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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
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Ent:r0y Op: rations,Inc.
River Bond Statron Q=,llll! 5485 U S Highway 61
" ENTERGY ; a L 70,zs Tol 504 336 G225 Faa SO4 615 5008 y '.-
James J. Fisicuro
$e$ Satety October 26,1995 U.S. Nuclear Regulatory Commission Document Control Desk Mall Stop PI-37 Washington, D.C. 20555 l
Subject:
Supplement to Rerponse to Follow-Up to the Request for Additional l Infonnation Regarding Generic Letter 92-08 Issued Pursuant to 10 CFR 1
50.54(t) on December 28,1994 (TAC No M85596)
River Bend Station - Unit 1 License No. NPF 47 ,
l Docket No. 50-458 File Nos.: G9.5, G9.33.4 ;
RBG-42029 RBF1-95-0241
)
Gentlemen-l The Follow up to the Request for Additional Information Regarding Generic Letter (GL) 92-08 Issued Pursuant to 10 CFR 50.54(f) on December 28,1994 requested, in part, that Entergy Operations, Inc., (EOI):
Submit the schedule for obtaining and verifying all of the imponant barrier parameters. After the infonnation has been obtained and verified, submit a written supplemental report that confinns that this effort has been completed and provides the results of the examinations and inspections Verify that the parameters of the in-plant configurations are representative of the parameters of the fire endurance test specimens. Describe any changes to previously submitted plans or schedules that result from the examinations.
EOl's response dated March 28,1995 (RBG-41346), explained that the destructive examination walkdowns were completed and the results of the destnictive examinations were being reviewed and verified at that time. The review and verification have since been completed. Attached is a summary of the results of the destnictive examinations and inspections. .
,0 0910310369 951026 Ij PDR ADOCK 05000458 P PDR
Supplement,t,o Response to Follow-Up to the Request for AdditionalInfonnation Regarding Gendric Letter 92-08 Issued Pursuant to 10 CFR 50.54(f) on December 28,1994 (TAC No.
ht85596)
October 26,1995 RBO 42029 RBF1-95 0241 Page 2 of 2 As explained previously, River Bend Station (RBS) is pursuing a comprehensive program to evaluate applications of Thenno-Lag in the plant. The project consists of two sections. The first is a re-analysis of the Safe Shutdown hiethodology. This effort is expected to result in a significant reduction in the amount of fire wrap material required. The second ponion of the project will address Thenno-Lag directly. This portion will review the Thenno-I2g installations that remain and detennine if the Thenno-Lag can be qualified as-is through additional testing, if the Thenno-Lag can be upgraded economically using methods similar to those tested by the Nuclear Energy Institute, or if the Thenno Lag must be n:placed with a different material. Verification that the parameters of the in-plant configurations are representative of the panuneters of the fire endurance test specimens will be included as part of the development of the required test configurations. >
Resolution of Thenuo-Lag issues and completion of corrective actions is scheduled to be completed by the end of refueling outage 7, currently scheduled to begin in September 1997.
The destmetive examinations did not result in any changes to this schedule, i
Should you have any questions or require additional infonnation, please contact Mr. David N.
Lorfing of my staff at (504) 381-4157. l 1
Sincerely,
- Y W f JJF/kym i attachment cc: U.S. Nuclear Regulatory Commission Mr. D. L. Wigginton Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 11555 Rockville Pike Arlington, TX 76011 M/S OWFN 13-H-3 4 Rockville, MD 20852 NRC Resident Inspector P.O. Box 1051 St. Francisville, LA 70775
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-47 DOCKET NO. 50-458 IN THE MATTER OF GULF STATES UTILITIES COMPANY CAJUN ELECTRIC POWER COOPERATIVE AND ENTERGY OPERATIONS, INC.
AFFIRMATION I, James J. Fisicaro, state that I am Director of Nuclear Safety of Entergy Operations, Inc., at River Bend Station; that on behalf of Entergy Operations, Inc., I am authorized by Entergy Operations, Inc. to sign and file with the Nuclear Regulatory Commission, this Supplement to Response to Follow-up to the Request for Additional Information Regarding Generic letter 92-08 Issued Pursuant to 10 CFR 50.54(f) on December 28,1994 (TAC No. M85596), that I signed this supplement as Director-Nuclear Safety at River Bend Station of Entergy Operations, Inc.; and that the statements made and the matters set forth therein are true and correct to the best of my knowledge, information, and belief.
WA Jams J. Fisicaro STATE OF LOUISIANA WEST FELICIANA PARISH SUBSCRIBED AND SWORN TO before me, Notary Public, commissioned in the Parish of East Baton Rouge and qualified in and for the Parish and State above named, this c_16 O day of $0Advo ,1995.
}
'*"^'t buh,B -
U Jane Russell Notary Public My Commission expires with life.
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DESTRUCTIVE EXAM! NATION SAMPLING PLAN AND
SUMMARY
OF RESULTS h
l ENTERGY OPERATIONS, INC.
RIVER BEND STATION
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4 TABLE OF CONTENTS l
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i i SECTION PAGE 1
l 1.0 - PURPOSE...... . . . . . . ..... . . . . . . . . . . . . . ... .......3 4
2.0 PLAN .. .. . . .. .. . . .. . .. ... .. .. . . . . . . ......3 :
L 1 1 BASIS....................
3.0 . . . . .. . .. . . ...... .... .......5 l l
4.0
SUMMARY
OF EXAMINATIONS . .. . .. . .. . .... .. . . . . . .. 7 l
5.0 REFERENCES
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4 10 ' PURPOSE The purpose of this plan is to provide a methodology which identifies the internal (hidden) parameters for the as-installed Thermo-Lag installations at RBS based on a sampling of these configurations. This plan selects the configurations to be examined, establishes the basis for the sampling i being representative of the installed configurations and then documents the result of these examinations.
2.0 PLAN The original plan indicated that 33 configurations would be destructively examined and 5 opened for visual inspection. After these items were examined it was determined that one (1) additional item, a Thermo-Lag ceiling assembly, was also accessible for examination and three (3) of the -
configurations revealed additional information about other types of coverage (e.g., destruction of a box panel revealed airdrop coverage).
This brings the total number to 42 configurations examined. This is based on a review of the as-installed Thermo-Lag configurations using Drawings ,
EE-34YA through EE-34YH and the design specification for the !
installation of Thermo-Lag (Reference 3.5).
Enclosures were chosen utilizing the following criteria:
- 1. A minimum of 1 configuration selected from each main fire area / zone in the plant where Thermo-Lag was installed. ;
I
- 2. The sampling will include both 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> enclosures.
- 3. The sampling will be representative of the various types of coverage found at RBS such as coverage on pull and terminal boxes, conduits, and cable trays. To establish consistency of construction techniques, two (2) samples minimum of each type of barrier configuration selected will be examined.
- 4. Wherever possible Thermo-Lag configurations which are no longer required and are abandoned in place will be utilized in order to minimize the impact of this examination.
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- 3 .._2. > .q-- .s - - - --:. - n - .. n. -. ..a l
. 'The main attributes to be verified by this examination are as follows:
- 1. Materials
- a. Panels with or without ribs
- b. Thickness of material
- c. Stress skin on the interior
- 2. Joining techniques ,
i
- a. Prebuttered or post buttered joints (including sufficient quantities of trowel grade (mastic) to compensate for shrinkage)
- b. Butt, mitered or score and fold joints
- c. Joint orientation (side piece in compression, etc.)
1
- 3. Interior support for the enclosure
- a. Panels secured against the protected commodity (pull boxes, conduits etc.)
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- b. Interior support mechanisms independent of the protected commodity (e.g., Unistrut, angle iron, tube steel, banding, etc.)
i
- c. Extent of and size of unsupported panel sections
- 4. Condition of installed enclosure I
- a. Continuity of the interior stress skin
- b. Proper utilization of joining techniques
- c. Damaged Thermo-Lag material j l
- 5. Other ,
- a. Continuity of coverage on adjacent structural steel or nonessential raceways per the 9"(1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) and 18"(3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />) l rules ;
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1 1
1 Once the destructive examination was compin q, at least one additional I configuration for each type and rating of coverage was examined externally (non destructive) in detail utilizing the results of the destructive examinations in order to further validate the consistency of installation.
3.0 BASIS The 42 samples selected are representative of the Thermo-Lag instalianons at RBS based on the following:
- 1. At least 1 configuration at each main fire area / zone where Thermo-Lag is installed and at least two samples of each type of configuration were examined. Since it is not known which crew of installers worked in which locations, this will provide a ,
representative sampling of the installation practices used throughout the plant. l
- 2.
- Of the 42 samples selected,27 are 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> configurations and 15 are 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> configurations broken down as follows:
1 Hour l
- a. 6 straight conduit runs
- b. 2 conduit radial bends
- c. 2 cable air drops
- d. 9 junction box / pull box /condulet/LBD's
- e. 2 unistrut supported box enclosures -(1) MOV enclosure, l (1) Instrument rack
- f. 3 cable trays
- g. 3 multi-tray enclosures - unistrut supported 3 Hour
- a. 3 straight conduit runs
- b. 3 conduit radial bends
- c. 1 cable air drop
- d. 2 junction box / pull box /LBD/condulet
- e. 2 unistrut supported box enclosures
- f. 2 cable trays
- g. 1 multi-tray enclosure - unistrut supported, covered with Thermo-Lag panels
- h. .1 flow switch covered with preshaped conduit sections 5
~
% 20 samples were selected for nondestructive external examination.
9 were 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> confe; rations and 11 were 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> configurations broken down as follows:
1 Hour
- a. 1 straight conduit runs and supports
- b. 2 conduit radial bends
- c. 1 cable air drops
- d. 2 junction box / pull box /condulet/LBD
- e. 1 cable tray
- f. 1 multi-tray enclosures - unistrut supported
- g. 1 floor / ceiling assembly 3 Hour
- a. 3 straight conduit runs
- b. 3 conduit radial bends
- c. 1 cable air drop
- d. 1 box enclosure
- e. 1 cable tray
- f. 1 multi-tray enclosure - unistrut supported
- g. 1 floor penetration This distribution of barrier configurations represents a reasonable cross section of the various types of configurations installed. The samples selected coupled with the subsequent external examinations and the design specification therefore provides a high level of confidence in the consistency of installation techniques for the type of coverage.
Part of the sampling effort (19 of 45 samples) concentrated on the unique configurations where external inspection alone does not provide an adequate verification of barrier parameters due to multiple items being covered and relatively large boxed enclosures around the items. The sampling of box enclosures represents approximately 42% of these types of enclosures which is sufficiently representative. The results of the destructive examinations, the subsequent detailed external examinations, and the design specification should provide a high level of confidence in the overall consistency of installation techniques used to construct the box enclosures.
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4.0
SUMMARY
OF DESTRUCTIVE AND NONDESTRUCTIVE
. EXAMINATIONS The following is a summary of the findings from the destructive and ,
nondestructive examinations. j l
A. Materials l
- 1. Panels used for both 1 and 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> enclosures had V-ribs.
The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> panels and preshaped half rounds had stress ,
skin on the inside and the 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> panels and preshaped half l rounds had stress skin on the inside and outside. l l
- 2. It was common to find at least some missing stress skin on both panels and half rounds and some missing V-ribs on .
panels. The missing stress skin and V-ribs was more l prevalent on the cut pieces and on larger pieces where they l mated at corners or covered trays and a tight fit was l desired. There were however several cases where large amounts of stress skin /v-ribs were removed but these were !
more the exception than the rule. l l
- 3. Panel and V-rib thicknesses were good with some 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> material being used on 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> applications.
B. Joiaing Techniques
- 1. Most of the joints were post-buttered but pre-buttered joints were commonly found. The joints were mostly butted together but there were several locations where mitered joints were used on boxed enclosures.
- 2. Radial bends on conduit coverage were generally mitered, but there was some bending of half rounds to minimize the amount of mitered joints. This was much more common on half round coverage on flex-conduits, air drops and conduit bends less than 90 There were several cases where gaps between mitered half round segments were 1" to as much as 3". These gaps were filled with trowel grade to the required thickness.
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,j '.- 3. Where larger half rounds were used to cover LBD's or conduit supports there was generally a good overlap of smaller conduit coverage sections but there were occasions [
where gaps occurred due to the different shapes of the pieces and the gaps would be filled with trowel grade but would be less than the required thickness. j l
- 4. Joint orientaticiiin the panel enclosures varies. Sometimes f side panels were in compression and sometimes they were i not.
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- 5. There were several situations where additional st!sss skin and trowel grade were installed over the outside of both panels and half rounds but this generally only involved part of the joints at any one location.
- 6. Generally the gaps at joints were kept to a minimum but there were cases, especially where small pieces were fitted around conduits, etc., where excessive gaps were created (greater than 1/2") and the gaps were not always filled with !
trowel grade to the required thickness.
C. Interior support for the enclosure i
- 1. Generally panels over junction boxes, LBD's, condulets and ,
cable trays were tight to the protected commodity and half )
rounds on conduits were tight to the conduit. There were i situations on conduits and flex-conduits where there was a i gap of 1/2" or more between the coverage and the item.
This was more prevalent on bends but also occurred on some straight segments.
- 2. Larger enclosures around MOVs, instrument racks and !
multiple trays had Thermo-Lag installed against and bolted to unistrut frames which were independent of the protected commodity. These structures generally provided good j interior support for these enclosures but there were several j cases where panels had bowed or sagged creating a j mismatch at joints. i 1
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'.D . Condition of installed enclosure
- 1. The continuity of interior stress skin and V-ribs varied due to the numerous situations where stress skin and V-ribs were missing.
- 2. The use of pre-buttered versus post-buttered varied ,
between enclosures and there were instances where both !
joining methods were used on the same enclosure. Joint gap tolerances were good overall with only a few enclosures where joint gaps were excessive.
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- 3. The quality of the Thermo-Lag materials was generally good with no evidence of voids or gaps in the panels or half rounds but there were several cases where the panels had 1 s
been damaged either by being stepped on cr from sagging.
l E.' Structural Interfaces l
- 1. Structural interfaces varied where raceways went through blockouts filled with penetration seal material. The coverage either continued through the penetration seal or l flared out and was bolted to the structure. Where covered i cables ran along the structure or went through sleeves that were grouted into the structure, the coverage was generally l butted to structure with trowel grade applied at the interface. l l
F. Coverage on supports and intervening steel Primary support steel carrying the load of the protected item was completely covered to the structure. Secondary support steel and intervening steel were covered a minimum of 18" from the protected item. I G. Fasteners Tie-wires were predominantly utilized but both bands and tie wires were used as fasteners. Hilti type bolts were used to anchor the Thermo-Lag to concrete floors and walls where the Thermo-Lag was flared out at the wall or floor interface. Fastener spacing was consistently maintained at 12 inches or less but there was no requirement for installing fasteners within 2" of joints so there is a generic problem where bands / wires are greater than 2" from joints.
9
5.0 ', REFERENCES 5.1 Criterion 240.201 A, "10 CFR 50, Appendix R Safe Shutdown Analysis", Rev.1 5.2 Appendix R Raceway Fire Protection Details drawings.
3.2.1 EE-34 YA, Rev. 3 3.2.2 EE-34 YB, Rev. 3 3.2.3 EE-34 YC, Rev. 4 3.2.4 EE-34 YD, Rev. 3 3.2.5 EE-34 YE, Rev.1 3.2.6 EE-34 YH, Rev. 0 5.3 USAR 9.5.1 Fire Protection Systems and Associated Figures, Rev.
6 5.4 SSER 9.5, May 1984 including Supplement 2, August 1985 and Supplement 3, August 1985.
5.5 File No. 3228.410-982-0004A, TSI 20684, Thermo-Lag 330 Fire Barrier System Installation Manual, Rev. V 5.6 File No. 3228-41-095-003A, " Installation Procedures for " Appendix R" Fire Barrier Materials and Establishment of One and Three Hour Rated Fire Protection Envelopes", Rev. 0 i
5.7 Specification 228.410, Furnishing and Installation of Thermal Insulation Outside of the Drywell, Rev. 2 5.8 VECTRA Engineering Report No. 0103-00112-TR-01, Rev.1,
" Report on Thermo-Lag 330-1 Installed at River Bend Station" 10
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