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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] Category:UTILITY TO NRC
MONTHYEARRBG-33517, Responds to NRC Re Violations Noted in Vendor Interface & Procurement Team Insp Rept 50-458/89-200. Corrective Actions:Maint Instruction Index for Diesel Engine Reviewed1990-09-10010 September 1990 Responds to NRC Re Violations Noted in Vendor Interface & Procurement Team Insp Rept 50-458/89-200. Corrective Actions:Maint Instruction Index for Diesel Engine Reviewed RBG-33466, Responds to Deviations Noted in Insp Rept 50-458/90-16 on 900709-19 Re Suppression Pool Water Level.Corrective Actions:Operator Aids Will Be Developed to Inform Control Room Operators of Actual Instrument Range1990-08-30030 August 1990 Responds to Deviations Noted in Insp Rept 50-458/90-16 on 900709-19 Re Suppression Pool Water Level.Corrective Actions:Operator Aids Will Be Developed to Inform Control Room Operators of Actual Instrument Range RBG-33460, Forwards Certified Cash Flow Statements for Guarantee of Funds in Event of Retrospective Call Under Secondary Financial Protection Program,Per 10CFR140.211990-08-28028 August 1990 Forwards Certified Cash Flow Statements for Guarantee of Funds in Event of Retrospective Call Under Secondary Financial Protection Program,Per 10CFR140.21 RBG-33496, Advises That KT Allbritton No Longer Needs to Maintain License for Facility Due to Termination of Employment1990-08-28028 August 1990 Advises That KT Allbritton No Longer Needs to Maintain License for Facility Due to Termination of Employment RBG-33450, Forwards Rev 3 to River Bend Station Updated Fsar. Rev Covers Period 890301-9003011990-08-28028 August 1990 Forwards Rev 3 to River Bend Station Updated Fsar. Rev Covers Period 890301-900301 RBG-33424, Requests That Proposed Tech Spec 3.0 & 4.0,when Approved,Be Issued as Effective Immediately W/Implementation to Be Completed by 9009291990-08-22022 August 1990 Requests That Proposed Tech Spec 3.0 & 4.0,when Approved,Be Issued as Effective Immediately W/Implementation to Be Completed by 900929 RBG-33372, Forwards Semiannual Rept on fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d).No Weaknesses in Program Identified1990-08-10010 August 1990 Forwards Semiannual Rept on fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d).No Weaknesses in Program Identified RBG-33310, Responds to NRC Re Exercise Weaknesses Noted in Insp Rept 50-458/90-06.Corrective Actions:Computer Clock Synchronized to Correct Time & Logic Changed for Making Location Addresses in Retransmission of Messages1990-08-0101 August 1990 Responds to NRC Re Exercise Weaknesses Noted in Insp Rept 50-458/90-06.Corrective Actions:Computer Clock Synchronized to Correct Time & Logic Changed for Making Location Addresses in Retransmission of Messages RBG-33300, Forwards Schedule for Submittal of Repts Re Reactor Physics Methods & Reactor Transient Analysis Methods Rept,Per 900712 Meeting1990-07-30030 July 1990 Forwards Schedule for Submittal of Repts Re Reactor Physics Methods & Reactor Transient Analysis Methods Rept,Per 900712 Meeting RBG-33294, Forwards Decommissioning Trust Agreement for River Bend Unit 1 & Nuclear Decommissioning Trust Fund Agreement Between Cajun Electric Power Cooperative,Inc & Hibernia Natl Bank1990-07-26026 July 1990 Forwards Decommissioning Trust Agreement for River Bend Unit 1 & Nuclear Decommissioning Trust Fund Agreement Between Cajun Electric Power Cooperative,Inc & Hibernia Natl Bank RBG-33196, Forwards Rev 0 to River Bend Station,Cycle 3 Core Operating Limits Rept Jul 1990. Use of Core Operating Limits Rept in Lieu of cycle-specific Parameters in License Amend Request Approved W/Amend 42 to License,Per Generic Ltr 88-161990-07-13013 July 1990 Forwards Rev 0 to River Bend Station,Cycle 3 Core Operating Limits Rept Jul 1990. Use of Core Operating Limits Rept in Lieu of cycle-specific Parameters in License Amend Request Approved W/Amend 42 to License,Per Generic Ltr 88-16 RBG-33150, Responds to NRC Re Violations Noted in Insp Rept 50-458/89-11.Corrective Actions:Implementation of New Computerized Tagging Sys Being Developed1990-07-0202 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-458/89-11.Corrective Actions:Implementation of New Computerized Tagging Sys Being Developed RBG-33143, Addresses Progress of Procurement & Evaluation Activities for Sys to Meet Reg Guide 1.97 Neutron Monitoring Requirements.Bid Spec to Incorporate NRC & BWR Owners Group Guidance Will Be Issued Prior to Fourth Quarter 19901990-06-29029 June 1990 Addresses Progress of Procurement & Evaluation Activities for Sys to Meet Reg Guide 1.97 Neutron Monitoring Requirements.Bid Spec to Incorporate NRC & BWR Owners Group Guidance Will Be Issued Prior to Fourth Quarter 1990 RBG-33132, Suppls Response to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Will Reverify Switch Settings on Initial Surveillance Interval of 5 Yrs1990-06-28028 June 1990 Suppls Response to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Will Reverify Switch Settings on Initial Surveillance Interval of 5 Yrs RBG-33120, Responds to 900621 Request for Addl Info Re Effects on Containment Dynamic Loads Which Will Result from Increasing Suppression Pool Temp from 95 F to 100 F.Original Design Basis of 100 F Included in Steam Condensation Loads1990-06-26026 June 1990 Responds to 900621 Request for Addl Info Re Effects on Containment Dynamic Loads Which Will Result from Increasing Suppression Pool Temp from 95 F to 100 F.Original Design Basis of 100 F Included in Steam Condensation Loads RBG-33114, Requests Withdrawal of 900202 Application for Amend to License NPF-47,revising Div I & II Diesel Generator Crankshift Insp Scheduling,Per 900529 Telcon1990-06-26026 June 1990 Requests Withdrawal of 900202 Application for Amend to License NPF-47,revising Div I & II Diesel Generator Crankshift Insp Scheduling,Per 900529 Telcon RBG-33113, Requests Implementation of Generic Ltr 87-09 Wording for Bases for Spec 4.0.3 Re Reporting Requirements of 10CFR50.73 for Missed Surveillances to Enable NRC to Continue Review of 880930 Application for Amend to License1990-06-26026 June 1990 Requests Implementation of Generic Ltr 87-09 Wording for Bases for Spec 4.0.3 Re Reporting Requirements of 10CFR50.73 for Missed Surveillances to Enable NRC to Continue Review of 880930 Application for Amend to License RBG-33100, Requests Waiver of Compliance W/Tech Spec 3/4.6.3.1 Until Exigent Processing of Tech Spec Change Request LAR 90-08 Completed.Change Revises Max Temp for Suppression Pool to 100 F to Avoid Limiting Plant Operation in Jul & Aug 19901990-06-22022 June 1990 Requests Waiver of Compliance W/Tech Spec 3/4.6.3.1 Until Exigent Processing of Tech Spec Change Request LAR 90-08 Completed.Change Revises Max Temp for Suppression Pool to 100 F to Avoid Limiting Plant Operation in Jul & Aug 1990 ML20043G2211990-06-14014 June 1990 Responds to 900509 Request for Addl Info Re 900209 Response to Violations Noted in Insp Rept 50-458/89-41.Procedure Being Developed to Provide Guidelines for Future Troubleshooting of Recirculation Flow Control Valve Sys ML20043G8191990-06-12012 June 1990 Forwards Rev 5A to Pump Valve Inservice Testing Plan,For Review.Rev Provides Addl Info & Clarification for Requests for Relief Noted in Rev 5 ML20043E6531990-06-0606 June 1990 Forwards Addl Info Re 880930 Application for Amend to License NPF-47 to Implement Generic Ltr 87-09 Requirements Re Preplanned Use of Addl Operating Flexibility ML20043F9801990-06-0606 June 1990 Forwards Response to NRC 890731 Request for Addl Info Re Util 890731 Application for Amend to License NPF-47 to Implement Generic Ltr 87-09.Justifications for Use of Proposed Tech Spec 3.0.4 Will Be Submitted Separately ML20043D5591990-06-0101 June 1990 Provides Status of Actions Re Insp Rept 50-458/89-45 Which Dealt W/Dual Coil Solenoid Operated Valves Used to Control MSIVs ML20043D5421990-06-0101 June 1990 Forwards Addendum to River Bend Station - Unit 1,Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989. ML20043D5401990-06-0101 June 1990 Provides Update to 900125 & 0315 Responses to Insp Rept 50-458/89-200.Util in Process of Performing Retrofit Review of in-stock Items Purchased Between 850101-900101 ML20043D2371990-05-31031 May 1990 Provides Suppl to 890929 Response to Violations Noted in Insp Rept 50-458/89-31.Safety Tagging Administrative Procedure Being Revised to Make Clearance Program Easier to Understand & Follow ML20043C8011990-05-29029 May 1990 Forwards Rev 12 to Physical Security Plan.Rev Reflects Current Activities of Plant Security Programs.Rev Withheld (Ref 10CFR73.21.) ML20043B4231990-05-21021 May 1990 Forwards Rept Re Investigation Involving Unsatisfactory Performance Test Result by Dhhs Certified Lab Under Contract to Util to Perform Drug Screen Testing Under 10CFR26, Fitness-For-Duty Program. ML20043A4271990-05-14014 May 1990 Forwards Authorization of Util Board of Directors for Tf Plunkett & Wh Odell to Sign Ltrs to NRC Transmitting Amends to OL or Responses to Insp Repts ML20042G7031990-05-0909 May 1990 Responds to NRC 900405 Ltr Re Weaknesses Noted in Insp Rept 50-458/90-06 on 900220-23.Corrective Action:Software in Simulator Changed to Duplicate Software in Control Room & More Training Time on Computers Given to Operators ML20042F9741990-05-0707 May 1990 Responds to Violations Noted in Insp Rept 50-458/90-02 on 900122-26.Corrective Actions:Electrical Power Removed from Valves,Safety Assessment of Spurious Opening Performed & QA Performed on Energized Valves ML20042G2521990-05-0404 May 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants.' ML20042E3781990-04-0606 April 1990 Responds to Violations Noted in Ofc of Investigations Rept 4-88-027,per Enforcement Action 90-043.Corrective Actions: Util Auditing self-screening Contractor Programs to Assure Compliance & Audit Will Be Evaluated for Acceptability ML20042D8351990-03-30030 March 1990 Submits Supplemental Info Re Util Response to Station Blackout Rule & Advises That Results of Plant Evaluations Demonstrate Ability to Cope W/Station Blackout for Proposed 4 H Duration W/O Reliance on Ac Power Sources ML20042E3501990-03-30030 March 1990 Forwards Evaluation of Unsatisfactory Performance by Dhhs Certified Lab Performing Drug Testing ML20012F1571990-03-28028 March 1990 Requests Extension Until 900601 to Submit Changes to Facility Tech Specs Re Leak Detection & Inservice Insp Program,Per Generic Ltr 88-01 ML20012F1551990-03-28028 March 1990 Suppls 890411 Response to Violations Noted in Insp Rept 50-458/86-04.Operations QC Instructed QC Planners & Lead Inspector to Include Hold Point of Electrical Maint Work Request for Category I Electrical Equipment Panels ML20042D7041990-03-21021 March 1990 Forwards Results of Ultrasonic Testing Conducted on N4A-2 Feedwater nozzle-to-safe End Weld During mid-cycle Outage at Plant.Circumferential Indication Identified in Buttered Area on Safe End Side of Weld During Second Refueling Outage ML20012E0001990-03-20020 March 1990 Forwards Marsh & Mclennan 900313 Ltr Containing Summary of Property Insurance Coverage for Facility,Per 10CFR50.54(w)(2) ML20012C7901990-03-16016 March 1990 Forwards Response to Violations Noted in Insp Rept 50-458/89-39.Response Withheld (Ref 10CFR73.21) ML20012C9931990-03-15015 March 1990 Forwards Duke Engineering & Svcs,Inc 900105 Ltr to BC Fichtenkort Re Proposed Crankshaft Insp Variation & Recommends Variation Be Presented to Clearinghouse Members at 900111-12 Meeting ML20012C7881990-03-15015 March 1990 Provides Updated Status for Corrective Actions Being Taken for Discrepancies Identified in Insp Rept 50-458/89-200. Thirty-six Items identified.Twenty-eight Items Completed. Three of Eight Remaining Items Require Evaluation of Stock ML20012C0381990-03-0909 March 1990 Advises That Senior Reactor Operator License 43188-1 & Reactor Operator License 42087-2 for a Middlebrooks & DG Looney,Respectively,Expired on 900105 & 900201 ML20012A4431990-03-0101 March 1990 Requests Addl Clarification to Prepare Response to Generic Ltr 90-01 Re Survey of Time Spent by Key Nuclear Power Plant Managers in Responding to Various Operational Insps & Audits ML20012B3001990-03-0101 March 1990 Forwards Fitness for Duty Program Rept 90-F-02 Re Investigation of Unsatisfactory Performance Test Result by Certified Lab Under Contract to Util to Perform Drug Screen Testing,Per 10CFR26 ML20012A9161990-02-28028 February 1990 Forwards Response to Inspector Followup Item Noted in Insp Rept 50-458/89-42 on 891113-17.Corrective Actions:Rev to Procedure EDP-AA-10 Re Issuance of Training Matrix on Semiannual Basis Will Be Issued to Remove 2-yr Rereading ML20011E8431990-02-0909 February 1990 Responds to Violations Noted in Insp Rept 50-458/89-40. Corrective Actions:All Prestaged Matl Removed from Containment & Radiation Protection Personnel Cautioned on Placement of Matl on 95-ft Elevation of Containment ML20011E6741990-02-0909 February 1990 Responds to Violation Noted in Insp Rept 50-458/89-41 on 891101-15.Corrective Actions:Procedure Which Would Provide Guidelines for Future Troubleshooting of Recirculation Flow Control Valve Sys Being Developed ML20011E1531990-01-29029 January 1990 Provides Currently Identified Outage & nonoutage-related Activities to Update NRC of Util Licensing Activities in Order of Priority ML20006C0061990-01-25025 January 1990 Forwards Notification of Nuclear Liability Insurance Coverage for Facility 1990-09-10
[Table view] |
Text
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1 a 4 GULF STATES ' UTILITIES ' COMPANY
. RAVER BEND STATION PO$1 OFFICE BOX 220 ' ST FRANC!SVILf. LOUISlANA 70776 AREA CODE 604 635 60944 346 8651 l
September.11, 1987 RBG-26592 File Nos. G9.5, G9.33.1-U.S. Nuclear Regulatory Commission [)
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Gentlement "
River Bend Station - Unit l' Docket No. 50-458 Attached .is Gulf . States Utilities Company (GSU) response to NRC Bulletin No. 87-01, Thinning'of' Pipe Walls in Nuclear Power Plants.
This. response provides the requested information concerning Gulf States Utilities program for monitoring the thickness of pipe walls in piping systems at River Bend Station.
If further assistance is required, please contact Mr. Rick J. King at (504)'381-4146.
Sincerely, Y'%
J. E. Booker Manager, River Bend Oversight River Bend Nuclear Group E / SF ch Attachment.
cc: U.S. Nuclear Regulatory. Commission Doc'ument Control Desk Washington, D.C. 20555 Senior Residen* Inspector Post Office Box 1051 St. Francisville, LA 70775 5\
8709210347Og9y58 -
'T-PDR ADOCK O PDR t g p sn - - - - - - -. -- - - - _ - ___
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UNITED STATES OF AMERICA-NUCLEAR REGULATORY COMMISSION i STATE OF LOUISIANA 5' PARISH OF WEST FELICIANA. $
i.
.In the Matter of. $ Docket No. 50-458 1 g GULF STATES UTILITIES COMPANY $
I
.(River Bend Station. $
Unit 1)~ $
AFFIDAVIT
.' J . E. Booker, being duly sworn, states that-he is Manager-River Bend Oversight for-Gulf States Utilities Company; that he is authorized on the
.part of said Company to sign and file with the Nuclear Regulatory Commission the documents attached hereto; that he has read all of the statements contained in such documents attached thereto and made a part l thereof; and that all such statements made and matters set forth therein i
are true'and correct to the best of his knowledge, information and belief.
he f lh p.E. Booker Subscribed and sworn to before me, a Notary Public in and for the State and Parish above named, this' // day of deO beni Ae r ,
19 h'[.
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JdA { j J
j'oanW.Middlebtfooks v Notary Public in and for West Feliciana Parish, Louisiana !
My Commission is For Life:
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- j RESPONSE TO ACTIONS REQUESTED IN NRCB NO.,87-01 This response will address each of the' actions requested in NRC Bulletin No. 87-01: Thinning of Pipe Walls in Nuclear Power Plants. Attachment 1' lists specific line numbers identified by Engineering as being susceptible to. Erosion / Corrosion. Attachment 2 is the' General Electric Design' Specification, 22A5495 Revision 1, Lused by. Stone and Webster Engineering Corporation in determining the corrosion allowances used in wall thickness evaluation.
- 1. Safety- related (QA Cat' I) carbon steel piping. was' designed, fabricated, and erected in accordance with ASME III .1974. Codes & '
Standards: Design, fabrication, and erection of non-safety related (QA Cat. II) carbon steel piping was in accordance with ANSI
'B31.1-1973 through Winter,- 1979 Addendum, Table 126.1, Specifications ~ (Piping- material - ASTM A106, CR.B; fittings - ASTM A105 & A234WPB).
- 2. Scope- and Extent: The' Erosion / Corrosion Control Program is described in Engineering Department Procedure-Mechanical Engineering-71 (EDP-ME-71). This procedure describes the purpose as establishing and implementing through the Maintenance Work Order a program of augmented inspection and analysis of Balance of Plant (QA Cat II) high energy, carbon steel. piping for the purpose of detecting evidence of pipe wall thinning caused by erosion / corrosion (E/C).
EDP-ME-71 briefly explains the various erosion / corrosion parameters and establishes acceptance criteria for the inspection results.
These inspections will be performed by qualified Quality. Control (QC) personnel using their approved visual and ultrasonic (UT) procedures. The procedure also gives guidelines on selection of sections of piping or components having greater potential for wall thinning due to erosion / corrosion. Keller's Equation is to be used as the. primary basis for prioritizing components for inspection during- future outages. The first refueling outage will have an
,. ' abbreviated inspection effort for the purpose of gaining experience.
Inspections will include areas of piping identified by~ industry failures as being'nighly susceptible to erosion / corrosion: 1.e.,
condensate suction to feedwater pumps, feedwater short cycle min-flow recire, heater drains, extraction, and turbine cross-under piping. Nine lines have been identified and two control valves will be disassembled and inspection.
Erosion / corrosion inspection is applicable to all high energy (high temperature and high pressure) carbon steel piping and components in the balance of plant (QA Cat II). The inspections are QA-Not Applicable.
The following systems are included in the Erosion / Corrosion Control Program (additions / deletions may be made based upon industry and station inspection experience):
Cold Reheat (Turbine Cross-under Piping)
Hot Reheat (Turbine Cross-over Piping)
High Pressure Turbine Extraction Low Pressure Turbine Extraction Heater Drains and Vents Feedwater Condensate Specific line numbers identified by Engineering as being susceptible to Erosion / Corrosion are shown on Attachment #1.
Inspections will be documented (by mapping where necessary) and attached to the Maintenance Work Order (MWO) package._ Engineering will review the inspection results to criteria identified in EDP-ME-71 and make recommendations to maintenance accordingly.
Reinspection schedules will be calculated and recorded in accordance with EDP-ME-71.
- a. The inspection points selected for thickness measurements are described in EDP-ME-71. Basically, they consist of elbows, and downstream of valves, orifices, and other flow restrictions.
- b. The frequency of inspection is based upon 100% inspection of the susceptible pipe Ifnes identified by Engineering (Attachment #1) by the sixth refueling outage. This equates to approximately ten (10) years, which is the industry average for experiencing these types of failures. Frequencies of inspected piping will be adjusted according to the results as described in EDP-ME-71.
With regard to the inspection of high steam flow piping for evidence of internal pipe wall erosion, Engineering requires inspection of the following during each refueling outage:
Extraction From HP Turbine (Rotate the inspection of the lines and MSR inspected during each subsequent outage, such that all similar items and lines will be inspected by the sixth outage.)
i
- 1. One of the six (6) cross under pipes form the High Pressure (HP) l Turbine to the Moisture Separator Reheater (MSR) and inlets of one of the MSRs.
- 2. All elbows of one of the two extraction lines from the HP Turbine to the first point feedwater heaters (line nos.
1ESS-107-4; IESS-108-4).
- 3. All elbows including the initial branch tee of one of the two extraction branch lines off to the cross under piping to the 2nd ,
point feedwater heaters (line nos. IESS-105-4; IESS-106-4). l l
Feedwater Drains and Auxiliary Systems I (Inspect in accordance with QC inspection procedures for UT including the first elbow down stream of the flow control valve.
Rotate the inspec. tion .of the selected lines during subsequent outages. such that all similar lines will be inspected by the th1rd refueling outage), j
- 4. One of the three feed pump min-flow recirculation lines.
- 5. The feed pump start-up.line to the condenser.
- 6. One of the two ist. point heater drain lines to the condenser.
- 7. One of the two ist point heater drain lines to the 2nd point heaters.
- 8. One of the two 2nd point heater drain lines to the condenser.
- 9. One of the two 2nd point heater drain lines to the 3rd point d heater.
- 10. One of the two 3rd point heater drain lines to the condenser.
- 11. One of the two 4th point heater drain lines to the condenser.
- 12. One of.the two 4th point heater drain cooler lines to the !
condenser.
- 13. One of the two 5th point heater drain cooler lines to the condenser.
- 14. One of the two drain receiver tank drain lines to the condenser.
Quality Control will verify and document these inspections and a copy of the inspection results will be sent to Engineering for evaluation. Depending upon the inspection results, the intervals for inspection may be adjusted by Engineering accordingly.
Should any significant evidence of pipe wall erosion be detected, then the remaining lines which perform similar functions must also be inspected for possible deterioration. Additional direction will i be provided by Engineering.
For each of the lines listed, excluding those in the Extraction Steam System, the area of concern is that portion of each line including and immediately downstream of the control valve. In each case, the pressure drop imposed by the valve could cause " flashing" and " cavitation" should occur at a poitc. less than f1ve (5) pipe diameters downstream of the control vab es.
The potential impact on operations due to erosion has been reduced in the design phase by either increasing the wall thickness of the
- downstream piping or utilizing materials (e.g., 1-1/4 CR- 1/2 Mo or
- 304 SS) in the downstream piping that are more resistant than carbon l steel to the effects of erosion.
o l
r i
. i i For the Extraction Steam System, the concern is the creation and
" carryover" of moisture in the steam at relatively high velocities that might cause erosion. This effect could occur anywhere in the ,-
system during operation. Again the potential impact on operations due to erosion has been reduced during the course of design by the extensive use of 1-1/4 CR- 1/2 Mo and 304 SS piping in this system.
A. Periodic Inspection of Control Valve Internals The internals of each control valve noted in Attachment I should be inspected periodically for erosion damage. In those cases where an increase in noise, an increase in vibration or a decrease in the efficiency of the control valve is noted during operation, immediate inspection is warranted.
B. Periodic Ultrasonic (UT) Inspection of Downstream Piping The wall thickness of each line noted in Attachment I downstream of the appropriate control valve should be inspected periodically for erosion damage via UT inspection. As a minimum, all piping should be scanned linearly from the control valve to a point five (5) pipe diameters downstream of the control valve (including fittings and bends) starting at each of four (4) positions around the piping (i.e., the 3:00, 6:00, 9:00 and 12:00 o' clock positions). An unacceptable indication of erosion is considered as any reading where the wall thickness is less than the minimum wall thickness (including manufacturing tolerances) for the specified schedule or nominal wall thickness of the piping installed. Should any indications of erosion exist in the first five (5) pipe diameters, the scan should be continued at one (1) pipe diameter intervals until no indications exist for at least two (2) pipe diameters.
C. Periodic Ultrasonic Inspection of Extraction Steam Piping The wall thickness of the Extraction Steam System lines should be inspected periodically for erosion damage via UT inspection.
All carbon steel Extraction Steam System lines except those i lines in the condenser should be scanned starting at each of the i first two changes in direction downstream of the extraction i point, for a distance not less than five (5) pipe diameters. If i erosion exists at the second change in direction, the scanning f should be continued to the next change in direction, etc.
D. Evaluation and Resolution of Erosion Indications All indications of erosion in valves and piping shall be brought to the attention of Engineering for evaluation and resolution as j deemed necessary by Engineering.
The below listed minimum inspections are to be performed during the Reload-1 refueling outage. This will allow River Bend to begin an Erosion-Corrosion Monitoring Program, and gain experience. Future inspections will be adjusted based upon experience. Since this first inspection is an attempt to initiate an erosion / corrosion 1 l
_ _ - _ _ _ _ b
, i inspection program, the criteria to which these first inspections are made are based mainly upon flow velocities, operating and design temperatures, and operating and design pressures. The Line Designation Table (LDT) was consulted and the selections were made to include those carbon steel lines which operate within a band of 350+90*F, and pressures having significant damage or injury potential (i.e. operating / design pressure greater than 100 psig).
- 1. Visual interior inspection of 42" steam cross-around piping form the HP Turbine to the MSR-1 inlet. (Approximately 60 ft.)
- 2. Extraction steam line (1ESS-010-107-4) from HP Turbine to the first Pt. Heater A will receive four UT scans of four feet in length at the nozzle, and circumferential band of UT at each downstream weld.
- 3. Extraction line off 42" cross-around to the second pt. heater (1ESS-016-106-4) will receive four UT scans of up to seven feet in length at the nozzle, and circumferential band of UT at each downstream weld.
- 4. Heater drain line (1 HDL-020-100-4) from discharge of heater drain pump, PIB and downstream from flow control valve (LV-4A) to condensate line (ICNM-020-78-4) will receive four UT scans of eight feet in length past the control valve and past a 90* elbow and gate valve (V258) with a circumferential band of UT at each downstream weld.
- 5. Heater drain line (1HDL-012-4-4) from the second Pt. Heater A to the third Pt. Heater A vill receive four UT scans of five feet at each of five 90* elbows, plus an inner and outer grid inspection (UT) at each elbow, and circumferential band of UT at each downstream weld of the above fittings.
- 6. Feedwater Pump C suction line (ICNM-020-82-4) will receive four UT scans for three feet past the 20x14 reducer including one 45* elbow, plus a circumferential band of UT at each downstream weld of the above fittings.
- 7. Feedwater short cycle min-flow recire line (IFWR-010-6-4) to connection 5A of the condenser will receive four UT scans for four feet past the flow control valve, plus a circumferential band of UT at the downstream weld of the valve.
- 8. HP Heater drain line (1HDH-016-13-4) from the first Pt.
Heater B to connection 9B of the condenser will receive four UT scans for seven feet in length past each of five 90*
elbows, plus a circumferential band of UT at the downstream weld of the elbows.
- 9. HP Heater drain line (1HDH-010-4-4) from the first Pt. Heater l A to the second Pt. Heater A will receive four UT scans four feet in length at each of two elbows, plus an inner and outer grid inspection (UT) at each 90* elbow and circumferential band of UT at each downstream weld of the above fittings.
l t
f
Ts +
'10.::Two flow control valves (IFWR-FV2A, lHDH-LV26A) will be disassembled and visually inspected for erosion / corrosion.
- c. The methods'used-to measure' thickness are visual'and ultrasonic h (UT) as described in EDP-ME-71.- These UT inspections will be in accordance with approved QA procedure QCI-3.28. '
- d. Repair / replacement decisions are described in. EDP-ME-71 and
. basically are determined by the design minimum wall thickness.
L Any inspections which measure at or below the design minimum L z wall thickness will be recommended for repair / replacement depending on the actual individual-circumstances.
- 3. Criteria .used for_ selecting points of inspection -for both liquid-phase 'and ftwo-phase systems are described in EDP-ME-71 and include the following~ factors:
l
- a. Piping material - carbon steel (lines fabricated of stainless or l
Cr-Mo steel are not selected).
I- Note:' Most of the turbine extraction piping is either 304 stainless or 1-1/4 Cr-1/2 Mo.
- b. Piping configuration - all fittings and restrictions to flow will be inspected. Piping configuration can also have a significant impact on turbulence. At .Surry, the feedpump suction line has- two quick changes in flow direction whereas with the River Bend design the suction line branches off the main header at a 45 degree angle and eventually levels out using a 45 degree elbow. This is a more favorable transition.
The piping selected at the Surry unit was 18" extra strong, which has a nominal wall thickness of 0.5 inches (min. code allowable is 0.36 inches). The piping at River Bend'is 20" sch.
40, which has a nominal wall thickness of 0.59 inches (min, code allowable is 0.39 inches). This provides River Bend with an additional 60 mils of pipe wall.
A review of the steam piping systems materials and design indicate that the extraction steam system piping was designed to utilize long radius elbows and adequate drains to remove moisture. The extraction steam-inside the condenser, feedwater heater und MSR drains downstream of the level control valves subject to flashing utilize type 304 stainless steel. The extraction steam-outside condenser utilizes 1-1/4% chromium, 1/2% molybdenum materials. Gulf St&tes Utilities does not believe the extraction steam piping containing 1-1/4% chromium and 1/2% molybdenum or stainless steel type 304 requires upgrade since the pipe materials containing one to two percent chrome are four to five times more resistant to erosion than carbon steel and stainless steel is roughly one thousand times more resistant.
e *
- 1. According to INP0 SOER No. 82-11, piping materials which contain I to 2 percent chrome have been found to reduce erosion rates by a factor of four to five times over carbon steel. A review of the extraction steam system flow diagrams shows the use of 1-1/4 percent chrome and 1/2 percent molybdenum steel piping material. This choice of material was applied to the piping for the first to fourth point heaters employ the use of a stainless steel piping material. The referenced INPO report states that his material can be significantly more resistant to erosion than carbon steel. The use of these materials alone would help to minimize the risk of piping system erosion.
] '
- 2. Although it is virtually impossible to remove all configurations which might promote erosion of the piping system, efforts are being taken to ensure that the potential l
1s reduced where possible. A review of the piping '
arrangement drawings associated with extraction steam was conducted. In general, all piping is sloped to prevent water traps, and no reducers were used that would create a water trap. Where lines are tied together in a manner where steam jet impingement could occur, lateral fittings have been used.
l c. PH is maintained between 5.6 and 8.6 in accordance with the GE I BWR-6 Fuel Warranty and Tech Spec Table 3.4.4-1; therefore, it l need not be considered in determining erosion / corrosion deterioration.
- d. Temperature - system design temperatures greater than 260*F are included,
- e. Velocity - high energy or systems having the potential for high flow or if unconfined may cause severe damage or personal injury, i.e., having pressures greater than 100 are included.
l 1
Based on the data supplied by INPO and the NRC, the fluid velocity at the Surry unit was 17.6 feet /second. At River Bend the fluid velocity thru the feedwater suction line is 10.5 feet /second. This shows a 33% decrease in feed water flow which would indicate less turbulence. Damage at the Surry unit occurred after the unit was operating for over 13 years as compared to River Bend's one year of operation.
- f. Oxygen content is mainrained between 20-50 ppb in accordance with the GE Fuel Warranty and does not need to be considered in determining erosion / corrosion determination.
NOTE: Although the water quality is set by Fuel Warranty and cannot be adjusted, it can be seen that the oxygen content, is high enough to inhibit erosion / corrosion.
- 4. Refueling Outage (RO) - #1 will be the first opportunity to initiate inspections specifically conducted for the purpose of identifying pipe wall thinning caused by erosion / corrosion.
o ,
n
- y c. L a, b, &;c The.~only inspection' conducted. to' date which. was specifically Jconducted for investigation of erosion / corrosion was performed via Maintenance Work Order-(MWO) 108559 this spring. . This inspection was a UT scan of
- the first elbow downstream'of a' relief valve in a high radiation area on the. heater drain system which was isuspected of. leakage past'the' seat 'and flashing to the-condenser.- The piping nominal thickness was .375 in. with a minimum design wall thickness of .276 in. Results of the -inspection were thicknesses of between .420 in. and
.450'in. for,the radius of the elbow and between .380 in, and. 390'in, at both ends of.the elbow. All results were acceptable being greater .than' the specified nominal thickness.
I
- d. The only other: piping . area identified as having significant I erosion / corrosion problems .was. the feedwater short-cycle min-flow _ recirc line back to the condenser.- This piping was so badly eroded'during the start-up phase of :the plant that .the-segments' .between the control valves and . isolation valves downstre'am-of the control valves-for'each of the three pumps was replaced with' stainless steel..
5L. River Bend. has no plans for developing new or additional programs-
- for monitoring pipe wall' thickness. The present program is-recently developed and is expected to be revised and refined as experience is gained during these inspections.
The safety-related . systems are not presently included in the' Erosion / Corrosion ' Control Program. Culf States Utilities believes
-that the ASME XI Inservice Inspection program examinations of welds will' identify evidence of any. erosion which will lead to further ultrasonic wall thickness' examinations if warranted.
l l
EEAR 37 -Rc309N
, TTAC H AA ENT. / Page / 7 c f ' , #"h' 16mdwr EDP4E-71
- Revisim 0 Page 22 of 45 ATDOM!NP 7.15.1 Page 1'of 3 l
'Da[E 1 I
BOP piping lines which should be considered for inspection as being susceptible to erosion / corrosion.. (Addition / deletions to this list may be made based upon industry experier.ce); '
Line Number FSK PID _EP
- 1. 42"-Steam Cross-Under (6) Visual 3-2 4-2G
- 2. 42" Steam Cross-Over (4) Visual 3-2 4-2G
- 3. 1ESS-010-107-4 3-4A 4-2G 4, 5
- 4. ,1ESS-010-108-4 3-4A 4-2G 4, 5
- 5. 1ESS-016-106-4 3-4A 4-2G 4, 5
-6. .1ESS-016-105-4 3-4A 4-2G 4, 5
- 7. 1HDL-018-98 4-2A 4-2C 25
- 8. 1HDL-006-13-4 4-2A 4-2C. 25 l
- 9. lHDL-016-125-4 4-2A 4-2C 25
- 10. 1HDL-016-126-4 4-2A 4-2C 25
- 11. 1HDL-020-11-4 4-2A 4-2C 25 12.' 1HDL-020-102-4 4-2A 4-2C 25
- 13. 1HDL-003-136-4 4-2A 4-2C 25
- 14. 1HDL-003-135-4 ~4-2A 4-2C 25 15.'1HDL-018-37-4. 4-28 4-2D 25
- 16. 1HDL-018-91-4 4-2B 4-2D 25
- 17. 1HDL-020-89-4 4-2B 4-2D 25
- 18. 1HDL-014-115-4 4-2B 4-2D 25
- 19. 1HDL-006-38-4 4-2B 4-2D 25 20, 1HDL-020-36-4 4-2B 4-2D 25 21 1HDL-016-123-4 4-2B 4-2D 25 22, 1HDL-016-124-4 4-2B 4-2D 25
- 23. 1HDL-020-93-4 4-2B 4-2D 25
- 24. 1HDL-008-43-4 4-2C 4-2E 25E 25, 1HDL-008-21-4 4-2C 4-2E 25E
- 26. lHDL-010-55-4 4-2D 4-2F 25E
- 27. 1HDL-016-54-4 4-2D 4-2F 25E 28, 1HDL-006-65-4 4-2D 4-2F 25E
- 29. 1HDL-016-63-4 4-2D 4-2F 25E
- 30. 1HDL-008-64-4 4-2D 4-2F 25E
- 31. 1HDL-010-70-4 4-2E 4-2F 25E
- 32. 1HDL-016-69-4 4-2E 4-2F 25E
- 33. 1HDL-006-80-4 4-2E 4-2F 25E
- 34. 1HDL-016-78-4 4-2E 4-2F 25E
EERR 87-RO3C9 l2
'. ArrAcHMENT *l p is cf ;#j Mmewr EDP 4E-71 Revisicm 0 Page 23 of 45 ATDCRE!Nr 7.15.1 Page 2 of 3 Line Number FSK PID _EP 35, 1HDL-012-4-4 4-2A 4-2C 25
- 36. 1HDL-018-12-4 4-2A 4-2C 25
- 37. 1HDL-018-6-4 4-2A 4-2C. 25
- 38. 1HDL-020-16-4 4-2A 4-2C 25
- 39. 1HDL-020-148-4 4-2A 4-2C 25
- 40. lHDL-012-29-4 4-2B 4-2D 25
- 41. 1HDL-018-31-4 4-2B 4-2D 25 42, 1HDL-020-41-4 4-2B 4-2D 25
- 43. 1HDL-020-150-4 4-2B 4-2D 25
- 44. 1HDL-008-151-4 4-2C 4-2E 25E
- 45. 1HDL-008-67-4 4-2C 4-2E 25E
- 46. 1HDL-010-24.-4 4-2C 4-2E 25E
- 47. 1HDL-010-152-4 4-2C 4-'2E 25E
- 48. 1HDL-008-44-4 4-2C 4-2E 25E
- 49. 1HDL-008-153-4 4-2C 4-2E 25E 50, 1HDL-010-46-4 4-2C 4-2E 25E
- 51. 1HDL-010-154-4 4-2C 4-2E 25E
- 52. 1HDL-008-56-4 4-2D 4-2F 25E
- 53. 1HDL-010-155-4 4-2D 4-2F 25E
- 54. 1HDL-012-58-4 4-2D 4-2F 25E 55, 1HDL-014-156-4 4-2D 4-2F 25E
- 56. 1HDL-008-71-4 4-2E 4-2F 25E 57, 1HDL-010-157-4 4-2E 4-2F 25E 58, 1HDL-012-73-4 4-2E 4-2F 25E
- 59. 1HDL-014-158-4 4-2E 4-2F 25E
- 60. 1HDL-008-79-4 4-2E 4-2F 25E
- 61. 1HDH-016-6-4 6-6 4-2A 61
- 62. 1HDH-010-4-4 6-6 4-2C 61
- 63. 1HDH-016-13-4 6-6 4-2B 61
- 64. 1HDH-010-11-4 6-6 4-2D 61
- 65. 1EWS-020-1-4 6-1A 6-1A 17A
- 66. 186-020-2-4 6-1A 6-1A 17A
- 67. 1Ews-020-3-4 6-1A 6-1A 17A i
- 68. 1FHS-008-1-4 6-1A 6-1A 17A
- 69. 1EWS-008-3-4 6-1A 6-1A 17A {
- 70. 1Eus-008-5-4 6-1A 6-1A 17A !
- 71. 1FWS-012-12-4 6-1A 6-1A 17A I
- 72. 1FWS-012-13-4 6-1A 6-1A 17A
- 73. 1Ews-020-10-4 -
6-1A 6-1A 17A q 74, 1Ews-020-5-4 6-1A 6-1A 17A l
- 75. 1FWS-020-9-4 6-1A 6-1A 17A
- 76. 1Ews-020-6-4 6-1A 6-1A 17A 1
' EEAR 8 7 *RD3c9 hTTACHMENT *l (L e. 19 cl .
J.
,,gy Mmewr amrisi=.
EDP4E-71 ,
Q Page 24 of 45 0
31//g7 ATDCIM!NT 7.15.1 ;]
Page 3 of 3 Line Number FSK PID g
- 77. 1FWS-020-8-4 6-1A 6-1A 17A
- 78. 1EWS-020-7-4 6-1A 6-1A 17A
- 79. 1EWS-020-80-4 6-1B 6-1A 17B
- 80. 1EHS-020-30-4 6-1B 6-1A 17B j
- 81. IEWR-010-6-4 6-3 6-1A 57A
- 82. 1HDL-014-110-4 4-2A 4-2C 25
- 83. 1CNM-020-82-4 4-1E 4-1B 18A' (18K)
- 84. 1CNM-020-83-4 4-1E 4-1B 18A (18K)
- 85. 1CNM-020-84-4 4-1E 4-1B 18A (18K)
- 86. 1EWR-008-1-4 6-3 6-1A 57A 87, 1EWR-008-3-4 6-3 6-1A 57A 88, 1EWR-008-5-4 6-3 6-1A 57A
- 89. lEWR-010-2-4 6-3 6-1A 57A -!
- 90. 1EWR-010-4-4 6-3 6-1A 57A I i
i l
\
i l
1
gTTACHmEtMT # EEAR 87-RC5cq 12 2.
. . . Peq zo & , qfi 4
,cri/ 7i
' 1.5 APPEtDIX D - 3,7 rim BEND S13LTION UNrr 1 '
GULF STkTES (irdin.sS ct3ggury g CGUtOSION AT Tnttpume 1.12 i
21.fsla .
2A21 1.15 verification of Piping Mininnan Wall and corrosion Allowance 1.17. !
D-2 1.18 Corrosion Allowance Table D -4 1
1.20
)
1 1
I ch-12210-1200j 04/07/90 153 h -
1
1
+ EEAR 8' 7-RC5C9 Ad
[TT CHMENT 2 D-2 e g cp 'A/
' epp )
/ YERIPIC&TI0I 0F BIFIN.EZIIBUB IALE AND C08803 ION ALLCR4ppy IN I' - -jach system tagineer is required sinissa vall thickness of the piping in his system to verify and the_ 1.25 L
to verify the adequacy of the corrosion allevance. Sritical 1.'28 also 1.2/
l systems (i.e., asia steam, feed vater, condensate, residual heat removal, and reactor t' greater than 24 la diameter mater- cleanup) and all piping 1.29 i are to be verified -)y: an 1.30 1
individual calculation checked. by a Piping Engineer. ,
Jacentioans (a) extraction steam piping
.' Xndd 8 PTP 26.1.7-0 and pipe covered by 1.31 i service, (b) interna $he classes specified for that .1.32
( aonsetallic pipiag.
lly lined pipe er plastic pipe, and '(c) 1.33 )
includia'g critical piping, will be 1.34 All piping, verified siniana vall issue of Jine by means of the Designation Tables (LDT). 2he_ 1.36 the LDT cospetes and prints out the 1 l
sinians glaculated design tem wall thickness for piping based upon the 1.37 3ressure, pipe class) perature, inputted for and each' pipe material (based on 1.38 line froe Ahediagram.
flow 1.39
, 2he systen En gineer is to follova:
perfore this verification- as 1.40 i L
R3113itinas i 1.42 i Jigiana Calgulated Wall Thigjgg33-(Tae) 1.44
)
(
j 2he piping wall thickness calculated from the design
- 1.45-
- formula ANSI B31.1give in 1551 III '(Article 58, NC, et 50 3641) or. 1.46 (paragraph 104) ssing design pressure, 1.47 i by individ ual calenlation or as given ,(pipe class),
temperature, and material stress allowable 1.48 I designation tables. in the line i
l i
Minimus Manufgg3sggj Wall ( T a)_ 1.49 I
I 2he piping wall thickness minians as supplied s tan dard supplied Ripe (see S8W STD-SP-1056-1-5 on 1.50 or established by salenlation or 1.51 STD- S P-10 56 5) for 1.52 )
Xndd 8 special pipe (larger than 24 inch OD), see PTP 26.1.1-0.
Corrosion allowamce iat 1.53 Jacess material above minians calenlated wall to allov 1.54 for the corrosion power ga the ID of the piping during the life of 1.55 plant, or as defined
>l
': &NSI 331.1, and additional thickness to la 455E III and (1) compensate 1.56 for 3aterial removed la threading, (2) provide for 1,57 corrosion and/or erosion, and J3) provide for structural 1.58 strength of the pipe during erection.
Zoe the River Bend Project the' corrosion allowance for
.f either rolled and gelded SA-156 pipe or for piping 2.2 2.1 l chr-12210-1200j 10/15/83 124
LM!
Arracumcur *2 EEAR 87dC3C9p&4gf1
/... o, Py e n cf gg 4M i systems which will contain acidic,5austic or other 2. 3 highly corrosive fluids shall be obtaine;d from, the Lead jgatorials Engineer. ssW 311 other piping on the River 2. 5 '
X Add 6 Bend og project will use the corrosion allowance standards 2.6 gg-NEBG Specification No. 22A-5495, Appendix III (attached) . Revision 1, or J,inimum corrosion 311owance shall be .080 in. for m 2. 7carbon
- 2. 0 steel and .002 in. for stainless steel.
- 1. On LTDs verify line class) , design numbers . (size and code pressure, 2.10 material (pip class) . j;emperature, and 2.11 J. compare Tac from calculation or LDT to "Tm" 2.12 (STD-SP-1056) thatn "Taca. to ensure _that atma is not less 2.13 J. If Item 1 above is satisfactory, subtract "Taca from "Tma and determine 2.14 the available 2.15 corrosion allowance aaa: ~
a=Tu - Tme.
2.17 4 compara and verify that ama is in compliance 2.19 with the criteria stated above.
- 5. If Items 1, 2, and 3 above are not satisfied, 2.20 a higher pipe class must be specified. >
I
{ chr-12210-1200 j 11/17/82 124 k
EEAR 1740.5c p?
+
. ATracumeNr 2
. . .X .Add ' . 6: -
l.- D-4 y
<J3 ch' ,
SENERAL$ILICTRIC
, As4ts = =. 12s -
auctuam emenoyavmon aty. I
,- Arrenots tus -
CDRRO$10N ALLOWAMCt
- 1. CORA0310N ALLOWANCI , ,
1.1 The following 40-year service life cor.resion allowances. based on corrosion I
. of one surface. have been includd in the Appendix !!.Scheevles which are used la the WR piping for which E has system responsibility. In those systass that are the responsiht11ty of others tt represents the mcommendatians of General Electric.
1.1.1 Carbon Steel tvstan=
Service terrosion Allowance inches
' (1) Contral Aod Drive Hydraulic Main Flow Lines satarmittant Flow Lines
- 0.080 0.080 (2). Reactor Water Clean-up Systasi *
'0.030 (3) Precoat Systans
, 0.000 "
(4) Re' actor Core Isola'tfon Cooltag 0.040 (5) Nigh Pressure Caelant Injection er Nigh Pressure Core Spray System -
' ' ~
0.080 (4') Core Spray Puap Suction and Discharge Piping '
' Piping Exposed to Reactor Watar , 0.080
.(7) Main Staas. M5!Y. Laakage contret Systan' . -
O.120 (8) Normally Flowing Auxiliary 3 teas Lfnas
, 0.120 .
(9) Normally Non-Flowing Auxilf ary Staan Lines 0.120 (10) Staas Line Oratas 0.120 (11) 4WR Watar (0.01 ppe Og ) 212*F 0.2
, 100*F 02 Saturated Watar ,0.040 (It) Feedwater -
~ 0.000 d (13) Fuel Pool Cooling System ..
, ,' 0.000
/ s, . ,
~
. EEAR 87-RCsc :
- o. -
x 4s4 4, N.rrAcHmsnr*2 P*p y c9 l .
D-5 .
ww<ifij, SIN ER AL @ ILICTRIC 22As4ss . m, Its -
mm.uasaamovomsen ,,,, I rinAL APPDI0lt !!! ,
1.1.1 (Continued)
Service . Corrosion Allowance fnees 1
Residual Heat Removal Systas - -
(14) RM Piping taposed to Reactor Water .
0.080 (15) Reactar Ver.t -
0.040 (14) Reactor vessel Flange Leak Offs 0.040 (17) Raaster Vassel Orata (next to vessel)
(la) Off-sas System Process Lines 0.120 (19) Deserstad Candensate ,
0.010 (20) Condensata and Destneralized Watar from Storage 0.000
, (21) Closed Coolind Water System ' O.100 (22) RaMsta Disposal - Lfquid .
0.080 (23) Non Flew Watar Piping (full during operation) 0.020
-(24) Suppress,1on Pool 0.250*
1.1.2 Stafnless steel $wtems ,
All Services 0.003
. \
1.1.3 A1ustnum Allor intees All Services ~
0.010 l 1
. . l 1
l
~
~
Tor submerged ofpine tAere two surfaces are wat the corroston allowance should be 80weled to 0.$00. itifaless steel is recommended for use in ts ead of carbon steel d for piping in the suppression pool. In weten case cerrosion alloence should be 0.006. .
4 .