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MONTHYEARML20058M4021993-12-0808 December 1993 Forwards TIA,93TIA006,interpretation of Reporting Requirements Re Multiple Failures of safety-related Components Project stage: Other ML20058L6931993-12-0808 December 1993 Forwards TIA 93TIA006,interpretation of Reporting Requirements Re Multiple Failures of safety-related Components Project stage: Other ML20058L0091993-12-0808 December 1993 Forwards NRR 931102 Response to Region IV 930413 Request for Interpretation of Reporting Requirements Re Multiple Failures of safety-related Components Identified During Performance of Surveillance Testing Project stage: Other ML20058K9811993-12-0808 December 1993 Forwards NRR 931102 Response to Region IV Request for Interpretation of Reporting Requirements Re Multiple Failures of safety-related Components Identified During Performance of Surveillance Testing for Info Project stage: Other ML20058K6001993-12-0808 December 1993 Forwards Tia,Interpretation of Reporting Requirements, 93TIA006 Re Multiple Failures of safety-related Components Project stage: Other ML20058K5961993-12-0808 December 1993 Forwards Tia,Interpretation of Reporting Requirements - 93TIA006,re Multiple Failures of safety-related Components Project stage: Other ML20058K5801993-12-0808 December 1993 Forwards Tia,Interpretation of Reporting Requirements - 93TIA006,re Multiple Failures of safety-related Components Project stage: Other ML20058K5611993-12-0808 December 1993 Forwards Tia:Interpretation of Reporting Requirements, 93TIA006.Guidance Provided in Response to Region 5 Request for Interpretation of Reporting Requirements for safety- Related Components Project stage: Other 1993-12-08
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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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pm RIcg UNIVE D ST ATES
. g WUCLEAR REGULATORY COMMISSION fW j necioN iv 611 RYAN PLAZA DRIVE, SUITE 400 p, [ ARLINGTON, TEXAS 76011-8064 4 e DEC 8 1993 Docket: 50-458 License: NPF-47 ,
Gulf States Utilities ATTN: John R. McGaha, Vice President :
River Bend Nuclear Group i P.O. Box 220 St. Francisville, Louisiana 70775
SUBJECT:
TASK INTERFACE AGREEMENT: INTERPRETATION OF REPORTING REQUIREMENTS - 93TIA006 (TAC NO. M86339)
The purpose of this letter is to provide for your information a copy of the guidance recently issued by the Office of Nuclear Reactor Regulation in their Memorandum of November 2, 1993, to Region IV (see enclosed). This guidance was provided in response to a Region IV request for interpretation of reporting requirements related to multiple failures of safety-related components that are identified during the performance of surveillance testing.
I We plan to implement this guidance during out future inspections at your facility. Should you have questions regarding this matter, please contact Tom Westerman of my staff at 817-860-8145.
rector Division of Reactor Safety
Enclosure:
(as noted) cc w/ enclosure: i Gulf States Utilities ATTN: J. E. Booker, Technical Assistant. ;
P.O. Box 220 St. Francisville, Louisiana 70775 Gulf States Utilities ATTN: Harold W. Keiser, Senior Vice President P.O. Box 220 St. Francisville, Louisiana 70775 Gulf States Utilities ATIN: Michael B. Sellman, Plant Manager P.O. Box 220 St. Francisville, Louisiana 70775 9312150334 931200 PDR M
P ADOCK 05000458 O PDR y-
]
l Gulf States Utilities )
Gulf States Utilities ATTN: James J. Fisicaro, Manager - Safety ,
Assessment and Quality Verification l P.O. Box 220 r St. Francisville, Louisiana 70775 t
Winston & Strawn !
ATTN: Mark J. Wetterhahn, Esq.
1401 L Street, N.W. '
Washington, D.C. 20005-3502 ,
Gulf States Utilities ATTN: Les England, Director Nuclear Licensing !
P.O. Box 220 j
t St. Francisville, Louisiana 70775 Mr. J. David McNeill, III William G. Davis, Esq. t Department of Justice ,
Attorney General's Office i P.O. Box 94095 i Baton Rouge, Louisiana 70804-9095 i H. Anne Plettinger !
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Cajun Electric Power Coop. Inc. I ATIN: Philip G. Harris {
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Hall Bohlinger, Administrator :
Radiation Protection Division 1' P.O. Box B2135 Baton Rouge, Louisiana 70884-2135 t
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f WASHINGTON. D.C. 2055b-0001 November 2, 1993 MEMORANDUM FOR: Samuel J. Collins, Director Division of Reactor Safety Region IV FROM: Elinor G. Adensam, Assistant Director for Regions IV and V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
SUBJECT:
TASK INTERFACE AGREEMENT: INTERPRETATION OF REPORTING REQUIREMENTS - 93TIA006 (TAC NO. M86339)
In response to your request dated April 13, 1993, we have reviewed the available guidance associated with the reporting requirements related to multiple failures of safety-related components that are identified during the performance of surveillance procedures. The specific examples cited in your questions regarded the outage surveillances related to primary or secondary safety relief valves and the discovery that the as-found setpoints were outside the allowable technical specification setpoint tolerances. Please note that the Public Document Room (PDR) has been included on the distribution for this response.
Licensees were stated to have presented interpretations of the reporting rules (10 CFR 50.72/50.73) and the related guidance provided in NUREG-1022, which supported the conclusion that the discovery of safety valve setpoint drift was not reportable. Specifically, question 2.3 of NUREG-1022, Supplement 1, had been used to argue that the condition was not reportable, because the condition could be assumed to have occurred at the time of discovery. Another argument presented by licensees was stated to involve analyses or evaluations which determined that the degraded setpoints did not result in the plant ,
operating outside its design basis, and therefore supported a conclusion that :
the condition was not reportable.
A review of 50.72 and 50.73 identifies several reporting criteria which might be relevant to the discovery of safety valves outside the setpoint tolerances given in the Technical Specifications. These criteria and a discussion of ;
their applicability is provided in Enclosure 1.
The assessment can be summarized as follows:
- The use of question 2.3 to NUREG-1022, Supplement 1, is not appropriate -
to justify a decision to not report many conditions found during refueling outage surveillances. Other guidance in Supplement 1 is clear i that if conditions are discovered during an outage, but are believed to have existed during operation, they are reportable so long as an ,
applicable threshold for reporting is reached.
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Samuel J. Collins November 2, 1993
- A licensee may determine that a condition such as safety valve setpoint drift, does not constitute operation outside the design basis of the !
plant, and therefore not report such events in accordance with those criteria in 50.72 and 50.73. However, as discussed below, the condition m y be reportable as a result of other criteria.
- 50.73(a)(2)(vii) is deemed the most relevant criterion for the reporting of primary or secondary safety valves found to be outside the acceptable setpoint tolerance. This is due to the fact that this criterion is based on the train or channel level and does not require the' loss of a-safety function but only the inoperability of multiple channels of a safety system. Some latitude might be given in light of the number of secondary safety valves; but, for most instances of setpoint drift, this criterion would result in the conditions being reportable. >
Note that we currently expect to include guidance along these lines in ,
the forthcoming Revision 1 to NUREG-1022; if so, that specific guidance '
should be consulted in the future in determining reportability. ,
Elinor G. Adensam, Assistant Director. ,
for Regions IV and V Division of Reactor Projects III/IV/V ;
Office of Nuclear Reactor Regulation '
Enclosure:
Criteria i cc w/ enclosure !
W. Hodges, Region I e A. Gibson, Region II :
G. Grant, Region III K. Perkins, Region V l
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t ENCLOSURE ASSESSF.ENT OF VARIOUS REPORTING REQUIREMENTS FOR APPLICABILITY TO '
PRIMARY OR SECONDARY SAFETY VALVES FOUND OUTSIDE TECHNICAL SPECIFICATION ACCEPTABLE SETPOINT TOLERANCE BAND
- 50.72(b)(1)(ii) Any event or condition during operation that results in the 50.73(a)(2)(ii) condition of the nuclear power plant, including its
- principal safety barriers, being seriously degraded; or results in the nuclear power plant being:
(A) In an unanalyzed condition that significantly !
compromises plant safety; i (B) In a 1 .,dition that is outside the design basis of l the plant; or *
(C) In a conditica not covered by the plant's operating and emergency procedures.
Discussion: The applicabi?ity of these criteria is determined by an i evaluation of the situation by the licensee. Upon determining that the setpoints were outside the allowable !
range of the technical specifications, the licensee would be expected to follow the required actions of the technical i specifications and assess the plant condition in regards to ,
equipment operability and required corrective actions. :
Guidance related to the evaluation of degraded and '
nonconforming conditions is provided by Generic Letter-91-18. As stated in the second draft of NUREG-1022, Revision 1, it is expected that licensees may use engineering judgement and experience in determining whether !
a condition meets these reporting criteria. The ability of '
a licensee to justify that a given condition is neither unanalyzed nor outside the design basis is dependent on the as-found condition of the equipment and the degree of analyses performed. -
I 50.72(b)(2)(i) Any event, found while the reactor is shut down, that, had it been found while the reactor was in operation, would have '
resulted in the nuclear power plant, including its principal safety barriers, being seriously degraded or being in an ;
unanalyzed condition that significantly compromises plant a safety.
Discussion: The arguments are very similar to those above and again can :
support either a reportable or non-reportable conclusion based on the licensee's assessment of the significance of the condition. However, this criterion was intended to capture potential problems which might be discovered only during refueling outage surveillances. Question 7.10 in . i NUREG-1022, Supplement 1, is considered relevant guidance in regard to the reportability of equipment found to be inoperable during cutage surveillances. ,
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Question 2.3 of NUREG-1022, Supplement 1, and the second draft of NUREG-1022, Revision 1, state that failures should be assumed to occur at the time of discovery unless there is 4 firm evidence to believe otherwise It seems appropriate to !
classify setpoint drift as a mechanism which would occur i some time (usuelly indeterminable) during the period between calibration and subsequent surveillance unless some factor, t such as an extended outage or testing conditions, could be identified as-a likely cause. If testing conditions or other causes are identified such that reporting is deemed unnecessary, the licensee would still be expected, under other programs and regulatory requirements, to evaluate the adequacy of the surveillance program to ensure that the '
activity is ensuring the operability of the safety valves or other components. A voluntary report may still be useful as a means of distributing the information related to the problem and its cause to the industry. Please note that although question 2.3 may be deemed an insufficient reason to determine safety valve drift is not reportable, the licensee may determine that the significance (see above) of :
the condition does not satisfy the reporting threshold. '
50.72(b)(2)(iii) Any event or condition that alone could have prevented the 50.73(a)(2)(v) fulfillment of a safety function of structures or systems i that are needed to:
(A) Shut down the reactor and maintain it in a safe shutdown condition, (B) Remove residual heat, (C) Control the release of radioactive material, or (0) Mitigate the consequences of an accident.
Discussion: The second draft of NUREG-1022, Revision 1, provides safety valve drift as an example of a common mode problem which may be reportable under this criterion. The example was added, to the case described in Information Notice 85-27 which dealt with multiple inoperable control rods. Although certain occurrences of multiple safety valve drift problems should be determined to be reportable under this criterion, it should not be assumed that all cases of one or more safety valves exceeding the technical specification tolerance band need be reportable in accordance with this criterion. As in the previously discussed reporting criteria, the licensee's engineering judgement should determine if the condition could have prevented the fulfillment of a safety function. Candidates for reporting include those cases in which the setpoints of multiple safety valves could have resulted in exceeding the associated system's design pressore. If experience or engineering judgement can reasonably estimate the maximum i
( ,
e drift which might occur and determine that the safety '
function would be maintained, the licensee can determine that the condition is not reportable.
Although discussed in the various drafts and revisions of NUREG-1022, it warrants repeating that the primary motivation behind evaluating plant conditions such as safety valve drift should be to ensure safety and only secondarily '
to determine reportability. If engineering assessments identify a problem and determine that plant equipment was not and reasonably could not be rendered inoperable by a phenomenon such as setpoint drift, the licensee can then ;
also justify a determination that the condition is not reportable. Voluntary reports are appreciated if the licensee feels the information might be helpful to others. l The staff should, as always, be cautious in recommending that a licensee make a " voluntary" report.
50.73(a)(2)(vi) Events covered in paragraph (a)(2)(v) of this section may ,
include one or more procedural errors, equipment failures, '
and/or discovery of design, analysis, fabrication,- e construction, and/or procedural inadequacies. However, I individual component failures need not be reported pursuant j to this paragraph if redundant equipment'in the same system (
was operable and available to perform the required safety function.
Discussion: (See above) 50.73(a)(2)(vii) Any event where a single cause or condition caused at least ,
one independent train or channel to become inoperable in i multiple systems or two independent trains or channels to .
become inoperable in a single system designed to:
(A) Shut down the reactor and maintain it in a safe shutdown condition, (B) Remove residual heat, (C) Control the release of radioactive material, or {
(D) Mitigate the consequences of an accident. '
Discussion: This criterion may be the most relevant to the specific example of safety valves found outside the technical specification tolerance band. As stated in the second draft-of NUREG-1022, Revision 1, the reporting threshold for this part of 10 CFR 50.73 is lower than for other parts since it is at the train or channel level rather than the system and function levels. Valves found outside the technical specification setpoint tolerance band can reasonably be considered to have been inoperable during operation unless a licensee determines that testing is not representative of conditions during operation (see item 50.72(b)(2)(i)). This
criterion was developed with general consideration given to the normal two train design level of redundancy. Given that most plants can satisfy pressure relief requirements with several main steam safety valves unavailable, a rigid interpretation of this criterica regarding the secondary safety valves (i.e., any case with more than one safety valve outside the tolerance band) may be overly conservative. However, the licensees are considered to have the weakest argument if they determine that this criterion is not applicable, and therefore the condition is not reportable, when finding multiple safety. valves outside the acceptable range.
50.73(a)(2)(i.8) Any operation or condition prohibited by the plant's technical specifications.
Discussion: Available guidance regardina operability and technical specification requirements generally have licensees enter the allowed outage time and associated action statements upon discovery of equipment inoperability unless a definite time of inoperability can be established. Technical i specifications are considered satisfied provided the allowed outage time and associated action statements are satisfied.
Therefore, provided that licensees restore compliance prior i to returning to power operation, reporting of safety valve l drift in accordance with this criterion would not be necessary. However, it is expected that upon identification of a problem such as safety valve setpoint drift, licensees should take actions to prevent recurrence or pursue a change in the technical specification requirements (such as increasing the acceptable tolerance range of the.setpoints).
If a licensee determines, through industry experience, information from a vendor, or self assessments, that a component may be inoperable during operation, appropriate actions should be taken in accordance with the technical specifications (reduce power or shutdown). This reporting
! criterion may be applicable if a licensee fails to satisfy l the required action or can determine that a limiting condition of operation had not been satisfied for longer than the allowed outage time following a specific cause for a component becoming inoperable.
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