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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
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARLD-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-90-067, 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-90-068, 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-90-055, 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) LD-90-003, Forwards Updated Pages for 881206 & 890727 Requests for Amends to License SNM-1067 Re Specific Criticality Safety Criteria,Liquid Wastes,Internal Exposure,Product Development & External Exposure (Dosimetry Requirements)1990-01-17017 January 1990 Forwards Updated Pages for 881206 & 890727 Requests for Amends to License SNM-1067 Re Specific Criticality Safety Criteria,Liquid Wastes,Internal Exposure,Product Development & External Exposure (Dosimetry Requirements) LD-89-146, Forwards Amended Application for Renewal of License SNM-1067,replacing Parts 1 & 2 of License Renewal Application Submitted by Pl Mcgill .Application Describes Facility Intended Configuration & Operation1989-12-28028 December 1989 Forwards Amended Application for Renewal of License SNM-1067,replacing Parts 1 & 2 of License Renewal Application Submitted by Pl Mcgill .Application Describes Facility Intended Configuration & Operation LD-89-129, Informs of Retirement of Pl Mcgill & Interim Appointment of CR Waterman as Vice President of Nuclear Fuel.All Correspondence to Pl Mcgill Attention Should Be Directed to CR Waterman Effective Immediately1989-11-22022 November 1989 Informs of Retirement of Pl Mcgill & Interim Appointment of CR Waterman as Vice President of Nuclear Fuel.All Correspondence to Pl Mcgill Attention Should Be Directed to CR Waterman Effective Immediately LD-89-127, Confirms Telcon Re Interpretation of License Requirements for License SNM-1067.Understands That Shipping Containers Covered by Certificates of Compliance & DOT Regulations.Sets of Trailers Will Be Separated by at Least 20 Ft1989-11-20020 November 1989 Confirms Telcon Re Interpretation of License Requirements for License SNM-1067.Understands That Shipping Containers Covered by Certificates of Compliance & DOT Regulations.Sets of Trailers Will Be Separated by at Least 20 Ft LD-89-122, Advises That Bioassay Program Used Since Last Quarter 1988 Includes Semiannual Lung Counting for All Personnel & Fecal & Urinalysis Sampling for Highest 25% of Pellet Shop Personnel,Per Notice of Violation1989-11-0707 November 1989 Advises That Bioassay Program Used Since Last Quarter 1988 Includes Semiannual Lung Counting for All Personnel & Fecal & Urinalysis Sampling for Highest 25% of Pellet Shop Personnel,Per Notice of Violation LD-89-111, Provides Update to Rev 4 of Physical Security Plan Amend Submitted on 890420.Encl Withheld (Ref 10CFR2.790(d))1989-10-0404 October 1989 Provides Update to Rev 4 of Physical Security Plan Amend Submitted on 890420.Encl Withheld (Ref 10CFR2.790(d)) LD-89-108, Forwards Figures 1,2,2A,3,4 & 5 from C-E Nucelar Fuel Mfg License Compliance Status Rept Transmitted in ,Per Confirmatory Action Ltr 88-23,Item 5.Encls I & II Provide Sept 1989 Status Rept.W/Six Oversize Figures1989-09-29029 September 1989 Forwards Figures 1,2,2A,3,4 & 5 from C-E Nucelar Fuel Mfg License Compliance Status Rept Transmitted in ,Per Confirmatory Action Ltr 88-23,Item 5.Encls I & II Provide Sept 1989 Status Rept.W/Six Oversize Figures LD-89-103, Responds to NRC Re Violation Noted in Insp Rept 70-1100/89-04.Corrective Actions:Next Facility Emergency Evacuation Drill Will Include Participation of Offsite Support Agencies to Test Communication Sys & Procedures1989-09-14014 September 1989 Responds to NRC Re Violation Noted in Insp Rept 70-1100/89-04.Corrective Actions:Next Facility Emergency Evacuation Drill Will Include Participation of Offsite Support Agencies to Test Communication Sys & Procedures LD-89-090, Forwards Corrected Page to 890731 Application for Amend to Fnmcp.W/O Encl1989-08-0707 August 1989 Forwards Corrected Page to 890731 Application for Amend to Fnmcp.W/O Encl LD-89-087, Responds to NRC Re Violations Noted in Insp Rept 70-1100/89-01.Corrective Action:Procedures Revised to Be Consistent W/Nrc Interpretation of License Requirements1989-08-0202 August 1989 Responds to NRC Re Violations Noted in Insp Rept 70-1100/89-01.Corrective Action:Procedures Revised to Be Consistent W/Nrc Interpretation of License Requirements LD-89-083, Responds to NRC Re Violations Noted in Insp Rept 70-1100/89-03.Corrective Action:Evaluation of Bioassay Results Conducted1989-07-28028 July 1989 Responds to NRC Re Violations Noted in Insp Rept 70-1100/89-03.Corrective Action:Evaluation of Bioassay Results Conducted ML20248A8891989-07-27027 July 1989 Responds to NRC Commenting & Requesting Clarification of 881206 Amend to License SNM-1067.Amend Eliminates Condition Incorporating Part Ii,Chapter 8 Into License ML20246F9411989-07-0707 July 1989 Responds to 890427 Request for Review of Agreements W/Present or Former Vendor Employees for Clauses Restricting Employee Freedom to Raise Safety Issues to Mgt & Nrc.No Restrictive Clauses Identified LD-89-066, Forwards Revised 890307 Amend Request Re Windsor Nuclear Fuel Mfg Facility organization.C-E Will Institute Facility Review Group to Assume Oversight Function Re Facility Operations.Tabulation of Affected Pages Also Encl1989-06-23023 June 1989 Forwards Revised 890307 Amend Request Re Windsor Nuclear Fuel Mfg Facility organization.C-E Will Institute Facility Review Group to Assume Oversight Function Re Facility Operations.Tabulation of Affected Pages Also Encl LD-89-063, Responds to Violations Noted in Insp Rept 70-1100/89-200. Response Withheld (Ref 10CFR2.790(d))1989-06-0909 June 1989 Responds to Violations Noted in Insp Rept 70-1100/89-200. Response Withheld (Ref 10CFR2.790(d)) LD-89-054, Requests Temporary License Condition Allowing Use of Roller Receipt Area.Wording for Temporary License Condition Suggested1989-05-18018 May 1989 Requests Temporary License Condition Allowing Use of Roller Receipt Area.Wording for Temporary License Condition Suggested LD-89-038, Requests one-time Waiver of Direct Measurement of U-235 Content in Low Level Waste Containers1989-04-12012 April 1989 Requests one-time Waiver of Direct Measurement of U-235 Content in Low Level Waste Containers ML20236A8311989-02-13013 February 1989 Forwards Commitment Status Update Resulting from Corrective Actions for Violations Delineated in Notices of Violation, Enforcement Conferences,Confirmatory Action Ltrs & Mgt Meetings ML20195J5471988-11-29029 November 1988 Forwards Radiological Survey Rept - Wooded Area C-E,Inc Property. Concurrence Requested to Release Area for Unrestricted Use LD-88-134, Forwards Pages Inadvertently Omitted from Rev 1 to Part 2 of C-E Nuclear Fuel Integrated Improvement Program,1988-11-11011 November 1988 Forwards Pages Inadvertently Omitted from Rev 1 to Part 2 of C-E Nuclear Fuel Integrated Improvement Program, LD-88-131, Forwards Rev 1 to Part 2 of C-E Nuclear Fuel Integrated Improvement Progam, W/Status of Commitments as of 8810241988-11-0909 November 1988 Forwards Rev 1 to Part 2 of C-E Nuclear Fuel Integrated Improvement Progam, W/Status of Commitments as of 881024 ML20205T6941988-11-0404 November 1988 Responds to NRC Re Violations Noted in Insp of License SNM-1067.Corrective Action:Trash Compactor Operation Established as Activity Governed by Radiation Work Permits & Personnel Required to Wear Lapel Air Sampler.Fee Paid LD-88-117, Forwards Presentation Matls from 880927 Meeting on Fuel Facility Revitalization1988-10-20020 October 1988 Forwards Presentation Matls from 880927 Meeting on Fuel Facility Revitalization LD-88-105, Forwards Fee for 880923 Request for Extension to 30-day Reporting Requirement for SNM Receipt Insp Measurement Data1988-09-30030 September 1988 Forwards Fee for 880923 Request for Extension to 30-day Reporting Requirement for SNM Receipt Insp Measurement Data LD-88-103, Forwards Nuclear Fuel Mfg Facility Independent Task Force Review Status Rept, Per Commitment 5 of1988-09-29029 September 1988 Forwards Nuclear Fuel Mfg Facility Independent Task Force Review Status Rept, Per Commitment 5 of LD-88-098, Responds to NRC Re Violations Noted in Insp Rept 70-1100/88-07 on 880725-29.Effort Currently Underway to Reconstruct Log Sheets from Other Sources & Steps Being Taken to Prevent Recurrence1988-09-20020 September 1988 Responds to NRC Re Violations Noted in Insp Rept 70-1100/88-07 on 880725-29.Effort Currently Underway to Reconstruct Log Sheets from Other Sources & Steps Being Taken to Prevent Recurrence LD-88-081, Transmits Addl Info & Clarifications Requested by Bidinger Including,Tabulation of Affected Pages & Rev Numbers & Provides Proposed Change Pages Supporting Amend Request1988-08-19019 August 1988 Transmits Addl Info & Clarifications Requested by Bidinger Including,Tabulation of Affected Pages & Rev Numbers & Provides Proposed Change Pages Supporting Amend Request LD-88-222, Forwards Corrections of Typos & Incorporates Clarifications & Technical Revs Suggested by Into Application for Amend to License SNM-10671988-08-16016 August 1988 Forwards Corrections of Typos & Incorporates Clarifications & Technical Revs Suggested by Into Application for Amend to License SNM-1067 LD-88-070, Provides Addl Info to Supplement Licensee Re Assessment of Facility Radiation Protection Program1988-08-0202 August 1988 Provides Addl Info to Supplement Licensee Re Assessment of Facility Radiation Protection Program LD-88-065, Requests That NRC Grant Condition to License SNM-1067, Authorizing Possession of U-235 Up to 5.0 Weight %,But Not Allowing Processing of Fuel Above 4.1 Weight % & Terminating Condition Upon Approval of Amend Request1988-07-28028 July 1988 Requests That NRC Grant Condition to License SNM-1067, Authorizing Possession of U-235 Up to 5.0 Weight %,But Not Allowing Processing of Fuel Above 4.1 Weight % & Terminating Condition Upon Approval of Amend Request LD-88-064, Forwards Addl Info & Clarifications in Support of 880120 Application for Amend to License SNM-1067 to Increase Weight of Enriched U That Can Be Processed from 4.1 to 5%,per NRC 880125 Meeting Request1988-07-28028 July 1988 Forwards Addl Info & Clarifications in Support of 880120 Application for Amend to License SNM-1067 to Increase Weight of Enriched U That Can Be Processed from 4.1 to 5%,per NRC 880125 Meeting Request LD-88-061, Provides Overview of Further Anticipated Changes to Facilities,Proposed for Next Two Yrs & Independent of Current Commitments to Upgrade Facilities.Requests Encl Be Withheld Per 10CFR2.7901988-07-26026 July 1988 Provides Overview of Further Anticipated Changes to Facilities,Proposed for Next Two Yrs & Independent of Current Commitments to Upgrade Facilities.Requests Encl Be Withheld Per 10CFR2.790 LD-88-054, Remits Fee for 880713 Application for Amend to License SNM-10671988-07-13013 July 1988 Remits Fee for 880713 Application for Amend to License SNM-1067 ML20151C4031988-07-0808 July 1988 Responds to NRC Re Violations Noted in Insp Rept 70-1100/88-03.Corrective Actions:Drums Labeled as to Estimated U-235 Content & Enrichment Limits & Review Conducted of All Secured Mass Limited Containers in Use LD-88-041, Provides Info Re C-E Plans for Reassessing Adequacy of Windsor Fuel Fabrication Facility Operations,Per WT Russell 880125,J Lieberman 880421 & GL Sjoblom 880606 Requests1988-06-17017 June 1988 Provides Info Re C-E Plans for Reassessing Adequacy of Windsor Fuel Fabrication Facility Operations,Per WT Russell 880125,J Lieberman 880421 & GL Sjoblom 880606 Requests 1990-09-13
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e COMBUSTION ENGINEERING July 8, 1988 Docket No. 70-1100 License SNM-1067 Mr. William T. Russell Regional Administrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
Subject:
Reply to Notice of Violation (NRC Inspection Report No. 70-1100/88-03)
Reference:
Letter, G. L. Sjoblum (NRC) to P. L. McGill (C-E),
dated June 6,1988
Dear Mr. Russell:
Combustion Engineering, Inc. has reviewed the Notice of Violation and Enforcement Conference Report received with the reference letter.
This letter provides Combustion Engineering's response to the subject Notice of Violation.
Based on a telephone conversation between Mr. J. Roth (NRC) and Mr. J. Kingseed of my staff on July 6,1988, it is our understanding that this response is considered timely.
Specific replies to each of the seven (7) violations are included in the Enclosure.
In addition to responding to the Notice of Violation, Combustion Engineering wishes to bring to your staff's attention a minor discrepancy recently discovered in our slides used to respond to Apparent Violation 6.
Specifically, in the background section the fourth and fifth bullet on the slide in question could suggest that two scales exist in or near the lower part of the hammermill hood. Only one scale exists (outside of the lower part of the hood) and the fourth bullet probably should not have appeared on the slide.
Further, in the response section we indicated that a revised form would be used in determining the appropriate weights.
We have since found implementation of a new form to be impractical.
We believe that an equally acceptable position is provided in our response to Violation E of the Enclosure.
We regret any confusion that this may have caused.
8807210345 000708 PDR ADOCK 07001100 C
PNU Power Systems 1000 Prospect Hill Road (203) 688 1911 Combustion Engineenng, Inc.
Post Offce Box 500 Telex: 99297 Windsor, Connectcut 06095-0500
(\\
LE o7
Mr. William T. Russell Page 2 l
July 8, 1988
)
If you any questions, please do not hesitate to call me or Mr. A. E. Scherer, i
our Director of Nuclear Licensing at (203) 285-5200.
Very truly yours, COMBUSTION ENGINEERING, INC.
P Vice President Nuclear Fuel PLM:ss
Enclosure:
As Stated cc:
J. Roth (NRC - Region I)
G. L. Sjoblum (NRC - Region I) i i
l
Attachm3nt Page 1 of 7 Combustion Engineering Response to NRC Notice of Violation Violation A Amendment No. 9 to License No. SNM-1067 dated April 8, 1987 incorporates Section 4.1.6, "Marking and Labeling of SNM," dated October 22, 1986 into the NRC-upproved license. application (Part 1-Criteria) which states, in part, that all mass-limited i
l containers shall be labeled as to enrichment and content, Contrary to the above, on February 29-March 1, 1988, the lids on seven mass limited containers (drums labeled as No. 5121, 4565, "contaminated oil", 4564, 4570, 4586, and 4611), containing unmeasured quantities of uranium-235, had been secured between December 20, 1987 and February 2, 1988, and the containers were not labeled with the actual uranium-235 content and enrichment.
Response
1.
The seven (7) drums in question have been labeled as to estimated uranium-235 content and enrichment limits.
Additionally, a review was conducted of all secured mass limited containers in use to ensure that they were properly labeled.
2.
To prevent recurrence, we have increased surveillance of materials in mass-limited containers to ensure that they are appropriately marked and labeled.
In addition, we are reviewing our operations procedures against the requirements of Section 4.1.6 of the NRC-approved license application.
Changes will be made as necessary.
We anticipate that the procedure / application compatibility review will be completed by the fourth quarter of 1988.
3.
All secured mass-limited containers are appropriately labeled in compliance with Section 4.1.6 of the NRC-approved license application at this time.
Attcchm:nt Pago 3 of 7 Violation C' Amendment No. 7 to License No. SNM-1067 dated August 4, 1986 incorporates Section 4.3.9, dated December 16, 1985 into the NRC-approved license application (Part 1-Criteria) which states that the uranium oxide thickness on each of the Pellet Storage Shelves shall be less than four (4) inches.
Contrary to the above, on February 29, 1988, the uranium oxide thickness, at five locations on the Pellet Storage Shelves, exceeded four inches by an amount of 1/8 to 3/4 of and inch.
Response
1.
Criticality limits on the pellet storage shelves were implemented by the following:
(a)
A nuclear criticality sign was located at the shelves specifying a 4 inch high slab limit, (b)
Pellet trays measuring two inches in height were limited to stacking two high so that the four inch slab limit would not be exceeded, and (c)
An engineered safeguard in the form of a steel bar was installed on the shelves.
(The purpose of this bar was to limit the stack height of trays to four inches.)
In the process of loading pellets into the trays, employees would occasionally load the pellets non-uniformly, resulting in the tray covers being slightly raised. When stacking two trays in this condition on the shelves, the steel bar would be, at times, raised slightly to slide the pellet trays under the bar.
To correct this situation, the following additional steps have been taken:
- Procedures have been modified to require leveling of pellets in trays, Employees have been instructed on the importance of leveling pellets, and As an additional engineered safeguard, an inflexible steel bar has been installed on the storage shelves to preclude its being raised beyond the 4 inch slab limit opening.
2.
Recurrence of this violation is precluded by the actions i
already taken and outlined in Item 1.
3.
Combustion Engineering believes that it is now in compliance with the 4 inch slab requirement of Section 4.3.9 of the NRC-approved license application.
2 Attachmsnt Pago 2 of 7 Violation B Amendment No. 9 to License No. SNM-1067, dated April 8, 1987 incorporates Section 2.7.2, dated October 22, 1986 into the NRC-approved license application (Part 1-Criteria) which states, in part,.that it is the responsibility of the Plant Manager to assure that all operations involving radioactive materials have written procedures which include the appropriate safety requirements.
Those procedures must be approved by the Manager, Nuclear Licensing, Safety, Accountability and Security (NLSA&S),
The Nuclear Criticality Safety Specialist, or the Supervisor, Health Physics and Safety prior to the start of any operation.
Contrary to the above, as of February 29, 1988, the Plant Manager did not assure that all operations involving radioactive materials had properly approved written procedures in that the Quality control procedures did not contain safety precautions nor were they properly approved.
For example, operations Sheet No.
945, Revision 39, dated December 10, 1987, did not include any safety precautions, and there was no written approval by the Manager, NLSA&S, the Nuclear Criticality Safety Specialist or the Supervisor, Health Physics and Safety.
Response
1.
The specific operation Sheet (No. 945, Revision 39) noted in the Notice of Violation has been reviewed and approved by the Manager NLSA&S.
2.
Combustion Engineering recognizes that room for improvement exists in our controls for including appropriate safety-precautions in shop operating procedures. We have already begun to correct this problem.
In this regard, the following actions have been or will be completed during the fourth quarter of 1988:
(a)
The new Plant Manager has been instructed to ensure that all changes to operations sheets are reviewed and approved and contain the appropriate safety precautions before being authorized.
(b)
As committed in a response to a related violation from a previous inspection, all operation Sheets are presently being rewritten and upgraded to include appropriate safety and criticality precautions.
These upgraded operation Sheets will be reviewed and approved by the appropriate personnel.
3.
Completion of the procedural upgrade task is expected by the fourth quarter of 1988.
t.
Attachmsnt
.Paga 4 of 7 Violation D
. Amendment No. 3 to License'No. SNM-1067 dated. October-1, 1984 incorporates Section-4.1.3 "Requests-for Changes,and CriticalityL Analysis" dated June 15, 1984 intoLthe NRC-approved license application-(Part.1-Criteria)'which states that-all proposed changes in process,: equipment,-and/or. facilities that could affect nuclear criticality, radiological 1or-industrial safety shall be approved in accordance with the requirements set forth in Section.2.2.2 of.this part.
Amendment 3 also incorporates-Section 4.1.5 "Internal Review Requirements" which states, in part, that all process / equipment / facility changes which~could.
affect nuclear criticality safety shall be reviewed.and~ approved in writing by the. Nuclear Criticality Specialist.. Section-2.2.2 states that the General Manager delegated 1to the Production and.
Material Control Managers and.to'the Engineering Manager responsibility to assure that all operations involving nuclear materials have'been analyzed to establish the required safety limits and controls. The Manager, NLSA&S or Nuclear Criticality-Specialist shall assist the Engineering Manager and the Production and' Material Control Manager by performing the analysis required and establishing.the appropriate controls.
Contrary to the above, at some time prior;to March'1, 1988, a change was made at the facility, namely, covering the Batch Makeup Hood Conveyor, resulting in the potential accumulation of uranium oxide powder under the conveyor, and an analysis was not performed prior to the change to establish the required-safety limits and controls.
Further, this change in equipment, which could affect nuclear criticality safety, was not reviewed'and approved in writing by the Nuclear Criticality. Specialist.
Response
1 i
1.
Subsequent to the NRC inspection,-the~ gap.between the Batch Makeup Hood and the conveyor.was reduced by the addition of a piece of sheet metal to minimize residual powder from potentially entering.and accumulating under the conveyor.
This change was reviewed and approved in. writing by the Nuclear Criticality Specialist for acceptability.
2.
The Manager, Radiological and Industrial Safety or the Nuclear Criticality Specialist'will review all future proposed process / equipment / facility changes and determine if a specific safety analysis is required.
All credible nuclear criticality scenarios will be analyzed before being approved.
3.
Combustion Engineering believes that it is now in compliance with the requirement of its'NRC-approved license application as regards analysis of credible nuclear criticality.
scenarios.
i
Attachm3nt-Page 5 of 7 Violation E Amendment No. 3 to License No. SNM-1067 dated October 1, 1984 incorporates section 4.1.4 "Posting of Limits", dated June 15, 1984, into the NRC-approved license application (Part 1-Criteria) which states, in part, that all work stations shall be posted with a nuclear safety sign approved by the Manager, Nuclear Licensing, Safety, Accountability and Security'(NLSA&S) or the Nuclear Criticality Safety Specialist.
Section 4.1.2 states, in part, that it shall be'the responsibility of the supervisor to assure that each work station is properly posted and that operations are performed in compliance with posted limits.
Contrary to the above, on February 27, 1988, a work station was not properly posted in that the posted nuclear safety limit of 24.0 kilograms uranium oxide appeared to be exceeded by about 1.1 kilograms as the result of a weighing error.
Response
1.
Combustion Engineering has instructed supervisory personnel and operators of the hammermill hood on.the correct procedures for determining total weight, tare weight and the balance of material remaining in the hammermill hood.
2.
To prevent recurrence, the operating procedure for the hammermill hood will be revised to include an administrative safeguard acticn limit. This action limit will be established at a value less than the criticality safety limit and will require supervisory personnel to verify the actual quantity of material in the hood.
Should the action limit be reached, the hammermill will be shut down if verification can not be established.
In addition, we intend to conduct an evaluation to determine if other means exist to ensure that safe criticality limits are not exceeded.
3.
Combustion Engineering believes that it is now in compliance.
In addition, we will complete the action limit and evaluation identified in item 2 by the first quarter of 1989.
l Attcchm:nt Pago 6 of 7 Violation F 10 CFR 70.51 (b)(1) states that each licensee shall keep records showing the receipt, inventory (including location), disposal, acquisition and transfer of all special nuclear material in his possession regardless of its origin or method of acquisition.
Contrary to the above, on March 2, 1988, the inspector determined that the licensee did not maintain inventory records, including
~
location, of between 70 to 300 grams of uranium-235 in enriched uranium oxide that was found in liquid waste tanks and pipes during 1985.
Response
1.
The subject material was previously identified to the NRC and added to the formal inventory records on May 2, 1988.
It was subsequently shipped to the Barnwell Waste Management Facility on May 13, 1988.
2.
In the future, the Manager of Accountability and Security will ensure that all materials are inventoried, as necessary, without undue delay.
3.
The actions noted sbove have corrected the inventory records discrepancy.
Combustion Engineering believes that it is now in compliance with 10 CFR 70.51 (b)(1).
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Attachm3nt Pago 7 of 7 Violation G Amendment No. 9 to License No. SNM-1067 dated April 8, 1987 incorporates Section 2.6.1 "Initial Training", dated October 22, 1986 into the NRC-approved license application (Part 1-Criteria) which states, in part, that all new employees shall attend a formal training session prior to working in restricted areas.
Specialized training for radiation protection and nuclear criticality safety shall be commensurate with the extent of the employees contact with radioactive materials.
All personnel whc will be working with radioactive materials must satisfactorily complete a test to ascertain the effectiveness of the training.
Contrary to the above, as of March 28, 1988, personnel working with radioactive material, who required specialized training in nuclear criticality safety, were not required to satisfactorily complete a test to ascertain the effectiveness of that training.
Response
1.
As committed in a response to a related violation from prior inspections, Ccmbustion Engineering is presently upgrading our General Employee Training Program.
The revised program, which will contain modules covering radiation protection and nuclear criticality safety, will be given to all employees who work with radioactive materials.
The employees will be required to complete a test to ascertain the effoutiveness of the training.
2.
The upgraded training and testing program should preclude recurrence of the subject violation.
3.
Combustion Engineering expects the upgraded training and testing program to be completed by the fourth quarter of 1988.
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