Letter Sequence Other |
---|
|
|
MONTHYEARRBG-44785, Forwards Proprietary Rev 1 to NEDC-32549P, Safety Review for RBS Cycle 7 Final Feedwater Temp Reduction (Ffwtr),In Support of Util 980409 LAR 97-16,allowing FFWTR to Extend Fuel Cycle.Proprietary Rept Withheld Per 10CFR2.7901999-01-13013 January 1999 Forwards Proprietary Rev 1 to NEDC-32549P, Safety Review for RBS Cycle 7 Final Feedwater Temp Reduction (Ffwtr),In Support of Util 980409 LAR 97-16,allowing FFWTR to Extend Fuel Cycle.Proprietary Rept Withheld Per 10CFR2.790 Project stage: Other 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 Project stage: Other 1999-01-13
[Table View] |
|
---|
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
[Table view] |
Text
___ ______ __ _ _ _________
. .- .i.'
A Cfr ug a 'N1 UNITED STATES f j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
,o June 3, 1999 Mr. Randall K. Edington Vice President - Operations Entergy Operations, Inc.
River Bend Station P. O. Box 220 St. Francisville, LA 70775
SUBJECT:
RIVER BEND STATION (RBS), UNIT 1 - REQUEST FOR WITHHOLDING INFORMATION FROM PUBLIC DISCLOSURE (TAC NO. MA1594)
Dear Mr. Edington:
By Entergy Operations, inc's. (EOl's), application dated April 9,1998, and General Electric Company's (GE's) affidavit dated May 5,1997, executed by George B. Stramback, EOl submitted an application for amendment on " Final Feedwater Temperature Reduction Analysis,"
and requested that Attachment 4, NEDC-32549P, " Safety Review for River Bend Station Cycle 7 Final Feedwater Temperature Reduction," Revision 0, be withheld from public disclosure pursuant to 10 CFR 2.790.
On January 13,1999, EOI submitted Revision 1 to Attachment 4, dated October 1998 that contains additional information regarding the feedwater nozzle fatigue evaluation as well as 4 changed the report sections containing GE-proprietary information. The January 13,1999, submittal superceding Revision 0 to Attachment 4, also provided GE's affidavit dated October 15,1998, executed by George B. Stramback, and requested that Attachment 4, NEDC-32549P, " Safety Review for River Bend Station Cycle 7 Final Feedwater Temperature Reduction," Revision 1, be withheld from public disclosure pursuant to 10 CFR 2.790. The information considered proprietary by GE is identified in Attachment 4 by enclosing the phrase with cingle brackets (e.g., "[ GENE proprietary information]").
The October 15,1998, affidavit stated that the submitted information should be considered exempt from mandatory public disciosure for the following reasons:
(4) a. [The] information discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by. General Electric's competitors without license from -
General Electric constitutes a competitive economic advantage over other companies.
- b. [The] information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.
(8) The information...is classified as proprietary because it contains detailed results of analytical models, methods and processes, including computer codes, which GE has developed, obtained NRC approval of, and applied to 9906090219 990603 PDR ADOCK 05000458 L P PDR E _ _ _ _ _ _ _ _ _ _ _
q . (,
R. K. Edington perform evaluations of different plant conditions and parameters for the l BWRs [ boiling water reactors).
The development and approval of the BWR models, methods, processes and computer codes was achieved at a significant cost, on i the order of a million dollars, to GE. I The development of the evaluation process along with the interpretation and application of the analytical results is derived from the extensive experience database that constitutes a major GE asset.
We have reviewed your application and the material in accordance with the requirements of ,
10 CFR 2.790 and, on the basis of your statements, have determined that the submitted j information sought to be withheld contains proprietary commercial information and should be withheld from public disclosure. Therefore, Attachment 4, NEDC-32549P, " Safety Review for
' River Bend Station Cycle 7 Final Feedwater Temperature Reduction," Revision 1, marked as
. proprietary (e.g., "[ GENE proprietary information]"), will be withheld from public disclosure pursuant to 10 CFR 2.790(b)(5) and Section 103(b) of the Atomic Energy Act of 1954, as '
amended.- The original report, Attachment 4, Revision 0, will be destroyed in accordance with EOl's and GE's request detailed in a May 18,1999, telephone call between Ms. Patricia Campbell, EOi, and R. J. Fretz, NRR Project Manager.
Withholding from public inspection shall not affect the right, if any, of persons properly and directly concerned to inspect the documents. If the need arises, we may send copies of this information to our consultants working in this area. We will, of course, ensure that the i consultants have signed the appropriate agreements for handling proprietary information.
If the basis for withholding this information from public inspection should change in the future such that the information could then be made available for public inspection, you should
- promptly notify the Nuclear Regulatory Commission (NRC). You also should understand that i
. the NRC may have cause to review this determination in the future, for example, if the scope of ;
a Freedom of Information Act request includes your information. In all review situations, if the
- NRC makes a determination adverse to the above, you will be notified in advance of any public disclosure.
If you have any questions regarding this matter, I may be reached at (301) 415-1324. ;
. Sincerely, )
/ ,
Robert J. Fretz, Project Manager, Section 1 Project Directorate IV & Decommissioning
- Division of Licensing Project Management-
- Office of Nuclear Reactor Regulation Docket No. 50-458 - .
cc: See next page
r,
" June 3,1 999
' a ' R. K. Edington perform evaluations of different plant conditions and parameters for
' the BWRs [ boiling water reactors).
The development and approval of the BWR models, methods, processes and computer codes was achieved at a significant cost, on the order of a million dollars, to GE.
The development of the evaluation process along with the interpretation and application of the analytical results is derived from
.the extensive experience database that constitutes a major GE asset.
'We have reviewed your application and the materialin accordance with the requirements of 10 CFR 2.790 and, on the basis of your statements, have determined that the submitted information sought to be withheld contains proprietary commercial information and should be
~ withheld from public disclosure. Therefore, Attachment 4, NEDC-32549P, " Safety Review for River Bend Station Cycle 7 Final Feedwater Temperature Reduction," Revision 1, marked as proprietary (e.g., "[ GENE proprietary information]"), will be withheld from public disclosure pursuant to 10 CFR 2.790(b)(5) and Section 103(b) of the Atomic Energy Act of 1954, as amended. The original report, Attachment 4, Revision 0, will be destroyed in accordance with EOl's and GE's request detailed in a May 18,1999, telephone call between Ms. Patricia Campbell, EOl, and R. J. Fretz, NRR Project Manager.
Withholding from public inspection shall not affect the right, if any, of persons properly and directly concerned to inspect the documents. If the need arises, we may send copies of this
'information to our consultants working in this area. We will, of course, ensure that the
. consultants have signed the appropriate agreements for handling proprietary information. I If the basis for withholding this information from public inspection should change in the future such that the information could then be made available for public inspection, you should promptly notify the Nuclear Regulatory Commission (NRC). You also should understand that the NRC may have cause to review this determination in the future, for example, if the scope of a Freedom of Information Act request includes your information. in all review situations, if the . Il 7)
NRC makes a determination adverse to the above, you will be notified in advance of any public disclosure.
' f you have any questions regarding this matter, I may be reached at (301) 415-1324.
I Sincerely, ORIG. SIGNED BY y., , ,_ . Robert J. Fretz, Project Manager, Section 1 0 ~' >; Project Directorate IV & Decommissioning Division of Licensing Project Management
- Office of Nuclear Reactor Regulation
, Docket No. 50-458 : DISTRIBUTION!
SughgMW3 '
PUBLIC : PD4-1 r/f OGC cc: See next page M. P. Siemien K. Brockman ACRS' DOCUMENT NAME: G:\PDIVJ1\RiverBend\LTRA1594.WPD -
To receive e cop r of his document, hdicate in he box C= Copy w/o attachment /erriosure E. Copy with attachment / enclosure N = No copy OFFICE ? PM/PDIV-in E LA/PDIVdr E SRXB , E: OGC- h SC/PDIV-1 O NAME RFretz:db h LBerry, ' b ~ JW M il" MPSiemidh RGramrh DATE f / S) /99 h/ /99 . [/ f /99 ( 5/ h /99 h/ V /99 OFFICIAL RECORD COPY-
]lY
r
', e'.
Mr. Randall K. Edington Entergy Operations, Inc. River Bend Station cc: l l'
Winston & Strawn Executive Vice President and 1400 L Street, N.W. Chief Operating Officer Washington, DC 20005-3502 Entergy Operations, Inc.
P. O. Box 31995 Manager - Licensing Jackson, MS 39286 Entergy Operations, Inc.
River Bend Station General Manager - Plant Operations P. O. Box 220 Entergy Operations, Inc.
St. Francisville, LA 70775 River Bead Station '
P. O. Box 220 Senior Resident inspector St. Francisville, LA 70775 P. O. Box 1050 St. Francisville, LA 70775 Director - Nuclear Safety Entergy Operations, Inc.
President of West Feliciana River Bend Station ,
Police Jury P. O. Box 220 P. O. Box 1921 St. Francisville, LA 70775 St. Francisville, LA 70775 Vice President - Operations Suppert Regional Administrator, Region IV Entergy Operations, Inc.
U.S. Nuclear Regulatory Commission P. O. Box 31995 611 Ryan Plaza Drive, Suite 1000 Jackson, MS 39286-1995 Arlington,TX 76011 Attorney General Ms. H. Anne Plettinger State of Louisiana 3456 Villa Rose Drive Pc O. Box 94095 Baton Rouge, LA 70806 Baton Rouge, LA 70804-9095
' Administrator Wise, Carter, Child & Caraway Louisiana Radiation Protection Division P. O. Box 651 ,
P. O. Box 82135 Jackson, MS 39205 Baton Rouge, LA 70884-2135 i
i 1
1 j
L j