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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7681999-10-19019 October 1999 Forwards Insp Rept 50-458/99-12 on 990822-1002.Four Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy RBG-45125, Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams1999-10-18018 October 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams ML20217J3751999-10-15015 October 1999 Informs That Applicable Portions of NEDC-32778P, Safety Analysis Rept for River Bend 5% Power Uprate, Marked as Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) IR 05000458/19990071999-10-0505 October 1999 Refers to Util Ltr Re Apparent Violations Described in Insp Rept 50-458/99-07 Issued on 990804 & Forwards Nov.Insp Described Two Apparent Violations Related to River Bend Station Division I EDG RBG-45123, Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required1999-09-30030 September 1999 Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required RBG-45124, Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl1999-09-24024 September 1999 Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl RBG-45122, Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-471999-09-23023 September 1999 Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-47 RBG-45113, Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp1999-09-21021 September 1999 Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp ML20212D8901999-09-16016 September 1999 Discusses 6 Month Review of Plant Midcycle Ppr.Advises of Plans for Future Insp Activities.Forwards Historical Listing of Plant Issues,Referred to as PIM ML20216F7881999-09-15015 September 1999 Forwards Insp Rept 50-458/99-10 on 990830-990903.No Violations Noted.Insp Covered Licensed Operators Requalification Training Program & Observation of Requalification Activities 05000458/LER-1998-003, Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents1999-09-0909 September 1999 Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents ML20211Q7721999-09-0909 September 1999 Expresses Appreciation for ,In Response to NRC 990702 Re Denial of Notice of Violation Cited in Concerning Insp Rept 50-458/98-16.Reply Found to Be Responsive to Concerns Raised in NOV RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted1999-09-0808 September 1999 Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted ML20211Q3921999-09-0808 September 1999 Forwards Insp Rept 50-458/99-08 on 990711-0821.One Violation Being Treated as Noncited Violation ML20211Q5541999-09-0808 September 1999 Discusses Meeting Conducted on 990830 in St Francisville,La Re Overall Performance Issues During 990403-0703 Refueling/ Maintenance Outage.Due to Proprietary Nature of Some Subject Matters,Meeting Closed to Public.Attendance List Encl ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) RBG-45095, Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status1999-09-0707 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status RBG-45097, Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves1999-08-31031 August 1999 Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves RBG-45094, Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation1999-08-25025 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation ML20211E2071999-08-23023 August 1999 Discusses Insp Rept 50-458/99-07 in Which 2 Violations Were Identified & Being Considered for Escalated Enforcement Action.Response Should Be Submitted Under Oath or Affirmation ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 RBG-45093, Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept1999-08-17017 August 1999 Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept ML20211A9291999-08-17017 August 1999 Forwards Insp Rept 50-458/99-11 on 990719-23.Areas Examined Included Portions of Licensee Physical Security Program. No Violations Noted ML20210T8881999-08-16016 August 1999 Forwards Replacement Pages 9-18 for Insp Rept 50-458/99-09, Issued on 990730 IR 05000458/19980101999-08-13013 August 1999 Forwards Summary of 990805 Mgt Meeting with Licensee in Arlington,Tx Re Radiological Control Problems Noted in Insp Repts 50-458/98-10 & 50-458/99-04.With Attendance List & Licensee Presentation ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210U3751999-08-12012 August 1999 Informs That Info Contained in Presentation, River Bend Station Fuel Recovery Project,Dtd 990622, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20210Q7691999-08-11011 August 1999 Forwards Request for Addl Info Re Licensee River Bend Individual Plant Exam External Events,Under GL 88-20,suppl 4,dtd 910628 ML20210R4591999-08-10010 August 1999 Ack Receipt of Which Transmitted Plant Emergency Plan,Rev 20 Under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required,Based on Determination That Changes Does Not Decrease Effectiveness of EP ML20210N1641999-08-0404 August 1999 Forwards Insp Rept 50-458/99-07 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210K4641999-08-0303 August 1999 Forwards SE Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Power-Operated Gate Valves, Issued on 950817 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K1351999-07-30030 July 1999 Forwards Insp Rept 50-458/99-09 on 990510-28 with in-office Insp Until 990701.Three Violations Being Treated as Noncited Violations ML20210J9691999-07-30030 July 1999 Discusses 990719 Meeting with Util in Arlington,Tx Re Region IV Staff Findings of Root Cause Investigation Into Fuel Cladding Failures That Occurred During Recent Cycle 8 Operation.List of Attendees & Organization Chart Encl RBG-45072, Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL1999-07-23023 July 1999 Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL ML20210E9001999-07-23023 July 1999 Informs That as Result of Staff Review of Licensee Responses to GL 92-01,rev 1,Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 RBG-45073, Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl1999-07-20020 July 1999 Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl RBG-45071, Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl1999-07-19019 July 1999 Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl 05000458/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 11999-07-15015 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 1 ML20196L0501999-07-0606 July 1999 Informs That NRC Insp Rept 50-458/99-03 Issued on 990519 with Errors in Tracking Numbers Assigned to Seven Noncited Violations & Error Re Actual Location of SRO During Refueling Activities.Revised Pages 2 & 4 Encl ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl ML20196K6851999-06-30030 June 1999 Ack Receipt of & Denial of NOV in Response to Transmitting NOV & Insp Rept 50-458/98-16.Listed Info Documents Results of Review of Response to Violation Re fire-induced Circuit Faults ML20196K0671999-06-30030 June 1999 Forwards Insp Rept 50-458/99-04 on 990412-16 & 28-29.Five Violations of NRC Requirements Occurred & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy.Meeting Scheduled for 990726 RBG-45048, Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept1999-06-29029 June 1999 Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept RBG-45047, Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output1999-06-29029 June 1999 Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output ML20196H5171999-06-21021 June 1999 Requests Withholding of Info Being Presented in Meeting of Entergy,General Electric & NRC Staff.Licensee Requested Meeting with NRC to Present Info on Recent Anomalous Conditions Found During Insp of Fuel Bundles.W/Affidavit 05000458/LER-1999-012, Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form1999-06-21021 June 1999 Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form RBG-45035, Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld1999-06-21021 June 1999 Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld ML20196E0601999-06-18018 June 1999 Forwards Insp Rept 50-458/99-05 on 990418-29.Four Violations Identified & Being Treated as Noncited Violations 05000458/LER-1999-011, Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-06-0909 June 1999 Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARRBG-45125, Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams1999-10-18018 October 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams RBG-45123, Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required1999-09-30030 September 1999 Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required RBG-45124, Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl1999-09-24024 September 1999 Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl RBG-45122, Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-471999-09-23023 September 1999 Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-47 RBG-45113, Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp1999-09-21021 September 1999 Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp 05000458/LER-1998-003, Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents1999-09-0909 September 1999 Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted1999-09-0808 September 1999 Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted RBG-45095, Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status1999-09-0707 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) RBG-45097, Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves1999-08-31031 August 1999 Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves RBG-45094, Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation1999-08-25025 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 RBG-45093, Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept1999-08-17017 August 1999 Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept RBG-45072, Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL1999-07-23023 July 1999 Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL RBG-45073, Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl1999-07-20020 July 1999 Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl RBG-45071, Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl1999-07-19019 July 1999 Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl 05000458/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 11999-07-15015 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 1 ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl RBG-45047, Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output1999-06-29029 June 1999 Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output RBG-45048, Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept1999-06-29029 June 1999 Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept ML20196H5171999-06-21021 June 1999 Requests Withholding of Info Being Presented in Meeting of Entergy,General Electric & NRC Staff.Licensee Requested Meeting with NRC to Present Info on Recent Anomalous Conditions Found During Insp of Fuel Bundles.W/Affidavit RBG-45035, Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld1999-06-21021 June 1999 Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld 05000458/LER-1999-012, Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form1999-06-21021 June 1999 Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form 05000458/LER-1999-011, Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-06-0909 June 1999 Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl 05000458/LER-1999-010, Forwards LER 99-010-00 for River Bend Station,Unit 1 IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-05-28028 May 1999 Forwards LER 99-010-00 for River Bend Station,Unit 1 IAW 10CFR50.73.Commitments Identified in Rept,Encl RBG-45021, Informs That Cycle 9 Operation Will Remain within MCPR Safety Limits Approved in Amend 105 to TS Issued by NRC in1999-05-26026 May 1999 Informs That Cycle 9 Operation Will Remain within MCPR Safety Limits Approved in Amend 105 to TS Issued by NRC in 05000458/LER-1999-009, Forwards LER 99-009-00 IAW 10CFR50.73.Commitments Contained in Ltr Are Identified on Commitment Identification Form1999-05-24024 May 1999 Forwards LER 99-009-00 IAW 10CFR50.73.Commitments Contained in Ltr Are Identified on Commitment Identification Form RBG-45017, Informs NRC of Addition of ASME Boiler & Pressure Vessel Code,Section Xi,Code Case N-496-1 to RBS Inservice Insp Program.Commitment Made by Util,Encl1999-05-14014 May 1999 Informs NRC of Addition of ASME Boiler & Pressure Vessel Code,Section Xi,Code Case N-496-1 to RBS Inservice Insp Program.Commitment Made by Util,Encl ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 05000458/LER-1999-007, Forwards LER 99-007-00 IAW 10CFR50.73.Commitments Identified in LER Are Noted in Attachment 11999-05-10010 May 1999 Forwards LER 99-007-00 IAW 10CFR50.73.Commitments Identified in LER Are Noted in Attachment 1 05000458/LER-1999-006, Forwards LER 99-006-00 Re Unplanned Automatic Standby Svc Water Initiation,Due to Procedure Inadequacy.Commitments Identified in Rept Noted in Attachment 11999-05-0606 May 1999 Forwards LER 99-006-00 Re Unplanned Automatic Standby Svc Water Initiation,Due to Procedure Inadequacy.Commitments Identified in Rept Noted in Attachment 1 05000458/LER-1999-005, Forwards LER 99-005-00 IAW 10CFR50.73(a)(2)(i).Commitments Identified in LER Are Noted in Attachment 11999-05-0303 May 1999 Forwards LER 99-005-00 IAW 10CFR50.73(a)(2)(i).Commitments Identified in LER Are Noted in Attachment 1 RBG-44993, Forwards RBS Annual Individual Monitoring Rept for Jan-Dec 1998,per Requirements of 10CFR20.2206(b).File Info Listed. Without Encl1999-04-30030 April 1999 Forwards RBS Annual Individual Monitoring Rept for Jan-Dec 1998,per Requirements of 10CFR20.2206(b).File Info Listed. Without Encl RBG-44998, Informs of Missing Documentation Re Examination Results Reported in RBS Owners Activity Report Forms Submitted to NRC on 9802241999-04-30030 April 1999 Informs of Missing Documentation Re Examination Results Reported in RBS Owners Activity Report Forms Submitted to NRC on 980224 ML20206E7811999-04-29029 April 1999 Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested 05000458/LER-1999-003, Forwards LER 99-003-00,per 10CFR50.73.Commitments Identified in Rept Are Noted in Attachment 11999-04-23023 April 1999 Forwards LER 99-003-00,per 10CFR50.73.Commitments Identified in Rept Are Noted in Attachment 1 RBG-44968, Submits Addl Info Re 981008 LAR 1998-02 Re Implementation of Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long- Term Solution.Clarifies Certain Aspects of Proposed Ts,Per 990406 Telcon with NRC1999-04-15015 April 1999 Submits Addl Info Re 981008 LAR 1998-02 Re Implementation of Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long- Term Solution.Clarifies Certain Aspects of Proposed Ts,Per 990406 Telcon with NRC RBG-44965, Responds to 990324 Telcon RAI Re SLMCPR Calculation Method for RBS Cycle 9 Slmcpr,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits. Proposed TS Pages, Encl1999-04-0808 April 1999 Responds to 990324 Telcon RAI Re SLMCPR Calculation Method for RBS Cycle 9 Slmcpr,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits. Proposed TS Pages, Encl RBG-44959, Withdraws 981120 LAR 1998-20,allowing Adjusting Control Pattern for Plant Startup If Outage Had Occurred Before Planned Refueling Outage.No Plant Outage Was Conducted & Plant Is Now in Eighth Refueling Outage1999-04-0808 April 1999 Withdraws 981120 LAR 1998-20,allowing Adjusting Control Pattern for Plant Startup If Outage Had Occurred Before Planned Refueling Outage.No Plant Outage Was Conducted & Plant Is Now in Eighth Refueling Outage ML20205F1781999-03-31031 March 1999 Forwards Consolidated Entergy Submittal to Document Primary & Excess Property Damage Insurance Coverage for Nuclear Sites of Entergy Operations,Inc,Per 10CFR50.54(w)(3) RBG-44939, Forwards Rbs,Unit 1 Annual Occupational Radiation Exposure Rept for 1998, Per TS 5.6.1.Rept Consists of Tabulation of Exposure for Personnel Receiving Exposures Greater than 100 Mrem Per Yr1999-03-31031 March 1999 Forwards Rbs,Unit 1 Annual Occupational Radiation Exposure Rept for 1998, Per TS 5.6.1.Rept Consists of Tabulation of Exposure for Personnel Receiving Exposures Greater than 100 Mrem Per Yr ML20196K7101999-03-26026 March 1999 Submits Reporting & Recordkeeping for Decommissioning Planning,Per 10CFR50.75(f)(1) RBG-44899, Provides Notification of Termination of Licensed Operator, AA Rouchon,License OP-42416-1,due to Resignation.Reactor Operator License Data,Listed1999-03-25025 March 1999 Provides Notification of Termination of Licensed Operator, AA Rouchon,License OP-42416-1,due to Resignation.Reactor Operator License Data,Listed ML20204G8701999-03-15015 March 1999 Responds to NOV Described in NRC Correspondance to Util ,expressing Disappointment in NRC Determination That AD Wells Deliberately Provided Incomplete & Inaccurate Info to NRC During Meeting on 971015 RBG-44925, Responds to NRC Re Violations Noted in Investigation Rept 4-97-059.Corrective Actions: Mgt Expectations for Communicating with NRC Issued to Site Personnel on 980212,by RBS Vice President,Operations1999-03-15015 March 1999 Responds to NRC Re Violations Noted in Investigation Rept 4-97-059.Corrective Actions: Mgt Expectations for Communicating with NRC Issued to Site Personnel on 980212,by RBS Vice President,Operations RBG-44924, Informs That Util Response to NOV Re Investigation Rept 4-97-059,will Be Issued by 990315,as Extended by NRC Ltr .Encl Check for $55,000 Is for Payment of Civil Penalty IAW Instructions in .Without Check1999-03-0505 March 1999 Informs That Util Response to NOV Re Investigation Rept 4-97-059,will Be Issued by 990315,as Extended by NRC Ltr .Encl Check for $55,000 Is for Payment of Civil Penalty IAW Instructions in .Without Check RBG-44912, Responds to Violations Noted in Insp Rept 50-458/98-13. Corrective Actions:Matls & Training Were Provided to Expedite Implementation of Existing Procedural Guidance to Supply Compressed Air1999-03-0303 March 1999 Responds to Violations Noted in Insp Rept 50-458/98-13. Corrective Actions:Matls & Training Were Provided to Expedite Implementation of Existing Procedural Guidance to Supply Compressed Air RBG-44904, Informs NRC of Date Change Re Commitment Made in Response to NOV 50-458/98-05-01.New Commitment Date 9912161999-02-25025 February 1999 Informs NRC of Date Change Re Commitment Made in Response to NOV 50-458/98-05-01.New Commitment Date 991216 RBG-44384, Submits Response to Fuel Cladding Defect Issues Raised in 10CFR2.206 Petition.Clear Technical Basis Exists in Info Provided by River Bend Station to Deny Petition1999-02-11011 February 1999 Submits Response to Fuel Cladding Defect Issues Raised in 10CFR2.206 Petition.Clear Technical Basis Exists in Info Provided by River Bend Station to Deny Petition ML20203C4201999-01-25025 January 1999 Submits Denial of NRC Request for Advance Info Re Concerns Raised by Ucs in 10CFR2.206 Petitions on River Bend & Perry Plants.Petitioners Were Not Required to Provide NRC with Info in Advance of Informal Public Hearings 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARRBG-33517, Responds to NRC Re Violations Noted in Vendor Interface & Procurement Team Insp Rept 50-458/89-200. Corrective Actions:Maint Instruction Index for Diesel Engine Reviewed1990-09-10010 September 1990 Responds to NRC Re Violations Noted in Vendor Interface & Procurement Team Insp Rept 50-458/89-200. Corrective Actions:Maint Instruction Index for Diesel Engine Reviewed RBG-33466, Responds to Deviations Noted in Insp Rept 50-458/90-16 on 900709-19 Re Suppression Pool Water Level.Corrective Actions:Operator Aids Will Be Developed to Inform Control Room Operators of Actual Instrument Range1990-08-30030 August 1990 Responds to Deviations Noted in Insp Rept 50-458/90-16 on 900709-19 Re Suppression Pool Water Level.Corrective Actions:Operator Aids Will Be Developed to Inform Control Room Operators of Actual Instrument Range RBG-33460, Forwards Certified Cash Flow Statements for Guarantee of Funds in Event of Retrospective Call Under Secondary Financial Protection Program,Per 10CFR140.211990-08-28028 August 1990 Forwards Certified Cash Flow Statements for Guarantee of Funds in Event of Retrospective Call Under Secondary Financial Protection Program,Per 10CFR140.21 RBG-33496, Advises That KT Allbritton No Longer Needs to Maintain License for Facility Due to Termination of Employment1990-08-28028 August 1990 Advises That KT Allbritton No Longer Needs to Maintain License for Facility Due to Termination of Employment RBG-33450, Forwards Rev 3 to River Bend Station Updated Fsar. Rev Covers Period 890301-9003011990-08-28028 August 1990 Forwards Rev 3 to River Bend Station Updated Fsar. Rev Covers Period 890301-900301 RBG-33424, Requests That Proposed Tech Spec 3.0 & 4.0,when Approved,Be Issued as Effective Immediately W/Implementation to Be Completed by 9009291990-08-22022 August 1990 Requests That Proposed Tech Spec 3.0 & 4.0,when Approved,Be Issued as Effective Immediately W/Implementation to Be Completed by 900929 RBG-33406, Forwards Rev 6 to Safeguards Contingency Plan.Rev Withheld (Ref 10CFR73.21)1990-08-17017 August 1990 Forwards Rev 6 to Safeguards Contingency Plan.Rev Withheld (Ref 10CFR73.21) RBG-33372, Forwards Semiannual Rept on fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d).No Weaknesses in Program Identified1990-08-10010 August 1990 Forwards Semiannual Rept on fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d).No Weaknesses in Program Identified RBG-33310, Responds to NRC Re Exercise Weaknesses Noted in Insp Rept 50-458/90-06.Corrective Actions:Computer Clock Synchronized to Correct Time & Logic Changed for Making Location Addresses in Retransmission of Messages1990-08-0101 August 1990 Responds to NRC Re Exercise Weaknesses Noted in Insp Rept 50-458/90-06.Corrective Actions:Computer Clock Synchronized to Correct Time & Logic Changed for Making Location Addresses in Retransmission of Messages RBG-33300, Forwards Schedule for Submittal of Repts Re Reactor Physics Methods & Reactor Transient Analysis Methods Rept,Per 900712 Meeting1990-07-30030 July 1990 Forwards Schedule for Submittal of Repts Re Reactor Physics Methods & Reactor Transient Analysis Methods Rept,Per 900712 Meeting RBG-33294, Forwards Decommissioning Trust Agreement for River Bend Unit 1 & Nuclear Decommissioning Trust Fund Agreement Between Cajun Electric Power Cooperative,Inc & Hibernia Natl Bank1990-07-26026 July 1990 Forwards Decommissioning Trust Agreement for River Bend Unit 1 & Nuclear Decommissioning Trust Fund Agreement Between Cajun Electric Power Cooperative,Inc & Hibernia Natl Bank RBG-33196, Forwards Rev 0 to River Bend Station,Cycle 3 Core Operating Limits Rept Jul 1990. Use of Core Operating Limits Rept in Lieu of cycle-specific Parameters in License Amend Request Approved W/Amend 42 to License,Per Generic Ltr 88-161990-07-13013 July 1990 Forwards Rev 0 to River Bend Station,Cycle 3 Core Operating Limits Rept Jul 1990. Use of Core Operating Limits Rept in Lieu of cycle-specific Parameters in License Amend Request Approved W/Amend 42 to License,Per Generic Ltr 88-16 RBG-33150, Responds to NRC Re Violations Noted in Insp Rept 50-458/89-11.Corrective Actions:Implementation of New Computerized Tagging Sys Being Developed1990-07-0202 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-458/89-11.Corrective Actions:Implementation of New Computerized Tagging Sys Being Developed RBG-33143, Addresses Progress of Procurement & Evaluation Activities for Sys to Meet Reg Guide 1.97 Neutron Monitoring Requirements.Bid Spec to Incorporate NRC & BWR Owners Group Guidance Will Be Issued Prior to Fourth Quarter 19901990-06-29029 June 1990 Addresses Progress of Procurement & Evaluation Activities for Sys to Meet Reg Guide 1.97 Neutron Monitoring Requirements.Bid Spec to Incorporate NRC & BWR Owners Group Guidance Will Be Issued Prior to Fourth Quarter 1990 RBG-33132, Suppls Response to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Will Reverify Switch Settings on Initial Surveillance Interval of 5 Yrs1990-06-28028 June 1990 Suppls Response to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Will Reverify Switch Settings on Initial Surveillance Interval of 5 Yrs RBG-33113, Requests Implementation of Generic Ltr 87-09 Wording for Bases for Spec 4.0.3 Re Reporting Requirements of 10CFR50.73 for Missed Surveillances to Enable NRC to Continue Review of 880930 Application for Amend to License1990-06-26026 June 1990 Requests Implementation of Generic Ltr 87-09 Wording for Bases for Spec 4.0.3 Re Reporting Requirements of 10CFR50.73 for Missed Surveillances to Enable NRC to Continue Review of 880930 Application for Amend to License RBG-33114, Requests Withdrawal of 900202 Application for Amend to License NPF-47,revising Div I & II Diesel Generator Crankshift Insp Scheduling,Per 900529 Telcon1990-06-26026 June 1990 Requests Withdrawal of 900202 Application for Amend to License NPF-47,revising Div I & II Diesel Generator Crankshift Insp Scheduling,Per 900529 Telcon RBG-33120, Responds to 900621 Request for Addl Info Re Effects on Containment Dynamic Loads Which Will Result from Increasing Suppression Pool Temp from 95 F to 100 F.Original Design Basis of 100 F Included in Steam Condensation Loads1990-06-26026 June 1990 Responds to 900621 Request for Addl Info Re Effects on Containment Dynamic Loads Which Will Result from Increasing Suppression Pool Temp from 95 F to 100 F.Original Design Basis of 100 F Included in Steam Condensation Loads RBG-33100, Requests Waiver of Compliance W/Tech Spec 3/4.6.3.1 Until Exigent Processing of Tech Spec Change Request LAR 90-08 Completed.Change Revises Max Temp for Suppression Pool to 100 F to Avoid Limiting Plant Operation in Jul & Aug 19901990-06-22022 June 1990 Requests Waiver of Compliance W/Tech Spec 3/4.6.3.1 Until Exigent Processing of Tech Spec Change Request LAR 90-08 Completed.Change Revises Max Temp for Suppression Pool to 100 F to Avoid Limiting Plant Operation in Jul & Aug 1990 ML20043G2211990-06-14014 June 1990 Responds to 900509 Request for Addl Info Re 900209 Response to Violations Noted in Insp Rept 50-458/89-41.Procedure Being Developed to Provide Guidelines for Future Troubleshooting of Recirculation Flow Control Valve Sys ML20043G8191990-06-12012 June 1990 Forwards Rev 5A to Pump Valve Inservice Testing Plan,For Review.Rev Provides Addl Info & Clarification for Requests for Relief Noted in Rev 5 ML20043E6531990-06-0606 June 1990 Forwards Addl Info Re 880930 Application for Amend to License NPF-47 to Implement Generic Ltr 87-09 Requirements Re Preplanned Use of Addl Operating Flexibility ML20043F9801990-06-0606 June 1990 Forwards Response to NRC 890731 Request for Addl Info Re Util 890731 Application for Amend to License NPF-47 to Implement Generic Ltr 87-09.Justifications for Use of Proposed Tech Spec 3.0.4 Will Be Submitted Separately ML20043D5591990-06-0101 June 1990 Provides Status of Actions Re Insp Rept 50-458/89-45 Which Dealt W/Dual Coil Solenoid Operated Valves Used to Control MSIVs ML20043D5421990-06-0101 June 1990 Forwards Addendum to River Bend Station - Unit 1,Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989. ML20043D5401990-06-0101 June 1990 Provides Update to 900125 & 0315 Responses to Insp Rept 50-458/89-200.Util in Process of Performing Retrofit Review of in-stock Items Purchased Between 850101-900101 ML20043D2371990-05-31031 May 1990 Provides Suppl to 890929 Response to Violations Noted in Insp Rept 50-458/89-31.Safety Tagging Administrative Procedure Being Revised to Make Clearance Program Easier to Understand & Follow ML20043C8011990-05-29029 May 1990 Forwards Rev 12 to Physical Security Plan.Rev Reflects Current Activities of Plant Security Programs.Rev Withheld (Ref 10CFR73.21.) ML20043B4231990-05-21021 May 1990 Forwards Rept Re Investigation Involving Unsatisfactory Performance Test Result by Dhhs Certified Lab Under Contract to Util to Perform Drug Screen Testing Under 10CFR26, Fitness-For-Duty Program. ML20043A4271990-05-14014 May 1990 Forwards Authorization of Util Board of Directors for Tf Plunkett & Wh Odell to Sign Ltrs to NRC Transmitting Amends to OL or Responses to Insp Repts ML20042G7031990-05-0909 May 1990 Responds to NRC 900405 Ltr Re Weaknesses Noted in Insp Rept 50-458/90-06 on 900220-23.Corrective Action:Software in Simulator Changed to Duplicate Software in Control Room & More Training Time on Computers Given to Operators ML20042F9741990-05-0707 May 1990 Responds to Violations Noted in Insp Rept 50-458/90-02 on 900122-26.Corrective Actions:Electrical Power Removed from Valves,Safety Assessment of Spurious Opening Performed & QA Performed on Energized Valves ML20042G2521990-05-0404 May 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants.' ML20042E3781990-04-0606 April 1990 Responds to Violations Noted in Ofc of Investigations Rept 4-88-027,per Enforcement Action 90-043.Corrective Actions: Util Auditing self-screening Contractor Programs to Assure Compliance & Audit Will Be Evaluated for Acceptability ML20042D8351990-03-30030 March 1990 Submits Supplemental Info Re Util Response to Station Blackout Rule & Advises That Results of Plant Evaluations Demonstrate Ability to Cope W/Station Blackout for Proposed 4 H Duration W/O Reliance on Ac Power Sources ML20042E3501990-03-30030 March 1990 Forwards Evaluation of Unsatisfactory Performance by Dhhs Certified Lab Performing Drug Testing ML20012F1571990-03-28028 March 1990 Requests Extension Until 900601 to Submit Changes to Facility Tech Specs Re Leak Detection & Inservice Insp Program,Per Generic Ltr 88-01 ML20012F1551990-03-28028 March 1990 Suppls 890411 Response to Violations Noted in Insp Rept 50-458/86-04.Operations QC Instructed QC Planners & Lead Inspector to Include Hold Point of Electrical Maint Work Request for Category I Electrical Equipment Panels ML20042D7041990-03-21021 March 1990 Forwards Results of Ultrasonic Testing Conducted on N4A-2 Feedwater nozzle-to-safe End Weld During mid-cycle Outage at Plant.Circumferential Indication Identified in Buttered Area on Safe End Side of Weld During Second Refueling Outage ML20012E0001990-03-20020 March 1990 Forwards Marsh & Mclennan 900313 Ltr Containing Summary of Property Insurance Coverage for Facility,Per 10CFR50.54(w)(2) ML20012C7901990-03-16016 March 1990 Forwards Response to Violations Noted in Insp Rept 50-458/89-39.Response Withheld (Ref 10CFR73.21) ML20012C9931990-03-15015 March 1990 Forwards Duke Engineering & Svcs,Inc 900105 Ltr to BC Fichtenkort Re Proposed Crankshaft Insp Variation & Recommends Variation Be Presented to Clearinghouse Members at 900111-12 Meeting ML20012C7881990-03-15015 March 1990 Provides Updated Status for Corrective Actions Being Taken for Discrepancies Identified in Insp Rept 50-458/89-200. Thirty-six Items identified.Twenty-eight Items Completed. Three of Eight Remaining Items Require Evaluation of Stock ML20012C0381990-03-0909 March 1990 Advises That Senior Reactor Operator License 43188-1 & Reactor Operator License 42087-2 for a Middlebrooks & DG Looney,Respectively,Expired on 900105 & 900201 ML20012A4431990-03-0101 March 1990 Requests Addl Clarification to Prepare Response to Generic Ltr 90-01 Re Survey of Time Spent by Key Nuclear Power Plant Managers in Responding to Various Operational Insps & Audits ML20012B3001990-03-0101 March 1990 Forwards Fitness for Duty Program Rept 90-F-02 Re Investigation of Unsatisfactory Performance Test Result by Certified Lab Under Contract to Util to Perform Drug Screen Testing,Per 10CFR26 ML20012A9161990-02-28028 February 1990 Forwards Response to Inspector Followup Item Noted in Insp Rept 50-458/89-42 on 891113-17.Corrective Actions:Rev to Procedure EDP-AA-10 Re Issuance of Training Matrix on Semiannual Basis Will Be Issued to Remove 2-yr Rereading ML20011E8431990-02-0909 February 1990 Responds to Violations Noted in Insp Rept 50-458/89-40. Corrective Actions:All Prestaged Matl Removed from Containment & Radiation Protection Personnel Cautioned on Placement of Matl on 95-ft Elevation of Containment ML20011E6741990-02-0909 February 1990 Responds to Violation Noted in Insp Rept 50-458/89-41 on 891101-15.Corrective Actions:Procedure Which Would Provide Guidelines for Future Troubleshooting of Recirculation Flow Control Valve Sys Being Developed ML20011E1531990-01-29029 January 1990 Provides Currently Identified Outage & nonoutage-related Activities to Update NRC of Util Licensing Activities in Order of Priority 1990-09-10
[Table view] |
Text
,. -- -
l
,e3..+ :.-
,o CORRECTED COPY * -
corrcction' occur:d on-Att chm:nt i l'pg.1 dated 4/10/90 GULF STATES UTILITIES C'OMPANY RfVip BEND STAllON . POS T Of DCf SOA 220 ST . F RANCISVILL&, LOOL %1ANA 70715 ,
AMEA CODI 50d . 635 6004 346 8601 March / 30,1990 RBG- 32596 File Nos. G9.5, G1.51- .;
b i t Director, Office of Nuclear Reactor Regulation :
U. S. Nuclear Regulatory Commission i Attn: Document Control Desk Washington,'D.C. 20555 4 Gentlemen: ,
River Bend Station - Unit 1- .
Docket No. 50-458 ,
Gulf States Utilities-Company-(GSU) reported to the NRC by letter-. I dated March 1.- 1990 (see RBG-32416) tha: comprehensive r investigation conducted- 'e ansatisfactory.
was. being ...
performance ~by a. DHHS certified laboratory, which is' under; contract to GSU to perform drug-screen testing under 10CFRPart 26
" Fitness For Duty Program".
Pursuant 10CFR26 Appendix A, Subpart B Section 2.8 (e)' -(4),- the attached report (FFD 90-F01) provides GSU's evaluation of the reported condition. l Should you have any questions relative to this report, please contactMr.DavidN.Lorfingat(504)381-4152.
Sincerely, 1 .' s W. H.;Odell .-
Manager-River Bend Oversight-River Bend Nuclear Group- 3 WH0/T ' S/pg cc: U. S. Nuclear Regulatory Commission l Region.IV "
611 Ryan Plaza Drive, Suite 1000 l Arlington, TX 76011 NRC Resident Inspector
- . ' Post Office Box 1051-St. Francisville, LA 70775 -
i L 9004200656 900330 PDR P ADOCK 05000'450 t r,w .
7
, b.. .
FFBGES PGt DUFY MCRhM REFGtr 90-P01
" False Negative" REPORTEDCONDITIg On 01/05/90 Gulf States Utilities Co. (GSU) fitness for duty (ETD) program supervisor forwarded a blind performance urine test sample to GSU's contract laboratory American BioTest Laboratories, Inc. (ABLI) , a U.S.
Departrent of Health and Human Services (DHHS) certified thoratory. We test sample was fortified (spiked) with a kncun 33 nann, cams per milliliter (ng/ml) phencyclidine (PCP),' prepared for and supplLd to GSU by ElSchly Iaboratories, Inc. (ELI) on August 16, 1989. By letter dated 01/11/90, GSU's medical review officer (MRO) reported the results frm ABLI for the blind test sample as being negative. (Ebr PCP, test results above the cut-off level of 25 ng/ml is considered positive.) GSU, believing this false negative to be an unsatisfactory performance test result issued a condition report (CR90-0047) and reported this event to the NRC via the Ebergency Notificaticri System at 1617 on 01/17/90 On 01/18/90, GSU's Quality Assurance Department requested ABLI to conduct an internal investigation to determine cause of the discrepancy in test results. In accordance with GSU's Fitness for Duty Program Procedure (ETD)-16-001, an investigation was performed by GSU's Quality Assiu ance Department. This event is being reported pursuant 10CFR26 Appendix A, Subpart B Section 2.8 (M (4). GSU has concluded that the. false negative reported to the NRC 'may not have been a true unsatisfactory performance test result in that the IABI test results may be considered within an allowable margin of error.
INVESTICATION To determine the cause of the event, a four part investigation was onducted to:
I. Establish a confidence level in the blind performance test samples:
The original positive blind performance test sample was prepared by ElSohly Labs on August 16, 1989 with a PCP concentration of 33 ng/ml (Attachment 1) . Subsequent analyses by imunoassay and gas chrunatography/ mass spectrcumtry (GC/MS) methods by ElSohly Labs and Northwest %xicologv (an independent laboratory) have verified the concentration between 29 and 34 ng/ml (Attachment 2) . Thece analyses indicated little or no degradation of PCP concentration while the sample was refrigerated and stored in a glass container.
The differences are attributed to normal sample data scatter.
II. Det ermine the accuracy of American Bio'Ibst Laboratories' results; Tho blind performance test sample was packaged and delivered to GSL on 12/21/89 in GSU's plastic specinen container. After l
1 M
e i
receipt acknowledgenent on 12/22/89, the spiked sa@le was frozen l
for long tem storage. On 01/05/90, the sa@le was rm oved from t storaae and sent to American BicTest Laboratories, Inc. (ABLI) as !
a bli.id perfomance test sample (with a known PCP concentration) ,
with GSU's serial ntsnber 900105-0011. On 01/08/90 the samle was
. screened positive for PCP on ABLI's Monarch Imunoassay machine.
On 01/09/90, a confirmatory gas chrmatography/ mass spectrunetry i
(GC/MS) test was perfomed and the sa@le analyzed to contain l' 23.31 ng/ml of PCP (Attachment 3) . Since the cutoff level for PCP is set at 25 ng/ml, the sanple was then reported to GSU as ;
neoative.
- l Verifications on the part of the laboratories indicate the ,
l following: r i .
Pharnchen's -independent analysis of ABLI's aliquot '
(Attachment 4) and Northwest Toxicology Laboratories' independent analysis of ElSohly's second test result l (Attachment 2) were within 4 ng/ml of the original laboratory's results.
I Analysis repeatability was' supported since consistent concentrations were determined by each originating laboratory weeks or months apart. Although repeat analyses are usually within two units of each other, variations of up to five -
units have been recorded for this 33 ng/ml sanple batch.
- l Conversations with Dr. M. A. EISohly and Mr. Don .Stafford, i l both of ElSchly Laboratories, Incorporated (ELI) as well as l Dr. Latven and Mr. Jim Merdink (Lab Director) of ABLI,
" indicate that as the concentraticn levels of the spiked samples beccrne less and less, (in particular near the cutoff a level of 25 ng/ml for PCP), the sensitivity level.for GC/MS ,
l test equipnent is reduced. Althougt. the labe indicate utmost I confidence in their results, they agree that the results are ,
near the limit of confidence in the current GC/MS l methodology.
On 01/29/90, GSU subnitted two specimen containers to ElSohly Labs (III) to be filled with the 33 ' ng/ml sample . batch. The first container was returned to GSU to be used as another QC blind ,
sanple while the second was subjected to an experiment by ELI to '
detemine any detrimental effects of shipment on PCP spiked samples. The second test sanple was inmediately aliquoted where one served as the " control" for the experiment when it'was stored frozen and the remainder was subjected to simulated interstate transportation by riding ,in ELI lab director's vehicle for 48 l hours. The two test sanples were then analyzed on 02/02/90 to contain 29 ng/ml of PCP each. This experiment by ELI determined:
that PCP concentration will not degrade appreciably due to time, heat, vibration or sample container properties, and Page 2 of 5
,r-*
l .
l _
t ..
- - that day to day variation of the GC/MS technique may be as high -
as five ng/ml. :
III. Perfom an operations Quality Assurance (00A) surveillance of i
an-site collection facility and procedures to assure ccanpliance I with regulations: -
GSU's cC.lection facility was surveyed by operations CA on 01/25/90 for ccrnpliance with station support manual procedure FTD-16-001 and 10CFR Part 26 requirements. OA surveillance CD-90-01-24 found the collection facility to be functioning in compliance with the abcre requirements.
IV. Obtain a concerting opinions j l
on 02/16/90, GSU sent a copy of CR90-0047 and other pertinent ,
information to Dr. William J. George, a-toxicologist at Tulane '
University Medical Center. Dr. George was asked to evaluate the CR to determine the following:
- Were the GC/MS nachines properly setup and operated to .
i yield accurate m sults? His answer was "Yes". ;
Is this a normal data scatter range for a low PCP concentration? His answer again was "Yes". L r
- Do you concur, disagree or wish to change the condition report's disposition? He agreed with the disposition.
Dr. George's response on March 7, 1990 indicates that this range of error is acceptable and is not cause for undue or unwarranted I actions, see Attachment 7 t Of the 14 spiked samples analyzed since initiation of the program, this was .
l the first occurrence of a false negative report.
To determine if ABLI's test result fell within the National Institute on !
Drug Abuse (NIDA's) 20 percent allowable error, the following analysis was performed. The GMS analyses performed on this OC batch prepared by ELI was 3 treated as a snaller version of NIDA's Iaboratory Cross Check Program. ,
Prem all the analysos, the arithmetic mean and the 20% ern3r window allowed
- by NIDA was determined. 'Ihen ABLI's results were campared to the ;
arithmetic mean taking the error window into account.
Date Concentration Lab 900109 23.31 ABLI 900123 24.09 ABLI 900124 27 PharmChen 890816 33 ELI Unknown
- 29 NorthW.est 'Ibxicology 891026 33 ELI 891217 34 ELI 900119 32.8 Erl Page 3 of 5
- + .e ,
e
,, . . 4 Arithmetic Mean: 236.2/8 - 29.52 ng/ml 20% Error Windows 29.52 (0.20) = 5.9 ng/ml Arithme' tic Mean Minus Error: 29.52-5.9 = 23.62 ng/mi Aniount ABLI Outside NIDA allowable Error: 23.62-23.31 = 0.31 ng/ml ABLI's initial GC/MS was 0.31 units lower than the NIDA allowed error 7 limit.
Test perfonted scmetine between 08/16/89 and 10/26/89
{
CORRDCTIVE ACTICN/REDfGDATIONS ALBI prepared a nonconforming activity report (NR) to investigate the possible . source (s) of error. 7he NR was dispositioned "no correctivo action necessary", see Attachnent 5. ELI, technical specialist for GSU's ITD program, has reviewed ABLI's nonconfonning activity report on this event and has accepted the laboratory's assumptions, root cause and corrective acten. Industry experience indicates that false negatives are not infrequent as laboratory procedures are ' primarily directed towards prevention of falso positives. ELI has reccanended that ABil review their quantitative bases for PCP analysis by GC/MS. They also r& w n.arsd that GSU continue sending PCP blind performance test sanples at the usual (present) intervals.
. Based on the ARLI's nonconforning activity reinrt and GSU's investigation, the reported false r.egative was detennined not to be an unsatisfactory performance by the laboratory. GSU will continue to use Anerican BioTest Laboratories, Inc. as its FTD program test laboratory.
ROCff CAUSE The root cause of this incident has not been specifically determined.
Contributing factors include inherent laboratory quantitative differences betw en the testing laboratory and the QC blind sample supplier, a ecnbination of GC/MS daily variance within irdividual laboratories, and calibration standard differences generated by the . -pective labs. GSU has concluded that this incident is not indicative of poor laboratory performance or inaccurate OC blind samples.
CORRDC11VE ACTICH WI'IEIN GSU Corrective actions to be taken by GSU to prevent recurrence include:
The functions of GSU's performance test sample supplier will be separated frtn its technical specialis+;. ,l The sample supplier will be required to obtain and provide to GSU I at least two other independent lab analyses so that the average of the test results may be used as the actual contaminate concentration.
i Page 4 of 5 l
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. *+
OA and GSU's technical specialist (ELI) will visit ABLI to review
,- quantitative analysis techniques in conjunction with the next annual audit.-
IMPACP '
his investigation was ocmpleted as required by 10CPR26, Appendix "A",
Subpart B,- Section 2. 8, (e) , (4) and SSM procedure . PfD-16-001, Hev. O, Attachment 3. Were was no inpact on security, plant safety or to the-safety and health of the. public.
GSU. requests that any additional findings in this regard be brought.to our attention.
e l
Page 5 of 5 t-l-
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'O ATTACm!ENT 1 CR 90-0041 page 1 cf 1 g CERTIFICATE OF ANALYSIS This im Lo certify thmL Lhe luL uusburu liuLad below have bwwu curLitivd by immunumsmay' and gau chromatography / mans spectrunwLry Lu uuutalu Lhw concenLraLion of drugs spoulflvd.
m L .- / A r d e _.
Malumuud A. EISu(ly, Ph.D., IdburmLury DirvuLor SPECIMEN CONTROL LOC Lab CSU DmLv Shippwd: 12/21/80 TCH4 NAME SSN Number DRUC ug/ml ACCESS 4 LABORATORY RESULTS e______________________ ________ . __________ _______
______________ g___________ __
1680A e_____
_____________________________.________________J___>
PCP 33 b /.
g
_____O.L_t7_,__[_
hw fro A a,fJ- &&CJ 6 eM *"- /
y /WfG i,
y
/
/
-1
. a ~e/ ) '
y ,,
l Shipment Prepared'B) Rvvlwwed (Ey htc/ Rwlvmmeddy-Rwevived By Purpuse of Change of Cuulud.v
.. L. - ______
- taa. ie ? ~7, / 2 M t. m J A__ n___ / ,
- s,4 4291p_c_wxe. ' fMDM_ _15.__ _0_ _ _ _ __ _ _ _ _ ___ _ _C__ ___________
__ __ :.vj.o.u_______'
____..e___________________N_____p-_.m..._____g-- _ggggggeggggye%gg gggggg
- e e en et e en e e e e o e en e GB e e en _ en e e e e e e e en ene., ,,,,4 ee ..
- .. '. ATTACEIGnfT'2 CR 90-0047 pag 3 1 cf 2 ElsoNy Laboratories, incorporated , *g 1tten .lochsen Avenue '
omens.nmessenegal asses 6
teot)asHeDe
)
January 22, 1990
)
Mr. Tom Stanberry
- - Gulf State-Utilities" -
River Bend Station St. Francisville, LA 70775 .
Dear Tom:
1 This is in reference to your inquiry about our phencyclidine batch #08169A ,
from which you had a specimen that was reported to you as being negative ,
by your drug testing laboratory. This batch was prepared on the 16th of August,1989, and certified in our laboratory both by immunoassay and i GC/MS as being positive for PCP at 33 ng/mL. Meanwhile, this batch was submitted to an outside reference laboratory (Northwest Toxicology) to t,e screened and confirmed for all drugs. This batch was found by Northwest Toxicology to be positive for PCP by immunoassay at the 25 ng/mL cutoff-and was confirmed by GC/MS at 29 ng/mL.- Therefore, according to our standard operating procedures, this batch was certified at- 33 ng/mL PCP ,
which is our own analysis.
Subsequent to that, we reanalyzed that batch on October 26, 1989, and ;
found the material to be stable with a GC/MS concentration of 33 ng/mL -
l PCP. On December 17, 1989, the batch was reanalyzed again by GC/MS and I found to contain 34 ng/mL PCP. Obviously, the material is not increasing in concentration but the difference between' 34 and 33 is within experimental error and therefore, again, we concluded the batch is still stable for that length of time. We routinely monitor the level of the .
drug in all our batches, and we perform an immunoassay check on every batch at the time of shipment to our clients. When this batch was shipped to Mr. Carter on December 21st, the analysis showed no problem with the batch.
Since you called the laboratory and discussed with' Don the possibility of renalysis, we carried out again another GC/MS confirmation. Our analysis on January 19, 1990, shows PCP level to be. 32.8 ng/mL, indicating that ,
there is no degradation of the batch. I have hard copies of all information related to each time this batch was analyzed as described above, and I am sending you the GC/MS records for the analysis carried out .
January 19th since this really is the analysis that reflects the current level of the drug in this batch. However, if you need documentation of the other analyses, please let me know.
w . .- . - ., - . - . - . . _ .. . _ _ _ - ._ - , . . - . . - . . . - . - - - . - .
l .. . ATTACBEENT 2 CR 90-0047
. page 2 cf 2 Tom I. hope everything goes well, and please let me know if you need any additional information or if I can help at any time.
With best personal regards.
Sincerely,
/Q# }/ Ih4P ic '
Nahmoud A E1Sohly, Ph.D.
Preside Laborat6ry Director
\
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_____;;;;;____h- m _.----;il'-~ 512:1 (e CR 90-0047 l.s *
! ATTACIDSWT 3 CAF ID 6--Ass l pago 1 of 2
Co. 80RDER 0.3194 2 HC0 POS 0.3219
-l '
3 HI POS 9.3482 4 BUNK MG 0.2788 5 -
114195 EG 8.2612 6 119492 EG 9.2682 7 10ssee MG 0.2653 8 196797 EG 0.2886 3^
, 9 194652 E E. 9.2777 18 186798 MC e.2755
- 11. 187441 EG 0.2736 12 -
2881965 MC 9.2629 -
13 195F8 EG 9.2672 :
14 195359 EG . 0.2677 !
15 180686 E G. 0.2635 ,
16 182685 NEG 0.2733 -
17 195329 HEC 8.2738 t 18 -195333 EG 0.2726 !
19 -
195349 .NEG 0.2742 i
, 20 185338 NEG 0.2738 21 195320 NEG 0.2674 p_ nsu m 4 EG 0, ace r m .s e&we
.t. us a.2145 a !
24 195332 re.u 8r2718
.4
'. : # 25. ~ 195343 'EG 0.2765 r
. . ...if '
.; 26
"' 195331 N!.C 0.2643 M
. 27 28 29 202E704 2832694 PEG
'EG 0.276$-
O.2680 h '
2832680 EG 0.2769
' 39 202818e NG 8.2690 l
31 2027177 EG 0.2766
! 32 Pere m y EG 0.2778 33 2001612 NEG 0.2491 i 34 111790 NEG 0.271?- !
35 111701 NEG 0.2776 l l
36 111782 EG 8.2750 i 37- 113883 EG ' O.2634 :
i 38 118E77 HEG 0.2557 '
CALIBRATED 08 JAN 90 13 46 m "!'
[ CUP 23 ID 195342_ 08 JRN 90 16 05 mc EG
- i EG /
f
\
ex 20s 3 HP VHc HEG i i
OPIAT NEG METHH HEG BARB tEG 9ENZO HEG
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[ MEQUA HEC LEG
, h n JAN 90 16:05 L i T% "
s e-ATTACBEENT 3 CR 90 0047 page 2 cf 2 1
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- Samols name
- 127742 Cata infected: 900109 18:20 i Cet f i l e .n a r.s t )M0305t:0E Misc. 'nfo. I FC' CONF !dfils : 10 N ! B t t R7.
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A-i PCP
- RT . 6.45 area of dreg . 4965.00 t Cone = 27.31 R.F. . .92
- Cone op :.s. . 44.00 i is it- = 6.45 Area of 1.5. - 9533.00 t %. #
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i Height A**0 4 i
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! 242/ 203 = 43 242' 200 - 39 !
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. . .- j ATTACBENT 4 CR 90-0047 l page 1 of 1 l 1
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i ! Pmw ww IABORATORIES, INC. : '1t- I,
l j IABORATORY' REPORT ] , , I,, a- .
COUNT:NIDOBER 000105500 BARCODE l 060750k i .
.i -l'.!i i SENDITO2 SPECIMEN ID:
i
ATT: Mr.tKaz Latten, President' SPECIMEN ID ' l America:IBiotest SPECIMEN DATE: 4' il 3350 Scott Blvd., Bldg.15 -
TEST TYPE i i ..i :.
San.ta:Clara, CA 95054 LOCATION CODE: i;,* 00
, .l.I i, li ACCESSION NUMBER: .
i
{ DATE RECEIFED: l!'l'0dO802 l '.01/231/'
, DATE REPORTED 1:
~.............1____. _.. -- - ...- 0.1/2of.l
. . . . . ,. 7 .--..
gg .
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i Drug or l Initial Test 1 Confirmation Test!
j ; Drug Clasa Method. :
Cutoff *l Method .: ' CjitOff 4'!
__ ______ _ _ - - - - - - - - - - - - - - - _ _ -- _ _ _ . . . . . . . . . . = _ - -- .: ,
P 4.encyclidine GCNS GCMS 25 ng/ mil IIj ll l
--..==-------w-I I
i Drug or
, TEST RESULTS Test ~
.l Drug or 1 ! Test
!!!I "
jDrug class
.==
Result Druig class ; Result ,
.. . -- . . . - - . . = . = = . - = = =;
Phancyclidine GCMS POSITIVE i .
. .i hl l );
CCDDENTS: * * *l * .* * * * * * * ** * !
I' i
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e i POSITIVE'
...**+,e** e**,-
t 7 3EM '
l!. I",
1 t I' certify that the specimen identified by this accession number ik.the s'r a cpecimen that bears the specimen identification barcode number set foi-th above .
that the specimen has been examined upon receipt, handled and analyzed ;
cccordance with applicable requirements, and that these results are 'for thi Opecimen. , ,
I i ggani.t.s : cartified_bys p ltRol(N f_
. . . . . - . = = = = = . - - - - _ _ _ - _ - . . . .
_ . _ j , __ _
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o_, , . _ _ . . . ._ ._, _..-..._. _ . -- - - - -
ATIACIMNT 5 NONCONFORMING ACITVliY REPOR Page 1 of 5 Subject F4233 h:3g2TV3 CII 3 LIED 00 sFECIMW: EITER BEEl_ _. M 19-JAN NON00MOEWNOACRVmf UN 18-JAN' 90 ABTL WAS NOTIFIED BT RTVER REED TRAT SaltFLE # 105342 EEromTED AS NEGATIVE, ACTUALLY CopTAINED 33 NG/ML PCP.
N I
T I MCOWENMDONE A InvEsTIoATE THE 30LicirIso 70sstaLE soaRcEs or saRos.: 1) INComaECT l PANEL man rom srar==w; 2) commECT rAsEL, suT scaEEsED usGATIvE s)
T scaEENED 70sTIT7E BUT CCEFIREED NEETIVE; 4) s0REENED OR CONFIRNED O rosIrIvE acT ImoamaECzz.T mErcam. l R
IF 2) OR 3), SEBID ALIQUOT OF SPECIMER TO AMOTHER. DERS CERIIFIED W TOR.
BRAMAfY313 INITRTOR R.K. IATVER F6D. DIE. [pt/ MTE 19 JAN-90
.5 RwremANmsen g INITIAL PANEL SEIUP RAS COREECT. FCP CUIOFF UsED Ras 25 NG/ML.
SPECIMEN SCREENING RESULT: '30RDER* (+- 10% CUICFF - 23 TO 27 NG). ,
P GC/us CONrInu&TIow vALuE: 23 mo/m.; REAmALTsis BT GC/Ms: 24 nC/xL.
ALIQ T sENT To raanxcaIn IAaCaATORIES AND REPOR2TD AT 27 NG/NL.
E coRREcmeAcnON R
AVERAGE OF TEREE QUANTITATIONS BY TWO NIDA 1ABORATORIEs INDICATES Y SPECIMER's ACICAL PCP CONCENTsATION To BE 24.6 NG/NL, BELOW CUTOFF
-g 0F 25 NG/ML. AND CGERECTLY REPORTED A5 NEGATIVE. 30 CORRECTTVE ACTION NECESSARY.
5 l J APPROVALBfSUPERVISOR tRTE 30-JAN.90 J.L.MIRDINK ( )
RE$PONSE EVALLMTED AND ACCEP1YD DM 1.FEB-90 l CORRECnVEACTIONSVERIMED '
Q .NO CORRECTIVE ACTION NECESSART A-M G .,,9i R.
von nenny a.g.IAT7En
] gg om 1. fen.90 NCAR CLOSURE R.L.IATVEN h DATE 1.FEB-90 Ameican Bid est Jnboratories,Inc.
"-- -- -E b U 22E d INI::$
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' 7
' HI 0.3219 l POS 0.3402 4 su:HK EG 5
5 0.279C 6
114195 EG 8.2612 7
119492 EG 0.2682 10seBe HEG 0.2653 !
e 136797 NEG ;
S 0.2895 :
10 194652 EG 0.2777 186798 EC 0.2755 11 187441 EG 12 0 2736 20e1965 EG 0.2629
'13 185358 HEG 14 9.2672 :
1953b9 EG 0 2697 !
15 182606 EG -
16 0.2635 102685 HEG 0.2733 17 195329 -HEG :
le 0.2730 19 195333 EG 0.2726 t
j 195340 NEG 0.2742 20 195338 NEG 1 21 0.2738 195320 NEG 0.2674 I w 185224 g3 gge EG 0. *'C ;
, . . .? r.us e.2145 ,
s 24 105332~ mu c/l- f' / 9.2718
.f
'.f Y.. . ..J.. y ' J 25 195343 NEG 0.2765 i
' 26 195331 EG 27 0.2643 262e704 HEG 0.2769 ,
g i e9 80.
l 30 .'2769 2020100 EG 0.2690 31 2027177 NEG 32 2 mtp m 7 0.2766 NEG 0.2778 33 2001612 NEG 0.1491 34 111700 NEG t
35 111701 0.2717 !
NEG 0.2776 36 111782 NEG 37 0,2750 .
113883 NEG ' O.2634 38 110277 NEG 1
0.2557 '
CALIBRATED OS JAN 90 13:46 m
T, CUP 23 ID 185342 _
08 JAN-90 "l
- 16405 THC NEG ce" HMFHr.
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000105500 BARCODENt8tBER: l',[060750Eh5 i 6 : !
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SPECIMEN ID:
1 > 1,; i 105342 i A23:
AmericanlBiotestMr. Kaz Latven, President '
SPECIMEN SPECIMEN DATES.
ID i
,': ;4, [; l ll '[ J 3350 scott Blvd. , Bldg.15 TEST TIPEsi .
1:.i j '. i ! !
SantaiClara, CA 95054 LOCATION CODE:
l
! 0000 j '7 l
i.
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! ACCESSION NUMBER: 'i' .00'08020$4 i
; l DATE RECEIVED:
l4 !:01/231/90 .
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I i DATE REPORTED:. I ;i.:0.1/24/90 t g _ . _ . . - -. -- .
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$aitial Test 1 Confirmatiod Tpst -
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! ',l'est
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..........,3i.-....----..=.==....=={--Result l i Pl}isacyc;11 dine GCMS POSITIVE l l 1 j i -i i i ll ! Il l Cconcorrs: i *
- 9
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; I I' certify that the specimen identified by this accession number i;s.the s;me a i -
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, unti the speciman has been awa.inm<i Iupon receipt, handled and analysed in
- cordance with applicable 1
meiman.
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and that i these results are'for i i that i i ; I 6 '
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. nom wacima onw em execunn nouve cnicano.umois esees nockvua.mm.Amo acesa Januarv 11, 1990 oc. Robert P. Carter Fitness for Duty Suuervisor Gulf States Utilities Riverbend Station P. O. B o x '.' 2 0 5t. Francisville, L.\ 707~5 N a :' M r . ila r t e r :
This is w inform -c en, that druc testing results ie.;ro negative for tue fvilowinu 5poeiments: submitted to ameri an BioTos:
.. :. ; o ra t o r i e s . Inc..
SPECIMEN I DE:-:T! ?IC ATION :
'>00100-0006 .00105-000?
'i/00105-0001- 2,00105-',008 900105-0000 90010i.-0003 900105-000:' ',00105-0010
^suG103-0000 d60105-0011]
Tne chain of custcar t:a s intact. The drucs f or i.h ich .mrit.an BioTest tested were:
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Cocaine (Phene s el idin -
.unpn e t am i n e
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sle t hampne tu tine i
- io rpn ine C.:. dine
!*thadone
.mbarbital d e-c o na r b i t al Pantobarbital
?henc ba rol cal -
I)e n 2 o d i a 0 0 p i n tt W, Is.- t h a tll a l o n e .
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ef** ' 1:D U Tib rec e i YQti hV .\bIf 0'./C$/5f0
=U1*y re=Ulet.wd be 3D.\ l 01/11/90 i i ne t r f.: ;V ysf r:t:? r ' .g ,m,,~ <
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," Tulane University Medical Cente7""
William J. George. Ph.D.
Director School of Medicine
.. ' Toxicology Center 1430 Tulane Avenue and New Orleans. LA 70112 Drug Analysis Laboratory (504) 588-5587 Department of Pharmacology March 7, 1990 .
Mr. Tom W. Stanberry Quality Assurance Engineer Gulf States Utilities Company River Bend Station P.O. Box 220 St. Francisville, LA 70775
Dear Mr. Stanberry:
I have reviewed the information provided me concerning the condition report dated 1/18/90 whereby on January 5, 1990 in accordance with the provisions of FFD-16-001, a positive blind performance test specimen was submitted to American Biotest Laboratories, Inc. (ABLI) on January 5,1990 for analysis of phencyclidine (PCP). - The control specimen which had a known concentration of PCP equal to 33 ng/ml (as prepared by El Sohly Laboratories, Oxford, Mississippi) was reported back by ABLI as being negative for PCP. In accordance with section 1, attachment 3 of the Fitness for Duty (FFD) evaluation. (FFD-16-001), the incorrect response was referred to you for laboratory At your request I reviewed information provided me concerning the incorrect response, which includes copies of the condition report, nonconforming activity report, chains of custody forins, GC/MS analysis sheets, GC/MS data sheets, and correspondence from Dr. M. A. El Sohly.
It is apparent that concentration of 33the PCP control specimen was standardized as having a ng/ml. 1
' by GC/ mass spectroscopy Subsequent immunoassay screening and confirmation 25 ng/ml and 29 ng/ml, re(Northwest spectively. Toxicology Labs) yielded values of ;
specimen and found it to contain 27 ng/mi Pharmchem of PCP. Laboratories tested this l was the one sent to American BioTest Laboratories on 1/5/90 as a blindThis same contro specimen and was reported as being negative because of a GC/MS confirmation value 25 of 23.31 ng/m1, which is less than the negative cutoff level for PCP of ng/ml.
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Mr. Tom W. Stanberry March 7, 1990 Page 2 '
The questions that I have been asked to address are as follows:
- 1. Were the GC/MS instruments properly set up and operated to yield accurate results?
The answer to this question is yes. The specific ions looked for and time of elution for PCP are appropriate.
2.
Is this a normal data scatter for a low PCP concentration?
The answer to this is also yes. According to testing done by El Sohly Laboratories, the specimen was reported to contain 33 ng/ml with an allowable range of 26.4-39.6 ng/mi according to the 20% range allowed by NIDA. With this allowable 20%
range, subsequent testing by American BioTest Laboratories could have produced results as low as 20% less than the 26.4 ng/mi or 21.1 ng/ml. The 33 ng/mi concentration given by El Sohl dilution, y and Laboratories follow-upistcsting.
a number based on a weighing, The correct value may not be 33 but some number higher or lower than 33 and, therefore, a range of concentrations may be more ap fixed 33 ng/ml for the control specimen.propriate than a
- 3. Is there concurrence or disagreement with the condition report's disposition?
I believe this single nonconforming report should be acceptable and that Gulf States Utilities should not change laboratories on the basis of this one test. It appears that good laboratory practices are being employed and that the results obtained are explainable. by. expected-var.iation around the . absolute values.
Sincerely, MMW L William J. George, h.D.
Professor Director of Toxicology Ji
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