Letter Sequence Draft 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:INCOMING CORRESPONDENCE
MONTHYEARRBG-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 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 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 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 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 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-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 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 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 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 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 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 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 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 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 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 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 05000458/LER-1999-010, Forwards LER 99-010-00 for River Bend Station,Unit 1 IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-05-28028 May 1999 Forwards LER 99-010-00 for River Bend Station,Unit 1 IAW 10CFR50.73.Commitments Identified in Rept,Encl RBG-45021, Informs That Cycle 9 Operation Will Remain within MCPR Safety Limits Approved in Amend 105 to TS Issued by NRC in1999-05-26026 May 1999 Informs That Cycle 9 Operation Will Remain within MCPR Safety Limits Approved in Amend 105 to TS Issued by NRC in 05000458/LER-1999-009, Forwards LER 99-009-00 IAW 10CFR50.73.Commitments Contained in Ltr Are Identified on Commitment Identification Form1999-05-24024 May 1999 Forwards LER 99-009-00 IAW 10CFR50.73.Commitments Contained in Ltr Are Identified on Commitment Identification Form RBG-45017, Informs NRC of Addition of ASME Boiler & Pressure Vessel Code,Section Xi,Code Case N-496-1 to RBS Inservice Insp Program.Commitment Made by Util,Encl1999-05-14014 May 1999 Informs NRC of Addition of ASME Boiler & Pressure Vessel Code,Section Xi,Code Case N-496-1 to RBS Inservice Insp Program.Commitment Made by Util,Encl ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 05000458/LER-1999-007, Forwards LER 99-007-00 IAW 10CFR50.73.Commitments Identified in LER Are Noted in Attachment 11999-05-10010 May 1999 Forwards LER 99-007-00 IAW 10CFR50.73.Commitments Identified in LER Are Noted in Attachment 1 05000458/LER-1999-006, Forwards LER 99-006-00 Re Unplanned Automatic Standby Svc Water Initiation,Due to Procedure Inadequacy.Commitments Identified in Rept Noted in Attachment 11999-05-0606 May 1999 Forwards LER 99-006-00 Re Unplanned Automatic Standby Svc Water Initiation,Due to Procedure Inadequacy.Commitments Identified in Rept Noted in Attachment 1 05000458/LER-1999-005, Forwards LER 99-005-00 IAW 10CFR50.73(a)(2)(i).Commitments Identified in LER Are Noted in Attachment 11999-05-0303 May 1999 Forwards LER 99-005-00 IAW 10CFR50.73(a)(2)(i).Commitments Identified in LER Are Noted in Attachment 1 RBG-44993, Forwards RBS Annual Individual Monitoring Rept for Jan-Dec 1998,per Requirements of 10CFR20.2206(b).File Info Listed. Without Encl1999-04-30030 April 1999 Forwards RBS Annual Individual Monitoring Rept for Jan-Dec 1998,per Requirements of 10CFR20.2206(b).File Info Listed. Without Encl RBG-44998, Informs of Missing Documentation Re Examination Results Reported in RBS Owners Activity Report Forms Submitted to NRC on 9802241999-04-30030 April 1999 Informs of Missing Documentation Re Examination Results Reported in RBS Owners Activity Report Forms Submitted to NRC on 980224 ML20206E7811999-04-29029 April 1999 Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested 05000458/LER-1999-003, Forwards LER 99-003-00,per 10CFR50.73.Commitments Identified in Rept Are Noted in Attachment 11999-04-23023 April 1999 Forwards LER 99-003-00,per 10CFR50.73.Commitments Identified in Rept Are Noted in Attachment 1 RBG-44968, Submits Addl Info Re 981008 LAR 1998-02 Re Implementation of Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long- Term Solution.Clarifies Certain Aspects of Proposed Ts,Per 990406 Telcon with NRC1999-04-15015 April 1999 Submits Addl Info Re 981008 LAR 1998-02 Re Implementation of Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long- Term Solution.Clarifies Certain Aspects of Proposed Ts,Per 990406 Telcon with NRC RBG-44965, Responds to 990324 Telcon RAI Re SLMCPR Calculation Method for RBS Cycle 9 Slmcpr,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits. Proposed TS Pages, Encl1999-04-0808 April 1999 Responds to 990324 Telcon RAI Re SLMCPR Calculation Method for RBS Cycle 9 Slmcpr,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits. Proposed TS Pages, Encl RBG-44959, Withdraws 981120 LAR 1998-20,allowing Adjusting Control Pattern for Plant Startup If Outage Had Occurred Before Planned Refueling Outage.No Plant Outage Was Conducted & Plant Is Now in Eighth Refueling Outage1999-04-0808 April 1999 Withdraws 981120 LAR 1998-20,allowing Adjusting Control Pattern for Plant Startup If Outage Had Occurred Before Planned Refueling Outage.No Plant Outage Was Conducted & Plant Is Now in Eighth Refueling Outage ML20205F1781999-03-31031 March 1999 Forwards Consolidated Entergy Submittal to Document Primary & Excess Property Damage Insurance Coverage for Nuclear Sites of Entergy Operations,Inc,Per 10CFR50.54(w)(3) RBG-44939, Forwards Rbs,Unit 1 Annual Occupational Radiation Exposure Rept for 1998, Per TS 5.6.1.Rept Consists of Tabulation of Exposure for Personnel Receiving Exposures Greater than 100 Mrem Per Yr1999-03-31031 March 1999 Forwards Rbs,Unit 1 Annual Occupational Radiation Exposure Rept for 1998, Per TS 5.6.1.Rept Consists of Tabulation of Exposure for Personnel Receiving Exposures Greater than 100 Mrem Per Yr ML20196K7101999-03-26026 March 1999 Submits Reporting & Recordkeeping for Decommissioning Planning,Per 10CFR50.75(f)(1) RBG-44899, Provides Notification of Termination of Licensed Operator, AA Rouchon,License OP-42416-1,due to Resignation.Reactor Operator License Data,Listed1999-03-25025 March 1999 Provides Notification of Termination of Licensed Operator, AA Rouchon,License OP-42416-1,due to Resignation.Reactor Operator License Data,Listed ML20204G8701999-03-15015 March 1999 Responds to NOV Described in NRC Correspondance to Util ,expressing Disappointment in NRC Determination That AD Wells Deliberately Provided Incomplete & Inaccurate Info to NRC During Meeting on 971015 RBG-44925, Responds to NRC Re Violations Noted in Investigation Rept 4-97-059.Corrective Actions: Mgt Expectations for Communicating with NRC Issued to Site Personnel on 980212,by RBS Vice President,Operations1999-03-15015 March 1999 Responds to NRC Re Violations Noted in Investigation Rept 4-97-059.Corrective Actions: Mgt Expectations for Communicating with NRC Issued to Site Personnel on 980212,by RBS Vice President,Operations RBG-44924, Informs That Util Response to NOV Re Investigation Rept 4-97-059,will Be Issued by 990315,as Extended by NRC Ltr .Encl Check for $55,000 Is for Payment of Civil Penalty IAW Instructions in .Without Check1999-03-0505 March 1999 Informs That Util Response to NOV Re Investigation Rept 4-97-059,will Be Issued by 990315,as Extended by NRC Ltr .Encl Check for $55,000 Is for Payment of Civil Penalty IAW Instructions in .Without Check RBG-44912, Responds to Violations Noted in Insp Rept 50-458/98-13. Corrective Actions:Matls & Training Were Provided to Expedite Implementation of Existing Procedural Guidance to Supply Compressed Air1999-03-0303 March 1999 Responds to Violations Noted in Insp Rept 50-458/98-13. Corrective Actions:Matls & Training Were Provided to Expedite Implementation of Existing Procedural Guidance to Supply Compressed Air RBG-44904, Informs NRC of Date Change Re Commitment Made in Response to NOV 50-458/98-05-01.New Commitment Date 9912161999-02-25025 February 1999 Informs NRC of Date Change Re Commitment Made in Response to NOV 50-458/98-05-01.New Commitment Date 991216 RBG-44384, Submits Response to Fuel Cladding Defect Issues Raised in 10CFR2.206 Petition.Clear Technical Basis Exists in Info Provided by River Bend Station to Deny Petition1999-02-11011 February 1999 Submits Response to Fuel Cladding Defect Issues Raised in 10CFR2.206 Petition.Clear Technical Basis Exists in Info Provided by River Bend Station to Deny Petition ML20203C4201999-01-25025 January 1999 Submits Denial of NRC Request for Advance Info Re Concerns Raised by Ucs in 10CFR2.206 Petitions on River Bend & Perry Plants.Petitioners Were Not Required to Provide NRC with Info in Advance of Informal Public Hearings 1999-09-09
[Table view] |
Text
Ent:rgy Operations,Inc.
River Bend Stahon 5485 U. S. H;ghway 61
~
PO. Box 220 y St. Francisville. LA 70775 Tel 504 336 6225 Fax 504 635 'E8 Rick J. King Dn ctor Nuclear Safety & Regulatory Affans December 19,1996 U. S. Nuclear Regulatory Commission Document Control Desk Mail Stop Pl-3 /
Washington, DC 20555
Subject:
River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47 Response to Request for AdditionalInformation, Ampacity Derating -H (TAC No. M85596)
File Nos. G9.5, G9.33.4 RBG-43571 RBF1-96-0477 Ladies and Gentlemen:
. i Please find attached the response to the NRC Request for Additional Information (RAI) dated October 16,1996. Attachment A contains the specific responses to the RAI. Attachments B j and C contain supporting draft calculations G13.18.14.0-178,"Ampacity Derating Factors for '
Thermo-Lag 330-1," Revision 0, and E-218, "Ampacity Verification of Cables within Raceways Wrapped with Appendix R Fire Protection Barrier," Revision 1, respectively. The I response is based primarily on these calculations which are currently in the veritication process. Once verified and approved, the calculations will be available at your request.
l The previous revision of calculation E-218, Revision 0, was completed in 1987 and was redewed by the NRC. The responses to the staff questions utilize the current draft (Revision
- 1) of E-218 and, where applicable, provide a comparison with the information previously provided in the Revision 0 calculation. As can be seen in the responses, E-218, Revision 1 I provides a more rigorous approach to the c oculation subject matter and eliminates many of the design assumptions provided in the origmal calculation. In addition, it should be noted that much of the information contained within the revised calculation is the result of field walk down data. i il 9701060112 961219 PDR ADOCK 05000458 i
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) Y P pop vvv - c
Response to Request for Additional Information, Ampacity Derating (TAC No. M85596)
December 19.1996 RBG-43571 RBF1-96-0477 Page 2 of 2 Should you have any questions, please call Tim Gates at 504-381-4866.
Sincerely, l
f-RJK/RMM/kvm Attachments cc: U. S. Nuclear Regulatory Commission (w/o Attachments B & C)
Region IV 611 Ryan P!na Drive, Suite 400 Arlington,TX 76011 NRC Sr. Resident Inspector (w/o Attachments B & C)
P. O. Box 1050 St. Francisville, LA 70775 Mr. David Wigginton NRR Project Manager U.S. Nuclear Regulatory Commission M/S OWFN 13-H-15 Washington DC, 20555
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ATTACHMENT A Responses to Request for . Additional Information :
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QUESTION 2.5: Eccl:stre 1 - June 28,1996, Submittcl i
1 OUESTION:
I 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, supersedes 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. !
RESPONSE
Initially, the Project Instruction, together with the Plant Data Management System (PDMS) ampacity computation results, was intended to supersede E-218, Revision 0. However, it was later decided that E-218 should be revised to include the new ampacity calculation methodology and the PDMS calculation results. The Project Instruction (PI) became a vehicle to (1) obtain EOI concurrence with the ampacity calculation methodology and (2) provide guidance for making the necessary PDMS software changes so that PDMS could perform the calculations in l accordance with the methodology. The PI has not been updated since June 18 and it will not be updated in the future. On October 10,1996, E-218, DRAFT Revision 1, (Attachment C to this letter) was issued for EOI review and comment. It contains the ampacity calculation l methodology previously included in the PI. The calculation is in the EOI review process and is ;
expected to be issued by January 31,1997. l l
Since the June 28,1996 submittal, EOI has performed other efforts to complete the Thermo-Lag !
(T-L) Ampacity Project. These efforts included:
- 1. Preparation of PDMS Software Changes - PDMS is an on-line relational database that I contains data for cables and raceways at RBS. It previously replaced the Electrical Cable Schedule Information System (ECSIS). PDMS was revised to include (1) program changes for performance of the ampacity calculations, (2) data base field additions for data j required to compute ampacity and (3) ampacity calculation repons, both on-screen and printed.
- 2. Preparation of Heat Transfer Calculation (Calculation Number G13.18.14.0-178)- This calculation (1) provides justification for using Texas Utilities, Comanche Peak ampacity derating factor (ADF) and ampacity correction factor (ACF) values for standard T-L enclosures and (2) computes values for uniquely configured T-L enclosures using classical heat transfer analysis techniques. This calculation is identified as Reference A.5.1.15 in the PI. The calculation has undergone initial review by EOI and comments were provided to the originator for resolution. Issuance of the final calculation will be in conjunction with the issuance of E-218, Revision 1.
- 3. Verification of T-L Enclosures - EOI performed a verification of all T-L wrapped raceways in the plant. The verification included reconciliation of drawing / document discrepancies and walkdown of several raceways to confirm T-L installation and
QUESTION 2.5: Ercl:stre 1 - June 28,1996, Submittal configuration. EOI also confirmed the correct ambient temperature for each fire zone that contains wrapped raceways.
- 4. PDMS Data Entry - For each cable contained in a T-L wrapped raceway, data entry included the load equipment identification number and the full load current and load factor (i.e. a cable sizing factor of 1.25 by default or lower in some justified cases) of the associated load equipment. Data entry also included nominal ampacity values for the various cable types, ACF values for the various T-L enclosure types, and ambient temperature data for each fire zone.
- 5. Preparation of DRAFT Revision I of E-218 - This revision ofE-218 provides a more rigorous methodology for the ampacity calculations than E-218, Revision 0. DRAFT Revision 1 methodology imposes the most current codes and standards. The major differences between DRAFT Revision 1 and Revision 0 are (1) DRAFT Revision 1 uses the latest available ampacity test data and analytical techniques for determination of ADF values for T-L enclosures and (2) Revision 0 used ICEA Standard P-54-440 and DRAFT Revision 1 uses the Stolpe's method for computation of nominal ampacity for random lay cables in tray. ICEA P-54-440 provides ampacity look-up tables based on discrete cable depths. The Stolpe's method determines ampacity based on actual tray depth and the methodology is easily adapted to computerized calculation.
OUESTION:
a) Tables A.4.2.5 and A.4.3.4 ofEnclosure 1 refers to a note for the ADF and 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 staffreview.
RESPONSE
Reference A.5.1.15, calculation G13.18.14.0-178 Draft Revision 0, is contained in Attachment B.
Please note that the enclosed calculation does not reflect recent changes resulting from various comments made by the independent reviewer since its submittal.
1 OUESTION:
b) Enclosure 1 describes conduit group and tray stack which utilizes a group wrap of Thermo-Lag material to form a single enclosure around each raceway type grouping. The subject configurations represent a significant departure from the simple configurations tested under i IEEE Standard P848, " Procedure for the Determination of the Ampacity Derating ofFire Protected Cables," methodology. It should be noted that Tennessee Valley Authority has submitted ampacity derating test reports for similar configurations for staff review. The l licensee is requested to providejustification for these nonstandard fire barrier configurations. l
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QUESTION 2.5: Erciosure 1 - Ju:e 28,1996, S:bmittal
RESPONSE
The particular T-L enclosure specified in the question is for Fire Zone PT-1. This enclosure contains a multiple tray stack and several conduits. For the most part, the enclosure is a very long 6-sided box; one side, the two ends and the roof of the enclosure ore the concrete ceiling and !
walls; the other two long sides are constructed of T-L panels. Calculation G13.18.14.0-178 Draft Revision 0 analyzes this enclosure, using classical heat transfer theory, to obtain ADF values for the contained trays and conduits. Recent analysis shows that the enclosure is no longer required ;
for fire safe shutdown and it is scheduled for demolition during the next refueling outage.
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EOI is not committed to the recommendations and requirements ofIEEE P848 which was recently issued as IEEE Standard 848-1996.
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j QUESTION 2.1: Attrchment 2, Lice:see Submittd dated 11/9/95, Item 1 1.
1 OUESTION:
} 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 funher by the subject analysis. Since the scope of Generic Letter 92-08 specifically address "all i raceways protected by Thermo-Lag 330-1 (for fire protection of safe shutdown capability or to j achieve physical independence of electrical systems)" the licensee analysis 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 j to confirm the scope ofits ampacity derating determinations.
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RESPONSE
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DRAFT Revision 1 of E-218 evaluates the ampacity of cables that have been contained in wrapped raceway at RBS except for the following cable types:
e Instrumentation cables (X cables)
Alarm cables (700 series C cables) s e Computer I/O cables (900 series C cables) e Intermittent duty power cables (for elevators, cranes, hoists and motor operated valves) l This scope is in agreement with Generic Letter 92-08.
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l' As of early November 1996, no T-L has been removed from electrical raceways. The only T-L that EOI has removed from the plant enclosed a small instnament rack. The T-L enclosure was a ,
i 6-sided box; two sides were the concrete floor and rear side. The front side of the T-L box was !
j removed; the remainder of the box was abandoned in place. Analysis showed that the enclosure was unnecessary for fire safe shutdown.
l EOI is currently in the process of removing T-L from some electrical raceways and EOI intends to j remove additional T-L during the next reF.; cling outage. Based on reevaluation of the Safe i Shutdown analysis, most of the raceways that are or have ever been wrapped are no longer j required to be wrapped. Power and control cablea contained within the enclosures being removed i or scheduled for later removal are included in E-218, DRAFT Revision 1.
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QUESTION 2,1: Att:chment 2, Lice:see S:bmitt:J d:ted 11/9/95, Item 10 OUESTION:
J The licens-e implies that the subject analysis will " calculate the depth of cables in each wrapped tray (other than cetrol 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 agrees with our contractor, Sandia National Laboratories (SNL) that the thermal insulation effects oflow or non-continuously 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.
RESPONSE
E-218, Revision 0 used an assumed tray depth to determine cable ampacity. That assumed depth
- included any control cables contained in the same raceway (s) as power cables.
E-218, DRAFT Revision I and the associated PDMS ampacity computations do not use an assumed tray depth. The ampacity computation uses the results of the PDMS tray fR calculation to compute the ampacity of random lay cables in K (600 Volt power) and C (600 Voit control) trays. PDMS calculates tray fill by summing the cross-sectional areas of all cables in the tray, irrespective of cable type, and then dividing by the tray cross-sectional area. In K tray, control cables may be present with the power cables; PDMS includes these in the calculation. Therefore, the results of PDMS ampacity computations are based on tray fill (or depth) that includes all 4
cables in the tray.
It is important to realize that the PDMS tray fill calculation is conservative because PDMS assumes that if a cable is in the tray anywhere, it is in the tray everywhere. The following figure and discussion explains this point.
CABLB7
- /j CABGB C^8"'
cABLs s CABLE 4
, i _ c^m E ' Ce l SBCTION B l SECTION C ^L CABLE 3 c^8'8 2 ^ CABLE 4 CABu i = // i , #CAntn >
CABLE 2 CABLEl Tray section A contains 7 cables (1 through 7), section B contains 5 cables (3 through 7), and section C contains 5 cables (3 through 6 and 8). None of the three tray sections contain all 8 cables. However, PDMS computes tray fill by summing the cross-sectional areas of every cable that enters or leaves the tray. In this example, PDMS computes tray fill based on the 8 cables in {
each of the three sections. I i
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~ - .- - - - - - . . . . - . - - -. .~ . . .- - _-- - -- . -- .
d QUESTION 2.2: Cele:12ti:2 E-218 - Greral M:thod91:gy l OUESTION:
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a) Calculation E-218, Revision 0, Page 2 of 35, Item 7: The calculation cites that the licensee s " takes credit for the guaranteed average diameters rather than guaranteed minimum cable diameters for 600 voit K and C cables. This assumption will result in slightly higher derating f cable ampacity (DCAs) for these cable types." What is the difference between the guarantced minimum diameter and average diameter? How large would the ampacity impact be if the i minimum diameter is used? In general, it would be considered more appropriate to use the minimum diameter value because this would be more conservative, and the manufacturer has j apparently indicated that these minimum values are not unlikely. If the DCA impact is significant, then the licensee should reassess its ampacity limits using the minimum cable diameter as the basis for analysis.
RESPONSE
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! a) Based on review of several cable specifications, the difference between the guaranteed
, minimum diameter and average diameter is 5% (i.e. minimum guaranteed diameter = 0.95 x
! average diameter). RBS rantends that cable ampacity for a single cable is not affected by
] cable diameter (i.e. insulation thickness). A #8AWG,3/c, 90*C rated cable that has 30 mils of XLPE insulation has the same ampacity as a #8AWG,3/c,90*C rated cable with 60 mils of 4
XLPE insulation. Changing cable diameter, however, may affect ampacity for many cables in 1 l a tray. This is due to the fact that a reduction in cable diameter reduces calculated tray fill (note that this is non-conservative for a tray fill calculation), which increases nominal cable ampacity. The following analysis is based on Calculation E-218, DRAFT Revision 1 methodology.
The ampacity computation for cables in K and C trays are based on Stolpe's methodology.
This methodology computes a heat intensity, Q, in the tray that is based on tray percent fill as:
3 2
Q = 300 * (% Fill)4" watts /ft/in PDMS calculates % fill for each tray by summing the cross-sectional areas of all cables in the i
tray and dividing by the tray cross-sectional area. PDMS uses maximum cable diameter for this computation. From the tray Q, PDMS computes the nominal ampacity of each cable as:
O I ,,, = 28.02
- where
- R, =
a.c. resistance of conductor at 90*C (Ohms /1000 ft) j D =
cable diameter (inches) n =
number ofconductors in the cable
{
i By using the minimum diameter (i.e. 0.95 times the average) versus the maximum diameter
.- (i.e.1.1 times the average) for these cables, the impact on the ampacity computation is as follows:
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QUESTION 2,2t C:lculation E-218 - G=cral Method:l:gy i
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- 1. Since % fill is based on the square of cable diameter, % fill for the mirdmum cable diameter case is (0.95 + 1.1)2 = 0.7459 times % fill for the maximum diameter case.
- 2. Based on the Q equation, Q for the minimum diameter case is (0.7459)* = 1.4117 times Q for the maximum diameter case.
- 3. Based on theI equation,I, for the minimum diameter case is (0.95 1.1)
- l (1.4117) = 1.026 times I ,,, for the maximum diameter case. <
1 Therefore, by using the minimum cable diameter instead of the maximum cable diameter used by PDMS, ampacity increases by 2.6%.
i Note that by using the minimum cable diameter, tray % fill decreases by 25%. This is a non-l conservative result.
QUESTION:
l b) Calculation E-218, Revision 0, Page 6 of 35, Item II-a-4: This item states that cables in K trays are based on an assumed depth of fill of 1.5 inches. This value appears again on Page 22 of 35, Item 1a, and Attachment 3 ofE-2.8 is cited as the basis for this value. However, Attachment 3 ofE-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 calculation.
RESPONSE: ,
1 b) This item is no longer a concern per E-218, DRAFT Revision I which does not use assumed tray depth for computation. Cable ampacity is based on actual computed tray fill which is the i sum of all cable cross sectional areas divided by the tray cross sectional area. Cable area is calculated from maximum cable diameter and all cables in the tray are included in the calculation.
OUESTION:
c) 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 SkV or higher voltage cables are applicable for the subject r.nalysis. If SkV or higher voltage cable systems are applicable to the subject analysis, the licensee shop!d cite the tables from which the ampacity limits for these cables are derived, and should describe the appropriate derating factors applied to the tabulated ampacities.
4 1
QUESTION 2.2: Cale:latiom E-218 - Ge eral Method:l::gy
$ RESPONSE:
c) RBS does not have any 15kV cables contained in T-L wrapped raceway. Calculation E-218, Revision 0 does provide detailed results for the calculation of ampacity for SkV cables. These results are shown in E-218, Revision 0, Attachment 1, anywhere that a 1CH### conduit or
, ITH### tray is identified. H in the third position of the raceway identification number indicates SkV voltage level. E-218, DRAFT Revision 1 also includes the SkV cables.
4 d
t i
1 k
4 h
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i i
QUESTION 2,3: Ct.lculatin E-218 - Specific Anlyses ,
l t
i OUESTION:
i a) Calculation E-218, Revision 0, Page 29 of 35, Item " Chart 2": There appears to be two !
possible discrepancies in the values cited in this chart (i.e., for the 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 cases, except the two pairs cited, this expectation is met. The licensee is requested to verify the ampacity values cited in l Column 3 of the subject chart and to resolve the apparent discrepancies for the two cable pairs.
RESPONSE
a) The values of ampacity for the 10AWG 7/C and 12/C cables, and for the 12AWG 7/C and 9/C cables do appear to be incorrect in E-218, Revision 0. Calculation E-218, DRAFT Revision 1 revises these values. The changes are based on the National Electrical Code,1996, Article 310-15, Note 8(a) ofNote:: to Ampacity Tables of 0 to 2000 Volts. Note that the Calculation E-218, DRAFT Revision 1 values cannot be compared directly to those in E-218, Revision 0, Chart 2 since the Ix' values in Column 3 are based on ICEA P-54-440 for control cable in tray with an assumed 2" depth.
OUESTION:
b) 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 the j conduit system as a whole whenever the total count of conductors exceeds three. In contrast, ,
the licensee has only applied these factors to individual multiconductor cables when the conductor count for a given cable exceeds three. This is an incomplete and nonconservative treatment. The licensee analyses should be revised to fully account for the conductor count adjustment factors for all conduit systems in which the conductor count exceeds three. I
RESPONSE
b) Calculation E-218, DRAFT Revision 1 shows the method that PDMS uses to compute ampacity for cables in conduit. The nominal ampacity of the cable is multiplied by a factor that is based on the total number of current-carrying conductors in the condulc. The appropriate factor is from the National Electrical Code,1996, Article 310-15, Note 8(a) of Notes to Ampacity Tables of 0 to 2000 Volts which is reproduced in E-218, DRAFT Revision
- 1. For tray, the Stolpe's method is used. This method applies a' square-root-of-the-number-of-conductors factor similar to the ICEA P-54-440 method.
QUESTION 2.3: Calcition E-218 - Specific Arlyses !
s The applicable equation from E-218, DRAFT Revision 1 is shown below. ;
I_ = 28.02
nRa where: R. =
a.c. resistance of conductor at 90*C (Ohms /1000 ft)
.D =
cable diameter (inches) n =
number ofconductors in the cable l I
OUESTION:
c) 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. The base ampacity values are from the Insulated Cable Engineers Association (ICEA) P-46-426 tables for a cable located in free air with no derating factors applied. The use of open air ampacity values for a general cable tray appears inappropriate and must be either corrected or furtherjustified by the licensee. In particular, this practice is not consistent with accepted ampacity 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.
RESPONSE
I c) Calculation E-218, DRAFT Revision I shows the method that PDMS uses to compute )
ampacity for cables in L tray (i.e. 600V level with maintained spacing). The methodology applies a correction factor that is based on the number of cables in the tray. The correction factor is from IPCEA P-46-426, Table VII and is reproduced in E-218, DRAFT Revision 1. j l
OUESTION:
d) The licensee has cited the 1984 version of the NEC handbook as the basis for its assumed conductor count correction factors. However, since 1990, NEC has published an updated listing of correction factors which are more conservative 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 specificallyjustify the applicability of the older adjustment factors on the basis of I existing cable load diversity.
RESPONSE
d) Calculation E-218, DRAFT Revision 1 uses the 1996 version of the National Electrical Code.
The multiple conductor correction factors are reflected in E-218, DRAFT Revision 1. Please note that E-218, Revision 0 was approved in 1987.
i l QUESTION 2.4t N:ml=.lly Overt:cded Ccble Arlyses l l
l I
_Q'JESTION-I Attachment 9 to Calculation E-218 documents supplemental assessments performed by the licensee for four specific cables that are nominally identified as operating at least part of the ,
! time under overload conditions with respect to ampacity limits. Two of the four cables service I I
certain compressor power loads. There are several points of concern related to the l supplemental assessments for these two specific cables:
a) If these cables have operated under the stated conditions for any significant length of time, l then the cables may have already exceeded their rated life expectancy. Rough estimates performed by SNL as part of this review indicate that these cables may exceed their nominal "40 year at 90 C" life in as little as seven years. 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.
RESPONSE
E-218, Revision 0, Attachment 9 includes supplemental calculations for five cables. Based on the results of E-218, DRAFT Revision 1 and the analysis shown below, these five cables are not overloaded.
e 1HVKBBC515 and 1HVKDBC506 - These cables are used for chiller controls. Each FLA is 8.33 A and the load factor is 1.1 which produces a load current or Cable Sizing Amps (CSA) of 9.16A. The 1.1 load factor is acceptable in this case because (a) circuit components are resistive so a 10% voltage variation must be considered and (b) unlike motors, resistive components are not susceptible to overload, therefore the additional 15% penalty typically used is unnecessary. Derated Cable Ampacity (DCA) is 10.65A based on a tray fill of 50% and a 0.62 ACF for the T-L. Since DCA > CSA, cable ampacity is acceptable. The cable is not overloaded and has not sustained any reduction in life.
. 1SCABNK508 - This is a feeder from a 480-240/120V transformer to a distribution panel. FLA is 37.5A and load factor is 1.25, producing a CSA of 46.88A. DCA is 55.46A based on a tray fill of 58% and a 0.56 ACF. Since DCA > CSA, cable ampacity is acceptable. The cable is not overloaded and has not sustained any reduction in life.
- 1SCAANK500 - This is also a feeder from a 480-240/120V transformer to a distribution panel. FLA is 62.5A and load factor is 1.1, producing a CSA of 68.75A.
DCA is 65.9A based on a conduit grouping factor of 0.86 and a 0.79 ACF. The cable does not meet the DCA 2 CSA criteia. However, DCA = 1.05 FLA. Therefore, for the cable to have sustained any loss oflife, it has to have operated at above nominal voltage (at least 105% since the load is resistive, not motor) and at transformer rated current. Either of these conditions is unlikely for any significant amount of time, therefore, it is unlikely that the cable has sustained any reduction in life.
QUESTION 2.4: NeminIly Overtcded Ccble Anityses e 1ENSBBH300 - This is a feeder from 4.16kV switchgear to a 4.16kV-480V transformer. FLA is 208A oased on transformer rating and load factor is 1.1, producing a CSA of 228.8A. DCA is 194.9A based on a conduit groaping factor of 0.86 and a 0.79 ACF. The cable does not meet the DCA 2 CSA criteria. However,
. according to recently issued calculation G13.18.3.6*011, Revision 0, the actual transformer load is only 142.6A based on secondary total connected load of 1236A.
Therefore, DCA = 194.9A > 156.9A = 1.1 x 142.6A and the cable has not sustained any reduction in life.
E-218, DRAFT Revision 1 voes show a number of cables that have potentially been operated at overloaded conditions. EOI is evaluating these cables. Once this evaluation is complete, EOI will perform compensatory actions to rectify any real cable overload or loss oflife ,
situations. Any operability questions will be addressed upon completion of the calculations in accordance with the RBS Condition Report system.
OUESTION:
b) The Snaljustification for the acceptability of the operating 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 conditions of normal operation, but are intended to cover only rarely encountered and unexpected emergency conditions of operation. Hence, reliance on overload ratings in this case is potentially inappropriate. At the least, this practice represents a fundamental departure from accepted ampacity assessment practices, and as such should be thoroughlyjustified and reviewed I before being accepted as a cable design practice. In particular, the licensee should consider the full context of the ICEA and Institute of Electrical and Electronic Engineers, Inc. ;
(IEEE) overload ratings which set severe limits on these overload ratings. The licensee should provide significant additionaljustification and validation of the subject design ;
practice, i
RESPONSE
EOI agrees that manufacturer's stated overload conditions are not generally intended to cover ,
anticipated conditions of normal operation. E-218, DRAFT Revision 1 evaluations do not rely on overload ratings for justification of operating currents that exceed derated cable ampacity.
OUESTIO_N; c) The licensee cites a specific passage in the IEEE 242 standard as the basis for its 1 assessment of overload conditions [ para.11.5.2(3)]. A review of this section of the !
standard (1986 version) revealed no relevance whatsoever to the issue of cable overload conditions. The licensee should clarify its intent in citing the IEEE 242 standard.
RESPONSE
.- - - ~ _ __. - ,. -. . . - . . _ -. - . . _ . - . . . . . - - ._- . .
QUESTION 2.4: Nominally Ovedrded Ccble A:talyses ;
i
~
4 The cited paragraph from IEEE 242-1975 was not available for review. However, this passage is probably equivalent to paragraph 8.5.2.3 ofIEEE 242-1986 which discusses the overload '
capacity of cables. Regardless of the E-218, Revision 0 intent, E-218, DRAFT Revision 1 evaluations do not rely on overload ratings ~forjustification of continuous operating currents that exceed derated cable ampacity.
OUESTION:
d) The licensee has cited a particular equipment qualification (EQ) test report as the basis for its assessment of operating life calculations for the subject cables (Okonite report SWGS-1282-2). The licensee is requested to provide further clarification to support its l conclusions based on the subject EQ report. !
RESPONSE
i The EQ test report was used in E-218, Revision 0 to determine the life of cables l IHVKBBC515,1HVKDBC506 and IENSBBH3'00 at the postulated overload conditions. l For 1HVKBBC515 and lHVKDBC506, Attachment 9, page I shows CSA = 14.35A and ,
DCA = 12.1 A which yielded a cable temperature of 110.3*C using the IEEE 242-1975, I Section 11.5.2 (2) equation. The cable life of 6.1 x 10' hours, equivalent to 6.96 years, was read from the chart on page 3 using the 110.3*C temperature. For 1ENSBBH300, Attachment !
9, page 6 shows CSA = 269A and DCA = 259A which yielded a cable temperature of 93.94*C, ,
The cable life of 2.5 x 10' hours, equivalent to 28.54 years, was read from the chart on page 9 )
using the 93.94*C temperature. '
E-218, DRAFT Revision 1, evaluated these cables as acceptable.
OUESTION:
T'ee 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 period of time in significant overload condition. The licensee should address the above concerns for worst case conditions or provide furtherjustification for the assumed ADF value.
RESPONSE
The updated ADF value for 3-hour tray from E-218, DRAFT Revision 1 is 44%; this is more l than twice the derating used in the Revision 0 calculation.
Based on the updated enclosure ADF and ACF values, E-218, DRAFT Revision I shows cables that have potentially been operated at overloaded conditions. EOI is evaluating these cables. Once this evaluation is complete, EOI will perform compensatory actions to rectify any real cable overload or loss oflife situations.
ATTACHMENT B DRAFT Calculation G13.7 R.14.0-178, Revision 0 "Ampacity Derating Factors for Thermo-Lag 330 1"