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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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.7 A+t NUCLEAR REGULATORY COMMISSION
$ REclON IV
611 RYAN PLAZA DRIVE, SUITE 400 0[ AR LlNGTON, TEXAS 760118064
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MAR 2 51998 John R. McGaha, Vice President - Operations River Bend Station Entergy Operations, Inc.
P.O. Box 220 St. Francisville, Louisiana 70775 l l'
SUBJECT: NRC INSPECTION REPORT 50-458/97-19
Dear Mr. McGaha:
j Thank you for your letter of March 9,1998, in response to our letter and Notice of Violation dated December 24,1997. We have reviewed your reply and find it responsive to the issues raised in our Notice of Violation: a failure of plant workers to maintain appropriate separation criteria l between a safety-related cable tray and a temporary cable; the failure to maintain the postaccident sample system to ensure the capability to take gaseous and liquid samples following an accident; and ineffective corrective actions to address air entrapment in reactor core isolation system instrument lines.
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.
Sincerely, (( 0
.O L Elmo E. Collins, Chief Project Branch C f Division of Reactor Projects I Docket No.: 50-458 License No.: NPF-47 f i cc: I Executive Vice President and Chief Operating Officer Entergy Operations, Inc.
P.O. Box 31995 -
Jackson, Mississippi 39286-1995 9903300131 980325 PDR ADOCK 05000458 G PDR I
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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 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
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Entergy Operations, Inc. -3-H. Anne Plettinger 3456 Villa Rose Drive Baton Rouge, Louisiana 70806 President 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
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Entergy Operations, Inc. -4- MAR 2 51998
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Regional Administrator
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Senior Resident inspector (Grand Gulf)
DRP Director DRS-PSB Branch Chief (DRP/C)~ MIS System Project Engineer (DRP/C) RIV File Branch Chief (DRPfrSS) Resident inspector DOCUMENT NAME: R:\_RB\RB719AK.GDR l To receive copy of document, indicate in box: "C" = Copy without enclosures "E" = Copy wth enclosures "N" = No copy -
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Entergy Operations, Inc. -4- WF . 5 i998 bec distrib. by RIV:
Regional Administrator Senior Resident inspector (Grand Gulf)
DRP Director DRS-PSB Branch Chief (DRP/C) MIS System
' Project Engineer (DRP/C) RIV File Brcnch Chief (DRPli SS) Resident inspector I
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i DOCUMENT NAME: R:\_RB\RB719AK.GDR To receive copy of document, Indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy RIV:DRP/C , C:DRP/Q),
PJAlter;df /f6 l EECollitif(/
3/tv /98 ..) 3 % /98 OFFICIAL RECORD COPY 300001
8. Ent:rgy operations. Inc.
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March 9.1998
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U.S. Nuclear Regulatory Commission l"
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4-Document Control Desk. OPI-17
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i Subject: Reply to Notices of Violation in IR 97-019 --
River Bend Station Unit I -~ ~
License No. NPF-47 i
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Docket No. 50-458
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File Nos.: G9.5.G15.4.1 RBG-44415 RBF1 98-0068
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Ladies and Gentlemen:
Pursuant to the provisions of 10CFR2.201, Attachments A, B and C provide the Entergy Operations. Inc. responses to the Notices of Violation (NOV) described in NRC inspection Report (IR) 50-458/97-019.
We have aggressively reviewed the subject violatiorts with a self-critical perspective to improve Riser Bend Station perfonnance. The lessons teamed are being addressed and integrated into our practices and programs as described in the attachments.
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Should you have any questions regarding the attached information, please contact Mr. David Lorfing of my staff at (504) 381-4157.
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a Reply to Notice of Violation in 50-458/97-019 March 9,1998 RBG-44415
' RBF1-98 0068 Page 2 of 2 cc: Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington,TX 76011
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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
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ATTACHMENT A Reply To A Notice of Violation IR 50-458/9719-01 Page 1 of 2 Violation:
10 CFR Part 50, Appendix B, Criterion V, states, in part, " Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings . . ."
Updated Final Safety Analysis Report Section 8.3.1.4.2 requires that safety-related cables from different divisions and nonsafety-related cables be separated per the minimum allowable separation distances in Table 8.3.9, " Separation Criteria Allowable Versus Tested." Table 8.3-9 requires one foot of separation between a horizontal tray and a cable.
Procedure ADM-0073, " Temporary Installation Guidelines," Revision 2, Step 5.2, requires that temporary installations adhere to the design separation from divisional cable and that plant personnel be cognizant of the separation requirements of a temporary installation to divisional cabling as specified on Drawing EE-34ZE.
Drawing EE-34ZE, " Standard Details for Separation Requirements," Revision 7, identifies the separation requirements for free air cables to trays as one foot.
~ Contrary to the above, on December 4,1997, an extension cord was draped across safety-related cable Tray ITX817B, with free-air cables, and the required one-foot separation was not maintained.
Reasons for the Violation: ,
A root cause analysis was performed which determined the root causes to be:
* Corrective actions from a previous condition report (CR) for a similar event were not ' '
yet fully implemented. As corrective action from the previous event, procedural changes to ADM-0073," Temporary Installation Guidelines," were made, but l
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Revision 3 of the procedure was not issued and available for plant personnel to use on December 4,1997. Additional means to prevent recurrence (such as temporary power cord tagging) had not been finalized at the time ofinstallation of the cable identified in the subject violation. ;
* Training on the proper installation of temporary electrical cords for the personnel involved had not been completed.
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Corrective Actions Which Have Been Taken and the Results Achieved:
* The subject extension cord was removed.
. ADM-0073, Revision 3 was issued on December 15,1997.
. Potential users of extension cords were notified of the changes to ADM-0073 to ensure that additional emphasis was being provided in Maintenance, Chemistry, l Radiation Protection and Operations. {
e Operations crews performed a walkdown of the plant to identify if other separation discrepancies were present. Items found were corrected. ;
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Corrective Actions That Will Be Taken To Avoid Further Violations: l e A briefing sheet will be prepared to provide Operations department personnel with information regarding the changes to ADM-0073.
. The Operations Superintendent will discuss the requirements of ADM-0073 with Operations crews.
e Tags will be procured which provide the separation criteria of ADM-0073. These ;
tags will be placed on extension cords in the tool room and distributed to other j departments with guidance for their use. j
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e Training covering ADM-0073 will be developed and implemented for plant l
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e ADM-0073 requirements will be added to the outage handbook.
- The process for handling temporary power cables will be changed to ensure that these cables are issued by the tool room.
Date When Full Compliance Will Be Achieved:
Full compliance was achieved on December 4,1997 when the subject extension cord was removed. Subsequent plant walkdowns were completed by January 31,1998 to ensure ,
that other discrepancies were identified and corrected.
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ATTACHMENT B Reply To A Notice Of Violation I IR 50-458/9719-03 Page 1 of 2 Violation: 1
Technical Specification 5.5 states, in part, "the following programs and manuals shall be established, implemented, and maintained ...
5.5.3 Post Accident Sampling... This program provides controls that ensure the capability to obtain and analyze reactor coolant, radioactive gases, and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions. The program shall include the following... Provisions for maintenance of sampling and analysis {
equipment."
Contrary to the above, between March 3 and December 12,1997, provisions for maintenance of sampling and analysis equipment were inadequate to effectively ensure the capability to obtain and analyze reactor coolant, radioactive gases, and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions.
The post accident sampling system was out of service for approximately 50 percent of the time during the subject period.
Reason For The Violation:
A root cause determination provided the following primary causes: j i
e Monitoring and ownership of the post accident monitoring system (PASS) were ineffective. Some personnel involved in monitoring of the system did not fully understand the scope of their responsibilities or have proper understanding of the impact ofissues on the system. Responsibility for ensuring prompt performance of corrective maintenance was not clearly understood. .,
* The design configuration allowed water intrusion into the dry nitrogen portion of the _
system. Some valves were found to be incorrectly installed. This led to equipment j degradation and system malfunction.
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Corrective Actions That Have Been Taken and the Results Achieved: j
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* A system engineer was assigned responsibility for PASS.
- A modification was installed to provide separation between the dry and wet sides of i
the nitrogen supply to PASS.
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e The PASS has been thoroughly inspected for degradation caused by the water intrusion.
e The incorrectly installed valves in the PASS sample station have been correctly installed.
- Other potential sources of water intrusion were researched and determined not to be {
valid sources of water intrusion.
- A walkdown was performed to ensure that plant configuration and design configuration match.
- Chemistry PASS sampling procedure, COP-1001, has been revised to include information related to pressurization of the system water tank. This will minimize the potential for water intrusion.
Corrective Action That Will Be Taken To Avoid Further Violations:
* Operations shift superintendents, control room supervisors, maintenance supervisors and work week managers will review Operations Policy 6," Active Limiting Conditions of Operation," to reinforce management expectations with respect to the use oflimiting conditions of operation.
l e An evaluation will be performed to determine if a process to review the accumulated effects of repeated entry into tracking LCOs (Limiting Conditions of Operation) is needed. l
e Other maintenance rule scoped systems will be evaluated to ensure proper assignment j of system ownership.
- Responsibilities for personnel outside system engineering who "own" systems will be !
clarified. Personnel outside system engineering who "own" a system will be informed of their responsibilities.
* A procedure will be developed describing how PASS satisfies Technical Specification 5.5.3 including the expectations and responsibilities of the various departments involved, o Engineering will evaluate and take appropriate action to ensure proper -
implementation of other similar programs identified in Technical Specification 5.5.
Date When Full Compliance Will Be Achieved:
Full compliance was achieved on March 7,1998 when the limiting condition on operation was removed.
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a ATTACHMENT C Reply To A Notice of Violation IR 50-458/9719-05 Violation
"10 CFR Part 50, Appendix B, Criterion XVI, states, in part, " Measures shall be established to assure that conditions adverse to quality, such as . . malfunctions ... are promptly identified and corrected. In the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective
. actions taken to preclude repetition . . ."
Contrary to the above, on January 23,1997, a significant amount of air was found in reactor core isolation cooling flow instrument sensing lines (a significant condition adverse to quality) but established measures did not assure the cause of the air entrapment was identified, and actions were not taken to preclude repetition. Consequently, the following problems were observed due to air entrapment in other system flow instrument lines: (1) on November 11,1997, the high pressure core spray minimum flow valve malfunctioned; (2) on December 11,1997, the residual heat removal Train C minimum flow valve malfunctioned; and (3) on December 12,1997, the residual heat removal Train B minimum flow valve malfunctioned."
Reasons for the Violation:
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Spurious gross failure nuisance alarms had been received in the RCIC (Reactor Core Isolation Cooling) flow transmitter circuit while running the HPCS (High Pressure Core Spray) system and were identified on a condition report in 1993. The condition report was dispositioned with the cause not determined. During the course of a follow-up review of the spurious gross failure alarms including the documented reports, an engineer was led to suspect air in the instrument sensing lines. A maintenance action item was generated on January 23,1997, and RCIC flow instrument sensing line high point vents were vented as part of the investigation into the above' mentioned long standing problem
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involving the receipt of spurious gross failure alarms. Air was found in the high point vent. The system engineer realized that other ECCS (Emergency Core Cooling Systems)
systems could have a simila problem and investigated further by reviewing the ADM-0064 log (Spurious Instrument Trip Log), walking down ECCS systems, checking system l
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indications and discussing the situation with other engineers and operations personnel.
. Based on this investigation, he concluded that other systems were not exhibiting symptoms of this problem and that a Condition Report (CR) was not warranted.
A root cause team was assigned to investigate the cause of the Criterion XVI violation.
The root cause was determined to be less than adequate communication and enforcement
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e of the condition report initiation threshold. The definition of when to initiate a condition report versus a maintenance work document while troubleshooting equipment is not clear.
The root cause team also evaluated previous similar conditions. Causes for these conditions were identified and are being addressed as part of the River Bend Station (RBS) corrective action program.
Corrective Actions That Have Been Taken and the Results Achieved:
As an interim action, a memorandum was issued by the General Manager Plant Operations to RBS personnel addressing management expectations conceming condition report initiation threshold.
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Corrective actions involving the presence of air in transmitter sensing lines was discussed in LER 97-010 as submitted on December 11,1997 and supplemented on February 26, l 1998. The completed actions to resolve this issue included:
. Maintenance and System Engineering personnel conducted troubleshooting to j determine the cause of the minimum flow valve failure.
e The sensing lines from the HPCS pipe to the flow transmitter were vented at the high point vents to remove air indicated by troubleshooting.
. The HPCS pump was run and no abnormalities were noted.
. Following the discovery of air in Residual Heat Removal (RHR) B and C transmitter sensing lines, a team of engineering, operations, and maintenance personnel reviewed safety related instrumentation to determine other susceptible transmitters. As a result, six additional locations were vented.
- An Operations Department Standing Order was issued to direct the venting of instrument lines with the high point vents when necessary.
- Instrumentation technicians and planners were made aware of the effects of entrapped air on instrumentation, and the need to vent instrumentation high point vents.
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Corrective Actions That Will Be Taken To Avoid Further Violations:
The short term actions to address the Criteria XVI violation include:
* The guideline delineating when a condition report should be written will be clarified.
- Reinforcement of the expectation that a CR should be generated if a condition investigation or operability determination of a safety related component identifies the potential to affect safety related system operation, indication, or identifies an unexpected response will be provided.
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r e Training will be provided to RBS personnel to emphasize:
1. Expectations with regard to when CRs should be initiated and actions to be taken when the scope of the CR expands.
2. Consideration of broader, generic implications of conditions, including investigation and identification of previous occurrences.
. The trending process will be improved to routinely review maintenance action items, condhion reports and tracking Limiting Conditions of Operation (LCOs) to identify repetitive failures in safety-related equipment and to provide for timely trend CR initiation.
- ADM-0064 will be revised to clarify when a CR should be initiated during the evaluation ofissues.
The long term corrective actions involving the presence of air in transmitter sensing lines included:
* System configuration will be reviewed to identify other instrumentation with high point vents.
- Final procedural guidance will be developed specifying the appropriate venting requirements for instrument line high point vents. This will include a plan for periodic venting.
- Training on this issue will be provided to appropriate operation's and maintenance personnel. !
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Date When Full Compliance Will Be Achieved:
Full compliance will be achieved by June 30,1998 upon the completion of the short term i corrective actions. (
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