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Category:INSPECTION REPORT
MONTHYEARML20211G7501999-08-25025 August 1999 Partially Withheld Insp Rept 70-1257/99-201 (Ref 10CFR2.790) on 990802-05.No Violations Noted.Major Areas Inspected:Exams of Core Procedures & Representative Records & Interviews with Personnel.Details Withheld ML20211B9261999-08-19019 August 1999 Insp Rept 70-1257/99-202 on 990802-05.No Violations Noted. Major Areas Inspected:Plant Operations,Criticality Safety Training,Administrative Controls,Internal Audits & Internal Reporting of Nuclear Criticality Safety Infractions ML20210R9071999-08-12012 August 1999 Insp Rept 70-1257/99-02 on 990712-16.No Violations Noted. Major Areas Inspected:Selected Aspects of Licensee Programs for Operational Safety,Radioactive Effluents,Environ Protection,Waste Mgt Programs & Followup of Open Items ML20207B3781999-05-21021 May 1999 Insp Rept 70-1257/99-01 on 990322-26,0514 & 21.Violations Noted.Major Areas Inspected;Licensee Programs for Radiation Protection,Emergency Preparedness,Operator Training, Transportation & Followup of Open Items from Previous Insps ML20198F6021998-12-15015 December 1998 Insp Rept 70-1257/98-05 on 981026-30.No Violations Noted. Major Areas Inspected:Operations,Operational Event Review Feedback & Mgt Organization ML20198B4361998-12-14014 December 1998 Insp Rept 70-1257/98-204 on 981109-13.Violation Noted. Major Areas Inspected:Open Item Completion,Review of Recent Licensee Criticality Safety Event,Validation & Criticality Safety Analysis ML20151X0721998-09-16016 September 1998 Insp Rept 70-1257/98-04 on 980810-14.No Violations Noted. Major Areas Inspected:Operational Safety,Maint & Surveillance,Transportation & follow-up of Open Items from Previous Insps ML20236R2841998-07-17017 July 1998 Insp Rept 70-1257/98-03 on 980615-19.Violations Noted.Major Areas Inspected:Selected Aspects of Operational Safety, Radiation Protection,Radioactive Waste Handling & Storage ML20248K0011998-06-0202 June 1998 Insp Rept 70-1257/98-02 on 980413-17 & 980504-08.No Violations Noted.Major Areas Inspected:Operational Safety, Radioactive Effluents & Environ Protection ML20217J8671998-04-0101 April 1998 Insp Rept 70-1257/98-201 on 980313-19.Violations Noted.Major Areas Inspected:Open Item Resolution,Configuration Mgt & Flowdown of Analytical Limits & Controls ML20203K3731998-02-24024 February 1998 Insp Rept 70-1257/98-01 on 980126-30.No Violations Noted. Major Areas Inspected:Review of Mgt Organization & Controls, Operational Event Review & Feedback,Operator Training & Qualification & Selected Aspects of Operational Safety ML20198S5181998-01-16016 January 1998 Insp Rept 70-1257/97-07 on 971215-19 & 971222-24.Violations Noted.Major Areas Inspected:Ep,Operations & Followup on Open Items from Previous Insps ML20199B9431997-11-0707 November 1997 Insp Rept 70-1257/97-202 on 971006-10.Violation Noted.Major Areas Inspected:Criticality Safety Analyses,Chemical Safety Assessment,Chemical & Criticality Safety Controls,Active Engineering Controls & Administrative Controls Flowdown ML20217G9641997-10-0808 October 1997 Insp Rept 70-1257/97-06 on 970915-19.No Violations Noted. Major Areas Inspected:Selected Aspects of Operations & Radiation Protection ML20198H4171997-09-0505 September 1997 Insp Rept 70-1257/97-201 on 970804-08.No Violations Noted. Info Re Major Areas Inspected Withheld,Per 10CFR2.790(d) ML20141K5791997-05-23023 May 1997 Insp Rept 70-1257/97-04 on 970414-18,23,24 & 0501.Violations Noted.Major Areas Inspected:Operations,Radioactive Effluent Discharges,Environ Protection,Solid Radioactive Waste Mgt & Transportation of Radioactive Matls ML20137P1301997-04-0404 April 1997 Insp Rept 70-1257/97-03 on 970303-07.No Violations Noted. Major Areas Inspected:Aspects of Plant Operations, Engineering,Maint & Surveillance Testing ML20136C1611997-03-0707 March 1997 Insp Rept 70-1257/97-02 on 970210-12.No Violation Noted. Major Areas Inspected:Physical Security Plan,Safeguards Events,Fixed Site Physical Protection of Special Nuclear Matl of Low Strategic Significance & Insp Folloup Item ML20134C7331997-01-30030 January 1997 Insp Rept 70-1257/97-01 on 970106-10.Violation Noted.Major Areas Inspected:Mgt Organization & Controls,Operator Training & Qualification,Plant Operations & Engineering ML20133D0291997-01-0303 January 1997 Insp Rept 70-1257/96-206 on 961202-05.Violations Noted. Major Areas Inspected:Fuel Fabrication Facility in Richland,Wa,Activities Associated W/Planned Startup of New Dry Conversion Facility & Review of Hq Insp Procedure 88015 ML20135D8221996-12-0505 December 1996 Insp Rept 70-1257/96-205 on 961104-07.No Violations Noted. Details Withheld ML20134K8161996-11-12012 November 1996 Insp Rept 70-1257/96-04 on 961021-25.Violations Noted.Major Areas Inspected:Emergency Preparedness,Fp,Followup on Licensee Events & Followup on Open Item from Previous Item ML20149H4771994-11-0202 November 1994 Insp Rept 70-1257/94-06 on 940926-30 & 1012-14.Violations Noted.Major Areas Inspected:Review Circumstances Re 940918 Event,Involving Spill of Approx 41 Kg of Low Enriched U Dioxide Power ML20058H9321993-11-22022 November 1993 Insp Rept 70-1257/93-12 on 931101-05.No Violations Noted. Major Areas Inspected:Fire Protection & Followup on Items of Noncompliance,Inspector Followup Items & NRC Info Notices ML20058D4261993-10-17017 October 1993 Insp Rept 70-1257/93-11 on 930908 & 0927-1001.No Violations or Deviations Noted.Major Areas Inspected:Criticality Safety,Operations & Followup on Open Items ML20057C5041993-08-26026 August 1993 Insp Rept 70-1257/93-10 on 930812.No Violations Noted.Major Areas Inspected:Announced Insp to Obtain Info on Licensee Employee Concerns Program ML20056E4111993-08-0808 August 1993 Insp Rept 70-1257/93-09 on 930726-30.Violations Noted But Not Cited.Major Areas Inspected:Maint/Surveillance Testing, Radiation Protection,Criticality Safety/Operations Review, Environ/Waste Mgt & Followup on Open Items ML20056E9041993-08-0404 August 1993 Insp Rept 70-1257/93-08 on 930628-0702.No Violations Noted. Major Areas Inspected:Review Licensee Emergency Preparedness Program & Followup on Open Items ML20056C8711993-07-0707 July 1993 Insp Rept 70-1257/93-07 on 930614-18.No Violations Noted. Major Areas Inspected:Environ Protection,Radwaste Mgt, Onsite Followup of Licensee Events & Followup on Open Items ML20127B1621992-12-23023 December 1992 Insp Rept 70-1257/92-09 on 921207-11.No Violations or Deviations Noted.Major Areas Inspected:Fire Protection & Followup on Items of Noncompliance,Inspector Followup Items & NRC Info Notices ML20126B3451992-12-0404 December 1992 Insp Rept 70-1257/92-08 on 921015-17 & 29.Violations Noted. Major Areas Inspected:Overflow of Low Enriched Uranyl Fluoride to U Hexafluoride Vaporization Chest ML20059H9681990-09-0505 September 1990 Partially Withheld Insp Rept 70-1257/90-201 on 900806-10 (Ref 10CFR2.790(d)).No Violations,Deviations or Declining Performance Identified.Major Areas Inspected:Physical Inventory & Measurement Control ML20059G8981990-08-31031 August 1990 Insp Rept 70-1257/90-03 on 900813-17.No Violations or Deviations Noted.Major Areas Inspected:Radiation Protection, Maint & Surveillance Testing,Transportation of Radioactive Matls & Criticality Safety ML20245H0751989-08-0909 August 1989 Matl Control & Accounting Insp Rept 70-1257/89-201 on 890612-21.No Violations,Deviations or Declining Performance Identified.Major Areas Inspected:Measurement Sys,Physical Inventory & Records & Repts ML20247H6391989-05-22022 May 1989 Insp Rept 70-1257/89-02 on 890417-21.No Violations Noted. Major Areas Inspected:Followup Actions on Open Items,Mgt Organization,Training & Retraining,Criticality Safety, Operations Review & Radiation Protection ML20247P5161989-04-0505 April 1989 Insp Rept 70-1257/89-200 on 890306-10.No Violations or Deviations Noted.Major Areas Inspected:Mc&A Sys Mgt & Assessment,Internal Controls,Measurement Sys,Measurement Controls & Matl Control & Accounting for Exports & Imports ML20195F9841988-11-18018 November 1988 Insp Rept 70-1257/88-08 on 880906-09 & 23.Violations Noted. Major Areas Inspected:Mgt Organization,Training & Retraining,Criticality Safety,Operations Review,Maint & Surveillance Testing ML20154J6151988-05-12012 May 1988 Insp Rept 70-1257/88-04 on 880418-22.No Violations Noted. Major Areas Inspected:Mgt Organization,Criticality Safety, Operations Review,Maint & Surveillance Testing & Radwaste Mgt ML20236C9151987-10-20020 October 1987 Insp Rept 70-1257/87-08 on 870928-1002.No Violations Noted. Major Areas Inspected:Mgt Organization & Controls, Criticality Safety,Operations Review,Training,Radiation Protection & Emergency Preparedness & Environ Protection ML20235X1551987-07-20020 July 1987 Insp Rept 70-1257/87-05 on 870606-12 & 0701.No Violations Noted.Major Areas Inspected:Mgt Organization & Controls, Criticality Safety,Operations Review,Transportation/Radwaste Mgt & Emergency Preparedness & Environ Protection ML20215C0731986-12-0808 December 1986 Partially Withheld Matl Control & Accounting Insp Rept 70-1257/86-09 on 861117-21 (Ref 10CFR2.790).No Violations or Deviations Identified.Major Areas Inspected:Followup on inspector-identified Problems & Unresolved Items ML20212K8191986-08-14014 August 1986 Insp Rept 70-1257/86-05 on 860721-25.Violation Noted:While Performing Equipment Maint,Electrician Spilled Uncontained Visible UO2 Powder Which Was Not Reported to Hpt ML20199C6741986-06-13013 June 1986 Insp Rept 70-1257/86-03 on 860512-16.No Violations Noted. Major Areas Inspected:Mgt Organization & Controls,Training & Retraining,Criticality Safety,Operations Review,Maint & Surveillance Testing & Radiation Protection ML20198J5571986-05-27027 May 1986 Partially Withheld Insp Rept 70-1257/86-04 on 860505-09 (Ref 10CFR2.790).No Violation or Deviation Noted.Major Areas Inspected:Followup on inspector-identified Problems & Unresolved Items ML20154Q8671986-03-13013 March 1986 Matl Control & Accounting Insp Rept 70-1257/86-01 on 860210-14 & 25.No Violations Noted.Major Areas Inspected: Facility Organization & Mgt Controls,Measurement Sys & Matl Control.Details Withheld (Ref 10CFR2.790) ML20154K2321986-02-26026 February 1986 Insp Rept 70-1257/86-02 on 860203-07 & 20.Violations Noted: Procedure Specified That Valves Be Tested Between 70 & 90 Psig Instead of 100 Psig & Protective Valve Cover on Cylinder Not Used After Removal from Vaporization Chest ML20136J0301986-01-0606 January 1986 Insp Rept 70-1257/85-13 on 851203-06 & 09-20.No Violations or Deviations Noted.Major Areas Inspected:Facility Organization & Mgt Controls & Facility Operations & Internal Control.Details Withheld (Ref 10CFR2.790) ML20138A7671985-12-0606 December 1985 Insp Rept 70-1257/85-12 on 851105-25.No Violations Noted. Major Areas Inspected:Mgt Organization & Controls,Training & Retraining,Criticality Safety,Operations Review & Maint & Surveillance Testing ML20135A3351985-08-21021 August 1985 Insp Rept 70-1257/85-10 on 850729-0802.Violation Noted: Visible Hole Identified on Bottom of Container in Shipment ML20127M3021985-06-20020 June 1985 Matl Control & Accountability Safeguards Insp Rept 70-1257/85-08 on 850528-30 & 0603-07.No Violations Noted. Major Areas Inspected:Facility Operations & Internal Control.Details Withheld (Ref 10CFR2.790) 1999-08-25
[Table view] Category:NRC-GENERATED
MONTHYEARML20211G7501999-08-25025 August 1999 Partially Withheld Insp Rept 70-1257/99-201 (Ref 10CFR2.790) on 990802-05.No Violations Noted.Major Areas Inspected:Exams of Core Procedures & Representative Records & Interviews with Personnel.Details Withheld ML20211B9261999-08-19019 August 1999 Insp Rept 70-1257/99-202 on 990802-05.No Violations Noted. Major Areas Inspected:Plant Operations,Criticality Safety Training,Administrative Controls,Internal Audits & Internal Reporting of Nuclear Criticality Safety Infractions ML20210R9071999-08-12012 August 1999 Insp Rept 70-1257/99-02 on 990712-16.No Violations Noted. Major Areas Inspected:Selected Aspects of Licensee Programs for Operational Safety,Radioactive Effluents,Environ Protection,Waste Mgt Programs & Followup of Open Items ML20207B3781999-05-21021 May 1999 Insp Rept 70-1257/99-01 on 990322-26,0514 & 21.Violations Noted.Major Areas Inspected;Licensee Programs for Radiation Protection,Emergency Preparedness,Operator Training, Transportation & Followup of Open Items from Previous Insps ML20198F6021998-12-15015 December 1998 Insp Rept 70-1257/98-05 on 981026-30.No Violations Noted. Major Areas Inspected:Operations,Operational Event Review Feedback & Mgt Organization ML20198B4361998-12-14014 December 1998 Insp Rept 70-1257/98-204 on 981109-13.Violation Noted. Major Areas Inspected:Open Item Completion,Review of Recent Licensee Criticality Safety Event,Validation & Criticality Safety Analysis ML20151X0721998-09-16016 September 1998 Insp Rept 70-1257/98-04 on 980810-14.No Violations Noted. Major Areas Inspected:Operational Safety,Maint & Surveillance,Transportation & follow-up of Open Items from Previous Insps ML20236R2841998-07-17017 July 1998 Insp Rept 70-1257/98-03 on 980615-19.Violations Noted.Major Areas Inspected:Selected Aspects of Operational Safety, Radiation Protection,Radioactive Waste Handling & Storage ML20248K0011998-06-0202 June 1998 Insp Rept 70-1257/98-02 on 980413-17 & 980504-08.No Violations Noted.Major Areas Inspected:Operational Safety, Radioactive Effluents & Environ Protection ML20217J8671998-04-0101 April 1998 Insp Rept 70-1257/98-201 on 980313-19.Violations Noted.Major Areas Inspected:Open Item Resolution,Configuration Mgt & Flowdown of Analytical Limits & Controls ML20203K3731998-02-24024 February 1998 Insp Rept 70-1257/98-01 on 980126-30.No Violations Noted. Major Areas Inspected:Review of Mgt Organization & Controls, Operational Event Review & Feedback,Operator Training & Qualification & Selected Aspects of Operational Safety ML20198S5181998-01-16016 January 1998 Insp Rept 70-1257/97-07 on 971215-19 & 971222-24.Violations Noted.Major Areas Inspected:Ep,Operations & Followup on Open Items from Previous Insps ML20199B9431997-11-0707 November 1997 Insp Rept 70-1257/97-202 on 971006-10.Violation Noted.Major Areas Inspected:Criticality Safety Analyses,Chemical Safety Assessment,Chemical & Criticality Safety Controls,Active Engineering Controls & Administrative Controls Flowdown ML20217G9641997-10-0808 October 1997 Insp Rept 70-1257/97-06 on 970915-19.No Violations Noted. Major Areas Inspected:Selected Aspects of Operations & Radiation Protection ML20198H4171997-09-0505 September 1997 Insp Rept 70-1257/97-201 on 970804-08.No Violations Noted. Info Re Major Areas Inspected Withheld,Per 10CFR2.790(d) ML20141K5791997-05-23023 May 1997 Insp Rept 70-1257/97-04 on 970414-18,23,24 & 0501.Violations Noted.Major Areas Inspected:Operations,Radioactive Effluent Discharges,Environ Protection,Solid Radioactive Waste Mgt & Transportation of Radioactive Matls ML20137P1301997-04-0404 April 1997 Insp Rept 70-1257/97-03 on 970303-07.No Violations Noted. Major Areas Inspected:Aspects of Plant Operations, Engineering,Maint & Surveillance Testing ML20136C1611997-03-0707 March 1997 Insp Rept 70-1257/97-02 on 970210-12.No Violation Noted. Major Areas Inspected:Physical Security Plan,Safeguards Events,Fixed Site Physical Protection of Special Nuclear Matl of Low Strategic Significance & Insp Folloup Item ML20134C7331997-01-30030 January 1997 Insp Rept 70-1257/97-01 on 970106-10.Violation Noted.Major Areas Inspected:Mgt Organization & Controls,Operator Training & Qualification,Plant Operations & Engineering ML20133D0291997-01-0303 January 1997 Insp Rept 70-1257/96-206 on 961202-05.Violations Noted. Major Areas Inspected:Fuel Fabrication Facility in Richland,Wa,Activities Associated W/Planned Startup of New Dry Conversion Facility & Review of Hq Insp Procedure 88015 ML20135D8221996-12-0505 December 1996 Insp Rept 70-1257/96-205 on 961104-07.No Violations Noted. Details Withheld ML20134K8161996-11-12012 November 1996 Insp Rept 70-1257/96-04 on 961021-25.Violations Noted.Major Areas Inspected:Emergency Preparedness,Fp,Followup on Licensee Events & Followup on Open Item from Previous Item ML20149H4771994-11-0202 November 1994 Insp Rept 70-1257/94-06 on 940926-30 & 1012-14.Violations Noted.Major Areas Inspected:Review Circumstances Re 940918 Event,Involving Spill of Approx 41 Kg of Low Enriched U Dioxide Power ML20058H9321993-11-22022 November 1993 Insp Rept 70-1257/93-12 on 931101-05.No Violations Noted. Major Areas Inspected:Fire Protection & Followup on Items of Noncompliance,Inspector Followup Items & NRC Info Notices ML20058D4261993-10-17017 October 1993 Insp Rept 70-1257/93-11 on 930908 & 0927-1001.No Violations or Deviations Noted.Major Areas Inspected:Criticality Safety,Operations & Followup on Open Items ML20057C5041993-08-26026 August 1993 Insp Rept 70-1257/93-10 on 930812.No Violations Noted.Major Areas Inspected:Announced Insp to Obtain Info on Licensee Employee Concerns Program ML20056E4111993-08-0808 August 1993 Insp Rept 70-1257/93-09 on 930726-30.Violations Noted But Not Cited.Major Areas Inspected:Maint/Surveillance Testing, Radiation Protection,Criticality Safety/Operations Review, Environ/Waste Mgt & Followup on Open Items ML20056E9041993-08-0404 August 1993 Insp Rept 70-1257/93-08 on 930628-0702.No Violations Noted. Major Areas Inspected:Review Licensee Emergency Preparedness Program & Followup on Open Items ML20056C8711993-07-0707 July 1993 Insp Rept 70-1257/93-07 on 930614-18.No Violations Noted. Major Areas Inspected:Environ Protection,Radwaste Mgt, Onsite Followup of Licensee Events & Followup on Open Items ML20127B1621992-12-23023 December 1992 Insp Rept 70-1257/92-09 on 921207-11.No Violations or Deviations Noted.Major Areas Inspected:Fire Protection & Followup on Items of Noncompliance,Inspector Followup Items & NRC Info Notices ML20126B3451992-12-0404 December 1992 Insp Rept 70-1257/92-08 on 921015-17 & 29.Violations Noted. Major Areas Inspected:Overflow of Low Enriched Uranyl Fluoride to U Hexafluoride Vaporization Chest ML20059H9681990-09-0505 September 1990 Partially Withheld Insp Rept 70-1257/90-201 on 900806-10 (Ref 10CFR2.790(d)).No Violations,Deviations or Declining Performance Identified.Major Areas Inspected:Physical Inventory & Measurement Control ML20059G8981990-08-31031 August 1990 Insp Rept 70-1257/90-03 on 900813-17.No Violations or Deviations Noted.Major Areas Inspected:Radiation Protection, Maint & Surveillance Testing,Transportation of Radioactive Matls & Criticality Safety ML20245H0751989-08-0909 August 1989 Matl Control & Accounting Insp Rept 70-1257/89-201 on 890612-21.No Violations,Deviations or Declining Performance Identified.Major Areas Inspected:Measurement Sys,Physical Inventory & Records & Repts ML20247H6391989-05-22022 May 1989 Insp Rept 70-1257/89-02 on 890417-21.No Violations Noted. Major Areas Inspected:Followup Actions on Open Items,Mgt Organization,Training & Retraining,Criticality Safety, Operations Review & Radiation Protection ML20247P5161989-04-0505 April 1989 Insp Rept 70-1257/89-200 on 890306-10.No Violations or Deviations Noted.Major Areas Inspected:Mc&A Sys Mgt & Assessment,Internal Controls,Measurement Sys,Measurement Controls & Matl Control & Accounting for Exports & Imports ML20195F9841988-11-18018 November 1988 Insp Rept 70-1257/88-08 on 880906-09 & 23.Violations Noted. Major Areas Inspected:Mgt Organization,Training & Retraining,Criticality Safety,Operations Review,Maint & Surveillance Testing ML20154J6151988-05-12012 May 1988 Insp Rept 70-1257/88-04 on 880418-22.No Violations Noted. Major Areas Inspected:Mgt Organization,Criticality Safety, Operations Review,Maint & Surveillance Testing & Radwaste Mgt ML20236C9151987-10-20020 October 1987 Insp Rept 70-1257/87-08 on 870928-1002.No Violations Noted. Major Areas Inspected:Mgt Organization & Controls, Criticality Safety,Operations Review,Training,Radiation Protection & Emergency Preparedness & Environ Protection ML20235X1551987-07-20020 July 1987 Insp Rept 70-1257/87-05 on 870606-12 & 0701.No Violations Noted.Major Areas Inspected:Mgt Organization & Controls, Criticality Safety,Operations Review,Transportation/Radwaste Mgt & Emergency Preparedness & Environ Protection ML20215C0731986-12-0808 December 1986 Partially Withheld Matl Control & Accounting Insp Rept 70-1257/86-09 on 861117-21 (Ref 10CFR2.790).No Violations or Deviations Identified.Major Areas Inspected:Followup on inspector-identified Problems & Unresolved Items ML20212K8191986-08-14014 August 1986 Insp Rept 70-1257/86-05 on 860721-25.Violation Noted:While Performing Equipment Maint,Electrician Spilled Uncontained Visible UO2 Powder Which Was Not Reported to Hpt ML20199C6741986-06-13013 June 1986 Insp Rept 70-1257/86-03 on 860512-16.No Violations Noted. Major Areas Inspected:Mgt Organization & Controls,Training & Retraining,Criticality Safety,Operations Review,Maint & Surveillance Testing & Radiation Protection ML20198J5571986-05-27027 May 1986 Partially Withheld Insp Rept 70-1257/86-04 on 860505-09 (Ref 10CFR2.790).No Violation or Deviation Noted.Major Areas Inspected:Followup on inspector-identified Problems & Unresolved Items ML20154Q8671986-03-13013 March 1986 Matl Control & Accounting Insp Rept 70-1257/86-01 on 860210-14 & 25.No Violations Noted.Major Areas Inspected: Facility Organization & Mgt Controls,Measurement Sys & Matl Control.Details Withheld (Ref 10CFR2.790) ML20154K2321986-02-26026 February 1986 Insp Rept 70-1257/86-02 on 860203-07 & 20.Violations Noted: Procedure Specified That Valves Be Tested Between 70 & 90 Psig Instead of 100 Psig & Protective Valve Cover on Cylinder Not Used After Removal from Vaporization Chest ML20136J0301986-01-0606 January 1986 Insp Rept 70-1257/85-13 on 851203-06 & 09-20.No Violations or Deviations Noted.Major Areas Inspected:Facility Organization & Mgt Controls & Facility Operations & Internal Control.Details Withheld (Ref 10CFR2.790) ML20138A7671985-12-0606 December 1985 Insp Rept 70-1257/85-12 on 851105-25.No Violations Noted. Major Areas Inspected:Mgt Organization & Controls,Training & Retraining,Criticality Safety,Operations Review & Maint & Surveillance Testing ML20135A3351985-08-21021 August 1985 Insp Rept 70-1257/85-10 on 850729-0802.Violation Noted: Visible Hole Identified on Bottom of Container in Shipment ML20127M3021985-06-20020 June 1985 Matl Control & Accountability Safeguards Insp Rept 70-1257/85-08 on 850528-30 & 0603-07.No Violations Noted. Major Areas Inspected:Facility Operations & Internal Control.Details Withheld (Ref 10CFR2.790) 1999-08-25
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARML20211G7501999-08-25025 August 1999 Partially Withheld Insp Rept 70-1257/99-201 (Ref 10CFR2.790) on 990802-05.No Violations Noted.Major Areas Inspected:Exams of Core Procedures & Representative Records & Interviews with Personnel.Details Withheld ML20211B9261999-08-19019 August 1999 Insp Rept 70-1257/99-202 on 990802-05.No Violations Noted. Major Areas Inspected:Plant Operations,Criticality Safety Training,Administrative Controls,Internal Audits & Internal Reporting of Nuclear Criticality Safety Infractions PNO-IV-99-036, on 990813,licensee Notified NRC Operations Ctr That Inaccurate Lab Analysis Method Resulted in Potential for Criticality Safety Limit to Be Exceeded by 23%.Affected Process Was Shut Down & Tagged Out.Region Will Conduct Insp1999-08-18018 August 1999 PNO-IV-99-036:on 990813,licensee Notified NRC Operations Ctr That Inaccurate Lab Analysis Method Resulted in Potential for Criticality Safety Limit to Be Exceeded by 23%.Affected Process Was Shut Down & Tagged Out.Region Will Conduct Insp ML20210R9071999-08-12012 August 1999 Insp Rept 70-1257/99-02 on 990712-16.No Violations Noted. Major Areas Inspected:Selected Aspects of Licensee Programs for Operational Safety,Radioactive Effluents,Environ Protection,Waste Mgt Programs & Followup of Open Items ML20207B3781999-05-21021 May 1999 Insp Rept 70-1257/99-01 on 990322-26,0514 & 21.Violations Noted.Major Areas Inspected;Licensee Programs for Radiation Protection,Emergency Preparedness,Operator Training, Transportation & Followup of Open Items from Previous Insps ML20207B3731999-05-21021 May 1999 Notice of Violation from Insp on 990322-26,0514 & 21. Violations Noted:On 980225,licensee Delivered Licensed Matl to Carrier for Transport Under General License Pursuant to 10CFR71.12 & Did Not Comply with Terms & Conditions PNO-III-99-005, on 990202,truck with Empty UF6 Cylinders Involved in Traffic Accident.Local Fire & Police Personnel Responded Immediately to Scene of Accident.Driver of tractor-trailer Received Minor Injuries1999-02-0303 February 1999 PNO-III-99-005:on 990202,truck with Empty UF6 Cylinders Involved in Traffic Accident.Local Fire & Police Personnel Responded Immediately to Scene of Accident.Driver of tractor-trailer Received Minor Injuries ML20198F6021998-12-15015 December 1998 Insp Rept 70-1257/98-05 on 981026-30.No Violations Noted. Major Areas Inspected:Operations,Operational Event Review Feedback & Mgt Organization ML20198B4361998-12-14014 December 1998 Insp Rept 70-1257/98-204 on 981109-13.Violation Noted. Major Areas Inspected:Open Item Completion,Review of Recent Licensee Criticality Safety Event,Validation & Criticality Safety Analysis ML20198B4191998-12-14014 December 1998 Notice of Violation from Insp on 981109-13.Violation Noted: Failure to Control Decommissioning Operations So That Operators Would Verify That Disassembled Equipment Was Free from Visible U Deposits Before Staging with Other Equipment PNO-IV-98-043, on 980922,NRC Operation Ctr Notified That Criticality Safety Specialist Noted Visible Accumulations of Solids in Disassembled Sections of Ductwork.Training Planned for Disassembly Crew in Aspects of Safety Requirements1998-09-23023 September 1998 PNO-IV-98-043:on 980922,NRC Operation Ctr Notified That Criticality Safety Specialist Noted Visible Accumulations of Solids in Disassembled Sections of Ductwork.Training Planned for Disassembly Crew in Aspects of Safety Requirements ML20151X0721998-09-16016 September 1998 Insp Rept 70-1257/98-04 on 980810-14.No Violations Noted. Major Areas Inspected:Operational Safety,Maint & Surveillance,Transportation & follow-up of Open Items from Previous Insps ML20236R2841998-07-17017 July 1998 Insp Rept 70-1257/98-03 on 980615-19.Violations Noted.Major Areas Inspected:Selected Aspects of Operational Safety, Radiation Protection,Radioactive Waste Handling & Storage ML20236R2741998-07-17017 July 1998 Notice of Violation from Insp on 980615-19.Violation Noted: Operational Safety Activities Not Implemented Iaw/Documented Standard Operating Procedures Appropriate to Circumstances in Listed Examples PNO-IV-98-022, on 980605,notified Nrc,Region IV That Mfg Sciences Corp Had Returned Shipment of Zirconium Cladding After Discovery of Two Unirradiated Fuel Pellets within Cladding.Nrc Region IV Will Perform follow-up Review1998-06-0505 June 1998 PNO-IV-98-022:on 980605,notified Nrc,Region IV That Mfg Sciences Corp Had Returned Shipment of Zirconium Cladding After Discovery of Two Unirradiated Fuel Pellets within Cladding.Nrc Region IV Will Perform follow-up Review ML20248K0011998-06-0202 June 1998 Insp Rept 70-1257/98-02 on 980413-17 & 980504-08.No Violations Noted.Major Areas Inspected:Operational Safety, Radioactive Effluents & Environ Protection PNO-IV-98-017A, on 980415,licensee Conducted Conducted Briefing of Region IV & Headquarters Staff on Details of Fire.Location & Matls Involved in Fire,Described in Original Preliminary Notification of Event or Unusual Occurrence1998-04-16016 April 1998 PNO-IV-98-017A:on 980415,licensee Conducted Conducted Briefing of Region IV & Headquarters Staff on Details of Fire.Location & Matls Involved in Fire,Described in Original Preliminary Notification of Event or Unusual Occurrence PNO-IV-98-017, on 980415,licensee Reported to NRC Operations Ctr That Fire Had Occurred in Handling Area of UO2 Bldg.Fire Initially Quelled w/CO2 & Then Extinguished W/Small Amount of Water.Licensee Scheduled to Conduct Briefing W/Nrc1998-04-15015 April 1998 PNO-IV-98-017:on 980415,licensee Reported to NRC Operations Ctr That Fire Had Occurred in Handling Area of UO2 Bldg.Fire Initially Quelled w/CO2 & Then Extinguished W/Small Amount of Water.Licensee Scheduled to Conduct Briefing W/Nrc ML20217J8671998-04-0101 April 1998 Insp Rept 70-1257/98-201 on 980313-19.Violations Noted.Major Areas Inspected:Open Item Resolution,Configuration Mgt & Flowdown of Analytical Limits & Controls ML20203K3731998-02-24024 February 1998 Insp Rept 70-1257/98-01 on 980126-30.No Violations Noted. Major Areas Inspected:Review of Mgt Organization & Controls, Operational Event Review & Feedback,Operator Training & Qualification & Selected Aspects of Operational Safety ML20198S4961998-01-16016 January 1998 Notice of Violation from Insp on 971215-19 & 971222-24. Violation Noted:On 971218,licensee Discovered That U Compounds Other than Oxide Pellets Were Being Stored in Temporary Storage Locations ML20198S5181998-01-16016 January 1998 Insp Rept 70-1257/97-07 on 971215-19 & 971222-24.Violations Noted.Major Areas Inspected:Ep,Operations & Followup on Open Items from Previous Insps ML20199B9431997-11-0707 November 1997 Insp Rept 70-1257/97-202 on 971006-10.Violation Noted.Major Areas Inspected:Criticality Safety Analyses,Chemical Safety Assessment,Chemical & Criticality Safety Controls,Active Engineering Controls & Administrative Controls Flowdown ML20199B9341997-11-0707 November 1997 Notice of Violation from Insp on 971006-10.Violation Noted: April 1977 Loss of Moisture Control Incident at Dry Conversion Pilot Plant Was Not Adequately Reviewed & Appropriate Corrective Actions Were Not Taken ML20217G9641997-10-0808 October 1997 Insp Rept 70-1257/97-06 on 970915-19.No Violations Noted. Major Areas Inspected:Selected Aspects of Operations & Radiation Protection PNO-IV-97-053, on 970917,Siemens Nuclear Corp Reported Discovery of Damp U Dioxide Matl in Transfer Line in Dry Conversion Pilot Facility Sample Analyses of Pyrohyrolysis Vessel.Licensee Rept Made,Per NRC Bulletin 91-0011997-09-18018 September 1997 PNO-IV-97-053:on 970917,Siemens Nuclear Corp Reported Discovery of Damp U Dioxide Matl in Transfer Line in Dry Conversion Pilot Facility Sample Analyses of Pyrohyrolysis Vessel.Licensee Rept Made,Per NRC Bulletin 91-001 ML20216J0851997-09-12012 September 1997 Notice of Violation from Insp on 970731.Violation Noted: on 970413,RL Rumley,Lead Operator,Defeated Breathing Zone Air Sampler by Placing Rubber Glove Over Air Sampler at Respective Work Station ML20198H4171997-09-0505 September 1997 Insp Rept 70-1257/97-201 on 970804-08.No Violations Noted. Info Re Major Areas Inspected Withheld,Per 10CFR2.790(d) ML20141K5781997-05-23023 May 1997 Notice of Violation from Insp on 970414-18,23,24 & 0501. Violation Noted:On 960603,licensee Shipped 405 NT-IX Shipping Packages Containing Fissile Matl W/O Installing Cushioning Matl ML20141K5791997-05-23023 May 1997 Insp Rept 70-1257/97-04 on 970414-18,23,24 & 0501.Violations Noted.Major Areas Inspected:Operations,Radioactive Effluent Discharges,Environ Protection,Solid Radioactive Waste Mgt & Transportation of Radioactive Matls ML20137P1301997-04-0404 April 1997 Insp Rept 70-1257/97-03 on 970303-07.No Violations Noted. Major Areas Inspected:Aspects of Plant Operations, Engineering,Maint & Surveillance Testing ML20136C1611997-03-0707 March 1997 Insp Rept 70-1257/97-02 on 970210-12.No Violation Noted. Major Areas Inspected:Physical Security Plan,Safeguards Events,Fixed Site Physical Protection of Special Nuclear Matl of Low Strategic Significance & Insp Folloup Item ML20134C7241997-01-30030 January 1997 Notice of Violation from Insp on 970106-10.Violation Noted: Field Change Made Under Open ECN (No.5533L) & Not Documented or Included W/Ecn Package Prior to Startup Approval on 960806 ML20134C7331997-01-30030 January 1997 Insp Rept 70-1257/97-01 on 970106-10.Violation Noted.Major Areas Inspected:Mgt Organization & Controls,Operator Training & Qualification,Plant Operations & Engineering PNO-III-97-004, on 970124,truck Carrying Four U Hexafluoride Cylinders in Accident Occurred.Truck Transporting Cylinders from Portsmouth Gaseous Diffusion Plant to Siemens Power Corp in Richland,Washington1997-01-24024 January 1997 PNO-III-97-004:on 970124,truck Carrying Four U Hexafluoride Cylinders in Accident Occurred.Truck Transporting Cylinders from Portsmouth Gaseous Diffusion Plant to Siemens Power Corp in Richland,Washington ML20133D0231997-01-0303 January 1997 Notice of Violation from Insp on 961202-05.Violation Noted: Licensee Failed to Update Posted Criticality Safety Limit Card for UF6 Cylinder Wash Operation to Reflect Change in CCS Limit ML20133D0291997-01-0303 January 1997 Insp Rept 70-1257/96-206 on 961202-05.Violations Noted. Major Areas Inspected:Fuel Fabrication Facility in Richland,Wa,Activities Associated W/Planned Startup of New Dry Conversion Facility & Review of Hq Insp Procedure 88015 PNO-IV-96-066, on 961211,licensee Notified Nrc,Walnut Creek Field Ofc of Electrical Fire & Partial Loss of Site Power. Licensee Formed Incident Investigation Board to Review Event.State of Wa Will Be Informed1996-12-12012 December 1996 PNO-IV-96-066:on 961211,licensee Notified Nrc,Walnut Creek Field Ofc of Electrical Fire & Partial Loss of Site Power. Licensee Formed Incident Investigation Board to Review Event.State of Wa Will Be Informed ML20135D8221996-12-0505 December 1996 Insp Rept 70-1257/96-205 on 961104-07.No Violations Noted. Details Withheld ML20134K8161996-11-12012 November 1996 Insp Rept 70-1257/96-04 on 961021-25.Violations Noted.Major Areas Inspected:Emergency Preparedness,Fp,Followup on Licensee Events & Followup on Open Item from Previous Item ML20134K7921996-11-12012 November 1996 Notice of Violation from Insp on 961021-25.Violation Noted: as of 961022,licensee Had Not Calibrated Three Sets of direct-reading Dosimeters Maintained for Er Since 950918,for Two Sets & Since 950725,for the Third Set ML20149H4581994-11-10010 November 1994 Notice of Violation from Insp on 940926-30 & 1012-14. Violations Noted:Licensee Did Not Provide Training to Operators Relative to Modification or Evaluate Need to Revise Operating Procedures Prior to Restarting Sys ML20149H4771994-11-0202 November 1994 Insp Rept 70-1257/94-06 on 940926-30 & 1012-14.Violations Noted.Major Areas Inspected:Review Circumstances Re 940918 Event,Involving Spill of Approx 41 Kg of Low Enriched U Dioxide Power ML20058H9321993-11-22022 November 1993 Insp Rept 70-1257/93-12 on 931101-05.No Violations Noted. Major Areas Inspected:Fire Protection & Followup on Items of Noncompliance,Inspector Followup Items & NRC Info Notices ML20058D4261993-10-17017 October 1993 Insp Rept 70-1257/93-11 on 930908 & 0927-1001.No Violations or Deviations Noted.Major Areas Inspected:Criticality Safety,Operations & Followup on Open Items ML20057C5041993-08-26026 August 1993 Insp Rept 70-1257/93-10 on 930812.No Violations Noted.Major Areas Inspected:Announced Insp to Obtain Info on Licensee Employee Concerns Program ML20056E4111993-08-0808 August 1993 Insp Rept 70-1257/93-09 on 930726-30.Violations Noted But Not Cited.Major Areas Inspected:Maint/Surveillance Testing, Radiation Protection,Criticality Safety/Operations Review, Environ/Waste Mgt & Followup on Open Items ML20056E9041993-08-0404 August 1993 Insp Rept 70-1257/93-08 on 930628-0702.No Violations Noted. Major Areas Inspected:Review Licensee Emergency Preparedness Program & Followup on Open Items ML20056C8711993-07-0707 July 1993 Insp Rept 70-1257/93-07 on 930614-18.No Violations Noted. Major Areas Inspected:Environ Protection,Radwaste Mgt, Onsite Followup of Licensee Events & Followup on Open Items ML20056C8411993-07-0202 July 1993 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $12,500.Noncompliance Noted:Ecn Not Used for Mod of Discharge Tube of Feed Hoppers on All Four Blenders by Installing Interlocks for Direct Control of Discharges 1999-08-25
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Docket No.: 70-1257 License No.: SNM-1227 Report No.: 70-1257/99-202 Licensee: Siemens Power Corporation Location: Richland, Washington 99352 Inspection Dates: August 2 - 5,1999 Inspectors: Dennis Morey, Criticality Safety Inspector, NRC llQ Sheryl Burrows, Criticality Safety inspector, NRC llQ Jeremy Smith, Criticality Safety Specialist, NRC IIQ Douglas Outlaw. Contractor, S AIC Approved By: Philip Ting, Chief Operations Branch Division of Fuel Cycle Safety And Safeguards Enclosure 9908250124 990819 PDR ADOCK 07001257 C PDR
2 SIEMENS POWER CORPORATION NRC INSPECTION REPORT 70-1257/99-202 EXECUTIVE SUMM ARY Introduction The Nuclear Regulatory Commission (NRC) perfonned a routine, announced criticality safety inspection at Siemens Power Corporation (SPC) located in Richland, Washington, from August 2 - 5,1999. The inspection focused on plant operations, criticality safety training, administrative controls, internal audits, internal reporting of nuclear criticality safety (NCS) .
infractions, and the criticality safety function. The inspectors reviewed documents, interviewed plant staff, and conducted walkdowns of affected plant areas.
During the inspection, the inspectors opened one IFI, closed three open items from previous inspections, and identified a weakness in the location of computerized training for operation employees.
Results The inspectors observed that the licensee used a high percentage of temporary employees in fissile material but no safety concerns attributable to the practice were identified.
Two minor process area infractions identified by the inspectors were immediately and effectively corrected by the iicensee.
The training program at SPC is adequate to provide new and existing employees a firm grasp of criticality safety concerns, limits, and responsibilities.
The location for the personal computer (PC) based training is inadequate. SPC has a new training classroom in a different location slated for construction later this year.
The inspectors determined that administrative controls for criticality safety and the overall scheme ofimplementation at the Siemens plant meets license requirements.
The inspectors determined that the internal audit program at SPC is adequate to assure compliance with NCS controls and limits.
The inspectors found that the SPC system for reporting, reviewing, and resolving internal criticality safety discrepancies met license and NRC Bulletin 91-01 requirements.
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3 The inspectors determined that licensee assumptions and controls for fire fighting in the Dry Conversion Area moderator exclusion area were adequate.
The inspectors determined that licensee cross-indexing of controls was a good management practice.
The inspectors noted that SPC had developed an excellent system for documenting physical dimensions important to criticality safety.
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4 REPORT DETAILS 1.0 Plant Operations
- a. Scope ofInspection The inspectors reviewed ongoing fissile material operations throughout the licensee facility and conducted informal interviews with operators and engineers regarding equipment, processes, and safety requirements.
- b. Observations and Findings The inspectors performed extensive walkdowns at the UO 2 facility including the uranium recovery area, dry conversion area, powder blending area, pellet forming area, rod loading area, and fuel bundle assembly area. The inspectors also performed walkdowns at the Engineering Laboratory and Office Facility, Warehouse #7, Modular Extraction Facility, and Lagoon Uranium Recovery / Solids Processing Facility.
The inspectors noted that the licensee is in the midst of a very heavy work cycle due to multiple contracts requiring simultaneous efTorts and that extensive activity was taking place in all production areas. The inspectors noted that the quantities of ma:erial in process appeared to be well within the capability of the facility. The inspectors were infonned that the licensee has made extensive use of temporary employees in production areas in order to support the increased workload. Very high percentages of temporary employees were being used in some production areas; for example,43% of the employees in the ceramics area during the day shift were temporary. The inspectors did not identify any safety concerns regarding the high reliance on temporary employees.
During a walkdown in the uranium recovery area, the inspectors observed a vinyl posting on overflow lines for fissile material systems. Tne posting stated that the line was to be kept clear at all times. The inspectors noticed that the overflow line for the Room 240 pellet dissolver lag tank (a safe geometry slab tank) did not have a posting. The licensee stated that this was a fissile system, and a sign was required. The licensee installed the required posting prior to completion of the inspection. The inspectors noted that this appeared to F>e an isolated incident.
The inspectors noted that used vacuum filter canisters are stored in positions designated by a metal frame on the floor at various locations in the facility. These locations are marked with a one-foot spacing line painted on the floor around the storage location.
Analytically, the filter canisters are treated as a fully moderated sub-critical unit which must be spaced at least one foot from other similar units. The inspectors observed a combustible trash container with fissile material bearing trash place inside the one-foot line. These trash containers are also considered fissile units under the license analysis.
5 The licensee immediately moved the can and contacted operators. The licensee determined that the canister did not contain any fissile material so no safety limit had been exceeded. Operators were subsequently briefed on all shifts that the combustible material containers were fissile units and should not be placed within one foot of other fissile units. The licensee acknowledged that if the canister had cc.ntained fissile material, the inspectors would have considered this a potential violation.
- c. Conclusions The inspectors observed that the licensee used a high percentage of temporary employees in fissile material but no safety concerns attributable to the practice were identified. Two minor process area infractions identified by the inspectors were immediately and effectively corrected by the licensee.
2.0 Criticality Safety Training
- a. Scope ofInspection f
The inspectors reviewed the criticality employee training program for content and applicability. The inspectors reviewed employee training records and observed in-process training.
- b. Obsenations and Findings The inspectors interviewed SPC training staff and determined that the staff had a good understanding of criticality safety and its importance in the workplace. The inspectors determined that the licensee lesson plans for training classes were comprehensive and adequate to give a new employee a good understanding of what criticality safety is, the associated dangers, limits and controls, and the necessary actions to take in an abnormal situation.
The inspectors noted that a large portion of the required entry and annual criticality safety training is performed on one of several personal coreputers dedicated to employee training. The inspectors determined that the layout of the PC based training and its '
coverage ofcriticality safety was good. Employees must score 80% or better on the general criticality safety examination, and 100% on the site-specific criticality safety examination before they are allowed to work at SPC. Additional work station specific criticality safety training is required for certain tasks. PC based training results are saved and maintained by the licensee training department along with adequate backups of all training records.
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6 Although training was determined to be adequate, the inspectors observed that the computer based training was located in an open operations area with a high activity level such as loudspeaker announcements, personnel walking by, talking, and so on. The inspectors determined and the licensee acknowledged that the area was not ideal for training. The licensee stated that a new and more suitable area had been identified for the training and was pending construction.
- c. Conclusions The training program at SPC is adequate to provide new and existing employees an adequate understanding of criticality safety concems, limits, and responsibilities. The inspectors detemiined that the location of the PC based training is inadequate. SPC has a new training classroom slated for construction later this year in a different location.
3.0 Administrative Controls
- a. Scope ofInspection The inspectors conducted a review of the implementation scheme fbr criticality safety administrative controls. The objective was to characterize the flow-down from the higher level Nuclear Criticality Safety Analysis (CSAs) to the applicable training, procedures and postings used at the facility for nuclear criticality safety controls.
- b. Observations and Findings The inspectors reviewed selected CSAs and observed that in each case there was a clear and documented link to a Criticality Safety Specification (CSS). The inspectors observed plant wide and system specific CSSs which implement CSA required controls. All CSAs are available on-line and are cross-indexed by specific controls to plant procedures for operations, preventative maintenance (such as cheel;ing interlocks), and repetitive maintenance (such as instrument calibrations). The inspectors also noted that time licensee cross-references NCS controls to operation and preventive maintenance using a common number so that controls may be quickly traced to their analytical basis. The inspectors determined that licensee cross-indexing of controls was a good management practice. <
Licensee postings include Criticality Safety Limit Cards and Criticality Safety Instruction Cards. Intemal audits and walkdowns are conducted to determine where postings should be placed. Licensee staffindicated that postings are not relied upon as a criticality safety control on their own. The licensee considers operating procedures and training as the primary administrative controls. Posted limits simply summarize key requirements for the benefit of operators.
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CSS P67-001," General Criticality Safety Guide Rules, Workstation Specific Training, and Recovery Actions" was reviewed. This specification requires workstation specific criticality safety refresher training at least quarterly which includes all applicable CSSs and postings. For less complicated processes, all CSSs and postings are covered quarterly. For more complex operations, topics are staggered so that different subject matter is reviewed quarterly, but all applicable material is covered each year. The inspectors examined training records for this training, and the facility was detennined to be in compliance with license requirements.
- c. Conclusions The inspectors determined that administrative controls for criticality safety and the overall scheme ofimplementation the Siemens plant meets license requirements. The
, reference to all procedures contained in the Criticality Safety Specifications was noted as a good practice.
4.0 Internal Audits a Scope ofInspection Inspectors reviewed the internal audits of plant operations by licensee criticality safety staff to determine compliance with license requirements.
- b. Observations and Findings The licensee performs internal audits in accordance with written procedures. The frequency ofinternal audits for various systems are spelled out on specification sheets, and each frequency is based on the safety significance of each system, not to exceed two years. This frequency is dynamic such that a low frequency area that has shown to be of concern will have its audit frequency increased. Internal audits include a review of previous audits to identify probable reas of ec,ncern, a review of the specification sheets, a posting check, and a preventative maintenance check. In addition, personnel re::ponsih!e far internal audits are rotated for each specific area audit to allow a different perspective as well as to ensure that every member of the criticality staffis cross trained i
in all areas.
The inspectors observed that the licensee identified substantive issues, reported as j required, and took timely, effective corrective actions. The inspectors detennined that for all new prouisses undertaken at SPC, a "Startup Council" is formed consisting of the subject experts to review every aspect of the system before startup, and always includes at least one representative from the criticality safety section.
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- c. Conclusions The inspectors determined that the internal audit program at SPC is adequate to assure compliance with NCS controls and limits.
5.0 Internal NCS Infraction Reporting
- a. Scope ofInspection The inspectors reviewed the system for reporting, reviewing, and resolving internal criticality safety discrepancies to confirm that the sv ; tem met license requirements and that incider.ts meeting the requirements of NRC Bul etin 91-01 were reported. The inspectors also reviewed the documentation of 41 incidents that had occurred to date in 1999 to verify that requirements were being followed and to determine whether adverse trends could be noted. I
- b. Observations and Findings l The inspectors determined that the licensee kept notebooks of criticality safety l occurrences. The licensee notebooks had the complete documentation files for each event. The inspectors reviewed both the 1998 and 1999 notebooks and determined that they adequately documented events in accordance with requirements of the I fcense and I the SPC Nuclear Criticality Safety Standards (EMF-30, Ch. 3, Section 11). For each event, the licensee had completed a Criticality Safety Corrective Action Report documenting the event and corrective actions needed. If an event was determined by the SPC criteria to be potentially reportable to the NRC, a separate evaluation was included that documented the basis for the decision on whether to report the incident. The inspectors determined that this system was adequate and met the requirements of the ;
license, as implemented by the SPC safety standards.
The inspectors reviewed the 4) incidents identified from January through July 1999 in more detail. The evaluations of reportability under NRC Bulletin 91-01 were reviewed, and in each case, were determined to no: be reportable. At least two unlikely additional failures were identified as necessary for a potential criticality.
The inspectors also reviewed the 1999 incidents and correctis e action reports to determine if corrective actions were adequate and were being implemented. The inspectors determined that corrective actions identified by the licensee appeared adequate to correct the immediate situation and generally attempted to prevent recurrence elsewhere. The files in the notebooks were sufficient to indicate progress in completing corrective actions.
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9 Corrective actions are also tracked in the licensee Manufacturing Regulatory Commitment Tracking System. The inspectors reviewed current list ofcriticality safety related open items to confirm progress in completing 1998 and 1999 corrective actions.
Progress indicated by the licensee was determined to be adequate by the inspectors.
The inspectors reviewed the 1999 incidents and corrective action reports to determine if the types of events occurring indicated adverse safety trends or could be precursors of future problems. The inspectors determined that the events were principally self reported by operations staff. The inspectors determined that the reports indicated that the incidents being reported were generally minor and random. The inspectors did not l
identify any systematic trends. In all cases reviewed by the ir.spectors, multiple unlikely '
controls remained in place to prevent a criticality.
The inspectors determined that the licensee criticality safety staff maintained a database of criticality safety inciden!s and used that database to track and trend incidents for review by licensee criticality safety staff and management. The trending data for 1993-1999 indicated a general correlation on numbec ofincidents with production rates with no other adverse trends.
- c. Conclusions The inspectors found that SPC system for reporting, reviewing, and resolving internal criticality safety discrepancies met license and NRC Bulletin 91-01 requirements. The inspectors did not find any adverse safety trends from reviewing the documentation on the 1999 criticality safety-related incidents.
6.0 Criticality Safety Function
- a. Scope ofInspection ;
The inspectors reviewed criticality safety assumptions and controls related to emergency
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operations in the dry conversion facility,
- b. Observations and Findings The inspectors noted that the pre-fire plan for the dry conversion facility restricts j firefighting methods in the powder preparation area to high expansion foam, CO2 , and dry chemicals. The Richland Fire Department maintains a copy of the pre fire plan at the -
. Central Fire Station but does not possess high-expansion foam or application equipment.
l The licensee stated that the pre-fire plans firefighting methods are not requirements but l are limitations on methods. After interviewing fire department and SPC safety staff, the inspectors determined that this was a common understanding of the pre-fire plan. i
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10 The inspectors reviewed assumptions in the Dry Conversion Area (DCA) CSA D830 to ensure that the assumptions corresponded to field conditions. The inspectors noted that the licensee had claimed that a fire occurring in the DCF was unlikely, The inspectors then observed that the goveming CSA did not call out a control restricting the introduction of combustibles iinto the facility. Combustibles were controlled in the Criticality Safety Specifications (CSS) for the facility due to the requirement being called l out in other related CSAs. The licensee stated that failure to list the control was an l oversight in the process of upgrading the affected CSA, and the requirement would be
( incorporated into a pending revision of the CSA. Incorporation of CSA controls on the l
introduction of combustibles into the DCF will be tracked as Inspector Followup Item (IFI) 70-1257/99-202-01. Prior to the completion of the inspection, the licensee demonstrated that the control had been inserted into a pending revision of the affected CSA.
l The inspectors noted that SPC had developed an excellent system for documenting !
physical dimensions important to criticality safety. This system allows both engineering i and criticality safety staff to quickly and simply determine whether a physical dimension l of an item or spacing is important to criticality safety. This safety system is significantly more efficient than typical industry practice.
- c. Conclusions t
The !nspectors determined that licensee assumptions and controls for fire fighting in the Dry Conversion Area moderator exclusion area were adequate. The inspectors identified a CSA that failed to call out a control which would be expected in order to justify an assumption.
7.0 Open Items 70-1257/98-201-02 This item tracks licensee actions to upgrade CSAs to a new format. The inspectors reviewed licensee actions and determined that the licensee has not completed all scheduled CSA upgrades. This item remains open.
70-1257/98-204-01 This item track.s the uniform implementation of facility-wide criticality safety limits.
There is an administrative control required by Criticality Safety Specification (CSS) P67, 253 that requires a 12-inch edge-to-edge spacing between carts to transport finished pellets and other fissile materials. This 12-inch spacing is defined by red tape or painted red lines. The inspector observed an empty (therefore no fissile material) cart inside the red line. The original concern was that the carts should never cross the line unless
I1 material was being added to that station / array and an administrative control was being violated. Since the cart was empty, i.e. no fissile material, the fact that a cart was across a red line was not in violation of any limit or control. However, this is not a good practice.
In a follow-up during this inspection, the inspector did not notice any empty carts inside of the red lines. Additionally, when ceramic operations workers were asked about the red lines, they indicated that they would never cross a red line tvith a cart unless it was empty and in transport and would never leave an empty cart inside of a red line. The inspector questioned the shift supervisor, an operator who works for Siemens, and a manpower worker (non-Siemens employee) who was relatively new to the operation. The contract operator indicated that there was no circumstance where he would cross a red line with a cart. The other operators, including the shift supervisor, indicated that if a cart was empty and in transit it could cross the line, but in no other case. The facility has 64 facility-wide CSSs that can be traced backward to the Criticality Safety Analysis (CSAs) and forward to administrative contmis. The plant wide criticality safety controls appear to be implemented uniformly iesed on a document review, a plant walkdown, and interviews with plant personnel. While this item will be closed, the inspectors agree that leaving an empty cart inside the red line is a poor practice. This does not to appear to be a common practice and was not observed during the current inspection. This item is closed.
70-1257/98-204-02 VIO 70-1257/98-204-02 concerned the failure of an operator to visually verify that any equipment disassembled was free from visible uranium before staging it with other disassembled equipment. The inspectors reviewed the immediate and long-term actions taken by the licensee to correct this problem. The actions taken included a formal SPC incident Investigation Board that identified the root causes of the incident as " Procedures Not Followed,"" Communications / Tumover Less Than Adequate," and '
" Training / Understanding Less Than Adequate." Review of the report from this board indicated that the root cause analysis was adequate. Each of the corrective actions identified by the SPC Incident Investigation Board and reported to the NRC in the January 12,1999, reply to the NOV was reviewed and verified to be adequate.
Corrective actions included rework of the ductwork to facilitate visual inspections, review of other portions of the plant for similar situations, and institution of pre-job briefings on ,
all non-routine maintenance activities that require a Maintenance Work Permit. All corrective actions are now complete, and no safety issues remain. This item is closed.
70-1257/98-204-03 This item tracks the licensee commitment to upgrade the validation report. The licensee has not initiated SCALE 4.4 implementation. Licensee has further committed to prepare tables for the heterogeneous cases in the SCALE 4.4 validation report. This item remains open.
12 70-1257/98-204-04 This item tracks the licensee commitment to revise internal 91-01 reporting requirements.
Review of the modified procedure EMF-30, " Reporting Criticality Safety Violations, Incidents, and Emergencies," Appendix 11, " Conditions that require reporting to the NRC," showed that adequate modifications to the procedure have been implemented.
Upon review of the subsequent NRC reportability determination reports, one report
(#99-036) was found to contain an error in implementing this methodology of reportability determination. The error did not effect the original determination and is not cited as a violation. The inspectors reviewed the modified reportability procedure and found it to be adequate to close out the open item. The nuclear criticality staffis reviewing the error found above and will take corrective actions. This item is closed.
8.0 Management Meetings The inspectors met with SPC management periodically during the inspection. The inspectors presented the inspection scope and findings to members oflicensee staiTat the conclusion of the inspection on August 5,1999. The licensee acknowledged the findings presented.
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ITEMS OPENED. CLOSED. AND DISCUSSED )
Opened i
l IFI 70-1257/99-202-01 Tracks licensee actions to incorporate required controls into a I CSA.
l l Closed IFI 70-1257/98-204-01 Tracked licensee actions to achieve uniform implementation of j facility-wide criticality safety limits.
l VIO 70-1257/98-204-02 Concerned the licensee failure to adequately control decommissioning operations.
IFl 70-1257/98-204-04 Tracked licensee correction of NRC Bulletin 91-01 reporting requirements.
Discussed IFI 70-1257/98-201-02 Tracks licensee action to upgrade older CSAs to the more rigorous standards of recent CSAs. I IFI 70-1257/98-204-03 Tracks licensee development of a new validation report.
l PARTIAL, LIST OF PERSONS CONTACTED Bernard Femreite Vice President, Manufacturing Bernie Bently Manager, Operations Loren Maas Manager, Regulatory Compliance JeffDiest Criticality Safety Cal Manning Criticality Safety Andy McGehee Criticality Safety Tom Probasco Manager, Safety Marilyn Law Manager, Analytical Services Ray Vaughan Manager, Safety and Licensing
A 14 ACRONYMS USED CO 2 Carbon dioxide CSA Criticality safety analysis CSS. Criticality safety specification DCF Dry Conversion Facility IFI Inspector Followup Item NCS nuclear criticality safety NOV Notice of Violation PC personal computer SCALE computer' code package SPC. Siemens Power Corporation UO 2 Uranium dioxide
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