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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
g O
GULF STATES UTILITIES CODfPANY es POST OFFICE BOX 2951
- BEAUMONT. TEXAS 77704 AREA CODE 713 830 6631 August 3, 1984 RBG-18,521 File Nos. G9.5, G9.33.4 Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulations U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Eisenhut:
River Bend Station - Unit 1 Docket No. 50-458 In a letter dated November 1, 1983 Gulf States Utilities Company (GSU) committed to respond to Generic Letter 83-28, " Required Actions Based on Generic Implications of Salem ATWS Events", Sections 1.1, 1.2, 2.1, 2.2 and 4.5 by August 3, 1984.
Attached please find forty (40) copies of CSU's final response to Sections 1.1, 2.1, 2.2 and 4.5 of Generic Letter 83-28. The response to Section'1.2 is under preparation and will be provided by October 1, 1984. The response to Sections 3.1 and 3.2 will be provided prior to fuel load as previously indicated in the November 1, 1983 letter.
Should you have any questions feel free to contact us.
Sincerely.
J. E. Booker Manager-Engineering, Nuclear Fuels & Licensing River Bend Nuclear Group JEB/LAE/kfH p Attachments
$0SI 8408140421 840803 2 PDR ADOCM 05000458 l gr A PDR t
A UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION STATE OF TEXAS 1 COUNTRY OF_ JEFFERSON I JIn the Matter of I Docket Nos. 50-458 50-459 CULF STATES l'TILITIES COMPANY I (River Bend Station, Units 1 and 2)
AFFIDAVIT J. E. Booker, being duly sworn, states that he is Manager-Engineering, Muclear Fuels, and Licensing! that this position rectiires him to submit documents to the Nuc1 car Regulatory Comiasion in behalf of Gulf States Utilities: that the documents attached hereto are true and correct t'o the best of his knowledge, 'information' and belief.
- d. E. 8: du
~
[J.E. Booker Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 8 day of /5tW , 19 .
(/vbiMu( ? & LbcAA'b
. Notary Public in and for /
Jeffernon County. Texas My Commission Expires J -//-[{
._ i
4 GULF STATES UTILITIES COMPANY ;
RIVER BEND STATION RESPONSE TO GENERIC LETTER 83-28
" REQUIRED ACTIONS BASED ON GENERIC IMPLICATIONS OF i
SALEM NNS EVENTS" AUGUST 3, 1984 l
f TABLE OF CONTENTS Pane No.
r
- 1. Response to Section 1.1 2 POST-TRIP REVIEW (Program Description and Procedure) l
- 2. Response to Section 1.2 7 POST-TRIP REVIEW (Data and Information Capability) ,
- 3. Response to Section 2.1 8 [
EQUIPMENT CLASSIFICATION AND VENDOR TKTERFACE (Reactor Trip Syncem Components)
- 4. Response to Section 2.2 10 EQUIPMENT CLASSTFICATION AND _ VENDOR INTERFACE '
(Programs for All Safety-Related Components)
$. Response to Section 3.1 13 POST-MAINTENANCE TESTING (Reactor Trip System Components) l
- 6. Response to Section 3.2 13 POST MAINTENANCE TESTING (All Other Safety-Related Components)
- 7. Response to Section 4.1 13 REACTOR TRIP SYSTEM RELIABILITY (Vendor-Related Modifications)
- 8. Response to Section 4.2 13 REACTOR TRIP SYSTEM RELIABILITY (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers)
- 9. Response to Section 4.3 13 .
REACTOR TRIP SYSTEM REf,TABILITY, (Automatic Actitation of Shunt Trip -
Attachment for Westinghouse and B&W Plants)
- 10. Response To Section 4.4 13 .e
-BEACIO_R TRIP SYSTEM RELIAHILITY i (Improvements in Maintenance and Test Procedures for B&W Plants)
- 11. Response to Section 4.$ 14 REACTOR __ TRIP SYSTEM fiEttABI!,1TY (System Functional Tasting) o e
Y
y~^
O SECTION 1.1 POST TRIP REVIEW (Program description and procedure)
The program for review and analysis of unscheduled reactor shutdowns at River Bend Station (RBS) is under development.
However, the following information is provided on the planned program and procedures for assuring that unscheduled reactor shutdowns are analyzed and that a determination is made that the plant can be restarted safely.
Item 1.1.1 The basic restart criteria developed by the BWR Owner's Group form the basis for the RBS procedures.
Restart criteria is addressed in three (3) RBS specific procedures: ADM-0022; " Conduct of Operations", A0P-0001; " Reactor Scram", and GOP-0007 "Ecram Recovery". ADM-0022 has been issued; the other two are drafted and in the review cycle. It is anticipated they will be issued by September 1, 1984.
Based upon technical judgment, utilizing approved plant procedures, control room indication and operator knowledge, the Shift Supervisor may make the decisior to recommend restart of the plant. Authorization for restart will be obtained from either the Operations Supervisor, or Plant Manager, depending on plant conditions and the following five criteria:
Criterion A The plant is shown to be in a safe condition.
The determination of the safe condition of the plant is assumed before any other criteria need to be examined. It is necessary to determine that safety limits have not been exceeded and that the issue at hand is one of justifying restart from a stable shutdown condition. If this is the case then the operator may begin an evaluation of the advisability of restart.
Criterion B The cause of the event is either understood or, after a comprehensive investigation, is considered to have been a spurious trip with a reasonably low potential for reoccurrence. In this circumstance, the Operations Supervisor may authorize restart.
The operator has many sources of information available to him which can be used both as a diagnostic tool in evaluating the cause of an unanticipated scram and in the identification of 2
l l
f_
m other-than-expected performance of plant systems and equipment.
The readouts of both safety related and non-safety related
.adicators (including such sources as the sequence of events recorder, alarm typer, trend recorder and process computer) provide a basis upon which technically defensibic actions can be initiated to determine the cause of the event and assure that the cause of the scram no lot.ger exists. See Caution No. 3 of the BWR Emergency Procedure Guidelines (EPG's) (Attachment-1). See also the response to Item 1.1.4.
It is important to understand the cause of an unscheduled trip so that reoccurences can be minimized. However, it is not realistic to ignore the possibility for spurious trips whose cause can not be identified. In the event that the cause of the unscheduled reactor shutdown cannot be determined, the Plant Manager or designated alternate authorizes a restart based on the following conditions:
a) All reasonable actions to determine the cause have been considered.
b) No physical damage was done by the event and a determination has been made that the plant had not operated beyond the boundaries established by approved plant safety and transient analyses.
c) Safety systems have actuated properly.
The discussion of the qualifications and responsibilities of the personnel making the restart recommendation is included in sections 1.1.2 and 1.1.3.
Criterion C The expected on-off automatic operation of plant safety related systems has been verified.
If the operator determines that a particular system should have initiated for a particular event, he need only establish that the systea did indeed initiate and in the proper sequence. A detailed analysis of the actual performance of that system following an unscheduled shutdown is not-a criterion for restart. Such a detailed analysis is accomplished through the normal surveillance testing procedure done at regular intervals. This step is consistent with the philosophy espoused in Caution No. 1 of the NRC approved BWR EPGs.
Since confidence in the accuracy of Control Room readout is provided both by the routine maintenance and surveillance activities associated with Engineered Safety Features, and normally scheduled and performed calibration activities associated 3
i
with such devices, adherence to these efforts mitigates the need to enter into a complete recalibration (i.e., pressure, flow, operating times, etc.) or performance reevaluation of the adequacy of system _ operation.
Criterion D Any need for corrective action has been determined and appropraitely implemented.
Once the cause of the event is determined the operator then needs to determine what, if any corrective action (s) need to be implemented.
If no corrective action has been determined to be necessary, normal restart procedures apply. If corrective action is necessary but is not required to meet Technical Specification requirements, then restart procedures apply and the needed corrective actions are taken following restart. If corrective action is required then it would be necessary to complete the effort before initiation of restart activities. These actions range in effort from a simple recalibration of the device causing the scram to replacement and/or recalibration of major portions of a system. This determination also needs to be based on the Technical Specification associated with startup activities (i.e.,
Technical Specifications allow restart with some devices out-of-service). Before startup activities are commenced, compliance to the Technical Specification must be assured.
Criterion E
~The approval of the Operations Supervisor, Plant Manager or designated alternate has been obtained.
The review of- the reactor trip is performed by the Shift Supervisor. The recommendation to restart is then made by the Shift Supervisor to the Operations Supervisor or Plant Manager.
The recommendation must be approved by the Operations Supervisor,
- Plant Manger or designated alternate in order to authorize restart.
-Item 1~.1.2 The review and analysis of the unscheduled reactor trip will be performed by the Shift Supervisor. Input to.the review process comes from operators or maintenance, Instrumentation & Control and i
other personnel involved in the reactor trip or correct.ve
. actions.
The responsibilities and. authorities of the Shift Supervisor are
- detailed in FSAR Section 13.1.2.2.5 and includes ". . . compliance 4
~
(Nl ' .n
. aug
~
s C
with4 applicable license and regulatory requirements, and the; safety of plant personnel:and equipment". The Shift Supervisor
.also has the responsibility "...to shut down the plant if, in his
' judgment, conditions warrant this action."
.The responsibilities and authorities of the Plant Manager who
, approves the restart.are: included'in FSAR Section 13.1.2.2.1.
-Item.1.1.3 LA position on Regulatory Guide 1.8 " Personnel Selection and
. Training" is presented in RBS FSAR Section 1.8. _ Plant Operations Structure and River Bend Shift Organization are found in FSAR.
figures 13.1-2 and 13.1-5 respectively. Resumes are found in FSAR f,
Appendix 13A.
L .As discussed in FSAR section 13.2.1.1, SRO candidates who will serve in the dual role'SR0/ Shift Technical Advisor (STA) capacity
, ?will have as a minimum, the education and training provided in
.NUREG-0737, " Clarification of TM1 Action Plan Requirements".
~
Present plans make use of Memphis State University's Advanced Technical Principle Program which contains, but.is not limited.to:
-Differential &-Integral Calculus, AdvancedLReactor Physics,.
Material Study, Fracture Mechanics, Corrosion Processes, Computer Technology, Electric Generation and Transmission, Thermodynamics,
- Heat Transfer, Fluid Mechanics,EHuman Behavior and Project Course.
Item 1.1.4
[
~
LAs stated in Item 1.1.1 above -the RBS procedures which will address the sources of information used to conduct the review and
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analysis of an unscheduled reactor trip are under development and will be available for review when completed.
Section 1.2 (scheduled for submittal by October 1, 1984) will
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address plant information sources avullable at RBS for analysis of unscheduled reactor shutdowns. These include the Annunciator / Sequence of Events Recorder for assessing sequence of -
events.during the scram,.as well as analog recorders for assessing.
the time history of analog variables and the functioning of safety-related equipment.
'When the plant computer is available there is additional sequence of events information on the sequence of events log,'and time history and equipment functioning information on the post-trip logs In addition to.all of the above, supplemental plant information is-available through the Emergency Response Information System (ERIE).
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- The information gleaned from the above instrumentation is combined with operator observations during the transient, operatcr knowledge of the plant, post-trip observations of equipment status and-available information from previous surveillance tests and transients in order'to reconstruct the* event accurately.
' Item 1.1.5 As stated in Item 1.1.1 above, the RBS procedures for Post-Trip Review which will address'the methods and criteria for comparing the event information with expected plant behavior are under development and will be available for review when completed.
Item 1.1.6 As stated in Item 1.1.1 above, the RBS procedures for Post-Trip Review which will address the need for independent assessment on an event are under development and will be available for review when' completed. Guidelines on the preservation of physical
. evidence to support independent analysis of the event will also be included in those procedures.
Item 1.1.7 RBS is establishing a systematic method to assess unscheduled reactor-shutdowns. The procedures which address the above items will be available for review as stated above.
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0-O SECTION 1.2 POST-TRIP REVIEW (Data and Information Capability)
GSU will submit the report required by Section 1.2 by October 1, 1984.
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.c SECTION 2.1 EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE
-(Reactor Trip System Components)
Generic Letter 83-28, Section 2.1 requires confirmation that all components whose function is. required to trip the reactor are identified as safety-related on documents, procedures, and information handling systems used in the plant to control safety-related activities. In addition, for the same components, a program to ensure that vendor information is complete, controlled, and current must be established, implemented, and maintained.
The BWR reactor trip system, as described in Section 3.1.2.5 of
-NUREG-1000, differs from the PWR designs. The GE reactor trip system consists of redundant plant process instrumentation that feed one-out-of-two taken twice logic that initiates a reactor trip by de-energizing solenoid operated scram pilot valves which
' vent' air from the scram valve diaphragms and insert the control rods. The components used in this process are contained within
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~several systems'at River Bend Station rather than one system called a reactor trip system. The components which provide the 51 reactor trip function are in the following plant-sytems: -
u, System Description Control Rod Drive Scram Valves, Scram Discharge Volume Water Level Sensors, Backup Scram Valves-Reactor Protection Logic, Power Supplies, Drywell Pressure Sensors, Turbine Sensors.
Neutron Monitcring Nuotron Flux S'ensors, Trips, Bypasses g; . Nuclear' Boiler Reactor Pressure and Level Sensor, Main Steam Line Isolation Valve Sensors-a Process Radiation Main Steam Line Radiation Sensors
. 1 Monitoring-Creation of a new system called the'" Reactor Trip System":with
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1 components from established systems would cause confusion with-exisiting documentation. The specific components that would form al" Reactor TripfSystem"'are not_ separately,1dentified. 'Thus,
- River Bend, Station's response to Section 2.1 is based-on the systems which contain components'that: perform the reactor trip 4 .
. function.
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" Item 2.2.1 describes River Bend Station's equipment. classification
- program for these' systems along with other systems-which contain safety-related components. This program will:ensuru that all,
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components whose function is required to trip the reactor are identified as safety-related.
In response to the vendor interface concern, Gulf States Utilities joined with 55 other utilities and formed an Institute of Nuclear Power Operations (INPO) Nuclear Utility Task Action Committee (NUTAC). This committee has developed and approved an industry-wide Vendor Equipment Technical Information Program (VETIP), which is described in detail in Attachment 2. This program promotes interaction among the major organizations involved in the generation of commercial nuclear power. As illustrated in Figure 1 to the previously mentioned attachment, individual Utilities exchange and disseminate safety related system and component information with vendors, the NRC, INPO and other Utilities. This exchange of information takes place via written notification (i e. , License Event Reports, NRC I&E Bulletins and Information Notices, industry newletters, etc.) as well as industry meetings and day-to-day verbal communications. The purpose of these information exchanges is to share equipment technical information to improve the safety and reliability of nuclear power generating stations. The primary purpose of the VETIP program is to ensure that current information and data will be made available to those personnel responsible for developing and maintaining plant instructions and procedures. These information systems and programs currently exist and are capable of identifying to the industry precursors that could lead to a Salem-type event. It should be noted that the VETIP_is industry-controlled and is mainly a hardware oriented program that does not rely on vendor action, other than the NSSS supplier, to provide information directly to Utilities. Instead, the VETIP provides information developed by industry experience through Significant Event Reports (SERs) and Significant Operating Experience Reports (SOERs) to the equipment vendor for comment before it is circulated to the Utilities concerned.
River Bend Station has an existing vendor equipment information program with General Electric Company (GE). This program consists of two major categories: (a) information regarding safety-related sytems and components; and (b) technical information intended to enhance safety and non-safety related eouipment reliability and improve plant performance. These programs include, but are not limited to:
(a) 10CFR21 Reporting. The General Electric Company has established a reporting system to handle safety concerns that complies with the requirements of 10CFR21.
Urgent Communications. In addition to the 10CFR21 reports, a procedure for handling urgent communications to BWR owner / operators has been established for use in providing fast notification of safety concerns. Theses communications 9
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- are usually in the form of a short letter which provides a brief explanation and advice or precautionary measures to be
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observed to avoid potential operational hazards. As a result i- of their urgent nature, these communications are processed to operating plants by the most effective method, either by telephone or, if transmitted in written form, they will be followed up or preceded by telephone call.
(b) Service Information Letters (SILs). These documents provide recommendations for equipment modification, plant design improvements or changes to procedures to improve plant performance.
Service Advice Letters (SALs). These letters are used to provide notification of product problems and/or service information on a broad range of GE consumer and industrial products. Those SALs that are recognized by the issuing product department as applying to devices used in nuclear plants are specially identified and are flagged for distribution to all nuclear plants.
Turbine-Information Letters (TILs). These documents are issued by GE's Large Steam Turbine Generator Department to -
provide descriptions of product problems / improvements and to recommend modifications that will mitigate problems or improve product performance.
Further description of River Bend Station's vendor interface program is included in Item 2.2.2.
SECTION 2.2 EQUIPMENT CLASSIFICATION-AND VENDOR INTERFACE (Programs for All Safety-Related Components)
Item 2.2.1.
This section describes.GSU's program for ensuring that all components of safety-related systems necessary for accomplishing required safety functions, are identified as safety related on.
documents, procedures,'and information handling systems used in the plant to control safety-related activities.
Item 2.2.1.1-River _ Bend Station's quality classification system, or Q-list, identifies-as safety-related those plant systems, portions of system,tstructures,3and equipment whose' failure or malfunction could cause a release of radioactivity in. excess of those limits
- specified in 10CFR100. . This class (GSU Quality. Class 11) also nincludes equipment:which is vital to a safe shutdown of the-plant-10
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v and to the. removal of decay and sensible heat, or equiment which is necessary to mitigate the consequences of a costulated design basis accident. -All ASME Code Class 1, 2, and 3 items, fabricated and installed under ASME Section III, are classified as safety-
-related.
Item 2.2.1.'2 The River Bend Station Q-list is being developed by Stone and WebsterLEngineerng Corporation, GSU's architect / engineer. The Q-list'was generated from computerized lists of mechanical and electrical equipment, instruments, valves, and piping. The compiled lists are validated against a controlled data base containing valid Piping and Instrument Diagram information, and against design documents. . The process of generating and updating the Q-list is controlled by a Stone and Webster project procedure.
GSU will use a similar procedure to control the Q-list data base.
The Q-list format will include, for each component listed, the marked number (identification number), a description and/or dimension, the electrical overlay code, the purchase order and/or specification number, the vendor name, the storage code, and the
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GSU Quality Class (QC). All components will be classified as-either GSU QC 1, 2, or 3. The scope of components on the Q-list will include all major electrical and mechanical equipment, and all piping,.but will not includ cable, racks, panels, supports (including cable trays, pipe h..tgers, and snubbers), or sub-component items.
Item 2.2.1.3-Activities are defined as safety related in 10CFR50, Appendix B, if they affect the safety-related functions of those systems, structures, and components which prevent or mitigate the consequences of postulated accidents which could cause undue risk to the health and safety of.the public. These activities may include designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, operating, maintaining, repairing, refueling, and modifying.
River Bend Station personnel will'use a project procedure which is-currently under development to determine whether a component is safety-related. All other procedures which control any of the activities listed above, are being revised to assure that the Q-list Utilization procedure is consulted during the course of the activity to determine whether components affected by the activity are safety related.
Item 2.2.1.4 The management controls utilized to verify that the procedures for preparation, validation, and routine utilization of the River Bend 11
l Station Q-list are contained by audits and surveillances in accordance with the GSU Quality Assurance Program.
Item 2.2.1.5 Plant Administrative Procedures require that spare parts are procured to the original specification requirements or that design verification is performed if the new part cannot be supplied to meet the original requirements. The original specifications include qualification testing for expected safety service conditions. GSU procedures will be in place to provide the same assurances when'GSU assumes the procurement function for equipment other than spare parts.
Item 2.2.2 Vendor Interface In response to the positicn stated in Generic Letter 83-28 Section 2.2.2, Gulf States Utilities participated in the development of a vendor equipment technical information program (VETIP) by the INPO Nuclear Utility Task Action Committee (NUTAC) on Generic Letter 83-28, Section 2.2.2. A detailed description of the VETIP is included as Attachment 2.
GSU Administrative Procedurcs have been established to provide a uniform,. systematic method for review of NRC I&E Bulletins and Notices, INPO Significant Event Reports, INP0/NSAC Significant Operating Event Reports, General Electric Service Information Letters, vendor manuals and other documents generated offsite and transmitted to the site. GSU will, prior to commercial operation establish administrative controls to ensure active participation in NPRDS.
Currently, River Bend Station's technical information such ar vendor manuals and drawings, is received, reviewed, approved, and controlled by Stone and Webster Engineering Corporation (SWEC). '
SWEC transmits this information to Gulf States Utilities, River Bend Administrative Support Group, which controls this documentation for use by River Bend Station project personnel and contractors. These functions are controlled by SWEC and GSU project procedures. When GSU assumes the functions presently performed by SWEC, GSU procedures will be in place to control this technical information.
The intent of Generic Letter 83-28, Section 2.2.2 is tc improve the safe operation of nuclear power generating stations by ensuring that utility personnel are provided with complete and curren'. technical information concerning safety-related equipment.
GSU procedures concerning control of technical information along with GSU's participation in VETIP meet this intent.
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S SECTION 3.1 POST-MAINTENANCE TESTING
'(Reactor Trip System Components)
As stated in GSU's November 1, 1983 letter (Booker to Eisenhut, RBG-16285) a response to Section 3.1 of Generic Letter 83-28 will be provided prior to fuel load.
SECTION 3.2 POST-MAINTENANCE TESTING (All other Safety-Related Components)
As stated in GSU's November 1, 1983 letter (Booker to Eisenhut, RBG-16285) a response to Section 3.2 of Generic Letter 83-28 will be provided prior to fuel load.
SECTION 4.1 REACTOR TRIP SYSTEM RELIABILITY (Vendor-Related Modifications Section 4.1 is not applicable to River Bend Station SECTION 4.2 REACTOR TRIP SYSTEM RELIABILITY (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers)
Section 4.2 is not applicable to River Bend Station SECTION 4.3 REACTOR TRIP SYSTEM RELIABILITY (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W plants)
Section 4.3 is not applicable to River Bend Station SECTION 4.4 REACTOR TRIP SYSTEM RELIABILITY (Improvements in Maintenance and Test Procedures for B&W Plants)
Section 4.4 is not applicable to River Bend Station 13
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SECTION 4.5 REACTOR TRIP SYSTEM RELIABILITY (System Functional Testing)
Item 4.5.1 The diverse reactor trip system features of the reactor protection system (RPS) include the normal scram logic and a backup scram logic.
On-line functional testing of the RPS will be performed consistent with RBS Technical Specifications. Channel functional testing is performed on the multiple and diverse reactor transient trip sensors. During the required trip sensor channel tests identified above, each scram contactor which actuates the scram pilot solenoid valves is tested. The simple operation of the scram contactors minimizr.s concerns of wear, and frequent testing assures that any failures are detected early. The scram pilot solenoid valves which are actuated by the scram contactors are all tested regularly. Redundant electrical protection assemblies (EPAs) which protect the scram pilot solenoid valves from low voltage chattering and the associated potential consequence of accelereted wear are also functionally tested. These surveillance testing requirements related to.the scram pilot solenoid valves assure that the probability of undeteced failures of these independently acting solenoid valves is small.
Channel functional tests are performed on-line for the following sensor trips:
a) Reactor Vessel Dome Pressure-High b) Reactor Vessel Water Level-Low c) Reactor Vessel Water Level-High d) Main Steam Line Isolation Valve-Closure e) Main Steam Line Radiation-High f) Drywell Pressure-High g) Turbine Control Valve Fast Closure, Control Oil Pressure-Low h) Turbine Stop Valve-Closure Channel functional tests are also performed for the average power range monitors (APRMs) and intermediate range monitors (IRMs).
It is shown that each of the above plant variables used to initiate a protective function is backed up by a completely different plant varaible as indicated by References 1 and 2. In fact, for the most frequent transients, scram is initiated by three diverse sensors in all but one case. This indicates that adequate redundancy exists in the design to provide protection against multiple independent sensor failures. Also, diversity among sensor types reduces the potential for common mode failures, 14
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failures due to human error, and increases in failure rate due to wearout.
Each sensor channel functional test includes full actuation of the assoc lated logic, the two output scram contactors in each channel, and the individual CRD scrap pilot solenoid valves for the associated logic division (both "A" and "B" solenoids are required for scram initiation) .
The most credible failures within the RPS logic will de-energize a set of scram solenoids which causes a half scram (i.e. , one of the two scram solenoids required for scram initiation is de-energized at some or all hydraulic control units). These failures would be
" SAFE" failures that would increase the probability of plant shutdown.
The less credible logic failures which prevent a channel from de-energizing will be detected during channel functional tests in compliance with Technical Specification requirements. The tests described above ensure that an increase in failure rate due to a wearout condition or a common mode failure potential will be detected early and corrective action taken before the failure condition becomes systematic.
Other channel functional tests include testing of the scram discharge volume (SDV) water level-high trip, manual scram trip, and resctor mode switch in the shutdown position every refueling.
The first two trips involve on-line testing and the latter mode switch test can only be conducted during reactor shutdown. The manual scram trip can be tested on-line without creating a scram.
The testing of the SDV water level-high trip is considered adequate based on the current designed redundancy and diversity incorporated into the system. There are two diversity incorporated into the sytem. There are two diverse and redundant sets of level sensors which scram the reactor in the unlikely event of high water level in either SDV. These trips are designed to allow sufficient scram water discharge volume given the scram trip point is reached.
Reference 2 concludes that reactor shutdown can be achieved if at least 50% of the control rods in the checkerboard pattern and 69%
in a random pattern are inserted in the core. The probability of independent failure of enough rods to prevent shutdown is negligible. The most unlikely type of failure would be some common mode mechanism that if undetected over a long period of time could cause unsafe shutdown. RBS Techincal Specification surveillance requirements adequately ensure that a failure mechanism affecting several individual drives which is considered to be very remote would not go undetected. One of the major features that ensures that several drives do not fail at one time 15
I due to wearout or a common mode failure is.the staggered maintenance and overhaul of selected CRDs or hydraulic control units (HCUs) at refueling outages. This ensures a mix of drives Jby age, component lot, maintenance time, servicing personnel, and testing.
The scram insertion time tests include, in addition to drive timing and insertion capability, a test of operability of the HCU scram insert and discharge valves including associated scram pilot solenoid valves. As stated in the previous paragraph, the required testing ensures that a systematic failure mechanism in the HCUs would be detected early enough and corrective action taken before the condition becomes a critical failure preventing
' scram.
In summary, the current reactor protection system on-line surveillance testing requirements, in conjunction with multiple and diverse sensors, assures thct the probability of failure of enough. control rods to prevent reactor shutdown is negligible.
Item 4.5.2 Included in Item 4.5.1 Item 4.5.3~
Gulf States Utilities (GSU) is participating in the BWR Owners -
Group Technical Specification Improvements Committee program.
This program will review existing intervals for on-line functional testing required by Technical Specifications to determine that the intervals are censistent with a'chieving high reactor trip system availability when. accounting for considerations such as:
a) Component failure rates b) Common mode failures rates c) Reduced redundancy during testing d) Human error rates during testing e) Component "wearout" rates caused by testing GSU will then utilize the results for specific application to RBS Unit 1.
The schedule for the above generic approach is currently being prepared by the Technical Specification Improvements Committee of the BWR Owners Group.
REFERENCES
- 1. NEDO-1-189,_"An Analysis of Functional Common-Mode Failures in GE BWR Protection and Control. Instrumentation," L. G.
Frederick, et. al., July 1970, 16
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'2. "BWR Scram System Reliability' Analysis," W. P. Sullivan, et.
al., September 30, 19876 (Transmitted'in letter from E. A.
Hughes (GE) to D. F. .Ross (NRC), " General Electric Company.
' A'NS Reliability Report," September 30, 1976).
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Attachment 1 %
OPERATOR PRECAUTIONS GENERAL This section lists " Cautions" which are generally applicable at all times.
CAUTION #1 Monitor the general state of the plant. If an entry condition for a
[ procedure developed from the Emergency Procedure Guidelines] occurs, enter that procedure. When it is determined that an emergency no longer exists, enter [ normal operating procedure].
CAUTION #2 Monitor RPV water level and pressure and primary containment temperatures and pressure from multiple indications.
4 CAUTION #3 If a safety function initiates automatically, assume a true initiating event has occurred unless otherwise confirmed by at least two independent indications.
CAUTION #4 Whenever RHR is in the LPCI mode, inject through the heat exchangers as soon as possible.
(I-5) Rev. 3 i-e y -m . .-- - ,-ry.4 - ,, ,- .