Letter Sequence Other |
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Results
Other: ML20129A051, ML20141H368, RBG-41123, Forwards Response to NRC follow-up to RAI Re GL 92-08, Requesting Addl Info for Section Ii.B, Important Barrier Parameters & Section Iii.B, Thermo-Lag Fire Barriers Outside Scope of NUMARC Program, RBG-42159, Forwards Response to 950925 RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers, Including Response to GL 92-08 Reporting Requirement 2(c) from & Calculations Which Will Be Used to Detemine Ampacity Derating Parameters, RBG-44230, Forwards Response to 970512 RAI Re Thermo-Lag Related Ampacity Derating Issues.Encl Also Contains Supporting Calculations,Rev 1 to G13.18.14.0-178 & Rev 1 to E-218, RBG-44325, Notifies That Actions Associated W/Resolution of Thermo-Lag Issues at Plant Completed,Per GL 92-08.First Phase Completed by Development of Revised Safe Shutdown Analysis
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MONTHYEARML20059C9671993-12-22022 December 1993 Forwards Request for Addl Info Re GL 92-08, Thermo-Lag 330-1 Fire Barriers, Per 10CFR50.54(f) Project stage: RAI RBG-41123, Forwards Response to NRC follow-up to RAI Re GL 92-08, Requesting Addl Info for Section Ii.B, Important Barrier Parameters & Section Iii.B, Thermo-Lag Fire Barriers Outside Scope of NUMARC Program1994-12-21021 December 1994 Forwards Response to NRC follow-up to RAI Re GL 92-08, Requesting Addl Info for Section Ii.B, Important Barrier Parameters & Section Iii.B, Thermo-Lag Fire Barriers Outside Scope of NUMARC Program Project stage: Other RBG-41346, Forwards Response to follow-up Request for Addl Info Re GL 92-081995-03-28028 March 1995 Forwards Response to follow-up Request for Addl Info Re GL 92-08 Project stage: Request RBG-42029, Forwards Destructive Exam Sampling Plan & Summary Results,As Supplement to 950328 Response to follow-up to RAI Re Generic Ltr 92-08 Issued Per 10CFR50.54(f) on 9412281995-10-26026 October 1995 Forwards Destructive Exam Sampling Plan & Summary Results,As Supplement to 950328 Response to follow-up to RAI Re Generic Ltr 92-08 Issued Per 10CFR50.54(f) on 941228 Project stage: Supplement RBG-42159, Forwards Response to 950925 RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers, Including Response to GL 92-08 Reporting Requirement 2(c) from & Calculations Which Will Be Used to Detemine Ampacity Derating Parameters1995-11-0909 November 1995 Forwards Response to 950925 RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers, Including Response to GL 92-08 Reporting Requirement 2(c) from & Calculations Which Will Be Used to Detemine Ampacity Derating Parameters Project stage: Other RBG-43067, Provides Supplemental Response to Request for Addl Info Re Ampacity Derating,Per GL 92-08, Thermo-Lag 330-1 Fire Barriers. Calculation Encl1996-06-28028 June 1996 Provides Supplemental Response to Request for Addl Info Re Ampacity Derating,Per GL 92-08, Thermo-Lag 330-1 Fire Barriers. Calculation Encl Project stage: Supplement ML20129A0511996-10-16016 October 1996 Requests Additional Info Re Ampacity Derating Methodology W/Respect to Thermo-Lag Fire Barriers & Forwards Ltr Rept Project stage: Other RBG-43571, Provides Responses to 961016 RAI Re Ampacity Derating Including Supporting Draft Calculations G13.18.14.0-178,Rev 0, Ampacity Derating Factors for Thermo-Lag 330-1 & E-128, Rev 1, Ampacity Verification....Fire Protection Barrier1996-12-19019 December 1996 Provides Responses to 961016 RAI Re Ampacity Derating Including Supporting Draft Calculations G13.18.14.0-178,Rev 0, Ampacity Derating Factors for Thermo-Lag 330-1 & E-128, Rev 1, Ampacity Verification....Fire Protection Barrier Project stage: Draft Other ML20141H3681997-05-21021 May 1997 Discusses Entergy Operations,Inc 930414,940209,1221,950328, 1026,1109,960628 & 1219 Ltrs in Response to GL 92-08,in Regard to Thermo-Lag 330-1 Fire Barriers Installed at River Bend Station,Unit 1 Project stage: Other RBG-44230, Forwards Response to 970512 RAI Re Thermo-Lag Related Ampacity Derating Issues.Encl Also Contains Supporting Calculations,Rev 1 to G13.18.14.0-178 & Rev 1 to E-2181997-10-0303 October 1997 Forwards Response to 970512 RAI Re Thermo-Lag Related Ampacity Derating Issues.Encl Also Contains Supporting Calculations,Rev 1 to G13.18.14.0-178 & Rev 1 to E-218 Project stage: Other RBG-44325, Notifies That Actions Associated W/Resolution of Thermo-Lag Issues at Plant Completed,Per GL 92-08.First Phase Completed by Development of Revised Safe Shutdown Analysis1997-11-25025 November 1997 Notifies That Actions Associated W/Resolution of Thermo-Lag Issues at Plant Completed,Per GL 92-08.First Phase Completed by Development of Revised Safe Shutdown Analysis Project stage: Other 1996-10-16
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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
[Table view] |
Text
'
- Mr. John R. McGaha, Jr. October 16, 1996 Vice_ President Operatiens Entergy Operations, Inc.
River Bend Station P. O. Box 220 St. Francisv111e, LA 70775
SUBJECT:
RIVER BEND STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION, AMPACITY DERATING (TAC NO. M85596)
Dear Mr. McGaha:
1 By letter dated November 9, 1996, Entergy Operations, Inc. (E01),1 submitted a response to the NRC Request for Additional Information related to Generic Letter (GL) 92-08, "Thermo-Lag 330-1 Fire Barriers," for the River Bend Station. By letter dated June 28,1996, E01 provided a supplemental response .
to GL 92-08 on its ampacity derating methodology with respect to Thermo-Lag fire barriers. We and our contractor, Sandia Nr.tional Laboratories, have developed additional questions on the ampacity evaluation which we will need i responses to in order for us to complete our review. It is requested that E01 provide the response or a schedule for submittal within 60 days of receipt of this letter.
If there are any questions on this request, please let me know.
Sincerely, ORIGINA SIGNED BY David L. W gginton, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-458
Enclosures:
- 1) Request for Additional Information ]
- 2) Letter Report; Sandia National Laboratories, June 7,1996 cc w/encls: See next page DISTRIBUTION (Docket File PUBLIC PD4-1 r/f E. Adensam (EGA1)
C. Hawes J. Roe D. Wigginton W. Beckner J. Dyer, RIV ACRS OGC (15818)
Document Name: RB85k96.RAI 0FC PM/PD4-NA/ (A)LA/PD4-1 t NAME a
DWiggintorl:>sp CHawesOMN Wof i DATE /kII/96 /p ////96 COPY /fEl/NO ( YES)NO 0FFICIAL RECORD CUPT' g@
- g= 88g Ma8she NRC FILE CENTER COPY l p PDR 1
, a ne:u g & UNITED STATES j
s# NUCLEAR REGULATORY COMMISSION t WASHINGTON, D.C. 2066Ho01
'+4 * * * * * $ October 16, 1996 Mr. John R. McGaha, Jr.
Vice President Operations Entergy Operations, Inc.
River Bend Station P. O. Box 220 St. Francisv111e, LA 70775
SUBJECT:
RIVER BEND STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION, AMPACITY DERATING (TAC NO. M85596)
Dear Mr. McGaha:
By letter dated November 9, 1996, Entergy Operations, Inc. (E01), submitted a response to the NRC Request for Additional Information related to Generic Letter (GL) 92-08, "Thermo-Lag 330-1 Fire Barriers," for the River Bend Station. By letter dated June 28,1996, E0I provided a supplemental response -
to GL 92-08 on its ampacity derating methodology with respect to Thermo-Lag fire harriers. We and our contractor, Sandia National Laboratories, have deve' aped additional questions on the ampacity evaluation which we will need responses to in order for us to complete our review. It is requested that E01 provide the response or a schedule for submittal within 60 days of receipt of this letter.
If there are any questions on this request, please let me know.
Sincerely, A ,x David L. Wi g nton, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-458
Enclosures:
- 1) Request for Additional Information
- 2) Letter Report; Sandia National Laboratories, June 7,1996 cc w/encls: See next page
i Mr. John R. McGaha ;
, Entergy Operations, Inc. River Bend Station <
cc:
I Winst'on & Strawn Executive Vice President and 1400 L Street, N.W. Chief Operating Officer p Washington, DC 20005-3502' Entergy Operations, Inc.
P. O. Box 31995 Manager - Licensing Jackson, MS 39286 Entergy Operations, Inc.
l River Bend Station General Manager - Plant Operations P. O. Box 220 Entergy Operations, Inc.
4 St. Francisville, LA 70775 River Bend Station P. O. Box 220 i Director St. Francisville, LA 70775 j Joint Operations Cajun '
- 10719 Airline Highway Director - Nuclear Safety l P. O. Box 15540 Entergy Operations, Inc.
j Baton Rouge, LA 70895 River Bend Station i P. O. Box 220 1 Senior Resident Inspector St. Francisville, LA 70775
- P. O. Box 1050 i St. Francisville, LA 70775 Vice President - Operations Support
- Entergy Operations, Inc.
- President of West Feliciana P. O. Box 31995 i Police Jury Jackson, MS 39286-1995 i P. O. Box 1921 4 St. Francisville, LA 70775 Attorney General l State of Louisiana i Regional Administrator, Region IV P. O. Box 94095 U.S. Nuclear Regulatory Commission Baton Rouge, LA 70804-9095 l 611 Ryan Plaza Drive, Suite 1000
- Arlington, TX 76011 Wise, Carter, Child & Caraway
- P. O. Box 651 i Ms. H. Anne Plettinger Jackson, MS 39205 i 3456 Villa Rose Drive Baton Rouge, LA 70806 Vice President & Controller
! Cajun Electric Power Cooperative
- Administrator 10719 Airline Highway Louisiana Radiation Protection Division P.O. Box 15540 P. O. Box 82135 Baton Rouge, LA 70895
- Baton Rouge, LA 70884-2135 i ,
1 l
1
RE0 VEST FOR ADDITIONAL INFORMATION RIVER BEND STATION FIRE BARRIER AMPACITY DERATING ISSUES (TAC NO. M855961 1.0 BACKGROUNO By Reporting Requirement 2(c) from & Calculations Which Will Be Used to Detemine Ampacity Derating Parameters|letter dated November 9,1995]], Entergy Operations Inc. (E01), submitted a response to the NRC Request for Additional Information (RAI) related to Generic Letter (GL) 92-08, "Thermo-Lag 330-1 Fire Barriers," for the River Bend Station (RBS) which includes Enclosure 1, Utility Calculation E-218 with Supplements A-C and Attachments 1-13 e1 titled "Ampacity Verification of Cables Within Raceways Wrapped with Appendix h Fire Protection Barrier." The licensee also provided by letter dated June 28, 1996, a supplemental response to GL 92-08 on its ampacity derating methodology with respect to Thermo-Lag fire barriers.
The RBS ampacity derating methodology is based on an analytical assessment of the nominal ampacity limits for the cables installed at RBS which includes factors such as the ambient temperature, grouping of conduits and cables and the ampacity impact based upon available test data.
2.0 QUESTIONS 2.1 attachment 2. Licensee Submittal dated 11/9/95 Item 1: The subject item states that the licensee analysis will focus only on " required and abandoned Thermo-Lag wrapped raceways."
This statement implies that those cables which were originally enclosed in fire barriers that were subsequently removed by the licensee will not be considered further by the subject analysis. Since the sco)e of GL 92-08 specifically address "all raceways protected )y Thermo-Lag 330-1 (for fire protection of safe shutdown capability or to achieve physical independence of electrical systems)" the licensee analysis s should include all cables which are either currently or previously enclosed by a fire barrier in order to assess any potential equipment age degradation impact on safety-related cable life. The licensee is requested to confirm the scope of its ampacity derating determinations.
ENCLOSURE 1
l' j!
- Item 10: The licensee implies that the subject analysis will " calculate the depth of cables in each wrapped tray (other than control cables)" and will "use this value to determine an ampacity
- derating adjustment for cable depth."- It is not clear whether those control cables which run in raceways with power cables will be included in depth of fill calculations. The staff i'
agrees with our contractor, Sandia National Laboratories (SNL) i that the thermal insulation effects of low or non-continuously i energized cables must be accounted for in the subject analysis ,
[see Attachment 1(a)]. The licensee is requested to clarify the use of subject assumption in the applicable calculations. ;
4 i 2.2 Calculation E-218 - General Methodology b
l - Calculation E-218, Revision 0. Page 2 of 35, Item 7: The calcula- l l
tion cites that the licensee " takes credit for the guaranteed
- average diameters rather than guaranteed minimum cable diameters for 600 volt K and C cables. This assumption will result in slightly j higher DCAs for these cable types." What is the difference between
- the guaranteed minimum diameter and average diameter? How large
- would the ampacity impact be if the minimum diameter is used? In j general, it would be considered more appropriate to use the minimum diameter value because this would be more conservative, and the
j manufacturer has apparently indicated that these minimum values are not unlikely. If the derating cable ampacity (DCA) impact is significant, then the licensee should reassess its ampacity limits j using the minimum cable diameter as the basis for analysis.
) - Calculation E-218, Revision 0, Page 6 of 35, Item II-a-4: This item i
states that cables in K trays are based on an assumed depth of fill l
of 1.5 inches. This value appears again on Page 22 of 35, Item la, I and Attachment 3 of E-218 is cited as the basis for this value.
! However, Attachment 3 of E-218 states that a depth of fill of 2.5 inches should be used for sizing cables in K trays. In particular,
{
does a value of 1.5 inches bound the upper limit on depth of fill for all such trays? If not, then either an upper bound value or the actual value associated with a given case should be used in the l
calculation.
- - Calculation E-218, Revision 0. Page 35 of 35, Item E
- The licensee has not provided any detailed results for the calculation of ampacity limits for SkV and 15kV cables. The licensee should either specify whether 5kV or higher voltage cables are applicable for the
' subject analysis. If SkV or higher voltage cable systems are t applicable to the subject analysis, the licensee should cite the
- tables from which the ampacity limits for these cables are derived, l'
and should describe the appropriate derating factors applied to the tabulated ampacities.
i
I d 2.3 Calculation E-218 - Snecific Analyses 1 i t
Calculation E-218, Revision 0, Page 29 of 35, Item " Chart 2": There
! appears to be two sossible discrepancies in the values cited in this chart (i.e., for tie 10AWG 7/C and 12/C cables, and for the 12AWG 7/C and 9/C cables). In general, the ampacity limits should
- decrease with an increase in the number of conductors. For all j cases, except the two pairs cited, this expectation is met. The j licensee is requested to verify the ampacity values cited in ,
~
Column 3 of the subject chart and to resolve the apparent discrepancies for the two cable pairs.
}
- The licensee application of the National Electric Code (NEC)
< conductor grouping ampacity correction factors for more than three .
. conductors in a cable or raceway is considered incomplete. In the !
, case of conduits, the NEC correction factors should be applied to '
l the conduit system as a whole whenever the total count of conductors l exceeds three. In contrast, the licensee has only applied these Jl factors to individual multiconductor cables when the conductor count j for a given cable exceeds three. This is an incomplete and 4 nonconservative treatment. The licensee analyses should be revised I to fully account for the conductor count adjustment factors for all j conduit systems in which the conductor count exceeds three.
i Calculation E-218, Revision 0, Page 24 of 35, Item " Chart 1": This
! item is described as a table of allowable ampacities for L-trays.
i The base ampacity values are from the Insulated Cable Engineers
, Association (ICEA) P-46-426 tables for a cable located in free air i- with no derating factors applied. The use of open air ampacity
- vrlues for a general cable tray appears inappropriate and must be either corrected or further justified by the licensee. In particular, this practice is not consistent with accepted ampacity 1
design practices, and hence would require explicit and detailed justification and validation. The licensee should also provide justification and validation for the K-tray or revise the subject
- calculation as necessary.
4 l The licensee has cited the 1984 version of '.he NEC handbook as the basis for i its assumed conductor count correction factors. However, since 1990, NEC has j published an updated listing of correction factors which are more conservative j for conductor counts of 10 or more. The older (1984) values included an
!* assumption of 50 percent or more load diversity in the installed cables. The licensee should either apply the more recent values in its corrections, or should specifically justify the applicability of the older adjustment factors j on the basis of existing cable load diversity.
! 2.4 Nominally Overloaded Cable Analyses Attachment 9 to Calculation E-218 documents supplemental assessments performed by the licensee for four specific cables that are nominally identified as t
4
i i
~
? ,
I operating at least part of the time under overload conditions with respect to
, ampacity limits. Two of the four cables service certain compressor power i
loads. There are several points of concern related to the supplemental 1 assessments for these two specific cables: i
- If these cables have operated under the stated conditions for any ,
significant length of time, then the cables may have already i exceeded their rated life expectancy. Rough estimates performed by ;
i SNL as part of this review indicate that these cables may exceed -
i their nominal "40 year at 90*C" life in as little as seven years. 1 j The licensee should provide an assessment of the impact of past operations on the operating life of these cables in addition to any
- assessment for future operating conditions.
i - The final justification for the acceptability of the operating l conditions of these two cables is based largely on the manufacturer's stated' overload conditions for operation. These :
overload ratings are not generally intended to cover anticipated 3
conditions of normal operation, but are intended to cover only rarely encountered and unexpected emergency conditions of operation. i i Hence, reliance on overload ratings in this case is potentially ,
j inappropriate. At the least, this practice represents a fundamental !
j departure from accepted ampacity assessment practices, and as such !
should be thoroughly justified and reviewed before being accepted as a cable design practice. In particular, the licensee should
- consider the full context of the ICEA and Institute of Electrical l and Electronic Engineers, Inc. (IEEE) overload ratings which set '
j severe limits on these overload ratings. The licensee should provide significant additional justification and validation of the
! subject design practice. ,
. (
l - The licensee cites a specific passage in the IEEE 242 standard as ;
the basis for its assessment of overload conditions [ para. 1 i 11.5.2(3)). A review of this section of the standard (1986 version) !
revealed no relevance whatsoever to the issue of cable overload I conditions. The licensee should clarify its intent in citing the 1 IEEE 242 standard.
i
- - The licensee has cited a particular equipment qualification (EQ) test report as the basis for its assessment of operating life i calculations for the subject cables (Okonite report SWGS-1282-2). 1 4 The licensee is requested to provide further clarification to 4 1 support its conclusions based on the subject EQ report.
j The licensee DCA values are based upon an assumed ampacity derating factor
- (ADF) for a 3-hour wrapped cable tray of 20.5 percent. A more realistic ADF
, value might well indicate that the subject cables have been operating for some i period of time in significant overload condition. The licensee should address j the above concerns for worst case conditions or provide further justification
- for the assumed ADF value.
1 l
i 2.5 Enclosure 1 -- June 28. 1996. submittal .
In general, it is not clear to what extent Enclosure 1, " River Bend Project Instruction on Ampacity Derating Evaluation," which was part of the licensee submittal dated June 28, 1996, supercedes Calculation E-218, Revision 0. In addition to the specific questions below, the licensee is requested to describe the relationship of the subject document with respect to other applicable station documents.
1 Tables A.4.2.5 and A.4.3.4 of Enclosure I refers to a note for the j ampacity derating factor (ADF) and ampacity correction factor (ACF) parameters for the 3-hour fire barriers. The applicable note states that the subject parameters will be provided by Reference A.5.1.15.
The licensee is requested to submit Reference A.5.1.15 for staff review.
l
- Enclosure 1 describes conduit group and tray stack which utilizes a group wrap of Thermo-Lag material to form a single enclosure around j ,
each raceway type grouping. The subject configurations represent a significant departure from the simple configurations tested under IEEE Standard P848, " Procedure for the Determination of the Ampacity 4 Derating of Fire Protected Cables" methodology. It should be noted that Tennessee Valley Authority has submitted ampacity derating test
! reports for similar configurations for staff review. The licensee is requested to provide justification for these nonstandard fire ,
1 barrier configurations. .
i
- Attachment 1(a)
- A Letter Report to the U.S. NRC, Revision 4, dated June 7, ;
1996, prepared by Steve Nowlen of Sandi National Laboratories 2
4 i
l l
l
-_. _ _ _ _ - _ - _ ~