|
---|
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 L-93-037, Requests That Extension Until 931008 Be Granted for Responding to NRC Bulletin 91-001,Suppl 1,as Result of Discussions W/M Tokar1993-09-17017 September 1993 Requests That Extension Until 931008 Be Granted for Responding to NRC Bulletin 91-001,Suppl 1,as Result of Discussions W/M Tokar 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-93-033, Proposes Extension Until 931102 for Response to NRC 930802 RAI Re Decommissioning Funding Plan Submitted on 9207021993-08-26026 August 1993 Proposes Extension Until 931102 for Response to NRC 930802 RAI Re Decommissioning Funding Plan Submitted on 920702 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 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 ML20056C3191993-05-0606 May 1993 Responds to 930218 & 0423 Ltrs Re Revs 5 & 6 to Physical Security Plan for Protection of Special Nuclear Matl of Low Strategic Significance.Changes Consistent W/Provisions of 10CFR70.32(e) & Acceptable ML20056H6261993-03-19019 March 1993 Transmits Current CEOG Generic Accident Mgt Guidelines Rev O Documents ML20128M3951993-02-16016 February 1993 Ack Receipt of Informing of C-E Intent to Change Date for Submitting Decommissioning Plan from 921230 to 930330 ML20128G1941993-02-0505 February 1993 Accepts Changes to FNMCP Submitted by Ltrs & 0204 L-93-004, Discusses Encl Proposed Amend to Windsor Fundamental Nuclear Matl Control Plan.W/O Encl1993-02-0202 February 1993 Discusses Encl Proposed Amend to Windsor Fundamental Nuclear Matl Control Plan.W/O Encl L-93-005, Informs That Windsor Decommissioning Plan Will Be Submitted to NRC by 9303311993-02-0101 February 1993 Informs That Windsor Decommissioning Plan Will Be Submitted to NRC by 930331 L-93-001, Advises That Draft Decommissioning Funding Plan in Final Stages of Internal Review & Expected to Be Submitted in Next Few Wks.Licensee Stated That Funding Plan Would Be Submitted by End of 19921993-01-0404 January 1993 Advises That Draft Decommissioning Funding Plan in Final Stages of Internal Review & Expected to Be Submitted in Next Few Wks.Licensee Stated That Funding Plan Would Be Submitted by End of 1992 ML20127H3191993-01-0404 January 1993 Forwards Insp Rept 70-1100/92-202 on 921207-10.One non-cited Violation Noted 1999-08-12
[Table view] Category:NRC TO VENDOR/MANUFACTURER
MONTHYEARML20059N8221990-10-0101 October 1990 Ack Receipt of Re Violations Noted in Insp Rept 70-1100/90-06 ML20059N2551990-09-28028 September 1990 Offers No Objection to Interior Const in Fuel Mfg Facility to Accommodate New Fuel Pellet & Rod Handling Equipment ML20058M5631990-08-0909 August 1990 Forwards Amend 18 to License SNM-1067,authorizing Mod of Ventilation Sys in Nuclear Fuel Mfg Facility & SER ML20058L3501990-08-0101 August 1990 Revises Amend SG-3 to License SNM-1067 Re Chapters 1.0-8.0 of FNMCP ,per Util 900608 Submittal of Revs to FNMCP ML20058M3931990-08-0101 August 1990 Forwards Insp Rept 70-1100/90-06 on 900613-14.Insp Performed to Review Addl Info Provided Re Violations in Insp Rept 70-1100/90-03.Two Violations Noted Withdrawn ML20055J2811990-07-26026 July 1990 Forwards Amend 17 to License SNM-1067,authorizing Organizational Changes,Deleting Condition 30 & Incorporating Revised Section 4.2.4A, Moderation Control. Safety Evaluation Also Encl ML20055H2371990-07-20020 July 1990 Forwards Safety Insp Rept 70-1100/90-05 on 900604-08 & Notice of Violation ML20059C0541990-07-19019 July 1990 Forwards SALP Rept 70-1100/88-99 on Jul 1988 - Mar 1990. Public Meeting Scheduled to Discuss Assessment.Licensee Should Be Prepared to Discuss Plans to Improve Performance ML20055C7181990-06-14014 June 1990 Forwards Insp Rept 70-1100/90-201 on 900507-10 & Notice of Violation ML20248H8671989-10-0404 October 1989 Forwards Amend 15 to License SNM-1067,adding Conditions 30 & 31 Re Production Manager & Emergency Director Having Bachelor Degrees,Terminating Conditions 11 & 12,deleting Conditions 28 & 29 & Correcting Typos in 9,20 & 22 ML20248J2621989-10-0303 October 1989 Forwards Insp Rept 70-1100/89-06 on 890823.No Violations Noted.No Evidence Found to Substantiate Alleged Improper Disposal or Storage of Radwaste at Either Site ML20248J2481989-10-0202 October 1989 Forwards Insp Rept 70-1100/89-80 on 890828-29 & 0905-08 & Notice of Violation.Licensee Should Be Prepared to Discuss Areas of Nuclear Fuel Integrated Improvement Program at 891005 Meeting ML20246H4241989-08-22022 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-1100/89-01 ML20246D9881989-08-16016 August 1989 Forwards Insp Rept 70-1100/89-04 on 890717-21 & Notice of Violation ML20247N3991989-07-25025 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-1100/89-01. Actions to Assure B-25 Waste Boxes Sealed to Preclude Possible Spread of Contamination Appear Inadequate ML20247A0071989-07-14014 July 1989 Responds to AB Scherer Re 890511 Notice of Violation,Per Insp 70-1100/89-200.Not Clear Why Eight Subparts of MFG-16-15xx Signed & Dtd & Five Not.Notice of Violation Withdrawn ML20246J1061989-07-12012 July 1989 Forwards Comments Re Review of 890420 Updated Rev 4 to Physical Security Plan,Entitled Physical Security Plan for Protection of SNM of Low Strategic Significance Used within Bldgs 5/17/21. Encl Withheld ML20246K0501989-07-0707 July 1989 Forwards Mgt Meeting Rept on 890627.Historical Info Provided Re Status of Completion of Facility Mods & Programmatic Upgrades at Facility Informative & Useful ML20246C0141989-06-30030 June 1989 Forwards Insp Rept 70-1100/89-03 on 890522-26 & Notice of Violation.Nrc Concerned That Violation May Have Been Caused by Inability of Responsible Individuals to Complete Proper Evaluation of Bioassay Analyses Results ML20247F7481989-06-23023 June 1989 Expresses Appreciation for Time & Effort Spent on 890607 Site Visit.Implementation of Crosby Process Will Be Watched W/Great Interest ML20245J0641989-06-22022 June 1989 Ack Receipt of in Response to 890511 Notice of Violation Re Violations Noted During Insp of License SNM-1067.NRC Evaluating Denial of Violation by Licensee & Determination Will Be Provided in Near Future ML20245E9511989-06-20020 June 1989 Forwards Request for Addl Info Re 890307 Application for Amend to License SNM-1067,for Response within 20 Days. Definition Not Clear as to Which Positions Perform Initial Analysis & Independent Review ML20247P4481989-05-31031 May 1989 Forwards Matl Control & Accounting Safeguards Insp Rept 70-1100/89-201 on 890508-12.No Violations or Deviations Noted ML20246K5901989-05-11011 May 1989 Forwards Matl Control & Accounting Safeguard Insp Rept 70-1100/89-200 on 890417-21 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR2.790(d)) ML20246K2691989-05-0808 May 1989 Advises That one-time Limited Exemption to 10CFR74.31(c)(2) Issued Per 890412 Request Re Authorization to Assign U-235 Values on Historical Data to Three B-25 Containers of Low Level Waste ML20245J9071989-04-20020 April 1989 Discusses Insp Rept 70-1100/89-02 on 890313-17 & Forwards Notice of Violation ML20248D8791989-03-27027 March 1989 Forwards Request for Addl Info Re 881206 Application for Amend to License SNM-1067 Re Spacing Criteria for Fuel Rod Transport Carts.Response Should Be Provided within 45 Days ML20236C0061989-03-14014 March 1989 Forwards Insp Rept 70-1100/89-01 on 890130-0203 & Notice of Violation.Seven Apparent Violations of NRC Requirements Identified ML20236A8151989-03-0707 March 1989 Forwards Summary of Mgt Meeting on 890216 Re Updated Schedule for Completion of Corrective Actions on Enforcement Items Previously Identified at Facility ML20235W3441989-02-27027 February 1989 Forwards Comments on Review of Rev 4 to Physical Security Plan.Comments Withheld (Ref 10CFR.790(d)) ML20235P8701989-02-23023 February 1989 Notifies of Change in Reviewer Assignment for Facilities. Advises That M Williams Replaced G Gundersen as MC&A Licensing Reviewer for Both Facilities ML20235R9181989-02-16016 February 1989 Forwards Meeting Rept of 890117 Mgt Meeting W/Nrc & Licensee in King of Prussia,Pa to Discuss Licensee Proposed Reorganization of Mgt Structure of Windsor Fuel Mfg Facility ML20235L3311989-02-15015 February 1989 Forwards Request for Addl Info Re 890118 Application for Amend to License SNM-1067.Response Should Be Submitted within 20 Days of Ltr Date ML20196D3531988-12-0606 December 1988 Ack Receipt of & Payment for Civil Penalty Proposed by NRC in in Amount of $12,500 ML20235Y7811988-10-0707 October 1988 Issues Temporary License Condition TC(MC&A)-2 to Safeguards Amend SG-1 to License SNM-1067,per 880923 Request to Be Allowed to Complete Measurements of Receipt & to Dispatch Associated Form 2 Months Later,Effective Immediately ML20155D6741988-10-0404 October 1988 Ack Receipt of 880427 Application for Renewal of License SNM-1067 ML20155B0601988-09-28028 September 1988 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-1100/88-03 ML20154R7281988-09-26026 September 1988 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-1100/86-04 ML20154Q4251988-09-21021 September 1988 Forwards SALP Rept 70-1100/86-99 for Jul 1986 -June 1988 ML20154N2671988-09-0909 September 1988 Confirmatory Action Ltr 88-23 Discussing NRC Understanding of Actions Licensee Will Take to Correct Weaknesses Noted in Insps Re Radiation Protection,Facility Operations & Mgt Controls,Per 880908 & 09 Telcons ML20153F7721988-08-29029 August 1988 Forwards Amend 14 to License SNM-1067,authorizing Use of U Enriched to Max 5% Weight in U-235,per Licensee 880816 Application ML20151Z9581988-08-18018 August 1988 Forwards Safeguards Insp Rept 70-1100/88-07 on 880725-29.No Violations Noted ML20151Y8331988-08-18018 August 1988 Forwards Summary of Enforcement Conference on 880803 in Region I Re Violations Noted in Insp Repts 70-1100/88-05 & 70-1100/88-06 Concerning Area of Radiological Controls, Transportation & Matl Control ML20151X4811988-08-16016 August 1988 Forwards Announcement of Criticality Alarm Sys Workshop Sponsored by Doe.W/O Encl ML20151T0431988-08-11011 August 1988 Forwards Amend 13 to License SNM-1067 & Ser.Amend Authorizes Receipt of U,Enriched to 5% Weight,In U-235 Isotope ML20151E6831988-07-12012 July 1988 Forwards Insp Repts 70-1100/88-05 & 70-1100/88-06 on 880525- 27.Deficiencies in Mgt Controls of Licensed Program Noted ML20150D2781988-07-0707 July 1988 Requests Addl Info in Support of 880120 Application to Amend License SNM-1067 to Permit Processing of U,Enriched to 5%,in U-235 Isotope ML20154H1601988-06-24024 June 1988 Responds to 880606 Request for Delay in Performing Physical Inventory.Temporary License Condition Issued ML20155F0911988-06-0606 June 1988 Discusses Enforcement Conference on 880510 Re Insp Rept 70-1100/88-03 & Forwards Meeting Summary & Notice of Violations.Violations Symptomatic of Same Underlying Deficiencies Noted in Late 1987 Re Radiation Protection ML20154P1581988-05-25025 May 1988 Grants Extension of Time Until 880619 to Respond to NRC Re Plans for Assessment of Radiation Protection Program & Institution of Corrective Actions,Per Licensee 880520 Request 1990-09-28
[Table view] Category:OUTGOING CORRESPONDENCE
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 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 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 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 ML20128P3991996-10-15015 October 1996 Ack Receipt of Ltr Dtd 960930,requesting Elimination of Annual License Fees 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 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) 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 ML20059C1801993-10-23023 October 1993 Forwards Insp Rept 70-1100/93-03 on 930915-17.No Violations Noted 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 ML20057A7571993-09-14014 September 1993 Accepts Proposed New Date for Submitting Addl Info Re Decommissioning Funding Plan 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 ML20056C3191993-05-0606 May 1993 Responds to 930218 & 0423 Ltrs Re Revs 5 & 6 to Physical Security Plan for Protection of Special Nuclear Matl of Low Strategic Significance.Changes Consistent W/Provisions of 10CFR70.32(e) & Acceptable ML20128M3951993-02-16016 February 1993 Ack Receipt of Informing of C-E Intent to Change Date for Submitting Decommissioning Plan from 921230 to 930330 ML20128G1941993-02-0505 February 1993 Accepts Changes to FNMCP Submitted by Ltrs & 0204 ML20127H3191993-01-0404 January 1993 Forwards Insp Rept 70-1100/92-202 on 921207-10.One non-cited Violation Noted ML20126L2741992-12-30030 December 1992 Forwards Insp Rept 70-1100/92-03 on 921116-1201.Ability to Implement EP & EPIPs in Manner That Would Provide Adequate Protective Measures for Health & Safety of Public Demonstrated ML20126J1251992-12-17017 December 1992 Responds to 921119 Request for Exemption from Payment of Annual Fees for Two LEU Fuel Mfg Licenses.Request for Exemption & Base to Annual Fee on Fuel Fabrication Capacity, Denied ML20126A6021992-12-17017 December 1992 Forwards Amend 25 to License SNM-1967,SER & Categorical Exclusion.Amend Incorporates Changes to Radiological Contingency Plan,Per 920903 Application & Suppl ML20062G5211990-11-16016 November 1990 Forwards Insp Rept 70-1100/90-202 on 900806-10.No Violations or Deviations Noted.Rept Withheld (Ref 10CFR2.790(d)) ML20058F3531990-10-31031 October 1990 Forwards Summary of E Scherer 900924 & E Tenerz & H Thornburg 900925 drop-in Visits to Region I ML20059N8221990-10-0101 October 1990 Ack Receipt of Re Violations Noted in Insp Rept 70-1100/90-06 ML20059N2551990-09-28028 September 1990 Offers No Objection to Interior Const in Fuel Mfg Facility to Accommodate New Fuel Pellet & Rod Handling Equipment ML20058M5631990-08-0909 August 1990 Forwards Amend 18 to License SNM-1067,authorizing Mod of Ventilation Sys in Nuclear Fuel Mfg Facility & SER ML20058L3501990-08-0101 August 1990 Revises Amend SG-3 to License SNM-1067 Re Chapters 1.0-8.0 of FNMCP ,per Util 900608 Submittal of Revs to FNMCP ML20058M3931990-08-0101 August 1990 Forwards Insp Rept 70-1100/90-06 on 900613-14.Insp Performed to Review Addl Info Provided Re Violations in Insp Rept 70-1100/90-03.Two Violations Noted Withdrawn ML20055J2811990-07-26026 July 1990 Forwards Amend 17 to License SNM-1067,authorizing Organizational Changes,Deleting Condition 30 & Incorporating Revised Section 4.2.4A, Moderation Control. Safety Evaluation Also Encl ML20055H2371990-07-20020 July 1990 Forwards Safety Insp Rept 70-1100/90-05 on 900604-08 & Notice of Violation ML20059C0541990-07-19019 July 1990 Forwards SALP Rept 70-1100/88-99 on Jul 1988 - Mar 1990. Public Meeting Scheduled to Discuss Assessment.Licensee Should Be Prepared to Discuss Plans to Improve Performance ML20055C7181990-06-14014 June 1990 Forwards Insp Rept 70-1100/90-201 on 900507-10 & Notice of Violation ML20248H8671989-10-0404 October 1989 Forwards Amend 15 to License SNM-1067,adding Conditions 30 & 31 Re Production Manager & Emergency Director Having Bachelor Degrees,Terminating Conditions 11 & 12,deleting Conditions 28 & 29 & Correcting Typos in 9,20 & 22 ML20248J2621989-10-0303 October 1989 Forwards Insp Rept 70-1100/89-06 on 890823.No Violations Noted.No Evidence Found to Substantiate Alleged Improper Disposal or Storage of Radwaste at Either Site ML20248J2481989-10-0202 October 1989 Forwards Insp Rept 70-1100/89-80 on 890828-29 & 0905-08 & Notice of Violation.Licensee Should Be Prepared to Discuss Areas of Nuclear Fuel Integrated Improvement Program at 891005 Meeting ML20246H4241989-08-22022 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-1100/89-01 ML20246D9881989-08-16016 August 1989 Forwards Insp Rept 70-1100/89-04 on 890717-21 & Notice of Violation ML20247N3991989-07-25025 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-1100/89-01. Actions to Assure B-25 Waste Boxes Sealed to Preclude Possible Spread of Contamination Appear Inadequate ML20247A0071989-07-14014 July 1989 Responds to AB Scherer Re 890511 Notice of Violation,Per Insp 70-1100/89-200.Not Clear Why Eight Subparts of MFG-16-15xx Signed & Dtd & Five Not.Notice of Violation Withdrawn ML20246J1061989-07-12012 July 1989 Forwards Comments Re Review of 890420 Updated Rev 4 to Physical Security Plan,Entitled Physical Security Plan for Protection of SNM of Low Strategic Significance Used within Bldgs 5/17/21. Encl Withheld ML20246K0501989-07-0707 July 1989 Forwards Mgt Meeting Rept on 890627.Historical Info Provided Re Status of Completion of Facility Mods & Programmatic Upgrades at Facility Informative & Useful 1999-08-12
[Table view] |
Text
. _ _ _
5 V
JUN 0 61988 Docket No. 70-1100 EA 88-127 Combustion Engineering, Inc.
ATTN: Dr. P. L. McGill Vice President - Nuclear Fuel Manufacturing l Nuclear Power Systems 1000 Prospect Hill Road Windsor, Connecticut 06095-0500 Gentlemen:
Subject:
NOTICE OF VIOLATION AND ENFORCEMENT CONFERENCE REPORT (NRC Inspection Report Number 70-1100/88-03 On May 10, 1988, an Enforcement Conference was held at the NRC Region I office with yot. and niembers of your staff to discuss apparent violations of nuclear criticality safety requirements at your Windsor Nuclear Fuel Manufacturing facility.
l The violations were identified during an inspection conducted on February 29 -
l March 4 and March 28-31, 1988. The inspection report was sent to you on April 21, 1988.
The enforcement conference was conducted to discuss (1) your position with respect to the inspection findings and apparent violations, the causes of the violations, and the short and loag-term corrective actions taken or planned in the criticality safety area; and (2) the status of corrective actions described in your letter dated February 23, 1988 concerning radiological safety controls at the Windsor facility. The Enforcement Conference Report is enclosed. During the conference, you contested some of the violations set forth in the inspection report. The NRC has reevaluated these violations based on the information pro-vided at the conference, and has determined that seven of the eight apparent violations described in the inspection report occurred as stated. These viola-tions are described in the enclosed Notice.
Although the vialations are each classified at Severity Level IV in accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions",
10 CFR 2, Appendix C, Enforcement Policy (1988), the NRC is nonetheless con- ,
cerned that the violations are symptomatic of some of the same underlying de.fic-iencies that contributed to violations of radiation prote: tion requirements identified in late 1987 for which an $12,500 civil penalty was issued on January 25, 1988. These deficiencies include inadequate identification and correction of causes of violations; apparent conflicts between safety and production; ineffective internal audits; lack of independent audits; deficient safety procedures; and inadequate attention to qualification and training of personnel.
OFFICIAL RECORD COPY CE ENFORCEMENT CONF. 88 0001.0.0 06/03/88 8806160287 880606 \\
PDR ADOCK 07001100 4
C DCD -
g/ _
Combustion Engineering, Inc. 2
$ JUN 0 6 1988 The NRC acknowledges that in response to those violations of radiation protection requirements that contributed to the previous civil penalty, a significant upgrade of management controls at the Windsor facility is ongoing.
However, these recent violations demonstrate the need for (1) additional inde-pendent evaluation of your controls in all areas (including criticality control),
and (2) prompt completion of the facility upgrades. We emphasize that a'y recurrence of these violations in the future may result in' additional enforce-ment action, such as civil penalties or orders.
You are required to respond to the enclosed Notice, and you should follow the instructions specified thereia when preparing your response. In your response, you should describe plans for expanding the scope of the current assessment of the radiation protection program to all licensed programs (including nuclear criticality safety), and you <hould give consideration to retaining an indepen-dent party to aid in this assessment. After reviewing your response, the NRC will determine if further enforcement action is needed to ensure compliance with requirements. We will continue to review the actions you have taken to correct the underlying deficiencies identified in your radiation and criticality safety programs by means of frequent inspections of your facility.
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosures will be placed in the NRC's Public Document Room.
The response directed by this letter is not subject to clearance by the Office of Management and Budget under the Paperwork Reduction Act of 1980, PL 96-511.
Sincerely, Orjeginal Signed By a len L. Sjoblom, Acting Director Division of Radiation Safety and Safeguards
Enclosures:
- 1. Meeting Summary Report
- 2. Licensee Handout Material
- 3. Notice of Violation cc w/ enc 1:
A. E. Scherer, Director, Nuclear Licensing C. B. Brinkman, Manager, Washington Nuclear Operations Public Document Room (POR)
Local Public Document Room (LPOR)
Nuclear Safety Information Center (NSIC)
State of Connecticut 0FFICIAL RECORD COPY CE ENFORCEMENT CONF. 88 0002.0.0 06/03/88
JUN 0 6' 1988 Combustion Engineering, Inc. 3-bec w/ enc 1:
Region I Docket Room (with concurrences)
Management: Assistant, ORMA (w/o enc 1)
Robert J. Bores, DRSS J. Roth, DRSS G. Bidinger, NMSS D. Holody, W. T. Russell E. Flack, OE J. Lieberman, OE
'II i
i i
I R. S R'o h/sh/geb I
asciak S R Bellamy RI S
p RI E Holody l
6/)/88 6/j/88 6/3 /88 6/3/88 6/J/88 RI:RC RI:RA Gutierrez n Russe 6/ /88 6/J/88
/
6/ 7/88 R OFFICIAL RECORD COPY CE ENFORCEMENT CONF. 88 0003.0.0 06/03/88
g
- ~
+5 ' /Sj. '
4 Enclosure 1 U.S. NUCLEAR REGULATORY COMMISSION REGION I MEETING.
SUMMARY
r Docket No. 70-1100 License No. SNM-1067 Licensee: Combustion Engineering, Inc.
1000 Prospect Hill Road Windsor, Connecticut 06095 Facility Name: Combustion Engineering - Nuclear Fuel Manufacturing Purpose of Meeting: Enforcement Conference to-discuss apparent violatic identified in NRC Inspection Report No. 70-1100/87-05.
Intrcduction:
An Enforcement Conference was held at the NRC Region I-office on May 10, 1988 at 10:45 a.m. The meeting was requested by the NRC Region I Staff to discuss 8 apparent violations in Nuclear Criticality Safety and Management Controls identified in NRC Inspection Report No. 70-1100/88-03 and to discuss the status of actions to correct the deficiencies identified during Inspection No.
70-1100/87-05.
NRC Attendees:
J. Allan, Deputy Regional Administrator, RI G. Sjoblem, Deputy Director, Division of Industrial and Medical Nuclear l Safety, NMSS l
F. Congel, Acting Director, DRSS, RI !
J. Joyner, Chief, Nuclear Materials Safety Branch, RI M. Shanbaky, Chief, Facilities Radiation Protection Section, RI W. Pasciak, Chief, Effluents Radiation Protection Section, RI D. Holody, Enforcement Officer, RI G. Bidinger, Senior Nuclear Process Engineer, NMSS J. Roth, Project Engineer, RI ,
R. Loesch, Radiation Specialist, RI l Combustion Engineering Attendees:
P. McGill, V.P. Nuclear Fuel, CE, Inc. l F. Stern, V.P. Nuclear Fuel Manufacturing, CE, Inc. '
A. Scherer, Director, Nuclear Licensing, CE, Inc.
G. Chalder, Plant Manager, NFM-Windsor R. Sherran Manager, Health and Safety, NFM-Windsor l J. Kingseed, Manager, Licensing, CE, Inc. l R. Bell, Counsel, CE, Inc.
i r> , - -
T T_v * - - - -- -
'- g 3=-*-W'
- isvv-- v- "*M-~$~T'q--+*-y v rv W W +^--T-* '---M f * gv'*-- -$vy- yv*=-1Y7-5-9+"9-
. . . _ ~ -
. .a q -
n:, . ut vyn ary
.q- .
o S. -
' Summary
- 1. The licensee acknowledged three, presented information to refute one, and contested four of the violations identified in the subject inspection.
report. Two of the four contested violations were characterized by the licensee as new examples of violations previously identified during In pection No. 70-1100/87-05.
- 2. The licensee presented a status report on their actions to correct the violations identified during Inspection No. 70-1100/87-05/
Details of the licensee's presentation appear as Enclosure 4.
I i
e l
1 l
1 a
i I
\
.6
. - , _~._-~_ . ._ - ~ ,
- ]
APPARENT VIOLATION 1 Fall.URE To PROPERLY MARK EACII MASS LIMITED CONTAINER WITH THE ACT
= IfRAN f UM CDNTF.NT AND ENRICHMENT (Item 3.a.) *
~
3 - 55 gallon drumn tempornrily otored on concrete pad on south side of Building 21 I drum contained radioactive materin1 contaminated Zirconium tubing. Drum was covered, unnealed and labeled as I drum contained contaminated springs from fuel 1 the springs. Drum van rods with Zirconium chips trapped in covered, unnenled and labeled as radioactive material.
I drum cantained contaminated pellet press oil.
- prenn oil, internni contamtnation. Drum vce covered, unsealed and marked as pellet Drumn were properly marked and placed on
, the approved storage pad.
Drums were not to be procenned in necordance vith 0.S. 1764.
contaminnted materful whic h can be nennyed. O.S. 1764 in used to process beenuse it contnined no detectable amount of uranium. The material in the drums could not be assayed Chem-Nuclent who would come on nite to do the work. These drums would be processed by 1
in concrete, in accordance with their own procedure. Chem-Fuclear would encapsulate all material 4 - 55 gallon drumn tempornrily stored in the of the Building 17 yard renidue trailer located in the north west corner i All 4 drumn contained contaminated nintering furnace. furnace brick and vacuum sweepings from the No. 2 De 4 drums also contained contaminated anbestos material frove the furnace insulation.
k.
To provide room in the pcIlet shop, the druma were d rumn were nenled (hernune temporarily stored in the residue trailer. The they contained aabenton remnants) and labeled radioactive materia.l n ene drumn were not to be processed under O.S. 1764 O.S.
i m
material which can be nnenyed. 1764 is used to process contaminated 5 no detectable amount of urnulum. The material in the drums could not be assayed because it contained
[E
%c 4 drumn were eventually brought 4 S
accordance with O.S. back into the pellet shop where they were processed in Barnwell for burin 1. 7003 which deals with packaging material in B-25's for shipment to ro
'?
t . '[
r i
6 APPAltFNT VIOLATION 1 FAII,IIDE TO PROPEfti,Y MARK EACH MASS LIMITED CONTAINER WITH THE ACUAI, IIItAN ItIM CONTENT AND ENRICHMENT (Item 3.a.)
i RESPONSE ~
Drums were in temporary storage awaiting further processing Drums did not require markings which specified U-235 content and enrichment ~
i l -
Drums were properly marked
- . O.S. 1764 will be clarified 1
1 s
C-E doen not helleve it had a violation i
j 1
l '.
j -a A
b, b i.
l ai '.
4
_ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ __ _ _ . __ __2
~
_.A._P_F_ANENT VIOLATION 2 Fall.t!RE 10 APPROVE OPERATION SHEETS AND FAII.URE TO INCL.tfDE APPROPRIATE CAFElY M.18:
AD1 IONS IN OPERATION SHEETS (Item 'l.h.) ' '
RACKGROUND This in one example of nn operation sheet that was selected for the type of problem noted in the apparent violation. There are other operation aheets with similar problems. We admit it.
~
For the apparent requirementa. viointion noted, however, a traveler describes the helium leak test operation The shop traveler spect f t en that 7 operation sheets will be used. No. 945 describes the operational steps and No. 1242 includes the necennary safety precautione, including criticality.
The operation door closure switch. of the helium lenk tent unit was designed such that it took 2 hande to operate the door with one hand. This design feature was defeated by some operators who could operate the The door switch in being reden!gned to prevent the operator from operating it with one hand.
We will fix the equipment rather than incorporate the warning in the operation sheet.
Un had nirendy agreed te. upgraele our extating shop floor procedurea (operation aheets) to include the appropriate precautionn. afgnneuren, necenanry operat Ing inntructions and applicable safety and criticality 4
L
- e 1
- oE.O A-
@ i
.X
.hi n
APPAHENT VIOLATION 2 FAILURE TO APPHOVE OPERATIONS SHEETS AND FAILURE TO INCLUDE APPROPRItT .
SAFETY PRECAtlTIONS IN OPERATIONS SIIEETS (Item 3.b.)
I RESPONSE i O.S.
should have been approved by Manager NL&S.
sheets have been signed. These particular operation Neconnary sa fet y precautions were included in another O.S.
! located at station Safety precaut ion on ringers in i tube not included on O.S. because of system desige i
1 j
CE had committed to an upgrade of the O.S.
violation "G" program as part of its response to as addressed in Dr. McGill's letter will he completed by the 4th Ouarter of 1988. of 2/23/88. This upgrade i
CE does not believe it had a repeat violation b
4 1
,s.
kk
- x 2 :p N
~
_ APPARENT VIOLATION 3 Fall.IIRE To MAINTAIN PEI,I.ETS WITHIN THE REQ 1tIRF.D 4" SLAR THICKNESS ON 11IE Fl!El. l'El.l.ET STORAGE SHEINF.S (Item 3.c.)
RACKGROUND Criticality limit entahlinhed bnned on an infinite array of optimally moderated pellet trays 4" high Criticality limit la implemented by:
Limiting pellet trny 007 weight to a safe amount 2
Limiting pellet trny atack height to 2 - 2" high trays 1 .
Specifying 4" alab limit on nuclear criticality sign at station In January 1988, Production from 8500 grams to 9300 grnmn. requent ed they be allowed to increase tray maximum UO2 weight This requent was reviewed and approved.
j The operntore, than apreading nt timen.
them out over Ioaded t iie ailditional pelle:s into the center of the tray rather the tray opening.
l When the pellets are distributed uniformly, theThis tray caused cover sits theflush.
tray cover to sit at an angle.
Operators would stack 7 trays on top of one another.
the bar opening on the pellet tray storage shelves. At times, double tray height would be above and slide pellet trayn under har. To get under bar, operators would push bar up [
. m. .
l
- - - - - - _ __ - . - - - - - - - - - - - - _ - _ _ . - - - - . - - - - _ _ - . _ _ _ _ _ _ _ _ _ _--___--a----_e- , - - - - , - - _ _ _ - - - - - - - - - - - _ - -- - - _ - - - - - - . - - - _ - - - _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ - - - - - - - -
APPA_ltENT VIOLATION 3 FAILURE TO MAINTAIN PEI,LETS WITilIN TIIE REQUIRED FOUR INCII SLAB THICKNESS ON TifE FUEL PEI.T.ET STORAGE SilELVES (Item 3.c.)
RESPONSE
The correct weight of pellets was put into each tray.
Trays were stacked a maximum of 2 high.
Trays with mounded pellets in center of tray have lower Keff.
Trays did oxceed the 4" limit.
CE admit.n to a procedural violation.
i y
1-2 Corrective action:
O.
p i
Procedures were corrected to require leveling of pellets in trays Operators trained on the importance of leveling pellets a
In flexible bar installed on storage shelves s 1
i t
i
APPARENT VIO1ATION 4 ,
I Ai1.tllu. tn (:0Nittit:r DAIl.Y AllillT.9 F.ACll WORKING I)AY (Item 4.a.(I))
RACKGROUND The nucient fuel manu facturing facility is formally audited once each working day by a Ifealth Physten techntrian for ifealth Physics compliance and criticality compliance.
The license doen not npecify the degree of audit detail required. This is left to the discretion of the lien 1 th Physicn aupervisor.
.I Our procedure in to conduct a fully detailed audit each working day that the shop is in
~
full operation and an nhbreviated audit when the shop is in partial operation.
Both the deta f leil anil nhbreviated audit are fully documented.
i j
2
,vi' .
g.
"+ '
1 '@.
.A1. 7 T.
?
.___ _ __m. -
.~
~
APPAltENT VIOI.ATION 4 ' ~
PAILUHE TO CONDUCT DAILY AUDITS EACH WORKING DAY (Item 4.a. (1) )
RESPONSE
We are required to conduct an audit each working day we elo conduct an audit each working day
+,
All audits are documented '
CE does not believe it had a violation
-l. .
, *y - .
-[
'Nh , "l:[-$
y ;N;-? --rf,
[ S' .
1
APPARENT VIOI.ATION 5 FAILURE 'IT) EVAI.UATE THE EFFECTS OF AN ACCUMUI.ATION OF URANIUM OXIDE POWDER UNDER 'n1E CONVEYOR ADJACENT TO THE BATCH MAKE-UP HOOD ON CRITICALITY SAFETT (It em 4.h. (2))
.B._ACKCROUND "Ihe batch make-tip hood / roller conveyor has been in place in the pellet shop s for the past If. yearn.
Ve evalunted the ponnib11ity of a gradual UO2 powder buildup and concluded, from 18 years of operntIng experience on thin equipment, that significant UO2 powder would not nerunu la t e under the conveyor and there was no cause for a
, e:ri t icali ty concern.
At 4.1% enrichment it would require 55 Kg's of UO2 optimally moderated and reficcted to form n crittent mann. We restrict hucket content in this hood to a maximum of V. Kg*n of I:02. We nIno require the bucket to be covered
?
prior to removal from the hood onto the conveyor.
4 Y
. s
'
Y I .n f./ , #
APPA, RENT VIOLATION 5
. . 3 l
FAILURE TO EVALUATE TIIE EFFECTS OF AN ACCUMULATION OF URANIUM OXIDE POWDER j
UNDER Tile CONVEYOH ADJACENT TO TIIE HATCII MAKE-UP HOOD ON CRITICALITY SAFETY.
(Item 4.b. (2) )
l-i i
t
RESPONSE
l' Nuclear Criticality Specialist was consulted prior to enclosing the hood t
we believe that the precautions we took were responsible and acceptable i
CE doen not believe it had a violation i
4 1
.h. .
.a I
s :-f
. m t G.
.b' q 4
a
APPARENT VIOLATION 6
r:WTHeil.1111~. AlslitTillN OF llHANillM OXII)E TO Tile IIAPWEHMil.l.
110 011 1 0 ASStiltIC TIIA1 Tile MASS 1,lMIT IS NOT EXCEEDED (Item 4.c.)
BACKGROUND UO2 powder, in a bucket, in put into the top of the 2 part hammermill hood.
ne operator records the weight of 1702 in the bucket (excluding tare weight of bucket) onto log sheet posted on hood.
he operator procensen the Ue2 powder through the hammermill where it accumuleten into a 5 gallon bucket (which han a tare weight of approximately 1 Kg) on the lower part of the hood.
he bucket in the lower part of the hood nits on a scale which han a digital readout that shows the combined weight of the bucket and powder.
h e operator removen the bucket from the lower part of the hood. He then weighs bucket. subtracts tare weight, nnd recorIn powder vetr.ht on log posted on hood.
he neiperv f =nr verfffen e len t c lie nin t ti cniculatinna are correct.
De NRC innpector found a 1.1 exceeded by 0.5 Kg of 107. l'a discrepancy which could have caused the 24 Kg hood limit to be g .
4 f-*
APPARr:NT VIOLATION 6 '
l FAILURE TO CONTROL Tile ADDITION OF URANIUM OXIDE TO TIIE HAMMERMILL IIOOD TO ASSilRE TIIAT TIIE MASS LIMIT IS NOT EXCEEDED (Item 4.c.)
l l
RESPONSE
A 1.1 kg discrepancy does exist on the milling hood log The reason for the discrepancy is indeterminate
. Likely cause: operator did not subtract bucket tare weight of approximately 1 Kg ,
we do not believe we violated the posted criticality limit but we cannot prove it CE cannot contest the apparent violation Corrective action
. we have etianged the form to not only record 002 weight, but also tare weight and total weight
, we have instructed supervisory personnel on the changed form i
. we will redesign the hood weighing / recording system to eliminate the problem -
l
~
4
_ _ _ _ _ _ _ _ . _ _ _ . - _ _ . _ . __ +-
APPARENT VIOLATION 7 "
4 FAllitM. 'In int'l.trl'E Tile IIRANIlfM-7% CONTAINF.D IN SEDIMENT REMOVED - -
FHitM WA:. l E TANF:. ANI) PIPF.S IN Millt. DING 6 ON INVFNTORY (Item 9.h.)
BACKCROUND In 1984 we discovered mnterial in an underground line that was adjacent to the old naval nuclear fuel fabrication facility.
The naval nuclear fuel f abrica tion facility stopped actively producing naval fuel in 1959 - 1960.
ne facilit r van decomminnioned and turned over to CE site personnel for other uses.
The material in the line van identified an high enriched uranium. The material had been in the line for approximately 24 years.
The NRC wan immed ia t + f y not i fi ed of the discovery.
The material (a mixture of nand, dirt, aluminum oxide, and uranium) was removed from the line, loaded into 5 gallon buckets, and stored in Building 6 for safeguarding purposes.
We voluntarily requented, in a high enriched material. ne NRC approved this request.
licenne change to the NRC, that we be allowed to possess the 1
We voluntarily nuhmitted a packaging and disposal procedure to the NRC for approval. The NRC approved thin request.
ne material waa analyred by an offaite laboratory.
' Baned on the Inbora tory ' n analynin, it was determined that there was about 70 grams of U-235 in all of the material found in the pipe. .
De materini was shipped to Barnwell for burial on May 4, 1988.
l
].
4:.
f.;
q
. p.
m.
7;
APP,ARENT VIOLATION 7 FAILURE FROM TO INCLUDE Tile URANIUM-235 CONTAINED IN SEDIMENT REMOVED WASTE TANi(S AND PIPES IN BUILDING 6 ON INVENTORY (Item 9.b.)
RESPONSE
Material owned by Government NRC immediately and fully notified Material properly safeguarded by C-E when we received were obligated to license inventoryrevision to possess material, we material.
until May 2, 1988 We failed to do this CE admits to a procedural violation l
l 4
(
V
.E i
~
'0 '
P1 'h
+
.E.
4
APPARfWP VIG.ATION 9 #
FAIIUFF. 'IU ADFBIATELY ASSESS '11E RESUL'IS T ' LYE CRITICALITY SAFT/IY TTMINnt; PIOGRAM (Item 10.a.2.)
, BACl(GROUND
'Ihis is one exarrple of a.nther trainirq violation. 'Ihem are other similar violations nyanliry trainiry of IP 'Ibchs arwi facility personnel. We admit it.
W had previously agreed to upgrade our existing training for both Health Physics
'Ibchs arrt facility yersonnel.
2 General avployee Training modules have alrmdy been coupleted and given to facility personno).
3 additional General nrployee Training modules have been conpleted and training in them modules has been scheduled.
licalth Thysics 'Ibch Trainiry modules have been started and a training schedule established.
v j;
m are workiry cn the entire trainirg progreen and are preparing.ccuplete training modules, lesson plans, and tests. -j
'q u
4 e
jip
- 4;.
.T tw ri l
~
APPARENT VIOLATION 8 '
FAILURE TO ADEOtfATELY ASSESS THE RESULTS OF THE CRITICALITY SAFETY TRAINING PROGRAM (Item 10.a.2.)
RESPONSE +
CE had committed to an upgrade of the training program as part of its response to violation "H" as addressed in Dr. McGill's letter of 2/23/ns we are on schedule for the completion of that commitment by the 4th Quarter of 1988 ,
l 1
CE does not believe it had a repeat violation g
- J l
'A
)
l
. :v.c 1
- 4 7'
l i
~
L
SUMMARY
CE admits to 2 procedural violations CE cannot contest I apparent violation CE believes that 5 of the apparent violations are incorrect
.j; p.
s-g
.: 4 h 5
a L
CORRECTIVE ACTIONS - LONGER TERM ROOT CAUSE ANALYSIS:
MANAGEMENT INATTENTION: FAILURE TO RECOGNIZE:
DEFICIENCIES IN EXISTING RADIATION PROTECTION PROGRAM DETERIORATION OF PROCESS EQUIPMENT / CONTAINMENT DEFICIENT WORK PRACTICES INADEQUATE RESOURCE ALLOCATION CORRECTIVE ACTIONS ADDRESS:
PROCEDURES AND PRACTICES TRAINING HUMAN RESOURCES PROCESS AND EQUIPMENT 4
+
3J
e
' ~
l'ROCEDURES AND PRACTICES l
OBJECTIVE ,
TO ENSURE THAT ALL PLANT OPERATIONS AND PERSONNEL PROTECTION PROGRAMS ARE PERFORMED CONSISTENTLY AND IN ACCORDANCE WITH REGULATORY AND OTHER REQUIREMENTS.
RADIATION PROTECTION f
WE HAVE RETAINED A CONSULTANT (RADIATION SAFETY ASSOCIATES INC.) TO WORK WITH US TO:
REVIEW THE ADEQUACY OF OUR EXISTING WRITTEN PROCEDURES 56 Procedures identified
- to be written or rewritten UPGRADE EXISTING PROCEDURES WHERE NECESSARY 36 Now in Draft DEVELOP NEW PROCEDURES WHERE REQUIRED PROVIDE A COMPLETE RADIATION PROTECTION MANUAL Complete 4th Quarter 1988 THIS PERMITPROCESS HAS BEEN COMPLETED FOR RESPIRATORY PROTECTION AND RADIATION WORK (RWP) PROCEDURES.
REMAINING PROCEDURES WILL BE COMPLETED BY JUNE 30, 1988. de @ a ver 1988 j THESHOP AND RADIATION PROTECTION PERSONNEL. MANUAL WILL FORM THE BASIS FOR TRAINING HEALTH PHYSICS s
1*
u;V..
{k.
t PROCEDURES AND PRACTICES (CONT'D) -
SHOP OPERAT_ IONS WRITTEN PROCEDURES CONTAMINATION CONTROL. (INSTRUCTIONS) HAVE BEEN ISSUED TO SHOP PERSONNEL FOR Completed 12/87 ,
m ADDITIONAL PROCEDURES (INSTRUCTIONS) TO SHOP PERSONNEL WILL BE DEVELOPED TO ADDRESS REMAINING RADIATION PROTECTION REQUIREMENTS.
Will be completed concurrently with 56 prt>cedures above 4th Quarter 1988 i -
SHOP PROCEDURES WILL BE USED TO PREPARE LESSON PLANS FOR PERSONNEL TRAI INTERNAL AUDITS A PROCEDURE HAS BEEN IMPLEMENTED TO PROVIDE FOR INDEPENDENT QUARTERLY AUDITS OF THE RADIATION PROTECTION PROGRAM AND PRACTICE.
Implemented 12/15/
k sn p
t
' ~
litMLING OBJECTIVE TO ENSURE THAT PERSONNEL AT ALL LEVELS KNOW AND UNDERSTAND THE DUTIES AND RESPONSIBILITI OF THEIR JOBS AND THE NEEDS AND PURPOSES OF PROTECTIVE PROCEDURES.
TRAINING OF HP STAFF RESPIRATORY PROTECTION COURSE (OCTOBER 1987) Complete and Ongoing RADIATION WORK PERMIT (DECEMBER 1987) Complete and Ongoing RADIATION SAFETY OFFICER COURSE (DECEMBER 1987) Complete
~
TRAINING IN SEPTLMblR 30,REMAlf3ING 1988). RADIATION PROTECTION PROCEDURES (COMPLETE BY 4 tit Qwtttet 1985 HP staff has beeri trairied in old manual will be retrained in new manual,
.)
4
(
~
4 s
lHAINING TRAINING OF SHOP PERSONNE_L TRAINING IN RESPIRATORY PROTECTION COMPLETED NOVEMBERComplete 1987. and ongoing TRAINING IN CONTAMINATION CONTROL COMPLETED NOVEMBER Complete 1987. and Ongoing UPGRADED EMPLOYEE TRAINING PROGRAM COMPLETE BY SEPTEMBER 30, 1988 -
l ANNUALLY THEREAFTER.
4 tin Quatttet 9 Training modules identified 8 modules written 2 modules given u
s 14 2
!!UMAN RESOURCES o OBJECTIVE TO PROVIDE AN ADEQUATE LEVEL OF QUALIFIED PERSONNEL TO MAINTAIN ALL PLANT OPERATIONS IN COMPLIANCE WITH REGULATORY AND OTHER REQUIREMENTS.
RADIATION PROTEXTION PROVIDE FULL TIME HEALTH PHYSICS COVERAGE AT ALL TIMES IN THE PELLET SHOP (NOVEMBER 1987). Increased HP staff .
RETAIN A QUALIFIED CONSULTANT TO ASSIST WITH PREPARATION OF RADIATIOr4 PRO TECT I O",1 [
PROCEDURES AND TRAirJING PROGRAMS (OCTOBER 1987). Implemented PROVIDE A QUALIFIED INDIVIDUAL TO PERFORM INTERNAL AUDITS OF COMPLIANCE WITH RADIATION PROTECTION REQUIREMENTS (QUARTERLY BEGINNING IN 1988). Implemented SHOP OPERATIONS PROVIDE ADDITIONAL SUPERVISION IN THE PELLET SHOP TO ASSURE OPERATOR COMPLIANCE WITH CONTAMINATIOff CONTROL AND OTHER PROCEDURES. (DECEMBER 1987). Implemented PROCESS ENGINEERING i
PROVIDE ADDITIONAL ENGIf4EERING SUPPORT IN THE PELLET SHOP TO IMPROVE CONTAMINATION CONTROL OF PROCESS EQUIPMENT (DECEMBER 1987). Implemented PLANT / EQUIPMENT MAINTEfMNCE :
PROVIDE PERSONNEL TO IMPLEMENT AN ONGOING PREVENTIVE MAINTENANCE PROGRAM FOR
~
EQUIPMENT AND CorJTAINMErJT/ VENTILATION SYSTEMS (APRIL 1988). Implemented
~
4 PROCESS _AND EQUIPMENT OBJECTIVE TO PROVIDE RFL I AllLE ENf lf41'ERI D SYSTEMS WillCH MAINTAIN MANUFACTURING OPERATIONS IN COMPLIANCL WITH HEGULATORY AND GTHER REQUIREMENTS.
Il1 MEDIATE ACTIONS UPGRADE JUfJE 1988). CONTAltJMEfJT/ VENTILATION 907 complete wi'l be complete by June SYSTEMS ON EXISTING EQUIPMENT (OCTO MODIFY MATERIAL 907, complete HAflDLING will complete by June SYSTEMS OUTSIDE CONTAINMENT (OCTOBER 1987 IMPLEMENT PREVEtJTIVE MAltJTENANCE PROGRAM (APRIL 1988).
Initiated January 1988 will te fully operational December 1988 LONGER TERM ACTIONS A MAJOR SHOP UPGRADIfJG PROJECT IS PLANNED OVER THE NEXT THREE YEARS. Ii i
e i t;'
u rf l
t
_