|
---|
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: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 ML20043D1011990-06-0404 June 1990 Advises That License Condition 1.1 to Safeguards Amend SG-3 to License SNM-1067 Revised to Read as Stated,Per ML20043C3791990-05-25025 May 1990 Advises That 900119 Rev 5 to Physical Security Plan Consistent W/Provisions of 10CFR70.32(e) & Acceptable ML20042G4071990-05-0808 May 1990 Forwards Mgt Meeting Rept 70-1100/90-04 on 900427 ML20034B9441990-04-20020 April 1990 Forwards Insp Rept 70-1100/90-03 on 900226-0302 & Notice of Violation.Nrc Concerned by Number of Violations, Especially in Light of Concerns Previously Identified. Assessment of Root Causes Requested by 900427 Meeting ML20034A8231990-04-17017 April 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp 70-1100/89-07 ML20033H1361990-04-0303 April 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-1100/89-03.Actions Will Be Examined During Future Insp ML20042D7251990-03-26026 March 1990 Forwards Safety Insp Rept 70-1100/90-02 on 900212-16 & Notice of Violation.Violation Concerned Failure to Maintain Records of Criticality Safety Evaluation ML20012E1311990-03-20020 March 1990 Ack Receipt of Informing NRC of C-E Intent to Terminate Prior Commitment to Follow Expanded Bioassay Program,Per 880115 Notice of Violation ML20033F0371990-03-0505 March 1990 Forwards Insp Rept 70-1100/89-07 on 891127-30 & Notice of Violation.Establishment & Implementation of long-term Corrective Actions for Addl Apparent Violation Will Be Reviewed During Subsequent Insp ML20006F2311990-02-14014 February 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp 70-1100/89-03.Signing Breathing Zone Results for Incident May Not Be Conservative Since Validity of Samples Never Determined ML20006B2631990-01-19019 January 1990 Forwards Mgt Meeting Summary Rept 70-1100/90-01 on 900104 ML19354E5561990-01-18018 January 1990 Forwards Amend 16 to License SNM-1067 & Safety Evaluation. Amend Authorizes Organizational Changes & Revises Condition 9 to Include Dates of 891211,13 & 20 ML20005G8911990-01-0909 January 1990 Forwards Mgt Meeting Insp Rept 70-1100/89-80 on 891005. NRC Understands That Self Assessment Will Be Conducted During First Quarter of 1990 & That Results Will Be Made Available for Review About 900401,per 891013 Telcon ML19332F5081989-12-11011 December 1989 Ack Receipt of Re Recent Mgt Changes at C-E ML20011D9061989-12-11011 December 1989 Informs That Violation B Re Inadequate Posting That Fails to Specify Two Nuclear Criticality Safety Limits,Required for Safe Storage of Four 35 Kg Fissile Units within Workhood Unchanged Per 891031 Response to Insp Rept 70-1100/89-80 ML20011D6331989-12-11011 December 1989 Confirms 891208 Telcon Re Quarterly Status Briefing on Implementation of Nuclear Fuel Integrated Improvement Program on 900104 in Region I Ofc.Results of Emergency Preparedness Exercise Held in Nov 1989 Should Be Discussed ML19327B1961989-10-16016 October 1989 Advises That Both Physical Security Plan & FNMCP Meets Requirements of 10CFR73.67(f) & (G) & Acceptable.License Conditions 1.1 & 2.1 to Current Amend SG-2 Have Been Revised & Reissue of SG-3 Encl ML19351A3801989-10-12012 October 1989 Forwards Matl Control & Accounting Safeguards Insp Rept 70-1100/89-02 on 890918-20.No Violations or Deviations Identified.Rept Withheld (Ref 10CFR2.790) ML19325D5831989-10-11011 October 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-1100/89-04 ML19325D2291989-10-0606 October 1989 Forwards Safeguards Insp Rept 70-1100/89-05 on 890927-29. No Violations Noted 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)) 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 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 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 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 ML20045E7571993-06-24024 June 1993 Forwards Insp Rept 70-1100/93-02 on 930602-04.No Violations Noted ML20045A7141993-06-0707 June 1993 Responds to Re FY93 Annual Fees for Licenses SNM-33 (Hematite Facility) & SNM-1067 (Windsor,Connecticut Facility) ML20044H5041993-05-21021 May 1993 Informs That Invoices AM00001-92,AM00042-92,AM00087-92 & AM07309-92 Have Been Cancelled & That NRC Is Requesting Dept of Treasury to Refund Listed Amount to Licensee ML20036A7991993-05-12012 May 1993 Forwards RAI Re 910627 Application for Amend to Emergency Plan to Reflect Results of Revised Nuclear Accident Analysis for Bldgs 6 & 17 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 ML20036A4801993-05-0505 May 1993 Forwards Comments & Request for Addl Info Re 921223 Application for Amend to License SNM-1067 Covering Storage of Low Level Radwaste ML20044E7161993-05-0303 May 1993 Advises That Commission Grants Exemption for FY91 Annual Fees for License SNM-1067 Invoice AM01091-91 Cancelled & NRC Requesting Dept of Treasury to Refund Stated Payment to Licensee 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 ML20029C4291991-03-20020 March 1991 Forwards Amend 21 to License SNM-1067 & Safety Evaluation. Amend Authorizes Operation of Centrifuge Sys 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 1999-08-12
[Table view] |
Text
o;
- q
?..
1 r
n
)' %
FEB 141990 Docket No. 70-1100
[
Combustion Engineering, Inc.
i ATTN: Mr. C. R. Waterman i
Acting Vice President - Nuclear Fuel Nuclear Power Systems I
o 1000 Prospect Hill Road Windsor, Connecticut 06095-0500 i
Gentlemen:
Subject:
Inspection No. 70-1100/89-03 l
This refers to your letter dated July 28, 1989, in response to our letter dated June 30, 1989, i
Thank you for the information provided in your response concerning your l
technique for the evaluation of bioassay results.
20.103(a)(3) requires, in part, that the licensee use suitable measurements of concentrations in air for detecting and evaluating airborne radioactivity and use measurements of radioactivity in the. body for the assessment of individual intakes of i
radioactivity by exposed individuals. During the evaluation conducted to determine'the individuals' intakes, you had information that caused you to question the accuracy and the validity of the breathing zone (BZ) air samples t
that had been collected from these individuals.
Specifically, you had reason to suspect that the BZ samples had been mishandled and thus may not represent realistic' measurements of the possible airborne exposures associated with this incident. The rationale you presented in support of using the air sample data to estimate intakes are. valid under normal circumstances, however, they are not i
applicable when there is reason to suspect that the sample has been mishandled so as to possibly invalidate the results. Therefore, assigning the BZ results for this incident may not have been conservative since the validity of the 1
samples was never determined.
Because the air sample data were suspected to be invalid, you appropriately I
collectedbioassay(fecal}samplestouseincombinationwithothermeasurements L
'to assess the individuals intakes, as required by 10 CFR 20.103(a)(3).
However, in your. analyses of the bioassay samples, you failed to measure the contribution of other significant uranium isotopes in addition to U-235 (e.g.,
most of the uranium alpha radiation from your enrichment mixture comes from
(
U-234). Therefore, consideration of only the U-235 activity for the bioassay
/
analyses, was inadequate.
If the alpha activity contributed by all the major uranium isotopes in your enrichment mixture was included, your pre-determined uranium alpha activity " action level" would have been exceeded. Because your "go/no go" action level was exceeded, further evaluation of the bioassay data was necessary.
Since this was not done, the actions taken to evaluate the
. intake of the individuals were not in full compliance with the requirements specified in 10 CFR 20.201 and 20.103(a)(3) and the violation stands.
OFFICIAL RECORO COPY RL CE 89-03A - 0001.0.0 9002270271 900214 f) 02/08/90 t
PDR' ADOCK 07001100
\\
C-PDC
1:
i Combustion Engineering, Inc.
2 l
You are required to submit to this office within thirty days of the date of this letter, a written statement that will provide (1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further violations; and (3) the date when full compliance will be achieved.
In this response, please describe any actions taken or planned including procedural changes, training or other activities to ensure that future bioassay results are appropriately evaluated and include all appropriate radionuclides. This response is not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.
Your cooperation with us is appreciated.
Sincerely, L
(SIGNED) MALCOLM R. KNAPP Malcolm R. Knapp, Director Division of Radiation Safety and Safeguards cc:
A. E. Scherer, Director, Nuclear Licensing C. B. Brinkman, Manager, Washington Nuclear Operations Public Document Room (POR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
State of Connecticut bec Region I Docket Room (with concurrences)
Mar,agement Assistant, DRMA (w/o encl)
J. Roth, DRSS G. Bidinger, NMSS 0
l RI.1 SS.
RI:DRSS RI:DRSS RI:DRSS l
It
.t. mk Austin B
Bella 9%
m h/90 2/f/90 2/7/90 2/8/90 MSS RI ;.D Voyner KnApp 02/7/90 02/ /90 0FFICIAL RECORD COPY RL CE 89-03A - 0001.1.0 02/08/90
p
=
1 EMM July 28,1989 LD-89-083 i
Docket No. 70-1100 License No. SNM-1067 I
Dr. Ronald R. Bellamy, Chief i
Facilities Radiological Safety an6 Safeguards Branch Division of Radiation Safety i
and' Safeguards 1
U.S. Nuclear Regulatory Commission
)
Region I 475 Allendale Road King of Prussia, Pennsylvania 19406
Subject:
Response to Notice of Violation t
(Inspection Report 70-1100/89-03)
Reference:
Letter, R. R. Bellamy (NRC) to P. L. McGill (C-E),
dated June 30,1989 t
Dear Dr. Bellamy:
Combustion Engineering has reviewed the Notice of Violation received with the referenced letter and our reply is provided herewith (Enclosure).
If I can be of further assistance on this matter, please do not hesitate to call me or Mr. J. F. Conant of my staff at (203)285-5002.
Very.truly yours, y
COMBUSTION ENGINEERING, INC.
Director Nuclear Licensing AES:lw I
L
Enclosure:
As stated cc:
D. McCaughey (NRC)
J. Roth (NRC - Region I)
.i Power Systems 1000 Prospect Hdt Road (203) 688 1911 Combustion Engineenng. Inc.
Post Office Box 500 Telox: 99297 L
Windsor, Connecticut 06095 0500 1
.. N 1 r21 t'1 Kh ~)G -
1%n w [ ] O d u l u v o "'
e) ff'
~
r.
Encicauro to LD-89-083 Page 1 of 4 Response to Notice of Violation (NRC Inspection Report No. 70-1100/89-03)
Statement of Violation
)
i 10 CFR 20.201 "SL m" atates, in part, that
" survey" means an eva(a) As used in the regulations in thiu p luation of the radiation hazards inc ;~nt to the production, use, release, disposal, or presence of radioactive materials or other sources of radiation under a specific set of conditions.
When oppropriate, such evaluation includes a physical survey of the location of materials and equipment, and measurements of levels of radiation or concentrations of radioactive material present.
(b) Each licensee shall make or cause to be made such surveys as (1) may be necessary for the licensee to comply with the regulations in this part.
Contrary to the above, between February 27 1989 and May 26, 1989, an adequate evaluation of bioassay re,sults required by 10 CFR 20.103(a)(3) was not conducted to assure compliance with the regulations in this part.
Specifically, the results of bionssay camples from two individuals exposed to radioactive materials on February 27, 1989 during removal of a contaminated sheet of plastic from the FA-1 ventilation system mezzanine floor were not cdequately evaluated to determine compliance with 10 CFR 20.103 (a) (3 ).
ResDonse Combustion Engineering has reviewed the records and actions taken with respect to two workers who had abnormally high lapel air campler activities.
Combustion Engineering believes that the cetions taken and the evaluations performed were in full compliance with the requirements specified in 10 CFR'20.201 and 2 0.103 (a) (3).
Ccmbustion Engineering believes that adequate surveys of the work crea were conducted and that, based on these surveys, both individuals were assigned lapel air samplers while working in the curveyed area.
Combustion Engineering further believes that ocsigning intakes to both of these individuals based on the lapel oir sampler activities complies with the requirements of
- 10. CFR 20.103 (a) (3).
Both our air sampling and bioassay programs
s' t
P;go 2 of 4 f
use guidance provided in WASH-1251, APPLICATIONS OF BIOASSAY FOR URANIUM, dated June 1974.
WASH-1251, Section IV-1.1 states in l
part, "if an air sampler is located such that airborne contamination, enroute from the source to the workers breathing aone, must pass by the sample head, the probability of missing anI 1
intake is considered to be too low to justify the additional i
s bloassays.
The additional bioassays are not performed for a cpecific individual if the licensee can demonstrate that the air campling system used to protect the individual is adequate to detect any significant intake."
combustion Engineering believes that when a lapel air sampler is used for determining the intake of radioactivity that all of the above conditions are met.
P Cased on the circumstances surrounding the higher than normal lapel air sampler activities, Combustion Engineering feels that using the activity readings from the lapel air samplers for calculating MPC hours and using that value in the seven day running total for, intake was conservative and meets all regulatory require *ments.
Basad on the seven day running total MPC hours, the Manager of Radiological Protection and Industrial Safety removed both individuals from the Pellet Shop until further evaluations could be completed.
Our procedure, RPI-208, Bioassay program, requires special bioasnays when 40 MPC" hours is cxceeded.
Since both individuals were involved in whatever cecurred causing the above normal air sampler readings, both individuals were requested to give urine.and fecal samples based cnly on one individual's seven consecutive day total intake Cxceeding 40 MPC hours.
(
The purpose for taking the bioassay samples was based on guidance
)
provided by an outside consultant.
This consultant provided the
.following guidance in determining the need for considering a change in work assignments:
\\s a.
In-vivo lung counting:
greater than 175 micrograms U235.
r P;ga 3 of 4 i
l b.
Urine bioassays greater than 141 dpm U/1 (sum of U234, i
U235 and U238).
J c.
Faces bioassay:
greater than 55 dpm U235 excreted per k
day, this being obtained by multiplying the dpm U235 per gram wet weight by the total wet weight per sample.
This assumes the total sample represents one days fecal loss.
However, even if the level of 55 dem U235 i
excreted eer day is exceeded. I don't recommend a consideration of chance in work assianment unless the in-vivo luna and urinary bioassav results exceed the levels in a and b above.
The Manager of Radiological Protection and Industrial Safety provided the bioassay results to the Program Manager, Radiological and Industrial Safety for his evaluation, to nake a determination as to whether or not these two individuals could be ellowed to go back to work in an area with airborne contamination.
The Program Manager, based on the urinalysis results for both individuals being 0 and focal U235 levels being considerably less than 55 dpm for both individuals, made a deter-Dination that both individuals could be returned to normal, unrestricted duty.
The action levels recommended by our consultant and used in our bioassay program and RPI's are based on chronic intakes and, therefore, are considered conservative when used for acute intakes.
P Based on the conservatism of these action levels a simple k
.go/no-go decision was deemed appropriate.
Combustion Engineering believes that the actions of responsible individuals within our organization were appropriate and were based on guidance provided in WASH-1251, Regulatory Guide 8.11, 4
.NUREG/CR-4884, and ICRP-30.
Nevertheless, as part of ongoing
~-
-w-e
(
l P ga 4 Cf 4 i
t P
Cfforts and to further assure that in the future proper actions concerning bioassays are conducted in an efficient manner, individuals responsible for taking and/or evaluating bionssay information will have their individual responsibilites clarified.
l
'We believe that this action will preclude any confusion which may"
}
have existed and which could potentially result in delays in properly processing bioassays.
\\
F r
i I
I f
i
+
4 e f
L
~
[
-