Removal of All Inventoried SNM in Bldgs 17 & 21 ML20057A7571993-09-14014 September 1993 Accepts Proposed New Date for Submitting Addl Info Re Decommissioning Funding Plan L-93-034, Submits 30 Day Rept of 930804 Criticality Alarm Sys Inoperability.Caused by Tripped Circuit Breaker Due to Inadvertent Circuit Overload.Circuits Walked Down & Checked by Electrician1993-09-0303 September 1993 Submits 30 Day Rept of 930804 Criticality Alarm Sys Inoperability.Caused by Tripped Circuit Breaker Due to Inadvertent Circuit Overload.Circuits Walked Down & Checked by Electrician L-93-032, Requests Changes to Windsor Low Level Radioactive Storage Amend Ltrs & 1223 Re Interim Storage of Low Level Radwaste1993-08-20020 August 1993 Requests Changes to Windsor Low Level Radioactive Storage Amend Ltrs & 1223 Re Interim Storage of Low Level Radwaste ML20046D3571993-08-17017 August 1993 Ack Receipt of Re Withdrawal of Application & 0716,requesting License SNM-1076 Be Separated Into Two Licenses.All Action Re Application Has Been Terminated ML20056G7481993-08-11011 August 1993 Advises That 930628 Changes to Physical Security Plan, Consistent W/Provisions of 10CFR70.32(e) & Acceptable for Inclusion Into Plan ML20056D6861993-08-10010 August 1993 Forwards Amend 26 to License SNM-1067 & Ser.Amend Authorizes Revs to Emergency Plan,Per 910627 Application & Suppl ML20046C5931993-08-0505 August 1993 Responds to NRC Re Violations Noted in Insp Rept 70-1100/93-01.Corrective Actions Not Encl L-93-106, Requests Withdrawal to Bifurcate License SNM-1067.Purpose Was to Bifurcate License to Cover Manufactoring & Lab Operations Which Have Been Discontinued1993-08-0303 August 1993 Requests Withdrawal to Bifurcate License SNM-1067.Purpose Was to Bifurcate License to Cover Manufactoring & Lab Operations Which Have Been Discontinued ML20046C1021993-08-0202 August 1993 Forwards Request for Addl Info Re Transmitting Decommissioning Funding Plan.Addl Info Requested in Encl Should Be Provided 30 Days from Date of NRC Ltr L-93-028, Forwards Corrections to 930615 Application to Bifurcate License SNM-1067 Into Two Licenses,One for Nuclear Fuel Mfg & Other for Product Research & Development1993-07-16016 July 1993 Forwards Corrections to 930615 Application to Bifurcate License SNM-1067 Into Two Licenses,One for Nuclear Fuel Mfg & Other for Product Research & Development ML20045G6561993-07-0808 July 1993 Forwards Insp Rept 70-1100/93-01 on 930511-13 & Notice of Violation.Unresolved Item Re Safety Control Specified on Sign Posted in Pellet Shop Identified ML20045J2911993-07-0202 July 1993 Provides Followup to Recent Telcons Re C-E Facility in Windsor,Ct,W/Respect to C-E Request in 1991 That DOE Include Certain Portions of Subj Facility Under C-E Formerly Utilized Sites Remedial Action Program L-93-026, Forwards Proprietary Update to C-E Physical Security Plan, Providng Info Re Removal of Room 224C in Bldg 5 of Product Development Facility from NRC Approved Security Plan,Since Vendor No Longer Plans to Handle SNM in Room.Encl Withheld1993-06-28028 June 1993 Forwards Proprietary Update to C-E Physical Security Plan, Providng Info Re Removal of Room 224C in Bldg 5 of Product Development Facility from NRC Approved Security Plan,Since Vendor No Longer Plans to Handle SNM in Room.Encl Withheld ML20045E7571993-06-24024 June 1993 Forwards Insp Rept 70-1100/93-02 on 930602-04.No Violations Noted L-93-023, Forwards Applications to Bifurcate License SNM-1067 Into Two Separate Licenses,Consisting of Mfg License & Lab License. Purpose of Separation Is to Simplify Shutdown of Mfg Operations W/O Impacting Ongoing R&D Operations1993-06-15015 June 1993 Forwards Applications to Bifurcate License SNM-1067 Into Two Separate Licenses,Consisting of Mfg License & Lab License. Purpose of Separation Is to Simplify Shutdown of Mfg Operations W/O Impacting Ongoing R&D Operations 1999-08-12
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20210F6891999-07-29029 July 1999 Forwards Amended Application Pages Which Reflect Change in New Organization.Effective Date of Transfer from Combustion Engineering,Inc to ABB Combustion Engineering Nuclear Power, Inc Was 990629 ML20195D3871999-06-0303 June 1999 Forwards Application for Amend to License SNM-1067 to Transfer All Assets & Liabilities Related to NRC Licensed Activities of Combustion Engineering,Inc to ABB Combustion Engineering Nuclear Power,Inc ML20211E0781997-09-19019 September 1997 Requests Further Changes Which Delete Request for Authorization to Possess SNM in Bldg 21.No Source Matl or SNM Has Been Possessed in or Around Bldg 21 Since 960208. Change Pages,Encl ML20217Q3001997-08-21021 August 1997 Submits Response to Questions on Amend Request to Downgrade License SNM-1067.Description of Revs to Submittal in ,List of Pages of Ltr to Be Replaced,Listing of Resulting Effective Pages of Pending Application & Changes,Encl L-96-505, Responds to NRC Request in Ltr Re Amend Request from Combustion Engineering to Downgrade License SNM-1067,1996-12-20020 December 1996 Responds to NRC Request in Ltr Re Amend Request from Combustion Engineering to Downgrade License SNM-1067, L-96-504, Requests Extension to Interim Storage Period by Increasing Time from 5 Yrs to 10 Yrs1996-10-31031 October 1996 Requests Extension to Interim Storage Period by Increasing Time from 5 Yrs to 10 Yrs L-96-503, Requests That Annual Fees for FY97 for SNM-1067 Be Assessed Per 10CFR171.16-1,Category 141996-09-30030 September 1996 Requests That Annual Fees for FY97 for SNM-1067 Be Assessed Per 10CFR171.16-1,Category 14 ML20129A7231996-09-0303 September 1996 Notifies NRC That Address of C-E Changed by Town of Windsor, Without Any Change in Physical Location of Facility L-93-062, Requests Extension on Completion Date for Next Assessment from 940117 to 0315 Re Fundamental Nuclear Matl Control Plan Due to Extraordinary Workloads of Qualified Independent Individuals Intended to Perform Assessment1993-12-22022 December 1993 Requests Extension on Completion Date for Next Assessment from 940117 to 0315 Re Fundamental Nuclear Matl Control Plan Due to Extraordinary Workloads of Qualified Independent Individuals Intended to Perform Assessment L-93-059, Forwards Proprietary Response to Violations Noted in Insp Rept 70-1100/93-201 Re Matl Control & Accounting Program. Encl Withheld Per 10CFR2.7901993-12-15015 December 1993 Forwards Proprietary Response to Violations Noted in Insp Rept 70-1100/93-201 Re Matl Control & Accounting Program. Encl Withheld Per 10CFR2.790 L-93-052, Provides Request for Addl Info Re Decommissioning Funding Plan Submitted on 9207021993-11-10010 November 1993 Provides Request for Addl Info Re Decommissioning Funding Plan Submitted on 920702 L-93-045, Provides Revised Organization Chart for License SNM-1067 W/Description for Each Key Position to Safety1993-10-26026 October 1993 Provides Revised Organization Chart for License SNM-1067 W/Description for Each Key Position to Safety L-93-040, Informs That Licensee Believes Response to NRC Bulletin 91-001,Suppl 1,is No Longer Required Due to Windsor Facility No Longer Being Fuel Fabrication Facility1993-10-0707 October 1993 Informs That Licensee Believes Response to NRC Bulletin 91-001,Suppl 1,is No Longer Required Due to Windsor Facility No Longer Being Fuel Fabrication Facility L-93-039, Confirms Termination of Nuclear Fuel Mfg Activities at Facility,Per Commitment Made in1993-09-30030 September 1993 Confirms Termination of Nuclear Fuel Mfg Activities at Facility,Per Commitment Made in RA-93-016, Notifies That C-E Will Terminate,By 930930,commercial Nuclear Fuel Mfg Operations at Windsor Facility.Subj Termination Will Consist of Cessation of Mfg of U Bearing Fuel & Removal of All Inventoried SNM in Bldgs 17 & 211993-09-15015 September 1993 Notifies That C-E Will Terminate,By 930930,commercial Nuclear Fuel Mfg Operations at Windsor Facility.Subj Termination Will Consist of Cessation of Mfg of U Bearing Fuel & Removal of All Inventoried SNM in Bldgs 17 & 21 L-93-034, Submits 30 Day Rept of 930804 Criticality Alarm Sys Inoperability.Caused by Tripped Circuit Breaker Due to Inadvertent Circuit Overload.Circuits Walked Down & Checked by Electrician1993-09-0303 September 1993 Submits 30 Day Rept of 930804 Criticality Alarm Sys Inoperability.Caused by Tripped Circuit Breaker Due to Inadvertent Circuit Overload.Circuits Walked Down & Checked by Electrician L-93-032, Requests Changes to Windsor Low Level Radioactive Storage Amend Ltrs & 1223 Re Interim Storage of Low Level Radwaste1993-08-20020 August 1993 Requests Changes to Windsor Low Level Radioactive Storage Amend Ltrs & 1223 Re Interim Storage of Low Level Radwaste ML20046C5931993-08-0505 August 1993 Responds to NRC Re Violations Noted in Insp Rept 70-1100/93-01.Corrective Actions Not Encl L-93-106, Requests Withdrawal to Bifurcate License SNM-1067.Purpose Was to Bifurcate License to Cover Manufactoring & Lab Operations Which Have Been Discontinued1993-08-0303 August 1993 Requests Withdrawal to Bifurcate License SNM-1067.Purpose Was to Bifurcate License to Cover Manufactoring & Lab Operations Which Have Been Discontinued L-93-028, Forwards Corrections to 930615 Application to Bifurcate License SNM-1067 Into Two Licenses,One for Nuclear Fuel Mfg & Other for Product Research & Development1993-07-16016 July 1993 Forwards Corrections to 930615 Application to Bifurcate License SNM-1067 Into Two Licenses,One for Nuclear Fuel Mfg & Other for Product Research & Development ML20045J2911993-07-0202 July 1993 Provides Followup to Recent Telcons Re C-E Facility in Windsor,Ct,W/Respect to C-E Request in 1991 That DOE Include Certain Portions of Subj Facility Under C-E Formerly Utilized Sites Remedial Action Program L-93-026, Forwards Proprietary Update to C-E Physical Security Plan, Providng Info Re Removal of Room 224C in Bldg 5 of Product Development Facility from NRC Approved Security Plan,Since Vendor No Longer Plans to Handle SNM in Room.Encl Withheld1993-06-28028 June 1993 Forwards Proprietary Update to C-E Physical Security Plan, Providng Info Re Removal of Room 224C in Bldg 5 of Product Development Facility from NRC Approved Security Plan,Since Vendor No Longer Plans to Handle SNM in Room.Encl Withheld L-93-023, Forwards Applications to Bifurcate License SNM-1067 Into Two Separate Licenses,Consisting of Mfg License & Lab License. Purpose of Separation Is to Simplify Shutdown of Mfg Operations W/O Impacting Ongoing R&D Operations1993-06-15015 June 1993 Forwards Applications to Bifurcate License SNM-1067 Into Two Separate Licenses,Consisting of Mfg License & Lab License. Purpose of Separation Is to Simplify Shutdown of Mfg Operations W/O Impacting Ongoing R&D Operations L-93-020, Provides Response to Request for Addl Info Re Low Level Radwaste Storage1993-06-0303 June 1993 Provides Response to Request for Addl Info Re Low Level Radwaste Storage L-93-017, Requests That Previous Windsor Payments Be Applied to Hematite Facility (License SNM-33) & That NRC Take No Action to Assess Interest,Administrative,Or Penalty Charges Against Licensee for Failing to Make Timely Payment1993-05-20020 May 1993 Requests That Previous Windsor Payments Be Applied to Hematite Facility (License SNM-33) & That NRC Take No Action to Assess Interest,Administrative,Or Penalty Charges Against Licensee for Failing to Make Timely Payment L-93-015, Forwards Revs & Corrected Pages to C-E Physical Security Plan for Windsor Nuclear Fuel Manufacturing Facility.Encls Withheld Per 10CFR2.790(d)1993-04-23023 April 1993 Forwards Revs & Corrected Pages to C-E Physical Security Plan for Windsor Nuclear Fuel Manufacturing Facility.Encls Withheld Per 10CFR2.790(d) ML20035B2041993-03-30030 March 1993 Forwards Decommissioming Plan, Reflecting Scope of Activities Being Terminated Under License SNM-1067 RA-93-003, Forwards Decommissioning Plan, Reflecting Scope of Activities Being Terminated Under SNM License SNM-10671993-03-30030 March 1993 Forwards Decommissioning Plan, Reflecting Scope of Activities Being Terminated Under SNM License SNM-1067 ML20056H6261993-03-19019 March 1993 Transmits Current CEOG Generic Accident Mgt Guidelines Rev O Documents ML20034G6281993-03-0303 March 1993 Forwards Proprietary Response to Violations Noted in Insp Rept 70-1100/92-202.Response Withheld L-93-010, Forwards Proprietary Update to C-E Physical Security Plan for Windsor Nuclear Fuel Manufacturing Facility.Update Provides Info Re Removal of Rooms 224A & B in Bldg 5.Plan Withheld Per 10CFR2.790(d)1993-02-18018 February 1993 Forwards Proprietary Update to C-E Physical Security Plan for Windsor Nuclear Fuel Manufacturing Facility.Update Provides Info Re Removal of Rooms 224A & B in Bldg 5.Plan Withheld Per 10CFR2.790(d) L-92-055, Forwards Corrected Pages 7-5 & 7-6 of Emergency Plan,Rev 1, Submitted by Ltr Dtd 920903.Change Pages Add Training for Radiological Assessment Survey Team Inadvertently Omitted & for Decontamination Team Which Was Incorrect1992-11-23023 November 1992 Forwards Corrected Pages 7-5 & 7-6 of Emergency Plan,Rev 1, Submitted by Ltr Dtd 920903.Change Pages Add Training for Radiological Assessment Survey Team Inadvertently Omitted & for Decontamination Team Which Was Incorrect L-91-009, Forwards Addl Info Re Application for Authorization to Operate Existing Liquid Waste Centrifuge,Relocated as Part of Windsor Nuclear Mfg Facility Revitalization Program,Per 910228 Request1991-03-0505 March 1991 Forwards Addl Info Re Application for Authorization to Operate Existing Liquid Waste Centrifuge,Relocated as Part of Windsor Nuclear Mfg Facility Revitalization Program,Per 910228 Request LD-90-088, Forwards Revised Info Re Emergency Plan for License SNM-1067 Per1990-11-13013 November 1990 Forwards Revised Info Re Emergency Plan for License SNM-1067 Per ML20058D0681990-10-30030 October 1990 Discusses Independent Audits of Windsor Nuclear Fuel Mfg Per 901023 Meeting LD-90-077, Withdraws 881206 Application for Amend to License SNM-1067 & 890727 & 900117 Submittals of Addl Info1990-10-0505 October 1990 Withdraws 881206 Application for Amend to License SNM-1067 & 890727 & 900117 Submittals of Addl Info LD-90-068, Advises That Planned Work in Redeployed Pellet Shop of Facility Includes Relocating Centrifuge Sys from Present Location1990-09-13013 September 1990 Advises That Planned Work in Redeployed Pellet Shop of Facility Includes Relocating Centrifuge Sys from Present Location LD-90-067, Advises That Redeployed Pellet Shop in Windsor Fuel Mfg Facility Needs Reconfiguring to Accommodate New Pellet & Rod Handling Equipment.Necessary Walls,Ceilings & Structural Steel Will Be Erected to Permit Installation1990-09-13013 September 1990 Advises That Redeployed Pellet Shop in Windsor Fuel Mfg Facility Needs Reconfiguring to Accommodate New Pellet & Rod Handling Equipment.Necessary Walls,Ceilings & Structural Steel Will Be Erected to Permit Installation LD-90-055, Forwards Request for Withdrawal of 900213 Amend Request to License SNM-10671990-08-0808 August 1990 Forwards Request for Withdrawal of 900213 Amend Request to License SNM-1067 LD-90-048, Forwards Certification of Financial Assurance for Decommissioning Under License SNM-10671990-07-19019 July 1990 Forwards Certification of Financial Assurance for Decommissioning Under License SNM-1067 ML20055F8191990-07-13013 July 1990 Responds to NRC Re Violations Noted in Insp Rept 70-1100/90-201.Corrective Actions:Biennial Audit Requirement Will Be Included in Data Base Used to Formally Track Various Plant Activities LD-90-042, Forwards Rev 1 to EPIP 3.01, Fire/Explosion, for Info. Meeting W/Town of Windsor Fire Chief Held on 900612 Re Needs of Fire Dept in Response to Emergency Situations at Facility1990-06-18018 June 1990 Forwards Rev 1 to EPIP 3.01, Fire/Explosion, for Info. Meeting W/Town of Windsor Fire Chief Held on 900612 Re Needs of Fire Dept in Response to Emergency Situations at Facility LD-90-039, Informs of Organizational Changes Affecting Reporting Chain for Selected Individuals Involved in Implementation of Fnmcp.Licensee Has Determined That Changes Do Not Decrease Effectiveness of Plan & as Such,Changes Implemented1990-06-0808 June 1990 Informs of Organizational Changes Affecting Reporting Chain for Selected Individuals Involved in Implementation of Fnmcp.Licensee Has Determined That Changes Do Not Decrease Effectiveness of Plan & as Such,Changes Implemented ML20042G3221990-05-11011 May 1990 Responds to Re Violations Noted in Insp Rept 70-1100/90-03.Corrective Actions:Addl Survey to Measure Dose Received by TLDs Placed Above Fuel Pellet Stacking Table Initiated on 900413 & Termination Repts Sent to NRC ML20042F1461990-04-24024 April 1990 Responds to NRC Re Violations Noted in Insp Rept 70-1100/90-02.Licensee Believes It Operated in Compliance W/License Requirements & Cited Violation Not Warranted LD-90-027, Responds to NRC Re Violations Noted in Insp Rept 70-1100/89-07.Corrective Actions:Desirable Location for Residue Storage Trailer,Minimizing Trailer Movement, Established & Training Session Conducted1990-04-0303 April 1990 Responds to NRC Re Violations Noted in Insp Rept 70-1100/89-07.Corrective Actions:Desirable Location for Residue Storage Trailer,Minimizing Trailer Movement, Established & Training Session Conducted ML20042G1581990-03-30030 March 1990 Summarizes Results of 891013 self-assessment of Windsor Nuclear Fuel Mfg Facility During First Quarter FY90 LD-90-024, Responds to NRC Re Violations Noted in Insp Rept 70-1100/89-03.Corrective Action:Responsibility for Individuals Taking &/Or Evaluating Bioassay Will Be Clarified in Future1990-03-15015 March 1990 Responds to NRC Re Violations Noted in Insp Rept 70-1100/89-03.Corrective Action:Responsibility for Individuals Taking &/Or Evaluating Bioassay Will Be Clarified in Future ML20006C0911990-01-31031 January 1990 Forwards Updated Completion Status Rept of Activities to Improve Regulatory Compliance & Mgt.W/Six Oversize Figures LD-90-004, Forwards Amend to Physical Security Plan,Eliminating Position of Vice President Due to Pl Mcgill Retirement.Amend Withheld (Ref 10CFR2.790)1990-01-19019 January 1990 Forwards Amend to Physical Security Plan,Eliminating Position of Vice President Due to Pl Mcgill Retirement.Amend Withheld (Ref 10CFR2.790) 1999-07-29
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I COMBUSTION ENGINEERING OWNERS GROUP
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a March 19,1993 CEOG-93-159 Mr. Robert Palla Jr.
U.S. NRC 1 White Flint North 11555 Rockville Pike Mail Stop 10E4 Rockville, MD 20852
Subject:
Transmittal of Current Status CEOG Generic Accident Management Guidelines Attachments:
1)
CEOG Generic Accident Management Guidelines Philosophy 2)
CEOG Requested Ground Rules for NRC and Battelle PNL Review 3)
List of Documents
Dear Mr. Palla:
At the most recent CEOG Accident Management Guidelines (AMG) workshop, the participants agreed to provide current CEOG AMG generic documents to the NRC for early review.
Although the documents are not yet complete, the overall layout, format and much of the content of the AMG's is essentially complete. The CEOG feels that an early and informal examination of the overall AMG process can benefit both ourselves and the NRC.
Subsequently, the purpose of this correspondence is to transmit the current CEOG Genede Accident Management Guidelines Revision 0" documents to both your office and to Jim Jamison at Battelle PNL.
Please notec that included as part of this correspondence are three attachments that briefly outline the following topics respectively: : CEOG Generic Accident Management Guidelines Philosophy : CEOG Requested Ground Rules for NRC and Battelle PNL Review : List of Documents 9309100222 930319 gaa noocao7oogo q3 p
I
Mr. R. Palla March 19,1993 3
Page 2 CEOG-93-159 If there are any questions, please do not hesitate to contact either myself at (504) 739-6265 or Mark Greene, Asst. Project Manager of the Generic AMG Development Project at (203) 285-2694, or Dr. William Dove, Project Manager of the Generic AMG Development Project at (203) 285-3445.
Sincerely, f
c<.-
Jerry Holman
- Chairman, CEOG Severe Accident Working Group Attachments cc:
R. Burski, Entergy Operations (Killona)
G. C. Bischoff, ABB i
P. J. Hijeck, ABB CEOG Representatives j
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ABB Generic Accident Management Guidelines Philosophy Generic Accident Management Guidelines (AMG) are currently being developed at ABB as Owners Group Task. The AMG development supports a NUMARC initiative to pgo' d
organized information to the plants Technical Support Center (TSC) during the various sta of a severe accident. The CEOG Generic AMG's are structured as guidance material to b utilized by personnel in the TSC. For additional information regarding this topic, please refer to the Executive Summary of the " Minimum Control Room Capability Report".
The Generic AMG's utilize a multistep process that is depicted illustratively on the front of each AMG document. The process includes the following steps and support documentation:
STEP 1:
This step is the initial diagnosis step whereby Dowcharts are solved that can
" place" the severe accident onto what is referred to as the " plant condition matrix" This matrix approach has been outlined in the EPRI Technical Basis Report and expanded upon by ABB as part of the deve!opment of generic AMG's.
Briefly, the matrix utilizes a 2 X 4 array composed of two RCS damage states and four containment states. The two RCS designates are called "BD" for badly damaged and "EX" for ex-vessel. For definitions of these two terms, please see the glossary located in the front section of the " Generic AMG Revision 0" document. The four containment designates are called "CC" for closed and
)
cooled, "CH" for challenged, "I" for impaired, and "B" for bypassed. Again, for definitions of these terms, please see the aforementioned glossary. Step 1 utilizes available plant data collected on the Data Table to solve one Cowchart that may place the accident into an RCS damage state and another flowchart that may place the accident into a containment damage state. The Step 1 process is considered to be a first order solution that can quick.ly process available plant data and make an initial diagnosis.
STEP 2:
If Step 1 of the AMG process can be referred to as the first order quantitative diagnosis, then Step 2 of the process is best described as the detailed, qualitative verification of the diagnosis.
Step 2
addresses the types of information that may not lend well to a flowchart (such as time dependant trending information) but are helpful to properly assess the plant condition.
Although the overall AMG diagnostics do apply more emphasis to Step 2, the Step 1 process is still considered to be an important, and autonomous part of the diagnostic scheme.
STEP 3:
Once the p! ant condition has been diagnosed with certainty on the plant condition matrix, the next step in the process is to consider and implement a set of prioritized candidate high level actions (called CHLA's) that address the symptoms of the particular matrix location.
e For each CHLA considered in Step 3, additional information must be considered (such as cautions, pros, cons, etc.) before that CHLA is recommended to the 7
control room for implementation. Please see the Step 3 Basis Document for a full i
discussion of the Step 3 CHLA selection process). Step 3 is structured to accommodate the availability of equipment to perform CHLA's. This also makes the process flexible enough to allow the plant staff to prioritize the recovery of any damaged or previously unavailable equipment.
STEP 4:
Step 4 of the AMG's is the assessment phase of the process where the expected l
plant response to the CHLA is compared to the actual response of the plant.
When completed, Step 4 will determine the next appropriate step to take within the AMG process by assessing the response of the plant condition following ilupiementation of a CHLA (or concurrent set of CHLA's).
i RESTORATIVE AMG'S:
If, at any time during the AMG process, insufficient information exists to confidently diagnose the location of the accident on the plant condition matrix, then the TSC may choose to exit that part of the AMG's and rely instead on the section imown as " Restorative AMG's". When completed, Restorative AMG's will provide general guidance based on available information to protect remaining fission product boundaries. Restorative AMG's will be structured in the overall i
process to be both entered and exited with relative ease depending on the condition of the plant and the information that is available as input for the Step 1 diagnosis.
t i
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i 5
ABB Requested Ground Rules for NRC and Battelle PNL Review 1.
Place priority on the overall process and structure of the " Generic AMG Revision 0" document.
Does the overall process flow smoothly from the Data Table through Restorative AMG'S? Are instructions clear and easy to follow?
2.
Does the concept of diagnosis (Step 1) followed by verification of diagnosis (Step 2) result in sufficient overall diagnostic confidence?
3.
Examine Step 3 more for its information presentation than its technical content.
4.
Step 1, Step 2, and Step 3 Basis Documents The basis documents are provided for your information and review.
5.
Calculational Aids Please comment on the format and use of the " Preliminary Combustible Gas Control Calculational Aid".
6.
Minimum Control Room Capability Paper Please briefly review the Executive Summary.
7.
It is agreed that there will be no fee incurred to ABB or the CEOG for this review by the NRC.
8.
The completion time for this review will be approximately May 1,1993.
9.
The NRC agrees not to provide this set of documents to any party other than NRC staff, Battelle PNL and other subcontractors as agreed upon between the NRC and ABB.
10.
The development of Generic Accident Management Guidelines will be essentially complete by June 1993.
Therefore, no major revisions to the document can be accommodated within the current seinedule and budget. Based upon this completion schedule the comments provided by the NRC will not be considered binding or mandatory by ABT1 or the CEOG.
l e
i List of Documents The following list of documents will be completed and delivered to the NRC in June 1993. For i
each document, a notation is made reflecting the current status along with the scope of what material is included in this preliminary delivery.
f Document 1: " Generic Accident Management Guidelines Revision 0" Current Status:
1.
Introductory Material - Completed and Included 2.
Data Table - Completed and Included 3.
Step 1 - Completed and Included 4.
Step 2 "Not in Severe Accident", "BD/CC" are Completed and
~
Included 5.
Step 3 "BB/CC", "EX/CC", "EX/CH", "EX/I", "EX/B" are Completed and Included 6.
Step 4 - Effort Recently Begun, Nothing Included 7.
Restorative AMG - Effort Recently Begun, Nothing Included i
i Document 2: " Generic Accident Management Guidelines Step 1 Basis" Current Status:
Completed and Included l
s Document 3: " Generic Accident Management Guidelines Step 2 Basis" Current Status:
Sections Completed as noted above and Included 7
Document 4: " Generic Accident Management Guidelines Step 3 Basis" i
Current Status:
Sections Completed as noted above and Included 1
l Document 5: " Generic Accident Management Guidelines Step 4 Basis" j
4 Current Status:
Recently Started, Only Cover Sheet Included I
Document 6: " Generic Accident Management Guidelines Restorative AMG" l
Current Status:
Recently Started, Only Cover Sheet Included j
i s
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