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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] |
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GULF STATES UTILITIES COMPANY P O S T O F FIC E B O X 2951 . BEAUMONT. TEXAS ?7704 AREA CODE 713 838-6631 November 8, 1984 RBG- 19,385 File No. G9.5, G9.8.2.6, G9.19.2 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
River Bend Station - Unit 1 Docket No. 50-458 Attached is Gulf States Utilitics Company's (GSU) revised response (Attachment 1) to the Staff Position regarding the River Bend Station (RBS) Drywell/ Containment Purge System transmitted to Mr. W. J. Cahill ,l from Mr. A Schwencer on January 23, 1984. This transmittal supersedes GSU's letter from Mr. J. E. Booker to Mr. H. R. Denton dated March 13, 1984 and reflects discussions held with the Staff on April 3, 1984.
In addition, GSU's position as stated herein represents the response to the Safety Evaluation Report (SER) Confirmatory Item #18 -
Containment Purge Valves (SER Section 6.2.4.3, pg. 6-29).
Attachment 2 contains revised text of the Final Safety Analysis Report (FSAR) to support statements in Attachment 1 and in combination with Attachments 3 and 4 address the Staff's Request for Additional Information on Purge and Vent Valve Operability transmitted to Mr. W.J.
Cahill from Mr. A. Schwencer on March 15, 1982. The revisions contained in Attachment 2 will be included in a future FSAR Amendment.
Sincerely, e h J. E. Booker Manager-Engineering, Nuclear Fuels & Licensing River Bend Nuclear Group OlOV 6y JEB/WJR/JWL/j e
' l Attachments (4) M'f \ ' '
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8412060379 84110s q
E PDR ADOCK 05000458 PDR A
r Attachment 1
- 1. STAFF POSITION Continuous containment purging through large diameter valves will not be allowed. We will require the applicant to develop appropriate interim guidelines that will establish provisions for a reduction in the use of the containment purge system. These guidelines will consider limitations on airborne activity levels to satisfy the as low as reasonably achievable (ALARA) levels and overall containment air quality in determining when use of the purge system is not needed. The interim guidelines shall be furnished to the NRC staff six months before the initial fuel load data.
RESPONSE
GSU has performed an analysis to estimate the number of hours per year that containment purge will be required for containment radiation purposes. This analysis is based on GE Document No.
22A5718, Revision 1, " Mark III Containment Dose Reduction Study",
dated March 11, 1980, using design basis main steam and coolant source terms. The buildup of airborne activity in the containment is assumed to be interrupted every 18 months for a refueling cutage. {
The basic criteria used in this analysis was to maintain airborne activities below 25 percent maximum permissible concentration (MPC) during normal operation. Using the normal containment purge rate of 7,000 cfm, the results of the analysis indicated that a normal containment purge usage of 7,300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year is required to limit the airborne setivity to 23 percent MPC. This analysis has been reflected in the proposed RBS Technical Specifications submitted July 17, 1984 (RBG-18,233).
- 2. STAFF POSITION The app.'.icant shall commit to implement a data collection effort to justify the need for containment purging. Before startup after the first regtlarly scheduled refueling outage, the applicant shall use the results from the above program (based on containment purge system (CPS) operating experience information) to evaluate the plant's need for purging. A summary of the evaluation shall be provided to the NRC staff before the plant returns to operation.
RESPONSE
GSU will implement a data collection program, during the first fuel cycle, to collect and evaluate RBS containment purge operating experience information. An evaluation of this information will be made to determine if personnel exposure can be reduced, if airborne concentrations were maintained less than 25% of the maximum permissible concentration as specified in 10CFR20, and if changes to the interim purge guidelines are warranted.
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4 GSU is aware that data gathered during the first fuel cycle may not necessarily be indicative of dynamic plant conditions and will consider future plant usage in evaluation of the interin guidelines.
Evaluation of the interim guidelines will include any applicable Mark III purge experience.
- 3. STAFF POSITION The applicant shall commit to develop a containment access management program so that access time requirements will be minimized as appropriate. Considerations of the total spectrum of activities to be performed, as well as when and how those activities can be accomplished, will be included. A description of this program shall be furnished to the NRC staff six months prior to the initial fuel load date.
RESPONSE
GSU has developed a containment access management program (CAMP) to minimize personnel access and residence time in containment.
The primary objective of the CAMP for River Bend Station is to control and evaluate containment access based on plant specific operational experience. In order to control and evaluate containment eccess, the CAMP will consist of the following activities:
- 1. Procedures to control containment access
- 2. Collection of access data during first fuel cycle
- 3. Evaluation of access data
- 4. Recommendations based on data evaluation Control of containment access will be by procedure which establishes criteria to be met prior to entry, coordinates the entry among the various site groups (i.e. Operations, Security, Maintenance) and directs the collection of access data:
- 1. When entries are made
- 2. Purpose of each entry
- 3. Duration of each entry
- 4. Number of personnel required for each entry Access data vill be evaluated at the end of the first fuel cycle to determine if regularly scheduled containment entries are being consolidated to the greatest extent possible and if equipment performance indicates that the frequency of operational checks and routine surveillances can be reduced based on the data evaluation.
Recommendations will be made by the ALARA Committee to Operations and Maintenance with regard to frequency and scheduling of operational checks and routine surveillances.
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( 1' a 4. -STAFF POSITION
, P' urging (of; the ~ containment shall' be secomplished lby.'use of a ._
- low-volume; purge l system, i.e'.,ipurge valve. size'shall not exceed-8" for Operattug : Modes' l', 2,. and.3 (i.e. , l power- operation, start up and hot. shutdown). LHowever, to' avoid delaysiin critical. path testing of:
~
~
-the-purge. system'and-the_ resultant l impact on fuel load schedules, it (E, .
'is. proposed that,the existing system betused until it is-determined, c
6 ~ based onJItems 1-3 above,1when: purging..isineeded;and the-line size
-= to' accomplish this'. The applicant:shall:also commit-to submit forn staff l review all available data and proposed programs that (demonstrat'eLthe reliability of the:36Linch diameter. valve utilized cat River Bend Station six months prior,to fuel load. .
.s
RESPONSE
Based on'GSU's stated position on Items 1-3 above, GSU is using the p .. : existing system equipment'for limited purge'in accordance with the interim guidelines. Based on the.results and evaluation of'.the.
icontainment purge operational data gathering program in Item 2, the purge 1 guidelines for the first. fuel cycle will'be evaluated and a-
! report submitted:to the-NRC.
~
Enclose'd'a'e r the Posi-Seal International, Inc..-report (see Attachment 4) supplemental technical justification (see Attachment
-3) and an evaluation of NRC Branch Technical Position (BTP).CSB 6-4,.
. outlined-in table form:(see Attachment 2). . In conjunction with the -
enclosed documentation, which outlines the considerations developed for. showing valve reliability, GSU will add actuator limit stops restricting the valves to.a 65-deg. opening and change the bolting Laaterial on valve 1HVR*A0V123 to SA354GRBD. The restriction was
'developedLin the LOCA and seismic analysis (Attachment 4) based on flow rates developed-with a conservative 9-psi pressure drop.across the antives. GSU is implementing the Poti-Seal recommendations for all-valves, even though our estimated dP will be 3' psi with
'significantly lower. aerodynamic torques. This is addressed in the
- technical justification. The bolts'are being changed to ensure that c ' valve 1HVR*A0V123 is not overstressed during seismic and LOCA:
. events.
- 5. STAFF POSITION
- Purge / vent valves that are to be used during Operating Modes 1 through 3 shall meet all staff requirements set forth in Branch Technical Position 6-4.
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I
RESPONSE
V. .
3, CSU will comply with the intent of BTP 6-4 with the following clarifications:
- 1. (a). Comply 1.(b)' The current number of primary containment /drywell purge supply and exhaust lines are limited to one supply and one exhaust line.
1.(c) The current design utilizes 36 inch containment isolation valves and 24 inch drywell isolation valves for the primary containment /drywell purge supply and exhaust lines.
1.(d-g) Comply
- 2. Comply
- 3. Recirculation of containment atmosphere is accomplished through an external purge filter.
- 4. Comply 5.(a-d) Comply
- 6. STAFF POSITION The drywell supply and exhaust isolation valves shall be normally
\
closed during Modes 1 through 3 except:
- a. To accommodate drywell pressure control or reduce drywell activity levels in Operating Mode 3, the applicant shall limit use of the drywell purge system to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per year (cumulative) for Operating Mode 3.
- b. To accommodate the need for drywell pressure control during Operating Modes 1 and 2.
(1) Either the exhaust or supply lines of the drywell purge system may be opened, but both lines shall not be opened at the same time, (2) While venting the drywell, the containment shall not be vented or purged, and j
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c ;x C . "'.. s (3) DThe total _. time of ventingsthe drywell shall'be limited to
.five: hours per.~ year (cumulative) for Operating. Modes 1'and' y'
-2. JThis restriction will.be withdrawn ~upon: receipt and
'_NRC approval:of' analyses to demonstrate acceptable (consequences on_the containment structure!and'the enclosed equipment following~ onset of4the most~1imiting primary::
, system break during use of the drywell' purge system.
RESPONSE-
- GSU.is currently _ studying'the nee'd,' availability and design of the idrywellipurge system in light.of'the' Staff's recommendations-and
- will respond 'ay December. 14, 1984.
"7. STAFF POSITION
^
If purging:(either-drywell or containment) is'through the SGTS, requirements-Sb of Branch-Technical Position 6-4 should be met,
-otherwise, the following restrictions should be implemented.
- a. Whenever the purge system is in use during Operating 1 Modes 1, 2, and 3, only-one of the two SGTS trains shall be_used, and b ~. - Both-SGTS trains are determined to be operable whenever1the
, purge system is in use.
RESPONSE.
Norma 1' primary containment purging (7000 cfa) in Operating Modes 1,,
2 and 3 will be.through the containment purge exhaust filter;
~however one standby gas treatment system (SGTS) subsystem may.be'in the purge flow path provided that both SGTS subsystems are operable.
The two=SGTS, trains will not be used in the fast purge mode (25,000
-cfm)-in Operating Modes 1, 2 or.3..
- 8. STAFF POSITION The hydrogen mixing system shall not be opened during Operating Modes 1 through 3 for drywell pressure control or airborne activity level reduction- since the valves on this system receive ru) LOCA isolation. signal.
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7
RESPONSE
The hydrogen' mixing system valves for the drywell close on a LOCA signal. This signal can be overridden by the operator upon verifying that an actual LOCA does not exist (see-revised FSAR Section 6.2.5.2.1 contained in Attachment 2.) In addition, the hydrogen mixing system valves are environmentally qualified; therefore, one inlet line or one exhaust line may be opened for drywell pressure control provided that the primary containment /drywell purge valves are closed. The potential for drywell bypass with the 6 inch hydrogen mixing system inlet valve open is 0.20 sq.ft which is bounded by the analyzed allowable bypass for the entire spectrum of breaks for RBS. Based on acceptable containment pressurization consequences under all break conditions with one hydrogen mixing line path open, GSU may elect to utilize this path for drywell pressure control with no limitations on total time for venting in a year. While venting the drywell using the hydrogen mixing system in Modes 1, 2 or 3, the primary containment /drywell purge system will not be operated.
- 9. STAFF POSITION The purging system (drywell and/or containment) shall not be utilized for temperature / humidity control during Operating Modes 1, 2 and 3.
RESPONSE
The primary containment /drywell purge system will not be utilized for temperature / humidity control during Operating Modes 1, 2 and 3.
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'FSAR REVISIONS-INCLUDING A-4 .
SUMMARY
EVALUATION OF CONTAINMENT - "
FURCE VALVES AGAINST NRC
_ BRANCH. TECHNICAL POSITION CSB'6-4 e . I Note: These revisions will be included in the FSAR.in a future amendment.
k i
as RBS-FSAR
- .;7.I. intent yof the technical
? f?' position requirement for 1eakage rate testing. The j system. complies :with this technical position for testing the availability of the valve isolation function. -Leak tightness and testing in accordance with 10CER50,
.. Appendix J,.are considered to satisfy the intent of the branch technical position
.c requirement for leakage rate I testing.
(4) BTP CSB 6-4 Position B.S.c:
The ECCS back pressure requirement is not applicable INSERT y to BWR containment.
- 6. Containment Hydrogen Purge The Containment Hydrogen Purge System complies with all applicable portions of NUREG-0737, Item II.E.4.2, except: 11 A' a. Positions 1 and 3:
. Manually operated containment isolation '
valves in the nonessential penetrations listed below are closed during. normal, shutdown, and postaccident operation.
Penetration Title Valve No.
1KJB*Z31 Containment Hydrogen 1CPP*SOV140 l . Purge Supply Line 1KJB*Z33 . Containment Hydrogen ICPP*MOV104 Purge Return Line 1CPP*MOV105
~
- For these motor-operated and solenoid-operated valves, administrative control includes mechanical devices to seal or lock the valve- closed or to prevent power from being supplied to the valve operator. Valve position and locking devices are. checked each time the
- containment is secured. In addition, the seal or lock is verified intact.at'least
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Insert (p.6'.2-74k)-
B Demonstration.of the operability of the containment purge valves and their ability._to'close during a design basis accident is sununarized in ,
HTable-6.2-52. .1 detailed report'has been submitted to'NRC under i f,
separate cover.(Ref. 27) The report verifies.that the valve actuator's torque capability has sufficient margin to overcome the torques and forces that resist closure when stroking from the initial open position to full seated in the time limit specified'following a design basis LOCA..
o 1
4 l
I N
I .
I r
F
, , 3.5 volume percent. Thus, the hydrogen mixing system is
- . n capable of removing -hydrogen at generation rate. a rate of 2.2 times the Initiation of the hydrogen mixing system requires an operator first to. energize an inlet valve in the line connecting the drywell and containment. Opening of the valve equalizes drywell and containment pressures if they are different.- An interlock is provided to prevent opening of the outlet valves before the inlet valves are fully '
opened. The operator then manually opens the outlet valves and, the with the valves in their fully opened position, starts hydrogen mixing fan (Fig. 7.3-8). There is no limitation to on pressure the initiation of hydrogen mixing system due differentials between the drywell and containment.
Using extremely conservative system initiation is not required assumptions, hydrogen mixing until at least 3 hr following the LOCA.
An alarm is sounded in the main control
-rocm when hydrogen concentration at any of the four drywell sample points is determined by the analyzer to be greater-
.than or equal to 3.5 volume percent. This alarr signals the -
operator INSERT 1 to manually initiate the hydrocen mixina system.<w T,1e requirement for manual operation ensures that spurious signals dc not prematurely actuate the system and, ms, therefore, do not result in inadvertent steam bypass leakage from the drywell to the primary containment. The valve interlock previously described ensures that a single operator mixing fans.
error does not result in initiation cf the hydrogen Although a single operator error could result in the opening of one 6 in hydrogen mixing system inlet
- path, the allowable steam hypass leakage capacity for the River Bend Station drywell -
bypass leakac e capacity of this leakaae (A//k = 1.0 f t2) exceeds the INSERT 2 oathias discussed in Section 6.2.1.1.3.4.
Drywell and containment conditions of pressure, temperature, and hydrogen concentration are continuously monitored and are available to the main control rocm operator,s.
6.2.5.2.2 Hydrogen Recombiner System The long-term centrol of hydrogen below the '4 percent by volume flammable limit is achieved by means of thermal hydrogen recombiners located in the primary containment.
The hydrogen recombiner system is fully redundant. and consists of two 100 percent capacity hydrogen recombiners.
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' ' Insert 1.for Page 6.2-80.,
y.
The hydrogen mixingl. system valves c.1ose'on a.LOCA signal whichican be
' overridden by the operator-upon verifying that.an actual.LOCA does not 1 exist.
.. -r .
- Insert 2 far Page. 6.2-80.
, (A//F=0.'2sq.ft.) .1 W
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RBS ESAR
- 24. Regulatory Guide 1.141, Containment Isolation Provisions
. for Fluid Systems, April 1978.
- 25. Regulatory Guide 1.11, Instrument Lines Penetra. ting Primary Containment, March 10, 1971; supplement, 33 February 17, 1972.
- 26. BWR Owners' Group, NUREG 0578, Implementation Analyses and Positions. for Plan-Unique Submittals NEDO-24782, BONED 006 Class I, August 1980.
- 27. Transmittal letter from J.E. Booker to H.R. Denton dated November 8, 1984 (RBG-19,385); Docket No. 50-458.
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Amendment 11 6.2-97 January 1984 ,
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f TABLE 6.2-52
SUMMARY
OF CONTAINMENT PURGE VALVE OPERABILITY DEMONSTRATION Consideration RBS Analysis
- 1. Valve closure rate vs time Valve closure is within 3 seconds. This is ensured in Reference 1. The 3-second closure ensures worst-case differential pressure of 3 psi or less (see Item 2).
- 2. Flow direction through valve Flow direction evaluation in and dP across the valve Reference 1. 1HVR*A0V165 and r 166 are in preferred direction for closure, and 1HVR*A0V123 and 128 are in nonpreferred direction.
The maximum differential pressure is less than 3 psi based on various accidents outlined on FSAR Figures 6.2-4 through 6.2-7. Isolation occurs based on drywell pressure.
See Logic Description, FSAR Figure 7.3-9, sheet 14.
- 3. Single valve closure vs In performing the LOCA analysis, simultaneous valve closure it was assumed that the valves close individually. This assump-t tion is considered more conserva-tive because if both valves closed simultaneously, the resistance in the system would be greater, and consequently, the flow and the aerodynamic torque would be less.
- 4. Containment backpressure The backpressure effect on venting effect on closing torque pilot air to the containment is margins of the air-operated conservatively addressed in Reference valves, which vent pilot air 1 (i.e., assumed 9 psi containment inside containment backpressure).
- 5. Adequacy of accumulator Accumulator not required. Valves close by spring force on release of air from operator.
- 6. Adequacy of torque-limiting No terque-limiting devices are devices required because of the valve design.
- 7. Effect of upstream and down- The effect of the piping system stream piping system was addressed in Reference 1.
Only one valve, lHVR*A0V123, R
m-_ -. -_ - _ - - - . _ - - - -
- . = _ . - - - ---
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i
. required that the; effects =of an
-elbow be addressed. An investi =
"i ,
gation by Posi-Seal could.not.
develop conclusive results'about
'the effects of elbows on the U flow stream. For this reason L Posi-Seal made estimates:about
~ '
effects on'the flow. stream
-through.the bend and added:this to the LOCA-developed torques through a . straight run of pipe.
Posi-Seal's analysis, outlined; in Referenced 1,. indicated that.
the valve actuator would develop
~
-enough torque to close the valve.
After. reviewing the effects'of'a
!' 3 psi pressure differential across the valve, the-LOCA-developed torque was doubled through a-straight run of pipe in accordance-
-with the NRC concern outlined in-Enclosure 4 of Reference 3.
Doubling of this torque'did not
. exceed.the available actuator closing torque th'us indicating-that the valves would close.
- 8. Effects of butterfly valve The effect of the valves' disc ~
disc and shaft orientation and shaft orientations was ad-on valve operation dressed in Reference 1. The analysis, assuming a.9 psi pressure drop across the valves.
-indicated that valve 1HVR*A0V123' be restricted at 65 deg open. To be conservative, all four valves will be restricted to 65 deg open. When restricted to this size opening, and considering the valve disign, flow will tend to close the valve.
- 9. Seismic and stress loading Valves were seismically analyzed and analyzed for stress-conditions developed by a'LOCA in
~
the Reference 1 report. The report, in combination with the Post-Seal seismic report (Reference 2) and SWEC supplemental ~ calculation No. SQE 2005, qualifies the valve for all seismic and dynamic loading conditions. The NAMCO EA-740 Qualification Report No. QTR111 l
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..(Reference 4) and SWEC .
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! supplemental. calculation No.;SQE;
~
,~ '2008 address 'the dynamic loading::
"< -- conditions for thel limit.
= switches. The ASCO HV206-832-6F
,' . solenoids are qualified'for; ,
~
4 (seismic'and dynamic!1oading conditions by Raport. No.:AQR 67368 (Reference 3).and SWEC' supplemental Calculation No. SQE:
12042.
10.' Effects of environmental The environmenta1' qualification conditions on valves (i.e., ; program will qualify the valves .
- radiation temperatures, contain- and.their limit switch and. sole-
' ' ment sprays, etc)- -lnoid attachments to a qualified life. Preliminary analysis in-dicates-that each valve assembly 1 -;
(including attachments)-is qualified for a maximum of 1.76 years. This analysis indicates that the solenoids must be changed every 1.76 years. , Valves.
1HVR*A0V165 and 166.have a=
qualified life-of 17.9 years'and.
valves 1HVR*A0V123'and 128 a-qualified life of 26.9 years.
- 11. Seal integrity after closure Valves were pressure leak-tested
- of valves, including .by the vendor-to a minimum of environmental effects 75.psig using the halogen diode detector method outlined in-accordance with ASM Section V, Article 10. Paragraph-T-1040.. '
During plant operation. the
, ' valves will be subject .to the integrated leak rate test in accordance with 10CTR50, Appen .
dix J. At least once every 92 days, the seals will be tested to demonstrate their integrity in accordance with Technical Specifications Section 4.6.1.8.2.
The seals were evaluated under the environmental mechanical equipment qualification program,.
resulting in 40-year qualified ,
i life.
- 12. Debris screens Debris screens have been instal-i led in accordance with NRC requests in Branch Technical Position CSB 6-4 (see FSAR 7, Section 9.4.6.2.5).
1 n
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13.TScope of operational andileak. . Valves have.been.hydrostatically eJ tests. performed on valves. . tested by the seller for adher-L,, -
ence to requirements of Paragraph' y
NC 6000, Code' Class 2 ASME III.
The valves have been' leak tested to requirements outlined in. Item jf- 11 of this table.-
The valv'es have been cycled by..
the seller to indicate that they' open against a maximum differential pressure of 15 psi.'
^
Valve 1HVR*A0V128 has been' tested for operability with a' simulated static load.of 3.0 g placed on-the. valve. The test was outlined .
in the Posi-Seal Static Operability Report (Reference'5),
. qualifying valves 1HVR*A0V123, 128, 165, and 166..
.During plant operation,-the valves seals-will be demonstrated operable every 92 days in
. accordance with Technical Specification Section 4.6.1.8.2.~
In accordance with Reference 1 ,.
hydrodynamic testing was.
performed by Posi-Seal on valves-
.up to 14 inches. The
' hydrodynamic testing, in
t ' combination with the analysis outlined'in Reference 1,
+
developed aerodynamic torque coefficients for the subject valves. The results of this combination of testing and analysis was applied to RBS's design conditions to verify.that valves 1HVR*A0V123, 128, 165, and i 166 will isolate the containment during the postulated LOCA.
~
i t . _ .-. _ _ . . _ _ _ . . _ _ _ _ _ _ _ _ . - - _ _ . _ . _ _ - _ - - _ - . .
7 h
ry .
F- - References
- 1. Posi-Seal International, Inc., Seismic and LOCA. Report No.
g 10837SL-001 (SWEC-File No. 4228.241-092-016)
- 2. Posi-Seal-Seismic Report _(SWEC-File No.- 4228.241-092-004)
- 3. ASCO Qualification Report No. AQR67368 (SWEC File No.
6228.241-092-010B).
J
, 4. NAMCO Qualification Report for EA740' Limit Switches No.-QTR111 (SWEC
-File No. 6228.241-092-008)
~
. 5. Posi-Seal Static Operability Qualification Report No. 10837ST-001
'(SWEC File No. 4228.241-092-011) >
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Attachment 3 SUPPLEMENTAL TECHNICAL JUSTIFICATION
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1 4
-Estimate of' Required Torque for g Closure of Posi-Seal Actuators
. With a 3 psi. Differential Pressure
- 1. Assumptions:-
i a .' Bearing, packing end' seal torques will remain the same as
' calculated-for the 9 psi pressure differential b.- Compressibility. effects at 'dP of 3 psi ~are smail:
ac . LNonsyme'tric approach flow due to bends and elbows will double the flow torque (reference a).
- 2. Method:
. Torque due to flow is a function of valve construction, disk
. angle.. fluid density and velocity-and Mach number for compressible.
~
flow. Considering a dP. of 3 psi the compressibility effects will be small thus flow torque will be a function of density and velocity for the same disk angle. Assuming the densities are approximately the same for the 9 psid and'3 psid conditions, then torque is proportional to velocity squared which in turn is proportional to
. the pressure drop access the duct. For conservatism, the flow torque at 3 psid will be multiplied by 2 to account for'non-symetric flow approach and the seal torque which occurs at the no flow condition will be added to the bearing, packing and flow torques for calculating required actuator torque for closure.-
From Appendix B of reference b (values in IN-LBf) s Valve Flow torque Bearing Packing; Seal . LTorque Required 9 paid 3 paid torque torque torque for closure at 3 paid A0V 123 3548 2400 1766 1663 10,452 16,281 A0V 128 3419 2300 1766 1663 10,452 16,181 A0V 165 3415- 2300 1766 1663 17,420 23,149 A0V 166 3415 2300 1766 1663 17,420 23,149
Reference:
a) Attachment #4 to NRC letter 12/21/82 b) Posi-Seal Report 10837SL-001
^,
Attachment 4 PURGE VALVE QUALIFICATION REPORT 4
!