Letter Sequence Approval |
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MONTHYEARML20154D4921998-09-25025 September 1998 Responds to Requesting Certain Info Be Withheld from Public Disclosure,Per 10CFR2.790(b)(4).Not All of Six Reasons Apply to Subject Document.Licensee Has Thirty Days from Date of Ltr to Submit Properly Marked Document Project stage: Other ML20195B9681998-11-12012 November 1998 Responds to & Affidavit ,requesting That Info Concerning Nuclear Fuel Manufacturing Process Be Withheld Per 10CFR2.790(b)(4).Determined That Info Sought to Be Withheld Contains Proprietay Info & Will Be Withheld Project stage: Other ML20196B0421998-11-23023 November 1998 Informs That NRC Has Received License Annex Submittals for Several Operating Sys at W Plant.List of Submittals NRC Has Received,Dates of Documents & Assigned TAC Numbers,Listed. TAC Numbers Should Be Used on Associated Correspondence Project stage: Other ML20198M8511998-12-18018 December 1998 Ack Receipt of License Annex Submittal for URRS Dissolver Sys,Dtd 981030.Initial Review of License Annex Has Been Completed with No Administrative Omissions.Projection of Technical Review Schedule Will Be Provided Project stage: Approval ML20199E0161998-12-31031 December 1998 Responds to Ltrs & 30,with Attached Affidavit ,requesting That Info Re Nuclear Fuel Manufacturing Process Descriptions & Corresponding Nuclear Safety Analyses Conducted for W,Columbia,Sc Plant,Be Withheld Project stage: Other ML20199E0561999-01-0404 January 1999 Requests Addl Info for Info Not Found During Review of Listed Licensing Documents.Nrc Is in Process of Preparing Rtm Suppl for Each Fc Facility,Per .Suppl Assist NRC Incident Response Staff as Emergency Assessment Tool Project stage: Approval ML20199E0441999-01-0404 January 1999 Requests Addl Info for Info Not Found During Review of Listed Licensing Documents.Nrc Is in Process of Preparing Rtm Suppl for Each Fc Facility,Per .Suppl Assist NRC Incident Response Staff as Emergency Assessment Tool Project stage: Approval ML20199D8761999-01-0404 January 1999 Requests Addl Info for Info Not Found During Review of Listed Licensing Documents.Nrc Is in Process of Preparing Rtm Suppl for Each Fc Facility,Per .Suppl Assist NRC Incident Response Staff as Emergency Assessment Tool Project stage: Approval ML20205S9321999-04-14014 April 1999 Submits Comments on RAI for Emergency Response Technical Manual Supplements.Licensee Is Confident That NRC Will Concur That Info in Environ Evaluation Rept & in Licensee Annex Provides Sufficient Detail for Intent of Supplements Project stage: Supplement 1998-12-31
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P0971999-10-20020 October 1999 Forwards Combustion Engineering Third Sample Event Rept in Conjunction with Hdrogeologic Investigation & Ground-Water, Soil & Stream Characterization, as Requested ML20217M1451999-10-19019 October 1999 Forwards Amend 29 to License SNM-33,allowing Requested Time Extension to Certain Commitments in Fundamental Nuclear Matl Control Plan Re Temporary Change to UF6 Receipt Sampling Procedure.Safeguards Evaluation Rept,Encl RA99-138, Forwards Eighth Status Rept on Criticality Safety Program Update (Cspu),Per Cspu Plan & Subsequent Revs. Rept Covers semi-annual Period from 990401-9909301999-10-0808 October 1999 Forwards Eighth Status Rept on Criticality Safety Program Update (Cspu),Per Cspu Plan & Subsequent Revs. Rept Covers semi-annual Period from 990401-990930 ML20212J0161999-09-29029 September 1999 Forwards Insp Rept 70-0036/99-04 on 990907-10.No Violations Noted ML20216E7441999-09-13013 September 1999 Grants six-month Extension of Time for Combustion Engineering to Further Develop & Refine in-situ Leaching (Isl) Process for Recovery of U from Soils Beneath Evaporation Ponds ML20212A8951999-09-10010 September 1999 Forwards Proprietary Updated Physical Security Plan for Protection of Special Nuclear Matl of Low Strategic Significance for Abb Combusting Engineering Nuclear Power, Inc,Hematite Facility,Per 10CFR73.67.Plan Withheld RA99-133, Forwards Third Sampling Event Rept in Conjunction with Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization. Ltr from Leggette,Brashears & Graham,Inc, Authorizing Reproduction of Repts,Encl1999-08-25025 August 1999 Forwards Third Sampling Event Rept in Conjunction with Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization. Ltr from Leggette,Brashears & Graham,Inc, Authorizing Reproduction of Repts,Encl ML20211B4291999-08-19019 August 1999 Forwards Amend 28 to License SNM-33,changing Name of Licensee to Abb Combustion Engineering Nuclear Power,Inc & Incorporating Date of 990618,for Decommissioning Financial Assurance.Ser Also Encl ML20210V0971999-08-18018 August 1999 Confirms Meeting Scheduled for 990915 at Licensee Facility in Festus,Missouri.Purpose of Meeting to Discuss Current Plant Performance,Future Plant Activities,Recent Insp Activities & Pond Decommissioning RA99-129, Forwards License Application Pages Reflecting Recent Changes Made to Corporate Name.Ltr Replaces Entire 990729 Submittal1999-08-13013 August 1999 Forwards License Application Pages Reflecting Recent Changes Made to Corporate Name.Ltr Replaces Entire 990729 Submittal RA99-082, Provides Update on Status of Abb Cenp Former Evaporation Ponds Decommissioning & Planned Actions Regarding Same1999-08-13013 August 1999 Provides Update on Status of Abb Cenp Former Evaporation Ponds Decommissioning & Planned Actions Regarding Same ML20210Q3781999-08-11011 August 1999 Forwards Insp Rept 70-0036/99-03 on 990803-04.No Violations Noted RA99-120, Forwards License Application Pages Affected by Corporate Name Change,Consistent with Amend 27 to License SNM-331999-07-29029 July 1999 Forwards License Application Pages Affected by Corporate Name Change,Consistent with Amend 27 to License SNM-33 ML20209B3031999-06-28028 June 1999 Ack Receipt of Transmitting Hydrogeologic Investigation & ground-water,soil & Stream Characterization & Ltr Transmitting Second Sampling Event Rept. Proposed Actions Appear Appropriate ML20195D3741999-06-0303 June 1999 Forwards Application for Amend to License SNM-33 to Transfer Combustion Engineering,Inc Assets & Liabilities Related to NRC Licensed Activities to Combustion Engineering Nuclear Power,Inc ML20195C9991999-06-0202 June 1999 Forwards License SNM-33,amend 26,allowing Time Extension for Distributing Result Repts for Apr 1999,physical Inventory.Temporary Safeguards License Condition SG-1.9,is Being Issued to Read as Listed,Effective Immediately RA99-099, Forwards Second Sampling Event Rept in Conjunction with Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization, Rept Developed After Second Quarter of Sampling Under CEs Hydrogeologic Work Plan1999-05-26026 May 1999 Forwards Second Sampling Event Rept in Conjunction with Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization, Rept Developed After Second Quarter of Sampling Under CEs Hydrogeologic Work Plan ML20207A6031999-05-21021 May 1999 Forwards Insp Rept 70-0036/99-02 on 990426-30.No Violations Noted RA99-093, Requests Extension of Time Periods for Submission of Annual Inventory Repts,As Required by Licensee Fundamental Nuclear Matl Plan & NUREG/BR-0007.NRC Forms 742C & 742 Will Be Submitted by 990604 & NRC Form 327 Submitted by 9907021999-05-20020 May 1999 Requests Extension of Time Periods for Submission of Annual Inventory Repts,As Required by Licensee Fundamental Nuclear Matl Plan & NUREG/BR-0007.NRC Forms 742C & 742 Will Be Submitted by 990604 & NRC Form 327 Submitted by 990702 ML20206U5701999-05-19019 May 1999 Confirms Cancellation of 990524 Meeting in Festus,Mo.Meeting Will Be Rescheduled in Future ML20196L2761999-05-19019 May 1999 Forwards Amend 25 to License SNM-33 & Ser.Amend Revised Fundamental Nuclear Matl Control Plan.Nrc Has Completed Review of Submitted Changes & Determined That Changes Do Not Decrease Effectiveness of MC&A Program ML20196L1391999-05-18018 May 1999 Forwards Partially Withheld Insp Rept 70-0036/99-203 Conducted on 990419-23.No Violations Noted.Major Areas Inspected:Mc&A Safeguards Program.Rept Details Withheld,Per 10CFR2.790(d) ML20196L2721999-05-18018 May 1999 Ack Receipt of ,Transmitting Copy of Semiannual Status Rept of C-E Criticality Safety Program Update Covering Period from 981001-990331 RA99-088, Provides Third Response to GL 98-03, NMSS Licensee & Certificate Holders Year 2000 Readiness. Licensee Has Upgraded Systems Having Safety or Safeguards Functions & Is Y2K Ready & Y2K Compliant1999-05-12012 May 1999 Provides Third Response to GL 98-03, NMSS Licensee & Certificate Holders Year 2000 Readiness. Licensee Has Upgraded Systems Having Safety or Safeguards Functions & Is Y2K Ready & Y2K Compliant ML20206G9341999-05-0303 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-0036/99-01 Issued on 990323 ML20206B0371999-04-26026 April 1999 Forwards Insp Rept 70-0036/99-202 on 990405-09.No Violations Noted RA99-074, Responds to NRC Re Violations Noted in Insp Rept 70-0036/99-01.Corrective Actions:Special Evaluation Traveler Was Implemented to Assure That Sys to Prevent Overfilling of UF6 Cold Trap Would Perform Intended Safety Function1999-04-22022 April 1999 Responds to NRC Re Violations Noted in Insp Rept 70-0036/99-01.Corrective Actions:Special Evaluation Traveler Was Implemented to Assure That Sys to Prevent Overfilling of UF6 Cold Trap Would Perform Intended Safety Function RA99-075, Forwards App A,Figure 10 from Hydrogeologic Investigation & Groundwater,Soil & Stream Characterization Rept.Figure Was Inadvertently Ommitted from Original Submission1999-04-21021 April 1999 Forwards App A,Figure 10 from Hydrogeologic Investigation & Groundwater,Soil & Stream Characterization Rept.Figure Was Inadvertently Ommitted from Original Submission ML20205R6161999-04-19019 April 1999 Confirms Meeting Scheduled for 990524 in Festus,Missouri to Discuss Current Plant Performance,Future Plant Activities, Recent Insp Activities & Progress of Nuclear Criticality Safety Upgrade Program ML20205P5241999-04-0909 April 1999 Forwards Amend 24 to License SNM-33,changing Mailing Addresses of Corporate Ofc & of Facility at Which Licensed Activity Will Be Conducted.Ser Also Encl RA99-068, Informs That Info Re Facility Has Been Reviewed & Verified, with Listed Discrepancies Noted,As Requested by NRC 990323 Fascimile1999-04-0707 April 1999 Informs That Info Re Facility Has Been Reviewed & Verified, with Listed Discrepancies Noted,As Requested by NRC 990323 Fascimile RA99-070, Forwards Criticality Safety Program Update Seventh Status Rept for Oct 1998 - Mar 1999. Next Rept Will Be Submitted by 9910071999-04-0707 April 1999 Forwards Criticality Safety Program Update Seventh Status Rept for Oct 1998 - Mar 1999. Next Rept Will Be Submitted by 991007 ML20204J2981999-03-23023 March 1999 Forwards Insp Rept 70-0036/99-01 on 990301-05 & NOV Re Failure to Implement Program,As Required,For Testing,Calibr & Insp of Component Defined by Integrated Sa/Hazard Analysis ML20205M4321999-03-18018 March 1999 Forwards Amend 23 to License SNM-33 & Ser.Amend Incorporates Changes Made to Emergency Plan.Safety Condition S-1 Revised to Include Date of 990115 ML20207M1231999-03-11011 March 1999 Informs That Encl Ltr Explains How NRC Plans to Institute Round Robin Sample Exchange Program Administered by Nbl for Verifying Quality of Licensee U Destructive Measurement Sys.Invoice FL0232-99 Encl RA99-045, Forwards Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization, Rept Developed After First Quarter of Sampling Under Hydrogeologic Work Plan Dtd 980428. Reproduction Release Authorization,Also Encl1999-03-0909 March 1999 Forwards Hydrogeologic Investigation & Ground-Water,Soil & Stream Characterization, Rept Developed After First Quarter of Sampling Under Hydrogeologic Work Plan Dtd 980428. Reproduction Release Authorization,Also Encl ML20207K2711999-03-0404 March 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-0036/98-204. Implementation of Corrective Actions Will Be Reviewed During Future Insps ML20206S5091999-02-0505 February 1999 Forwards Insp Rept 70-0036/99-201 on 990118-22.No Violations Noted.One Violation,Nine Inspector Followup Items & Two Unresolved Items Closed ML20203B2941999-01-27027 January 1999 Forwards Amend 22 to License SNM-33.Amend Allows Requested Time Extension to Certain Specified Commitments in Fundamental Nuclear Matl Control Plan.Safeguards Evaluation Rept,Encl ML20202B4791999-01-26026 January 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-0036/98-04 Issued on 981021.Response Indicated That Licensee Conducted Root Cause Analysis & Scheduled 990209 Meeting to Discuss Issues ML20202B5541999-01-26026 January 1999 Confirms Meeting Scheduled for 990209 in Lisle,Illinois to Discuss Recent Insp Findings on CE Assessment of Lapel Air Samples & Results of Root Cause Assessment & Procedure non-conformance ML20199G3851999-01-19019 January 1999 Forwards Partially Withheld Insp Rept 70-0036/98-204 on 981207-11 & Notice of Violation.Violations Noted.Rept Details Withheld (Ref 10CFR2.790) RA99-005, Informs That CE Will Present follow-up Info in Response to Violations Noted in Insp Rept 70-0036/98-04,at Meeting with Region Iii.Licensee Has Conducted Root Cause Analysis of Causes That Lead to Violation & Reviewed DAs for 19981999-01-15015 January 1999 Informs That CE Will Present follow-up Info in Response to Violations Noted in Insp Rept 70-0036/98-04,at Meeting with Region Iii.Licensee Has Conducted Root Cause Analysis of Causes That Lead to Violation & Reviewed DAs for 1998 RA99-006, Forwards Revised Pages to Hematite Nuclear Fuel Mfg Facility Emergency Plan, Revising Sections 2.1.6 & 2.1.7 Re Postulated Fire & Explosion Incidents1999-01-15015 January 1999 Forwards Revised Pages to Hematite Nuclear Fuel Mfg Facility Emergency Plan, Revising Sections 2.1.6 & 2.1.7 Re Postulated Fire & Explosion Incidents RA99-002, Requests Temporary Change to UF6 Receipt Sampling Procedure to Allow Drawing & Analyzing of UO2F2 Samples for Cylinders by 990401,as Discussed on 990107 with Tn Pham.Doe/Nrc Form 741, Nuclear Matl Transaction Rept Encl1999-01-0808 January 1999 Requests Temporary Change to UF6 Receipt Sampling Procedure to Allow Drawing & Analyzing of UO2F2 Samples for Cylinders by 990401,as Discussed on 990107 with Tn Pham.Doe/Nrc Form 741, Nuclear Matl Transaction Rept Encl ML20199D8761999-01-0404 January 1999 Requests Addl Info for Info Not Found During Review of Listed Licensing Documents.Nrc Is in Process of Preparing Rtm Suppl for Each Fc Facility,Per .Suppl Assist NRC Incident Response Staff as Emergency Assessment Tool RA98-836, Provides Response 2 to GL 98-03, NMSS Licensees & Certificate Holders Y2K Readiness1998-12-31031 December 1998 Provides Response 2 to GL 98-03, NMSS Licensees & Certificate Holders Y2K Readiness ML20198E8001998-12-18018 December 1998 Informs That NRC Received Ltr Dtd 981201,clarifying Intent of Section 4.2 of Hematite Evaporation Ponds Dcommissioning Plan ML20197H4111998-12-0707 December 1998 Discusses 981030 Meeting with Hematitle Fuel Operations & NRC at Region III Office Re General Plant Topics Which Included Part 70 Rulemaking & Nuclear Criticality Safety Program Updates ML20197G8621998-12-0101 December 1998 Informs of Licensee Determination That Uranium Is Present in Evaporation Pond at Depth of Sixteen Feet Below Ground Surface.Core Sampling Will Be Taken & Statistical Analysis Will Be Performed to Demonstrate Recommendation Criteria 1999-09-29
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M1451999-10-19019 October 1999 Forwards Amend 29 to License SNM-33,allowing Requested Time Extension to Certain Commitments in Fundamental Nuclear Matl Control Plan Re Temporary Change to UF6 Receipt Sampling Procedure.Safeguards Evaluation Rept,Encl ML20212J0161999-09-29029 September 1999 Forwards Insp Rept 70-0036/99-04 on 990907-10.No Violations Noted ML20216E7441999-09-13013 September 1999 Grants six-month Extension of Time for Combustion Engineering to Further Develop & Refine in-situ Leaching (Isl) Process for Recovery of U from Soils Beneath Evaporation Ponds ML20211B4291999-08-19019 August 1999 Forwards Amend 28 to License SNM-33,changing Name of Licensee to Abb Combustion Engineering Nuclear Power,Inc & Incorporating Date of 990618,for Decommissioning Financial Assurance.Ser Also Encl ML20210V0971999-08-18018 August 1999 Confirms Meeting Scheduled for 990915 at Licensee Facility in Festus,Missouri.Purpose of Meeting to Discuss Current Plant Performance,Future Plant Activities,Recent Insp Activities & Pond Decommissioning ML20210Q3781999-08-11011 August 1999 Forwards Insp Rept 70-0036/99-03 on 990803-04.No Violations Noted ML20209B3031999-06-28028 June 1999 Ack Receipt of Transmitting Hydrogeologic Investigation & ground-water,soil & Stream Characterization & Ltr Transmitting Second Sampling Event Rept. Proposed Actions Appear Appropriate ML20195C9991999-06-0202 June 1999 Forwards License SNM-33,amend 26,allowing Time Extension for Distributing Result Repts for Apr 1999,physical Inventory.Temporary Safeguards License Condition SG-1.9,is Being Issued to Read as Listed,Effective Immediately ML20207A6031999-05-21021 May 1999 Forwards Insp Rept 70-0036/99-02 on 990426-30.No Violations Noted ML20206U5701999-05-19019 May 1999 Confirms Cancellation of 990524 Meeting in Festus,Mo.Meeting Will Be Rescheduled in Future ML20196L2761999-05-19019 May 1999 Forwards Amend 25 to License SNM-33 & Ser.Amend Revised Fundamental Nuclear Matl Control Plan.Nrc Has Completed Review of Submitted Changes & Determined That Changes Do Not Decrease Effectiveness of MC&A Program ML20196L1391999-05-18018 May 1999 Forwards Partially Withheld Insp Rept 70-0036/99-203 Conducted on 990419-23.No Violations Noted.Major Areas Inspected:Mc&A Safeguards Program.Rept Details Withheld,Per 10CFR2.790(d) ML20196L2721999-05-18018 May 1999 Ack Receipt of ,Transmitting Copy of Semiannual Status Rept of C-E Criticality Safety Program Update Covering Period from 981001-990331 ML20206G9341999-05-0303 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-0036/99-01 Issued on 990323 ML20206B0371999-04-26026 April 1999 Forwards Insp Rept 70-0036/99-202 on 990405-09.No Violations Noted ML20205R6161999-04-19019 April 1999 Confirms Meeting Scheduled for 990524 in Festus,Missouri to Discuss Current Plant Performance,Future Plant Activities, Recent Insp Activities & Progress of Nuclear Criticality Safety Upgrade Program ML20205P5241999-04-0909 April 1999 Forwards Amend 24 to License SNM-33,changing Mailing Addresses of Corporate Ofc & of Facility at Which Licensed Activity Will Be Conducted.Ser Also Encl ML20204J2981999-03-23023 March 1999 Forwards Insp Rept 70-0036/99-01 on 990301-05 & NOV Re Failure to Implement Program,As Required,For Testing,Calibr & Insp of Component Defined by Integrated Sa/Hazard Analysis ML20205M4321999-03-18018 March 1999 Forwards Amend 23 to License SNM-33 & Ser.Amend Incorporates Changes Made to Emergency Plan.Safety Condition S-1 Revised to Include Date of 990115 ML20207M1231999-03-11011 March 1999 Informs That Encl Ltr Explains How NRC Plans to Institute Round Robin Sample Exchange Program Administered by Nbl for Verifying Quality of Licensee U Destructive Measurement Sys.Invoice FL0232-99 Encl ML20207K2711999-03-0404 March 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-0036/98-204. Implementation of Corrective Actions Will Be Reviewed During Future Insps ML20206S5091999-02-0505 February 1999 Forwards Insp Rept 70-0036/99-201 on 990118-22.No Violations Noted.One Violation,Nine Inspector Followup Items & Two Unresolved Items Closed ML20203B2941999-01-27027 January 1999 Forwards Amend 22 to License SNM-33.Amend Allows Requested Time Extension to Certain Specified Commitments in Fundamental Nuclear Matl Control Plan.Safeguards Evaluation Rept,Encl ML20202B4791999-01-26026 January 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-0036/98-04 Issued on 981021.Response Indicated That Licensee Conducted Root Cause Analysis & Scheduled 990209 Meeting to Discuss Issues ML20202B5541999-01-26026 January 1999 Confirms Meeting Scheduled for 990209 in Lisle,Illinois to Discuss Recent Insp Findings on CE Assessment of Lapel Air Samples & Results of Root Cause Assessment & Procedure non-conformance ML20199G3851999-01-19019 January 1999 Forwards Partially Withheld Insp Rept 70-0036/98-204 on 981207-11 & Notice of Violation.Violations Noted.Rept Details Withheld (Ref 10CFR2.790) ML20199D8761999-01-0404 January 1999 Requests Addl Info for Info Not Found During Review of Listed Licensing Documents.Nrc Is in Process of Preparing Rtm Suppl for Each Fc Facility,Per .Suppl Assist NRC Incident Response Staff as Emergency Assessment Tool ML20198E8001998-12-18018 December 1998 Informs That NRC Received Ltr Dtd 981201,clarifying Intent of Section 4.2 of Hematite Evaporation Ponds Dcommissioning Plan ML20197H4111998-12-0707 December 1998 Discusses 981030 Meeting with Hematitle Fuel Operations & NRC at Region III Office Re General Plant Topics Which Included Part 70 Rulemaking & Nuclear Criticality Safety Program Updates ML20196C3601998-11-24024 November 1998 Forwards Insp Rept 70-0036/98-05 on 981102-06 & Notice of Violation.Violation of Concern Because of Indication of Lack of Attention to Detail in Implementation of Posted Criticality Safety Controls for Routine Operations in Plant ML20196D2341998-11-24024 November 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-0036/98-04 & 990115 Commitment to Provide Addl Steps to Be Taken Subsequent to Mgt Review of Root Cause Assessment Team Findings ML20196A9331998-11-20020 November 1998 Ack Receipt of Ltrs & 1103,which Provided Biennial Update for Demonstration Sections of License SNM-33.Update Reflects Current Operations & Includes Operational Data & Info on Current Environmental Release ML20155B7141998-10-28028 October 1998 Informs That Staff Reviewed Response to Violations Noted in Insp Rept 70-0036/98-202 & Determined Response Meets Requirements of 10CFR2.201.Implementation of Licensee Corrective Actions Will Be Reviewed During Future Insps ML20154R4251998-10-21021 October 1998 Forwards Insp Rept 70-0036/98-04 on 980914-18 & Nov.One Violation Identified & of Concern Because Examples Indicate Weakness in Implementation of Mgt Program for Performance of Certain Operations ML20154L4861998-10-14014 October 1998 Ack Receipt of 980827 & 1005 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-0036/98-03 Issued on 980730.C/As Will Be Examined During Future Insp ML20155A6331998-10-13013 October 1998 Ack Receipt of Ltr Dtd 980925,transmitting Copy of Semiannual Status Rept of C-E Criticality Safety Program Update Covering Period from 980331-0930 ML20154J8371998-10-13013 October 1998 Confirms Meeting Scheduled for 981030 in Lisle,Il to Discuss General Facility Performance ML20154D5111998-10-0202 October 1998 Forwards Nuclear Criticality Safety Insp 70-0036/98-203 on 980804-07.One Unresolved Item & One non-cited Violation Was Noted.Unresolved Item Involved Need to Identify Un Tank in Recovery Area as Single Parameter Control Component ML20236V5761998-07-30030 July 1998 Forwards Insp Rept 70-0036/98-03 on 980713-17 & Notice of Violation ML20236V0181998-07-23023 July 1998 Forwards Amend 21 to License SNM-33 & Ser.Amend Reflects Changes & Improvements in Chapter 4, Nuclear Criticality Safety of License Application.Safety Condition S-1 Has Been Revised to Include 980710 Date ML20236K8811998-07-0202 July 1998 Forwards Partially Withheld Insp Rept 70-0036/98-202 on 980608-12 & Notice of Violation.Violation Is of NRC Concern Because It Indicates Complete Understanding of Licensee Requirements.Rept Details Withheld,Per 10CFR2.790 ML20249B1601998-06-17017 June 1998 Informs That Staff Determined That Results of Field Work Specified in Hydrogeolic Investigation Plant Should Provide Reasonable Amount of Hydrogeological Characterization of Site,To Determine Appropriate Decommissioning Actions ML20249B2001998-06-16016 June 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-0036/98-01 on 980506 ML20249B2911998-06-0808 June 1998 Informs of NRC Plans to Develop Emergency Response Technical Manual Suppls for Fuel Fabrication Facilities ML20248D8061998-06-0101 June 1998 Ack Receipt of ,Transmitting C-E Response to .Nrc Determined Licensee Response Consistent W/ 10CFR70.22(d),as Result ML20247M9101998-05-19019 May 1998 Forwards Insp Rept 70-0036/98-02 on 980512-13.No Violations Noted ML20247E3081998-05-0707 May 1998 Summarizes 980430 Public Meeting W/Listed Attendees to Discuss NRC Evaluation of Plant Performance in Five Major Areas of Safety Operations,Safeguards,Radiological Controls, Facility Support & Licensing Activities ML20247D3311998-05-0606 May 1998 Forwards Insp Rept 70-0036/98-01 on 980406-09 & Notice of Violation.Nrc Completed Operations Review,Mgt & Organization,Operator Training & Environ Insp at Facility ML20247N2711998-05-0606 May 1998 Ack Receipt of Transmitting Copy of Semiannual Status Rept of CE Criticality Safety Program Update Covering Period from 971001-980331.NRC Continues to Endorse Methods Described in Alche Handbook ML20217K4071998-04-28028 April 1998 Ack Receipt of Response to Violations Noted in Insp Rept 70-0036/98-201 & Have Determined That Response Is Adequate & Corrective Actions Should Prevent Recurrence 1999-09-29
[Table view] |
Text
. . . _ . _ . _ . . . - _ . _._.-._.._m.._ - . - _ _ . - _ . _ . . _ . ._._ _ ... _ -__. . , _ _ _ _ _ _ _ _ _ _ .
p UNITED STATES
!* j 2
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 4 001
%s,g/ January 4, 1999 Mr. Robert W. Sharkey, Director Regulatory Affairs Combustion Engineering, Inc.
3300 State Road P Hematite, MO 63047 l 3
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR RESPONSE TECHNICAL MANUAL SUPP.LEMENTS (TAC NO. L20002) 1 1
Dear Mr. Sharkey:
As indicated in the letter, dated June 8,1998, from M. Weber to you, the U.S. Nuclear Regulatory Commission (NRC) is in the process of preparing an RTM Supplement for each fuel cycle facility. These Supplements will not be available to the public; however, a copy of the Supplement for your facility will be provided to you for your use. All proprietary and classified j information will be protected by NRC policy accordingly.
Based on a review of licensing documents, we have prepared this request for additional information (RAl) to request information not found in those documents. The following licensing documents have been reviewed: (1) Part i License Application, includes amendments, renewed license, and NRC SER, dated July 1994; (2) Part ll License Safety Demonstration, dated .
l August 30,1996; (3) Emergency Plan, Rev. O, dated October 28,1993; (4) NRC Safety L Evaluation Report: Application Dated August 12,1997, Rei, ease of Hydrofluoric Acid;
- (5) Federal Register, Summary of Hematite EA; (6) NRC Environmental Assessment, dated l March 17,1994; and (7) Additional Information
- Amendment Request for Unrestricted Release of HF, dated December 8,1997.
l The RTM Supplement is designed to assist NRC incident response staff as an emergency
- assessment tool to facilitate event assessment, guide in determining potential health impacts on L site workers and the public, and assist in event mitigation. This emergency resource will improve NRC's ability to perform its emergency function in addition to minimizing the impact on licensees during an emergency event.-
t The NRC understands that gathering the requested information is resource intensive. Mr. Sean Soong, the Project Manager for your facility, and Ms. Yen-Ju Chen, the Project Manager for this Supplement project, will contact you shortly to coordinate an acceptable schedule for completing this RAl. Mr. Soong and Ms. Chen will also discuss with you your preference for providing the information through submittals to NRC or through site visits. Please reference the above TAC number in future correspondence related to this request.
~
cp
,s 1
9901200236 990104 8
PDR ADOCK 07000036 C .
PDR ,
p p q {; c m 7 rgny c
um m - mw
Mr. Robert W. Sharkey 2 If you have any questions about this RAI, please contact Mr. Soong at (301) 415-8155 or Ms. Chen at (301) 415-5615.
Sincerely, Original signed by:
Charles W. Emeigh, Acting Chief Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS Docket 70-36 License SNM-33
Enclosure:
Request for AdditionalInformation cc: MFertel, NEl FKillar, NEl Distribution: w/ enclosure Docket 70-36 PUBLIC NRC File' Center NMSS r/f FCLB r/f FCSS r/f Region ill PHiland, Rlli -FC'_9 e'd
[RAl: a:\abb-ce1.ltr, abb-ce.wpd]
OFC SPB E SPB b FCLB L FCLB C FCLB d' FCLB NAME YChe M hway W SSoong g( MHorn k, CEmeigh DATE t@8 s V/l198 '
1V/4'98 /2/4 98 /h//99 C= COPY E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY l
I
,. . -. .- - , . .. _ - ... - . - - ~.._. - - .- -.--- . . . -.- . . _ -. ~ . - - - . . ..
i
- l l !
l' i j 4 Mr. Robert W. Sharkey 2 l i
If you have any questions about this RAI, please contact Mr. Soong at (301) 415 bis 5 or 1 Ms. Chen at (301) 415-5615.
Sincerely, )1 D. U . bvtfl.
Charles W. Emeigh, ActinhChief j Licensing Branch !
Division of Fuel Cycle Safety i I
and Safeguards, NMSS (
l i Docket 70-36. !
' License SNM-33 !
i
Enclosure:
Request for AdditionalInformation I
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Request for AdditionalInformation Response Technical Manual Supplement Combustion Engineering, Inc.
Docket 70-36 Please provide the following additional information. Appropriate references to the GDP RTM Supplement are provided to demonstrate how the information will be presented in the document and ic give an example of the level of detail that is needed.
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- 1. Provide a legible, reproducible map or data that indicates the safe ingress and egress routes and staging areas at the plant or provide a description of the locations of safe ingress and egress route and staging areas.
- 2. The primary objective of the RTM Supplement is to provide a method for NRC staff to I assess and estimate possible consequences from an accident at a fuel cycle facility.
The estimates will be used to determine or confirm appropriate protective actions for workers, the public, and the environment. Provide any previously performed consequence analysis that could be used to develop the consequence assessment portion of the RTM Supplement.
- 3. The following buildings or areas have been identified as having or potentially having in them, or nearby, significant quantities of hazardous materials (radiological and/or j chemical). Address specific items as indicated for each building. !
3.1 UF Storage Pad (not numbered): Address items a through h.
3.2 Building 230, Rod Load and Assembly: Address items a through h.
3.3 Building 235, West Vault: Address items a through k.
3.4 Area 240-1, Laboratory: Address items a through h, j, and I.
3.5 Area 240-2, Recycle and Recovery: Address items a through h and k.
3.6 Area 240-3, Incinerator, SNM Storage and Waste Processing: Address items a through h and k.
3.7 Anhydrous Ammonia Tank Area (Outside 240-4): Address items a through h.
When addressing item e, also address the following questions: How many j tanks are used to store anhydrous ammonia? Are they only located southeast '
of Building 2407 What maximum quantities are stored in each of the tanks? Is there any hazardous material (radiological and/or chemical) in Building Area 240-47 3.8 Building 252, South Vault: Address items a through I and k.
3.9 Building 253, Utility: Address items a through h.
3.10 Building 254, Pellet Plant: Address items a through h.
3.11 Building 255, Special Pellet Plant: Address items a through h.
3.12 Building 256-1, Pellet Drying: Address items a through I and k.
3.13 Building 256-2, Warehouse: Address items a through h and k.
3.14 Building 260, Oxide and UF, Vaporizers and Dock: Address items a through h.
3.15 HF Tank Area: Address items a through h. When addressing item e, also provide locations of the " Hold" Tank and " Day" and " Qualification" Tanks and the maximum volumes allowed in the " Day" and " Qualification" Tanks.
Enclosure
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. Request for AdditionalInformation Docket 70-36
- a. Verify that the building does contain hazardous materials. If there is no hazardous material in this building, it is not necessary to address the rest of the items.
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- b. Provide legible, reproducible floor plan or layout for the building / area
, (preferably 8.5" x 11" or 11" x 17"). The map should show the north onentation.
- c. Provide the location and description of fixed chemical and radiation I
instrumentation (including criticality) in the building / area. l l
- d. Provide the typical number of workers that may be in the building during each shift.
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- e. Provide a list of all radiological and chemical hazardous materials in the building. Include in the list the maximum quantity (in appropriate units such as !
pounds, kilograms, curies, becquerels) that may be on present at any one I time. Provide locations of these materials n- or outside of the building (tank farms, storage pads, etc.). A legible floor plan or diagram showing the locations would be helpful. (This information will be used to develop bounding accident consequence assessment, in both tables and figures, as shown in Section 2 of GDP RTM Supplement.)
- f. Identify the primary barrier of each material (such as tank, cylinder, process piping or other container and the capacity). Note the number of containers and their locations in the storage pad area. Identify any secondary barrier other than a building. Identify failure modes of the primary barriers (e.g., pigtail l
rupture, piping failure, breach of tank). (Tais information will be used to .
develop bounding accident consequence assessment, in both tables and l figures, as shown in Section 2 of GDP RTM Supplement.)
- g. Provide a description of the conditions under which the material is stored. <
Where applicable, identify security and access controls for the storage and use ;
locations. Identify any local or remote indicators that the barriers have failed.
Identify engineered safety features designed to prohibit or mitigate release of
- material. (This information will be used to develop bounding accident l consequence assessment, in both tables and figures, as shown in Section 2 of l GDP RTM Supplement.)
l l h. Provide the properties of the materials processed or stored in the building.
! The information should include, but not limited to, physical form and chemical characteristics of the material (e.g., solid, liquid, gas, flammability, density),
radiological characteristics, and temperature and pressure conditions under which materials are stored, processed, used, or transported. (This information 2
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l Request for AdditionalInformation Docket 70-36 l l
, will be used to develop bounding accident consequence assessment, in both l
tables and figures, as shown in Section 2 of GDP RTM Supplement.) '
l i. Provide a description of the building construction (type materials, number of l
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stories, type of facility, such as offices, cafeteria, labs, etc.). I J. Provide a list of major plant systems / equipment contained in the building (e.g., i HEPA ventilation, fire suppression, etc.). l
- k. I Provide the dimension (width, length, and height) of the building, including i number of floors,in meter or feet.
- l. Provide a brief description of the processes and functions of the building.
- 4. Identify any additional buildings / areas that have radological or chemical hazardous materials and are not listed in Question No. 3. Address items b through I in Question No. 3 for these buildings / areas.
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