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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:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 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 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 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 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 ML20196E0601999-06-18018 June 1999 Forwards Insp Rept 50-458/99-05 on 990418-29.Four Violations Identified & Being Treated as Noncited Violations ML20195G3121999-06-0909 June 1999 Ack Receipt of Re Changes to River Bend Station Emergency Plan,Rev 19.No Violations of 10CFR50.47(b) Were Identified ML20195G3671999-06-0909 June 1999 Ack Receipt of Ltr Dtd 981016,which Transmitted River Bend Station Emergency Plan,Rev 18 Under Provision of 10CFR50, App E,Section V.No Violations of 10CFR50.54(q) Identified During Review ML20195D6041999-06-0303 June 1999 Discusses EOI Request That Attachment 4,NEDC-32549P, Safety Review for River Bend Station Cycle 7 Final Feedwater Temp Reduction, Rev 0,be Withheld from Public Disclosure. Determined Info Proprietary & Will Be Withheld DD-99-08, Informs That to Extent That Union of Concerned Scientists Requests Commission Undertake Formal Review of DD-99-08 & Hold Meeting to Directly Receive View on Decision,Request Denied.With Certificate of Svc.Served on 9905211999-05-20020 May 1999 Informs That to Extent That Union of Concerned Scientists Requests Commission Undertake Formal Review of DD-99-08 & Hold Meeting to Directly Receive View on Decision,Request Denied.With Certificate of Svc.Served on 990521 ML20206U4321999-05-18018 May 1999 Forwards Notice of Withdrawal of Licensee 961106 Request for Approval of Deviation from Approved Fire Protection Program to Extent Program Incorporated Technical Requirements of Section III.G.2 of App R to 10CFR50 ML20206U6081999-05-18018 May 1999 Forwards Insp Rept 50-458/99-03 on 990307-0417.Eight Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20207A8051999-05-15015 May 1999 Forwards Insp Rept 50-458/99-06 on 990419-23.No Violations Noted.Inservice Insp Activities at River Bend Station Were Being Implemented in Accordance with ASME Code & Regulatory Requirements ML20206N7081999-05-12012 May 1999 Informs That NRC Ofc of NRR Reorganized,Effective 990328. Reorganization Chart Encl ML20206N8811999-05-12012 May 1999 Forwards Notice of Withdrawal of 981120 Amend Request for License NPF-47.Proposed Amend Would Have Established New TS 3.10.9, Control Rod Pattern - Cycle 8, Added to Section 3.10, Special Operations ML20206H9191999-05-0707 May 1999 Informs That on 990407,NRC Administered Generic Fundamentals Exam Section of Written Operators Licensing Exam.Facility Did Not Participate in Exam,However Copy of Master Exam with Key Encl.Without Encl NUREG-1434, Discusses Licensee 960418 Request for Amend for Plant That Would Permit Addl Method of Fuel Movement & Loading in Core Upon Removal of Control Rods from Defueled Core Cells.Nei TSs Task Force Process Will Be Used to Review TSTF-2261999-05-0505 May 1999 Discusses Licensee 960418 Request for Amend for Plant That Would Permit Addl Method of Fuel Movement & Loading in Core Upon Removal of Control Rods from Defueled Core Cells.Nei TSs Task Force Process Will Be Used to Review TSTF-226 ML20206J2291999-05-0303 May 1999 Discusses Responding to NOV Issued on 990105.NOV Was Based on NRC Conclusions That Licensee Provided NRC Inspector with Info Licensee Knew Was Inaccurate & Incomplete ML20206E6381999-05-0303 May 1999 Ack Receipt of 990305,990315 & s Responding to NOV & Proposed Imposition of Civil Penalty, .EOI Paid Civil Penalty & Requested Withdrawal of NOV & Civil Penalty for Reasons Stated.Finds NOV & Civil Penalty Appropriate ML20206E4531999-04-27027 April 1999 Discusses Request That Attachment 4, Final Calculation of RBS Cycle 9 SLMCPR (Safety Limit for Mcpr), Submitted with 981216 License Amend Request,Be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20206A2031999-04-21021 April 1999 Discusses EOI Second 10-year IST Program for River Bend Station Submitted on 980106 & 980910 Which Included One Pump Relief Request & Two Valve Relief Requests.Forwards SE Authorizing Pump Relief Request & One Valve Relief Request ML20205N7251999-04-13013 April 1999 Forwards Summary of 990408 Meeting with EOI in Jackson, Mississippi Re EOI Annual Performance Assessment of Facilities & Other Issues of Mutual Interest.List of Meeting Attendees & Licensee Presentation Slides Encl ML20205J5331999-04-0606 April 1999 Ack Receipt of Denying Request from NRC That Addl Info Be Provided Prior to Informal Public Hearing Held on 990222 Re River Bend Station & Perry Nuclear Power Plant 10CFR2.206 Petitions ML20205K0681999-04-0505 April 1999 Submits Summary of 990325 Meeting Re Engineering Performance at Site & Assessment of Organization Strengths & Opportunities for Improvement.List of Attendees & Matl Used in Presentation Enclosed ML20205A4531999-03-26026 March 1999 Forwards Insp Rept 50-458/98-10 on 990222-26.Violation Noted & Being Treated as Non-Cited Violation.Concludes That Radiation Work Permit Program Poorly Implemented Until July 1998 Because of Inadequate Program Implementing Procedures ML20205D7691999-03-26026 March 1999 Forwards Insp Rept 50-458/99-02 on 990124-0306.One Violation Identified & Being Treated as non-cited Violation.Licensee Conduct of Activities During Insp Generally Characterized by safety-conscious Operations & Sound Engineering ML20205D5361999-03-26026 March 1999 Forwards Ser,Accepting Util 980107 Request for Alternative to Augmented Reactor Pressure Vessel Exam Requirements for Plant,Unit 1 Pursuant to 10CFR50.55a(g)(6)(ii)(A) for First 10-year Insp Interval.Technical Ltr Rept Also Encl ML20204G8081999-03-24024 March 1999 Refers to 990303 Reply to NRC NOV & Proposed Imposition of Civil Penalty .Since Licensee Paid Civil Penalty & C/A Found Responsive to NRC Concerns,Matter Considered Closed ML20205A4021999-03-23023 March 1999 Forwards Insp Rept 50-458/99-301 on 990222-0303.No Violations Noted.Insp Included Evaluation of Three Applicants for Senior Operator Upgrade & for Senior Operator Instant & Eight Applicants for Reactor Operator License ML20205F3131999-03-19019 March 1999 Advises of Planned Insp Effort Resulting from River Bend PPR Review,Which Was Completed on 990211.Performance of River Bend Staff During Assessment Period Was Acceptable 1999-09-09
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l Randall K. Edington, Vice President - Operations River Bend Station Entergy Operations, Inc.
P.O. Box 220 l St. Francisville, Louisiana 70775 SUBJECT: NRC INSPECTION REPORT 50-458/98-12
Dear Mr. Edington:
l Thank you for your letter of August 27,1998, in response to our letter and Notice of Violation dated July 29,1998. We have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation involving a breaker tagging error and a failure of most of the emergency sirens following a software upgrade. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintained. I
Sincerely,
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omas . n irector ivision of Reactor Projects Docket Nc.: 50-458 License Nc.: NPF-47
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. Executive Vica President and Chief Operating Officer Entergy Operations, Inc.
P.O. Box 31995 L Jackson, Mississippi 39286-1995 l
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Entergy Operations, Inc. -2-Vice President Operations Support
- Entergy Operations, Inc.
P.O. Box 31995
- Jackson, Mississippi 39286-1995 General Manager Plant Operations River Bend Station Entergy Operations, Inc.
P.O. Box 220 St. Francisville, Louisiana 70775 Director - Nuclear Safety River Bend Station Entergy Operations, Inc.
P.O. Box 220 St. Francisville, Louisiana 70775 Wise, Carter, Child & Caraway P.O. Box 651 Jackson, Mississippi 39205 Mark J. Wetterhahn, Esq.
Winston & Strawn
- 1401 L Street, N.W.
Washington, D.C. 20005-3502
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Manager - Licensing River Bend Station Entergy Operations, Inc.
P.O. Box 220 St. Francisville, Louisiana 70775 The Honorable Richard P. leyoub Attorney General Department of Justice State of Louisiana
~ P.O. Box 94005 Baton Rouge, Louisiana 70804-9005 H. Anne Plettinger 3456 Villa Rose Drive -
Baton Rouge, Louisiana 70806
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Pres' dent of West Feliciana Police Jury P.O. Box 1921 St. Francisville, Louisiana 70775 William H. Spell, Administrator Louisiana Radiation Protection Division ;
P.O. Box 82135 Baton Rouge, Louisiana 70884-2135 l
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Entergy Operations, Inc. -4 SEP - 9 1998
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Regional Administrator Resident inspector DRP Director DRS-PSB Branch Chief (DRP/C) MIS System Project Engineer (DRP/C) RIV File Branch Chief (DRP/TSS)
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Entergy Operations, Inc. -4 gg _ g g bec to DCD (IE01)
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Regional Administrator Resident inspector DRP Director DRS-PSB Branch Chief (DRP/C) MIS System .
Project Engineer (DRP/C) RIV File
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l DOCUMENT NAME: R:\_RB\RB812AK.GDR l To receive copy of document, indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy RIV:PE:DRP/C C:DRP/C D:DRP JFMelfi;df fm CSMarschall(%i TPGwynry ///2
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9/ 4 /98 V
9 4 /98 9/ C' /98 I' f OFFICIAL RECC RD COPY
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Rick J. King j
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August 27,1998
I U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk, OP-17 Washington, D.C. 20555 Subject: Reply to Notices of Violation in inspection Report 50-458/98-012 River Bend Station - Unit I License No. NPF-47 Docket No. 50-458 > j lg ri'~ ' m
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File Nos.: G9.5, G15.4.1 ll ? '
RBG- 44616 l~' S- 2r .
RBF1-98- 0227 Ladies and Gentlemen:
i Pursuant to the provisions of 10CFR2.201, Attachment 'A' provides Entergy Operations, Inc. (EOl) responses to the Notices of Violation 50-458/98012-01 and 50-458/98012-02. The commitments contained in this document are identified on Attachment 'B'.
Should you have any questions regarding the attached information, please contact Mr. David Lorfing of my staff at (225) 381-4157.
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Sincerely,
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Reply to Notice of Violation in 50-458/98-012 August 27,1998 '
l RBG-44616 RBF1-98-0227 '
Page 2 of 2 cc: Regional Administrator U.S. Nuclear Regulatory Commission ,
Region IV-
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611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 1 i
NRC Sr. Resident inspector P.O. Box 1050 St. Francisville, LA 70775 David Wigginton NRR Project Manager U.S. Nuclear Regulatory Commission M/S OWFN 13-H-3 Washington, DC 20555 l l
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ATTACHMENT A !
REPLY TO NOTICE OF VIOLATION 50-458/98012-01 Page 1 of 7 Violation:
Technical Specification 5.4.1 states, in part, " Written procedures shall be established, implemented, and maintained covering the following activities: The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978."
Regulatory Guide 1.33, Revision 2, Appendix A, February 1978 specifies, in part, procedures for equipment control (locking and tagging). l l
l Procedure ADM-0027, " Protective Tagging," Revision 16, requires the operator to, perform component positioning in the sequence shown.
The Clearance Order 98-0583 (Clearance Authorization / Installation /
Removal Sheet) specified, in part, that the 'C' Residual Heat Removal Pump breaker be racked-in.
Procedure SOP-0046, "4.16 KV System," Revision 13, Attachment 5 j defines steps necessary for racking-out and racking-in 4.16 KV plant breakers. As part of the racking-out process the procedure states,
"deenergize the breaker control power fuse block." This is accomplished by pulling the breaker's control power fuses.
Contrary to the above, on June 1,1998, while accomplishing Clearance Order 98-0583, the operator did not follow the sequence shown on the clearance order while positioning components in that he manipulated the Division 11 diesel generator output breaker (by pulling control power fuses) instead of the C residual heat removal pump breaker, which was the next component in sequence. The diesel generator output breaker was not specified on the clearance order.
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Reasons for the Violation:
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Following restoration of a clearance, which included the restoration of the 'C'
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Residual Heat Removal Pump Breaker, it was noticed in the Main Control Room (MCR) that the breaker had no " control power available" indication. The Control Room Supervisor instructed the Operator performing the restoration to remove
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and re-install the control power fuses. The assumption was that the fuse
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ATTACHMENT A REPLY TO NOTICE OF VIOLATION 50-458/98012-01 Page 2 of 7 contacts may not have made proper connection. The Operator performed this action, and reported it to the MCR. This action did not correct the problem. The Operator was instructed to rack out and reinstall the breaker believing that it was l possible that the breaker stabs had not made a good connection. The Operator then opened the cubicle door for the Division 11 Diesel Generator (DG) Output )
Breaker and removed the control power fuses. When alarms were received in ]
l the MCR, the Operator was contacted and instructed to immediately restore the l l Division 11 DG breaker control power fuses. Subsequently, 'C' Residual Heat l
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l Removal Pump breaker was racked out and then back into its cubicle, which l alleviated the original problem.
A task analysis of the event revealed that the removal and subsequent
- installation of the control power fuses was appropriately accomplished using ;
Operator " tool box skills" acquired from training and plant experience. The
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l breaker racking evolution was performed in accordance with Station Operating
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Procedures.
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A root cause investigation was conducted, and the primary cause identified was failure to adequately self-check (more specifically, the need to re-verify the correct component after breaking eye contact and prior to taking action).
River Bend Station's Operation Department Management recognized that this l specific violation is a potential indicator of a more generic underlying issue regarding human performance. River Bend Station, in order to proactively !
l address the broader issues, sponsored an Adverse Trend Condition Report and j l resulting investigation. The investigation included a review of several condition l reports for a period beginning September 1997 until July 1998. Notable during ;
l this review was the fact that the failures to self-check were primarily in the field i
- and not in the Main Control Room. This analysis helped to identify the l necessary corrective actions to address the trend and correct this specific violation.
Major causes identified during the investigation:
e Reinforcement of Expectations during activities external to the Main Control Room is less than adequate (both supervisory and peer reinforcement)
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ATTACHMENT A REPLY TO NOTICE OF VIOLATION 50-458/98012-01 Page 3 of 7
. Contact with personnel during activities external to the Main Control Room is too infrequent to detect work habit / attitude changes (supervisory methods)
. Job performance and self-checking standards are not properly communicated during activities external to the Main Control Room (supervisory methods)
. Self-imposed Schedule Pressure during accomplishment of field activities external to the Control Room (usually self-driven, not supervisory driven)
. Failure to obtain Independent Verification or a peer check / Failure to Self-Check when performing activities external to the Control Room
. Failed to Follow Procedure (also primarily applicable to field activities external to the Main Control Room (configuration control)
Actions to address this adverse trend and those that specifically address this violation are seen as mutually inclusive and are provided without distinction.
Corrective Actions That Have Been Taken:
. Counseled operator involved.
. A Condition Report was written to identify an adverse trend in Operation's human performance.
. The adverse trend was discussed with the Operations Senior Management Team (OSMT) to raise Supervisory awareness of this negative trend.
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! . The Operations Superintendent / Designee provided a bi'efino to Operations and Operations Training personnel on these and other recent human performance events, emphasizing STAR / Peer Checking, focusing on the task at hand, reducing self-imposed schedule pressure, personal accountability, and procedural compliance / ownership.
. Self-checking Simulator (STAR) Trainer was presented at Operations non-l licensed operator training.
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ATTACHMENT A REPLY TO NOTICE OF VIOLATION 50-458/98012-01 Page 4 of 7
. Operations Standards and Expectations (OS&E) on Peer Checking and Self Checking were revised to provide more specific guidelines.
. Operations Shift Superintendents (OSSs) discussed the recent incidents with their crews, emphasizing the importance of using Peer Checks and Self Checks.
Corrective Actions That Will Be Taken to Avoid Further Violations:
. Evaluate past breaker racking failures to determine if the cause is mechanical, or due to mis-operation.
. The STAR Trainer or Simulator Training will be provided to licensed operators during requalification with additional focus on coaching and management observations.
. The Operations Superintendent / Designee will discuss supervisory oversight expectations with each Operations Shift Supervisor / Control Supervisor in one-on-one sessions. As part of this discussion, include discussion on improving field coaching / oversight from afar, minimizing work distracters (non-productive tasks), use of effective pre-job /tailboard briefings, preventive vs reactive oversight, and bahncing administrative vs supervisory functions.
Date When Full Compliance Will Be Achieved:
Adequate controls were in-place at the time of the violation and full compliance was achieved immediately upon restoration of the Diesel Generator Breaker Control Power Fuses on June 1,1998.
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jn l ATTACHMENT A REPLY TO NOTICE OF VIOLATION 50-458/98012-02 l
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l Violation:
10 CFR 50.54q states, in part, "A licensee authorized to possess and operate a nuclear power reactor shall follow and maintain in effect emergency plans which meet the requirements in appendix E of this part."
10 CFR 50, Appendix E, Section D.3 states, in part,"The design objective of the prompt public notification system shall be to have the capability to essentially complete the initial notification of the public within the plume l
exposure pathway EPZ [ emergency planning zone) within about 15 l
minutes.
Section 13.3.5.4.1.2.2 of the River Bend Emergency Plan states, in part:
1) "The prompt notification system for the 10-mile EPZ of the RBS [ River Bend Station]... consists of high-powered electronic sirens and alert monitoring radios which provide comprehensive coverage of the local residential and transient population;" and 2)"RBS shall ensure that means exist to notify and provide prompt emergency instructions to the population in the plume exposure pathway EPZ."
Appendix 3 of NUREG-0654 states, in part,'Within the plume exposure EPZ, the system shall provide an alerting signal. The minimum acceptable l design objectives for coverage by the system are: a) capability for l providing an alert signal to the population on an area wide basis throughout the 10 mile EPZ, within 16 minutes . "
Contrary to the above, between May 14 and June 3,1998, the prompt notification system was not capable of providing an alert signal to the population on an area wide basis throughout the 10 mile EPZ within 15 minutes due to inadequate post-installation testing of system software.
l Reasons for the Violation:
During the monthly siren test on June 3,1998, only the first parish tested had sirens sound. River Bend Station (RBS) Emergency Preparedness immediately notified parish Emergency Operations Center (EOC) personnel of the failure and advised them to use their alternate means to alert the public. RBS Emergency Planning also notified state and federal agencies; and through the Control Room, reported the incident to the NRC Staff. The site investigation concluded that during the period of time from installation of the upgraded software until l
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ATTACHMENT A REPLY TO NOTICE OF VIOLATION 50-458/98012-02 Page 6 of 7 I
discovery (the period of May 14 to June 3,1998), if sounding had been i sequenced through the parish EOCs, then only the sirens in the first parish would have sounded. To sound other parishes would have inserted an added
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delay (as tested) of up to 18 minutes. The reason for this delay would have been to allow rebooting of the computer and enable use of the previous version of the software. This delay was not recognized until the problem was identified.
This delay may have affected the system's ability to assist state and local parish officials in the alert of the public within the 10-mile Emergency Planning Zone.
NUREG-0654 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" requires the system to be capable of being sounded within about 15 minutes after the decision to do so by the offsite authorities. ;
A root cause investigation was conducted with the following primary causes identified:
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. Did not use applicable procedures - i.e., Failure to enforce management ;
systems / Communications of Standards, Policies, and Administrative Controls
. An inadequate plan was used during post installation testing.
Corrective Actions That Have Been Taken:
. Reinstalled previous version of software.
. Tested the reinstalled version by sequencing silent activation through parish EOCs
. Conducted successful audio functional test Corrective Actions That Will Be Taken to Avoid Further Violations:
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. Provide Computer Software QA requirements training to Emergency ;
Preparedness personnel emphasizing proper system functional testing.
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. Compile Computer Software QA Compliance Package for siren software, that
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will test all software functions prior to releasing software for use. Establish a test bed in which to test the siren system.
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w ATTACHMENT A REPLY TO NOTICE OF VIOLATION 50-458/98012-02 Page 7 of 7 Date When Full Compliance Will Be Achieved:
Adequate controls were in-place at the time of the violation and full compliance
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i was' achieved on June 9,1998 following satisfactory performance testing of the '
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ATTACHMENT B COMMITMENT IDENTIFICATION FORM Page 1 of 1 Violation 50/458/98012-01 COMMITMENT ONE-TIME CONTINUING l ACTION COMPL!ANCE I Evaluate past breaker racking failures to determine if the X cause is mechanical, or due to mis-operation.
The STAR Trainer or Simulator Training will be provided to X licensed operators during requalification with additional l
focus on coaching and management observations.
L The Operations Superintendent / Designee will discuss X supervisory oversight expectations with each Operations Shift Supervisor / Control Room Supervisor in one-on-one sessions. As part of this discussion, include discussion on improving field coaching / oversight from afar, minimizing l work distracters (non-productive tasks), use of effective pre-job /tailboard briefings, preventive vs reactive l oversight, and balancing administrative vs supervisory l functions.
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Violation 50/458/98012-02 l COMMITMENT ONE-TIME CONTINUING l
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l ACTION COMPLIANCE Provide Computer Software QA requirements training to X Emergency Preparedness personnel emphasizing proper j system functional testing.
Compile Computer Software QA Compliance Package for X l
siren software, that will test all software functions prior to releasing software for use. Establish a test bed in which to test the siren system.
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