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| | number = ML20196L272 | | | number = ML20196L272 |
| | issue date = 05/18/1999 | | | issue date = 05/18/1999 |
| | title = Ack Receipt of 990407 Ltr,Transmitting Copy of Semiannual Status Rept of C-E Criticality Safety Program Update Covering Period from 981001-990331 | | | title = Ack Receipt of ,Transmitting Copy of Semiannual Status Rept of C-E Criticality Safety Program Update Covering Period from 981001-990331 |
| | author name = Emeigh C | | | author name = Emeigh C |
| | author affiliation = NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) | | | author affiliation = NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
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| | contact person = | | | contact person = |
| | document report number = TAC-L31187, NUDOCS 9905270305 | | | document report number = TAC-L31187, NUDOCS 9905270305 |
| | | title reference date = 04-07-1999 |
| | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 2 | | | page count = 2 |
| | | project = TAC:L31187 |
| | | stage = Other |
| }} | | }} |
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| This acknowledges receipt of your letter of April 7,1999, transmitting a copy of the semiannual status report of Combustion Engineering's (CE's) Criticality Safety Program Update (CSPU) covering the period from October 1,1998 to March 31,1999. | | This acknowledges receipt of your letter of April 7,1999, transmitting a copy of the semiannual status report of Combustion Engineering's (CE's) Criticality Safety Program Update (CSPU) covering the period from October 1,1998 to March 31,1999. |
| The CSPU plan was submitted on September 20,1996, and is designed to formalize and strengthen the nuclear criticality safety program at the Hematite, Missouri site. In that plan, CE committed to submit a quarterly progress report on the implementation of the CSPU. As agreed by the Nuclear Regulatory Commission (NRC), in a letter dated November 6,1997, the reporting frequency was changed to a semiannual basis. | | The CSPU plan was submitted on September 20,1996, and is designed to formalize and strengthen the nuclear criticality safety program at the Hematite, Missouri site. In that plan, CE committed to submit a quarterly progress report on the implementation of the CSPU. As agreed by the Nuclear Regulatory Commission (NRC), in a {{letter dated|date=November 6, 1997|text=letter dated November 6,1997}}, the reporting frequency was changed to a semiannual basis. |
| We note from your April letter that you have devoted additional resources to the CSPU plan to bring the progress concerning the Recycle / Recovery area back on schedule, and this effort has been largely successful. For the next reporting period, your work will be focused on the systems and operations in the front end of the pellet plant. | | We note from your April letter that you have devoted additional resources to the CSPU plan to bring the progress concerning the Recycle / Recovery area back on schedule, and this effort has been largely successful. For the next reporting period, your work will be focused on the systems and operations in the front end of the pellet plant. |
| Your letter also expressed the concems that the NRC's future final rule of the revisions to 10 CFR Part 70 will impose requirements above and beyond your current practices in the preparation of the Integrated Safety Analysis (ISA). As you know, the NRC is currently working closely with the nuclear industry in developing the proposed revisions to 10 CFR Part 70 to require ISAs and preparing a Standard Review Plan to provide the acceptable criteria for reviewing ISAs. The staff expects that additional guidance will be available to address your concerns in near future in conjunction with the rule making. | | Your letter also expressed the concems that the NRC's future final rule of the revisions to 10 CFR Part 70 will impose requirements above and beyond your current practices in the preparation of the Integrated Safety Analysis (ISA). As you know, the NRC is currently working closely with the nuclear industry in developing the proposed revisions to 10 CFR Part 70 to require ISAs and preparing a Standard Review Plan to provide the acceptable criteria for reviewing ISAs. The staff expects that additional guidance will be available to address your concerns in near future in conjunction with the rule making. |
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| This acknowledges receipt of your letter of April 7,1999, transmitting a copy of the semiannual status report of Combustion Engineering's (CE's) Criticality Safety Program Update (CSPU) | | This acknowledges receipt of your letter of April 7,1999, transmitting a copy of the semiannual status report of Combustion Engineering's (CE's) Criticality Safety Program Update (CSPU) |
| ~ covering the period from October 1,1998 to March 31,1999. | | ~ covering the period from October 1,1998 to March 31,1999. |
| The CSPU plan was submitted on September 20,1996, and is designed to formalize and strengthen the nuclear criticality safety program at the Hematite, Missouri site. In that plan, CE committed to submit a quarterly progress report on the implementation of the CSPU. As agreed by the Nuclear Regulatory Commission (NRC), in a letter dated November 6,1997, the reporting frequency was changed to a semiannual basis. | | The CSPU plan was submitted on September 20,1996, and is designed to formalize and strengthen the nuclear criticality safety program at the Hematite, Missouri site. In that plan, CE committed to submit a quarterly progress report on the implementation of the CSPU. As agreed by the Nuclear Regulatory Commission (NRC), in a {{letter dated|date=November 6, 1997|text=letter dated November 6,1997}}, the reporting frequency was changed to a semiannual basis. |
| We note from your April letter that you have devoted additional resources to the CSPU plan to bring the progress concerning the Recycle / Recovery area back on schedule, and this effort has been largely successful. For the next reporting period, your work will be focused on the systems and operations in the front end of the pellet plant. | | We note from your April letter that you have devoted additional resources to the CSPU plan to bring the progress concerning the Recycle / Recovery area back on schedule, and this effort has been largely successful. For the next reporting period, your work will be focused on the systems and operations in the front end of the pellet plant. |
| Your letter also expressed the concerns that the NRC's future final rule of the revisions to 10 CFR Part 70 will impose requirements above and beyond your current practices in the preparation of the integrated Safety Analysis (ISA). As you know, the NRC is currently working closely with the nuclear industry in developing the proposed revisions to 10 CFR Part 70 to require ISAs and preparing a Standard Review Plan to provide the acceptable criteria for l reviewing ISAs. The staff expects that additional guidance will be available to address your ! | | Your letter also expressed the concerns that the NRC's future final rule of the revisions to 10 CFR Part 70 will impose requirements above and beyond your current practices in the preparation of the integrated Safety Analysis (ISA). As you know, the NRC is currently working closely with the nuclear industry in developing the proposed revisions to 10 CFR Part 70 to require ISAs and preparing a Standard Review Plan to provide the acceptable criteria for l reviewing ISAs. The staff expects that additional guidance will be available to address your ! |
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MONTHYEARML20196L2721999-05-18018 May 1999
Ack Receipt of ,Transmitting Copy of Semiannual Status Rept of C-E Criticality Safety Program Update Covering Period from 981001-990331
Project stage: Other
1999-05-18
[Table View] |
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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
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
ML20206U5701999-05-19019 May 1999
Confirms Cancellation of 990524 Meeting in Festus,Mo.Meeting Will Be Rescheduled in Future
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
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)
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
RA99-070, 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
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
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
ML20154J8371998-10-13013 October 1998
Confirms Meeting Scheduled for 981030 in Lisle,Il to Discuss General Facility Performance
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
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
! ' way EN9 Mr. Robert W. Sharkey, Direct r Regulatory Aff; irs Combustion Engineering, Inc.
. 3300 State Road P Festus, Missouri 63028
SUBJECT:
CRITICALITY SAFETY PROGRAM UPDATE SEMI-ANNUAL STATUS REPORT (TAC NO. L31187)
Dear Mr. Sharkey:
This acknowledges receipt of your letter of April 7,1999, transmitting a copy of the semiannual status report of Combustion Engineering's (CE's) Criticality Safety Program Update (CSPU) covering the period from October 1,1998 to March 31,1999.
The CSPU plan was submitted on September 20,1996, and is designed to formalize and strengthen the nuclear criticality safety program at the Hematite, Missouri site. In that plan, CE committed to submit a quarterly progress report on the implementation of the CSPU. As agreed by the Nuclear Regulatory Commission (NRC), in a letter dated November 6,1997, the reporting frequency was changed to a semiannual basis.
We note from your April letter that you have devoted additional resources to the CSPU plan to bring the progress concerning the Recycle / Recovery area back on schedule, and this effort has been largely successful. For the next reporting period, your work will be focused on the systems and operations in the front end of the pellet plant.
Your letter also expressed the concems that the NRC's future final rule of the revisions to 10 CFR Part 70 will impose requirements above and beyond your current practices in the preparation of the Integrated Safety Analysis (ISA). As you know, the NRC is currently working closely with the nuclear industry in developing the proposed revisions to 10 CFR Part 70 to require ISAs and preparing a Standard Review Plan to provide the acceptable criteria for reviewing ISAs. The staff expects that additional guidance will be available to address your concerns in near future in conjunction with the rule making.
Your cooperation in keeping us informed of your progress on the CSPU is appreciated.
Sincerely, Original signed by Charles Emeigh, Section Chief Licensing Section Licensing and International I Safeguards Branch b ,
s Division of Fuel Cycle Safety /
and Safeguards, NMSS
/
Docket 70-36 License SNM-33 h
DISTRIBUTION: [ Completed]
Docket 70-36 PUBLIC NRC File Center FCSS R/F Region ill LIB R/F NMSS R/F PH; land, Riti Madams PPTing , ., .i r
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DATE 05/ /0 /99 05//0/99 05/ \h/99 05/ /L/ /99 Ub5/ g/ /99 9905270305 990518 PDR ADOCK 07000036 A[
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'* 4 2 - WASHINGTON, D.C. 20555-0001 May 18, 1999
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I r. Robert W. Sharkey, Director -
Regulatory Affairs Combustion Engineering, Inc.
3300 State Road P' - .; e Festus, Missouri 63028
SUBJECT:
CRITICALITY SAFETY PROGRAM UPDATE SEMI-ANNUAL STATUS REPORT (TAC NO. L31187)
Dear Mr,
Sharkey:
This acknowledges receipt of your letter of April 7,1999, transmitting a copy of the semiannual status report of Combustion Engineering's (CE's) Criticality Safety Program Update (CSPU)
~ covering the period from October 1,1998 to March 31,1999.
The CSPU plan was submitted on September 20,1996, and is designed to formalize and strengthen the nuclear criticality safety program at the Hematite, Missouri site. In that plan, CE committed to submit a quarterly progress report on the implementation of the CSPU. As agreed by the Nuclear Regulatory Commission (NRC), in a letter dated November 6,1997, the reporting frequency was changed to a semiannual basis.
We note from your April letter that you have devoted additional resources to the CSPU plan to bring the progress concerning the Recycle / Recovery area back on schedule, and this effort has been largely successful. For the next reporting period, your work will be focused on the systems and operations in the front end of the pellet plant.
Your letter also expressed the concerns that the NRC's future final rule of the revisions to 10 CFR Part 70 will impose requirements above and beyond your current practices in the preparation of the integrated Safety Analysis (ISA). As you know, the NRC is currently working closely with the nuclear industry in developing the proposed revisions to 10 CFR Part 70 to require ISAs and preparing a Standard Review Plan to provide the acceptable criteria for l reviewing ISAs. The staff expects that additional guidance will be available to address your !
concerns in near future in conjunction with the rule making.
Your cooperation in keeping us informed of your progress on the CSPU is appreciated.
]
Sincerely, 1
d.N- N
- l. Charles Emeigh, ection Chief
! Licensing Section l ,
Licensing and international :
Safeguards Branch Division of Fuel Cycle Safety ,
and Safeguards, NMSS Docket 70-36--
License SNM-33