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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:NRC TO VENDOR/MANUFACTURER
MONTHYEARML20059M5761990-09-24024 September 1990 Forwards Safety Insp Rept 70-0036/90-04 on 900905-07.No Violations,Deficiencies or Deviations Noted ML20059L4301990-09-17017 September 1990 Responds to Re Revised Pages for Hematite Nuclear Fuel Mtg Facility Fnmcp.Rev to License Condition 1.1 to Safeguards Amend SG-1 to License SNM-33 Being Issued ML20058M6691990-08-0101 August 1990 Confirms 900727 Telcon Re Upcoming Emergency Response Exercise at Facility.Emergency Response Exercise Will Be Held on Morning of 900906 W/Afternoon Critique Session ML20055G4961990-07-0909 July 1990 Grants Request to Delay Submission of Response to Insp Rept 70-0036/90-02 Until 900806,per to Dj Sreniawski ML20055E0511990-07-0505 July 1990 Forwards Request for Addl Info Re Groundwater Monitoring Plan,Submitted by .Response Requested within 45 Days of Receipt of Ltr ML20043G5261990-06-13013 June 1990 Forwards Insp Rept 70-0036/90-02 on 900423-27.No Violations Noted.Unresolved Items & Concerns Identified for Which Response Requested within 30 Days ML20043B2851990-05-23023 May 1990 Ack Receipt of 900212 & 0326 Ltrs Informing of Plan to Improve Quality of Safety Evaluations for All License Amends Re Criticality ML20034A8091990-04-16016 April 1990 Confirms Telcon Re Safety Assessment Team Insp Scheduled for 900423-27 at Hematite Facility.Requests Presentation by Licensee Staff Re Status of Facility Operations & Plant Revitalization Program & Tour of Facility ML20033G8121990-04-0505 April 1990 Responds to Re Certain 1-inch UF6 Cylinder Valves Mfg by Superior Valve Co.Based on Written Verification, Contained in That All Valves from Heat Lots 17-22 Returned to Vendor,Nrc 870819 Order Rescinded ML20042D6761990-03-19019 March 1990 Advises That 900221 Rev 2 to Physical Security Plan Consistent W/Provisions of 10CFR70.32(d) & Acceptable ML20012A9871990-02-26026 February 1990 Forwards Safety Insp Rept 70-0036/90-01 on 900207-09.No Violations Noted ML20006C8441990-01-30030 January 1990 Requests Location & Results of Samples on Four Limestones Conducted by Oak Ridge Associated Univ & Collected by C-E ML20006C7691990-01-24024 January 1990 Forwards Amend 17 to License SNM-33,authorizing Use of Poreformer & Lubricant in Pelletizing Lines,Storage of SNM in Bldg 254,rev to Condition 9 to Include Dates of 900103 & 900112 & Deletion of Conditions 36 & 37.SER Also Encl ML20005E3711989-12-27027 December 1989 Forwards Safety Insp Rept 70-0036/89-04 on 891113-17.No Violations Noted.Open Items Identified in Insp Rept ML20005D9981989-12-20020 December 1989 Forwards Amend 16 to License SNM-33 & Safety Evaluation. Amend Authorizes Possession & Use of 200 Uci Am-241 in Solid Sources ML19332G0641989-12-13013 December 1989 Ack Receipt of 891122 & 1208 Applications for Renewal of License SNM-33.Since Applications Received Prior to Expiration Date,License Will Not Expire Until Renewal Finally Determined by NRC ML19332F5081989-12-11011 December 1989 Ack Receipt of Re Recent Mgt Changes at C-E ML19351A4621989-11-27027 November 1989 Advises That Fee Required Re 891108 Application for Amend to License SNM-33 ML19332D9371989-11-24024 November 1989 Forwards Amend 15 to License SNM-33 & Ser,Authorizing Use of U Enriched to 5.0 Weight % in U-235 in Bldg 254 Pellet Production Lines & Revising Condition 9 to Include Dates of 890501,0818,1026 & 1108 ML19332C5871989-11-15015 November 1989 Forwards Amend 14 to License SNM-33,revising Condition 9 to Include Date of 891023.Amend Authorizes Use of U Source Matl in Bldg 254 Pellet Production Lines.Ser & Categorical Exclusion Also Encl ML19327B3221989-10-19019 October 1989 Forwards Request for Addl Info Re Licensee 890501 Application for Amend to License SNM-33.Response Requested in Form of Revised Pages to Application & within 20 Days ML19327B2901989-10-19019 October 1989 Forwards Augmented Team Insp 70-0036/89-03 on 890830,31,0901 07,08,22 & 23.Matters in NRC 890901 Confirmatory Action Ltr Considered Closed Based on 890919 Meeting,Licensee 890928 Rept & NRC Onsite Review of Corrective Actions ML19325E6731989-10-19019 October 1989 Forwards Oak Ridge Associated Univs Ltr Rept, Radiological Survey of Phase 2 Const Site,C-E,Hematite,Inc,MO. NRC Has Determined That Addl Decontamination Warranted Based on Survey Results ML19327A9421989-10-13013 October 1989 Forwards Safety Insp Repts 70-0036/89-02 on 890825.No Violations Noted ML20248H7991989-10-0202 October 1989 Forwards Transcript of 890824 Meeting in Hillsboro,Mo to Provide Info to General Public Re Expansion at Hematite. Transcript Is draft,final,marked-up Copy ML20247M9301989-09-13013 September 1989 Confirms 890912 Telcon Re 890919 Meeting in Glen Ellyn,Il Re Findings Associated W/Release of U During 890825-29 Operating Period & Util Proposed Corrective Actions to Be Taken Prior to Restarting U Conversion Process ML20246F3091989-08-22022 August 1989 Confirms Plans for 890824 Meeting W/Licensee to Review Concerns of Jefferson County Citizens & Elected Officials Re Planned Expansion of Combustion Engineering,Inc Hematite Facility ML20246A3421989-08-15015 August 1989 Forwards Safeguards Insp Rept 70-0036/89-202 on 890724-28.No Violations,Deviations or Declining Performance Noted ML20245G9861989-08-0909 August 1989 Forwards Matl Control & Accounting Safeguards Insp Rept 70-0036/89-201 on 890710-14.No Violations,Deviations or Declining Performance Identified ML20248B4301989-07-28028 July 1989 Forwards Amend 13 to License SNM-33,authorizing Startup & Testing of Pallet Production Lines W/Depleted U & Storage of Licensed Matl in Bldg 256-2.SER Also Encl ML20247P6391989-05-30030 May 1989 Forwards Matl Control & Accounting Safeguards Insp Rept 70-0036/89-200 on 890508-12.No Violations,Deviations or Declining Performance Identified ML20247M6641989-05-18018 May 1989 Forwards Environ Assessment & Finding of No Significant Impact Supporting Amend of License SNM-33,authorizing Startup Testing & Operation of New Pellet Production Lines at Hematite Facility ML20247A6741989-05-12012 May 1989 Forwards Safety Insp Rept 70-0036/89-01 on 890320-23.No Violations Noted ML20246P1111989-05-10010 May 1989 Forwards Amend 12 to License SNM-33,safety Evaluation & Categorical Exclusion.Amend Authorizes Mod of Conversion Reactor ML20245L6641989-04-20020 April 1989 Informs of Withdrawal of Violation Re QA Audit of Transportation Activities Noted in Insp Rept 70-0036/89-01, Per ML20235U4671989-02-24024 February 1989 Informs That NRC Has No Objection to Const of Pelletizing & Warehouse Flooring at Hematite Facility,Per 880930 Request.Residual Contamination Is Less than Option 1 Limit of 30 Pci/Gm for Enriched U,Per Branch Technical Position ML20235P8701989-02-23023 February 1989 Notifies of Change in Reviewer Assignment for Facilities. Advises That M Williams Replaced G Gundersen as MC&A Licensing Reviewer for Both Facilities ML20206B3461988-11-0707 November 1988 Forwards Amend 11 to License SNM-33,extending Expiration Date to 891231.SER & Categorical Exclusion Also Encl ML20195D7211988-10-31031 October 1988 Forwards Amend 10 to License SNM-33 ML20204C6951988-10-14014 October 1988 Forwards Amend 9 to License SNM-33,permitting Storage of Licensed Matl in Bldg 256,SER & Categorical Exclusion ML20155E6611988-10-0606 October 1988 Forwards Physical Security Insp Rept 70-0036/88-02 on 880913-14 (Ref 10CFR2.790).Violations Noted ML20151X4811988-08-16016 August 1988 Forwards Announcement of Criticality Alarm Sys Workshop Sponsored by Doe.W/O Encl ML20195J4741988-06-16016 June 1988 Forwards Amend 8 to License SNM-33,amending Condition 6 of License & Adding Conditions 31-34 & SER ML20151S2611988-04-21021 April 1988 Forwards Safety Insp Rept 70-0036/88-01 on 880216-19 & 0413-15.No Violations Noted.Progress in Correcting Several Concerns Re Radiation Protection Activities Noted in Section 5 of Rept Will Be Monitored During Future Insps ML20151D2231988-04-0808 April 1988 Forwards Draft Agenda for 880414 Meeting in Hematite,Per Discussion,To Discuss 871228 License Amend Application Re U Enriched to 5 W/O U-235 ML20149N0951988-02-25025 February 1988 Forwards List of Short Courses for Health Physics Technicians Per 880219 Discussion.W/O Encl ML20237E7691987-12-21021 December 1987 Forwards Safeguards Insp Rept 70-0036/87-04 on 871020 & 26 & 1106-10.No Violations or Deviations Noted ML20237A9261987-11-30030 November 1987 Forwards Safeguards Amend SG-1 to License SNM-33 in Response to Jan 1986 Submittal of Revised 10CFR74 Fundamental Nuclear Matl Control Plan ML20245C7021987-10-21021 October 1987 Responds to 871009 Rev to Hematite,Mo Facility Security Plan.Condition 12.1 to Amend MPP-3 to License SNM-33 Revised as Listed ML20236B7271987-10-20020 October 1987 Forwards Safety Insp Rept 70-0036/87-03 on 870921-25 & Notice of Violation.Progress in Completing Corrections to Weaknesses Noted During 861117-21 Insp Will Continue to Be Monitored 1990-09-24
[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
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, AUG o' L 1.990-y.
7.y N&
lDockstNo.70 W
'ABBtCombustion Engineering, Inc.
' ATTN:- Mr. John Conant l Manager of Nuclear k
Materials Licensing 1
l S
CEP 9332-407-k'indsor; CT 06095 k
Dear Mr. Conant:
m
'I.' appreciate' the. telephone conversation you, Chuck Molnar and I had on b
July.27, 1990, regardingithe upcoming emergency response exercise at the
' Combustion Engineering:(CE) Hematite facility.
' Based on our conversation, I understand the following:
1 1-The emergency response exercise for the CE Hematite facility will be held 4
' at the site on September 6,1990.
The exercise will'be conducted in the morning with an afternoon critique session.
- 2. -
LeeLDuel and Chuck Molnar of the CE organization will conduct-a 30 to 60: minute presentation on CE's emergency response organization (corporate and Hematite-facilities) and the type of work performed at the--
Hematite facility.
I have reserved a conference room in the Region III 1
. office at :1:00 'p.m.- (CDT) on August 7,1990 for this presen_tation.
I and other Region 7III staff members will provide you with an; overview of the 1
NRC'~s emergency response organization at Headquarters and R.egionLIII-7' following Lee and Chuck's presentation.
E 3.
The individuals in our organizations, who are developing or will rev'iew the exercise scenario will also' meet to review the'finalLscenario and j
Lexercise logistics in the afternoon on August 7?,l1990. The logistics ij
- will include scheduling'a'. pre-exercise meeting amongst CE-controllers and 0l'
!NRC controllers and observers at the Hematite facility.
'For you_r information, enclosed are some handouts other NRC licensees have-jprovided us 'du' ring presentations of their emergency response organizations.
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.Iflyou-have any questions, please contact-me at (708);. 790-5612.; I look forward to seeing you on August 7.
i Sincerely, m.
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,w manAl. sniv in u..1<a.. aus '
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. Bruce S. Mallett, Chief.
i Nuclear Materials Safety Branch o
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Enclosure:
As' stated o.
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J. A. Rode, Plant Manager JeremiahW.-(Jay) Senator.
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- Nixon, Missouri-State 1
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' bec w/o enclosure:
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E. Weinstein, AE0D, IRB' C. Trottier, NMSS,.IMNS s
.G. Bidinger, NMSS, l.oB W..Axelson, Rill-t C. Norelius, RIII j
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LSCS EMERGENCY CONTROL CENTE.RS T
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- ' The GSEP Station Group is the onsite emergency organization which is activated during an emergency.' The Station Group functions under a Station Director responsible for carrying out all on-site emergency r~
efforts.as well as for carrying out the Commonwealth initial offsite environs monitoring efforts which are necessary for assessing plant releases. l A diagram of the GSEP Station Group organization is shown in Figure 4.2-1.
The Shift' Engineer, as initial Station Director, Will take immediate action.during an emergency and will activate the GSEP Station Group as appropriate..In the Shift Engineer's absence or incapacitation, the line
- of succe'ssion is:
- 1) Shift Foreman;
- 2) ' Station control Room Engineer; The Shift Engineer, or his alternate,-may b.e relieved of the Station Director-position of responsibility when it is assumed by the designated Station Director or the Station Director's alternate.
An individual assigned the duty as a Station Control Rcom Engineer
.(SCRS) shall be available to the Control Room at all times, tmless relieved by responsible individuals.
It is the responsibility of the SCRE/STA to diagnose off-normal events and advise the operating. shift L
accordingly..
If conditions have degraded such that the Shift Engineer and' Shift Foreman are not available or for some-other reason are incapacitated, the SCRE/ Shift' Technical Advisor-(STA) is permitted'to;act as Station LDirector. Once the Technical' Support
- Center (TSC) is in command and control,' staffing shall be returned to the required functional' level.
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RECOMMENDED CON' TROL'HOOM STAFFING FOR EXTENDED OSEP EVENTS OF ALERT CLASSlFICATION OR ABOVE
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.l SHIFT ENGINEER l AFFECTED UNIT ONAFFECTED UNIT SHtFT TECHNICAL ADVISOR --
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' This le a secosamonded of 0anfretion. " Actual Control Room of tentzatlon ells be estabilohed by the Stetton ofrector based upon the event end the ov eltablif ty of shif t' stellin0-
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- Operettone Superussor le e Ilcensed endleiduel sutticiently
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TECHilICAL SUPPORT CEf1TER FIGURE 4.2-1
. GSEP STATION GROUP ORGAtilZATIOt1 1
l STATION DIRECTOR l w.... O,.............,3
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l OPER ATIONS 08 RECTOR l '
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' coord1 hating -.onsite emergency. efforts -(as ' well as" directing all other plant'.
activities).'. If ' the ' Recovery Group-1s t activated at the EOF, the Station v
- Director J will report : to the hanager of Emergency Operations.at the EOF but
- i fv111 not relocate from the TSC to the EOF.
5' Responsibilities assigned to the Station Director include:
s Classify emergencies in accordance with Section 5.0 of this plan.**
g
'o
'o Ensure 'that notifications are made as outlined in Section 6.0.
'(System Power Dispatcher, NRC, and ' State / local agencies in :a-1
= General. Emergency).
3 r
o Activate the 4SEP Station Group as outlined. by Figure 4.2-3 of m.
this plan.
o
. Notify. local support agencies, including. ambulance service, as required in order to expedite their response to the. emergency.
I:
o Provide for Jan assembly and evacuation 'of' nonessential personnel f
from the - site for a ' Site and General. Emergency.. or when -other s
F conditions warrant (refer to Section 6.4).
1
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to Keep the CCC Director, Manager of Emergency Operations,-
and
-(
Nuclear Regulatory Ccmmission informed as to' the status of the a
. plant as determined by the station staff.
o. Request. from the offsite GSEP organization,, additional material, uE
. manpower, and equipment as necessary, to perform decont' amination, repair, snd restoration work.
o Ensure ' adequate manning and access control of the TSC when
(
activated.
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, Implement emergency and recovery efforts u directed by the Corporate Command Center Director / Manager of Emergency Operations.
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.If the emergeacy involves a hazardous substance and/or oil i,
discharges (per the - Spill Prevention Control Countermeasure Plan),
ensure that the appropriate notifications and responses have been made (Additional' information is given in Section 9.3).
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. Authorize personnel exposure beyond 10CFR20 limits under emergency
}
conditions.**
i-Maintain a record of the GSEP related activities.
o L
Refer to Table 4.3-45 for Station Director's duties following EOF activation.
- Note: This responsibility can not be delegated.
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FIECCVERY. GROUP ORGANIZATION
--- EMERGEttCY OPERATIONS FACILITY?
l MANAGER OF l
EMERGENCY OPERATIONS -- CCC DIRECTOR
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TECHNIC AL SUPPORY --- ENGtNEERING ADVISORY SUPPORT a-INTELLIGENCE '
PUSLIC INFORM ATIOtt M AN AGER MANAGER DIRECTOR MANAOER OIRECTOR 1-(CORPOR ATE SPOKESM AN) l (CCC)
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[,f' Revision 6 4y V
S TABLE 4.3-13
.l MANAGER OF EMERGENCY OPERATIONS 6
The Manager of-Emergency Operations is the designated individual from
' 9 4;
Commonwealth Edison who has authority, management ability, and technical Il? p7 Jknowledge to manage the overall nuclear plant recovery. operations wheneverfthe:
W;hM Recovery Group is activated at the EOF Recovery Center. The primary j
g(")n individuel designated es the Manager of Emergency Operations is the Assistant 1
"9 Vice-President and General Manager, Nuclear Stations.
%h Specifically, the Manager of Emergency Operations shall:
l p
d o
Direct the Recovery Group and coordinate all company and industry support activities in coping with an emergency.
1 o-Ensure notification of Federal,. State, and appropriate local i
agencies of emergency declarations or reclassificatiur.s in accordance with Section 6.0 of'this plan.
l o
Ensure that Federal, State, and local authorities remain cognizant of the status of tho' emergency situation.
If requested,' dispatch informed individuals to State governmental l
)
emergency operations centers.
o Review (or direct the Advisory Support Manager to review) for-factual content all information intended for conveyance to the l
-news media.
s#
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Ensure that appropriate measures are promptly taken onsite to:
1
' ~ L Terminate the' condition causing the emergency.
Protect employees and the public.
R J h.
'i Minimize damage to the plant.
El gry Effect postaccident-recovery and deactivate the GSEP
{
l organizatir when appropriate.
r: e Request' assistance from outside emergency response organizations, o
such as the Department of Energy Chicago Operations Office, if L
required.
L<
o -Determine after consultation with appropriate GSEP personnel when to evacuate the EOF and to determine who are ESSENTIAL and Lt T
NOMESSENTIAL personnel. He also' determines where the evacuated personnel are to be reassembled.
i
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Maintain a record of the GSEP related activities.
R f
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ATTACIDtENT A
'Rovision 0--
Ji Augus t 3, -- 198*J 1
ASSDiBLY AREAS 4
4 Pad, taste Building j -
4 Service L; J -
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TECHNICAL SUP?CRT
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August 3, 1987 2-t g
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Protective Actions for On-site Personnet 1.
.The assembly alarm will be sounded when;the Station Director has
}
' determined that an assembly of personnel is necessary.
~
2.
-During a station assembly, personnel within tho' protected area will assemble at the following locations (refer to Attachment A):
i a.
-Operating Department personnel that are on shif t whose normal-work station is either.the Control Room'or Shift Engineer's office,4 shall assemble in the Control Room. Other Operating Department personnel shall-assemble,in the OSC.
Fuel 1tandlers 47 and Stationmen shall assemble in the Machine Shop.
b.
Rad / Chem Technicians and Rad / Chem Foremen'shall' assemble in the OSC.
Alliother Rad / Chem Management personnel shall assemble in the Machine Shop.
Maintenance' personnel'(Mechanical, Electrical and Instrument) c.
-shall assemble in the Machine Shop.
d.
- Technical Staff, Training, Clerical, Quality Control and Quality 1'
Assurance shall assemble in the Mezzanine Meeting Room.
e.
All Cont tor personnel shall assemble in the Unit' Two Turbine
. i M
Du11 ding n ackway.
f..
Security badged off-site CECO personnel shall assemble in the Hezzanine Meeting R s..
9 Visitors shall remain with their escorts and report to the escorts' respective assembly area.-
h.
Security personnel shall assemble in accordance with their shift orders.
i.
Station GSEP Directors and NRC representatives shall report to the TSC.
. i 2:
The GSEP Security Director has the overall responsibility for the accountability of all personnel within the protected area.
I-a.
Department teads shall account for their personnel. The names of personnel not accounted for shall be reported to the Security Director by each Department Head. Search and rescue teams will be organized to search for personnel that cannot be accounted for within a reasonable amount of time.
l:I T.
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l DOCUMENT ID 0090Z 5
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Accountability for the Control: Room,:OCC) and TSC shall be e
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handled by the GSEP Security. Director _with the assistance ofJ ap '
~
' appropriate TSC: staff.
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^3( " Personnel shall remain in the assembly-area until the condition is
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'? corrected or' instructed to move elsewhere.
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If-it is determined that projected dosus can be avoided by a l relocation of personnel, or other dangers exist that present a threat 4
M to the health and safety of-personnellinside the protected area, an=
_y-l 3g evacuation may be initiated at any time during the~ emergency.
- j Evacuation cf non-essential personnel shall be conside;ed immediately 7
$ils
-if a site. emergency or general emergency has been declared. If evacuation is deemed appropriate, it: shall' be acceaplished in al time gL '
i
-T frame commensurate with orderly implementation end reasonable caution.,
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If a site evacuation is considered necessary evacuate personnel u
"G V; nj to the. sites listed in order of preference:
.1)
Dresden Station.
-'I s
2)
Draidwood Station.
Jt 3)- ' Streator Area !!eadquarters; (refer to Attachment D for evacuation routs to the relocation centers).
i b.
Traffic control for on-site areas will be handled by the'LSCS
[
Security-Force.
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J
.c.
-Equipment and personnel are available at Dresden and-Braidwood i
"[
4V Stations for mqnitoring, decontamination and bioassay. At the j
0
-Streator Area lleadquarters, a team dispatched from 1,SCS will respond for screening the personnel for contamination control f
q gy.
purposer.
If major decontamination and followup are necessary,
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~
those individaals will be sent to Dresden and/or Uraidwood U
Station.
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