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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7681999-10-19019 October 1999
Forwards Insp Rept 50-458/99-12 on 990822-1002.Four Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy
RBG-45125, Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams1999-10-18018 October 1999
Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams
ML20217J3751999-10-15015 October 1999
Informs That Applicable Portions of NEDC-32778P, Safety Analysis Rept for River Bend 5% Power Uprate, Marked as Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b)
IR 05000458/19990071999-10-0505 October 1999
Refers to Util Ltr Re Apparent Violations Described in Insp Rept 50-458/99-07 Issued on 990804 & Forwards Nov.Insp Described Two Apparent Violations Related to River Bend Station Division I EDG
RBG-45123, Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required1999-09-30030 September 1999
Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required
RBG-45124, Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl1999-09-24024 September 1999
Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl
RBG-45122, Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-471999-09-23023 September 1999
Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-47
RBG-45113, Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp1999-09-21021 September 1999
Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp
ML20212D8901999-09-16016 September 1999
Discusses 6 Month Review of Plant Midcycle Ppr.Advises of Plans for Future Insp Activities.Forwards Historical Listing of Plant Issues,Referred to as PIM
ML20216F7881999-09-15015 September 1999
Forwards Insp Rept 50-458/99-10 on 990830-990903.No Violations Noted.Insp Covered Licensed Operators Requalification Training Program & Observation of Requalification Activities
05000458/LER-1998-003, Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents1999-09-0909 September 1999
Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents
ML20211Q7721999-09-0909 September 1999
Expresses Appreciation for ,In Response to NRC 990702 Re Denial of Notice of Violation Cited in Concerning Insp Rept 50-458/98-16.Reply Found to Be Responsive to Concerns Raised in NOV
RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted1999-09-0808 September 1999
Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted
ML20211Q3921999-09-0808 September 1999
Forwards Insp Rept 50-458/99-08 on 990711-0821.One Violation Being Treated as Noncited Violation
ML20211Q5541999-09-0808 September 1999
Discusses Meeting Conducted on 990830 in St Francisville,La Re Overall Performance Issues During 990403-0703 Refueling/ Maintenance Outage.Due to Proprietary Nature of Some Subject Matters,Meeting Closed to Public.Attendance List Encl
ML20211P4121999-09-0707 September 1999
Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d)
RBG-45095, Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status1999-09-0707 September 1999
Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status
RBG-45097, Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves1999-08-31031 August 1999
Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves
RBG-45094, Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation1999-08-25025 August 1999
Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation
ML20211E2071999-08-23023 August 1999
Discusses Insp Rept 50-458/99-07 in Which 2 Violations Were Identified & Being Considered for Escalated Enforcement Action.Response Should Be Submitted Under Oath or Affirmation
ML20211C5101999-08-19019 August 1999
Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15
RBG-45093, Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept1999-08-17017 August 1999
Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept
ML20211A9291999-08-17017 August 1999
Forwards Insp Rept 50-458/99-11 on 990719-23.Areas Examined Included Portions of Licensee Physical Security Program. No Violations Noted
ML20210T8881999-08-16016 August 1999
Forwards Replacement Pages 9-18 for Insp Rept 50-458/99-09, Issued on 990730
IR 05000458/19980101999-08-13013 August 1999
Forwards Summary of 990805 Mgt Meeting with Licensee in Arlington,Tx Re Radiological Control Problems Noted in Insp Repts 50-458/98-10 & 50-458/99-04.With Attendance List & Licensee Presentation
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
ML20210U3751999-08-12012 August 1999
Informs That Info Contained in Presentation, River Bend Station Fuel Recovery Project,Dtd 990622, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended
ML20210Q7691999-08-11011 August 1999
Forwards Request for Addl Info Re Licensee River Bend Individual Plant Exam External Events,Under GL 88-20,suppl 4,dtd 910628
ML20210R4591999-08-10010 August 1999
Ack Receipt of Which Transmitted Plant Emergency Plan,Rev 20 Under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required,Based on Determination That Changes Does Not Decrease Effectiveness of EP
ML20210N1641999-08-0404 August 1999
Forwards Insp Rept 50-458/99-07 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy
ML20210K4641999-08-0303 August 1999
Forwards SE Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Power-Operated Gate Valves, Issued on 950817
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
ML20210K1351999-07-30030 July 1999
Forwards Insp Rept 50-458/99-09 on 990510-28 with in-office Insp Until 990701.Three Violations Being Treated as Noncited Violations
ML20210J9691999-07-30030 July 1999
Discusses 990719 Meeting with Util in Arlington,Tx Re Region IV Staff Findings of Root Cause Investigation Into Fuel Cladding Failures That Occurred During Recent Cycle 8 Operation.List of Attendees & Organization Chart Encl
RBG-45072, Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL1999-07-23023 July 1999
Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL
ML20210E9001999-07-23023 July 1999
Informs That as Result of Staff Review of Licensee Responses to GL 92-01,rev 1,Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2
RBG-45073, Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl1999-07-20020 July 1999
Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl
RBG-45071, Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl1999-07-19019 July 1999
Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl
05000458/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 11999-07-15015 July 1999
Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 1
ML20196L0501999-07-0606 July 1999
Informs That NRC Insp Rept 50-458/99-03 Issued on 990519 with Errors in Tracking Numbers Assigned to Seven Noncited Violations & Error Re Actual Location of SRO During Refueling Activities.Revised Pages 2 & 4 Encl
ML20209B6081999-06-30030 June 1999
Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl
ML20196K6851999-06-30030 June 1999
Ack Receipt of & Denial of NOV in Response to Transmitting NOV & Insp Rept 50-458/98-16.Listed Info Documents Results of Review of Response to Violation Re fire-induced Circuit Faults
ML20196K0671999-06-30030 June 1999
Forwards Insp Rept 50-458/99-04 on 990412-16 & 28-29.Five Violations of NRC Requirements Occurred & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy.Meeting Scheduled for 990726
RBG-45048, Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept1999-06-29029 June 1999
Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept
RBG-45047, Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output1999-06-29029 June 1999
Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output
ML20196H5171999-06-21021 June 1999
Requests Withholding of Info Being Presented in Meeting of Entergy,General Electric & NRC Staff.Licensee Requested Meeting with NRC to Present Info on Recent Anomalous Conditions Found During Insp of Fuel Bundles.W/Affidavit
05000458/LER-1999-012, Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form1999-06-21021 June 1999
Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form
RBG-45035, Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld1999-06-21021 June 1999
Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld
ML20196E0601999-06-18018 June 1999
Forwards Insp Rept 50-458/99-05 on 990418-29.Four Violations Identified & Being Treated as Noncited Violations
05000458/LER-1999-011, Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-06-0909 June 1999
Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl
1999-09-09
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARRBG-45125, Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams1999-10-18018 October 1999
Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams
RBG-45123, Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required1999-09-30030 September 1999
Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required
RBG-45124, Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl1999-09-24024 September 1999
Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl
RBG-45122, Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-471999-09-23023 September 1999
Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-47
RBG-45113, Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp1999-09-21021 September 1999
Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp
05000458/LER-1998-003, Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents1999-09-0909 September 1999
Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents
RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted1999-09-0808 September 1999
Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted
RBG-45095, Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status1999-09-0707 September 1999
Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status
ML20211P4121999-09-0707 September 1999
Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d)
RBG-45097, Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves1999-08-31031 August 1999
Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves
RBG-45094, Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation1999-08-25025 August 1999
Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation
ML20211C5101999-08-19019 August 1999
Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15
RBG-45093, Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept1999-08-17017 August 1999
Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept
RBG-45072, Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL1999-07-23023 July 1999
Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL
RBG-45073, Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl1999-07-20020 July 1999
Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl
RBG-45071, Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl1999-07-19019 July 1999
Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl
05000458/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 11999-07-15015 July 1999
Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 1
ML20209B6081999-06-30030 June 1999
Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl
RBG-45047, Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output1999-06-29029 June 1999
Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output
RBG-45048, Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept1999-06-29029 June 1999
Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept
ML20196H5171999-06-21021 June 1999
Requests Withholding of Info Being Presented in Meeting of Entergy,General Electric & NRC Staff.Licensee Requested Meeting with NRC to Present Info on Recent Anomalous Conditions Found During Insp of Fuel Bundles.W/Affidavit
RBG-45035, Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld1999-06-21021 June 1999
Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld
05000458/LER-1999-012, Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form1999-06-21021 June 1999
Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form
05000458/LER-1999-011, Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-06-0909 June 1999
Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl
05000458/LER-1999-010, Forwards LER 99-010-00 for River Bend Station,Unit 1 IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-05-28028 May 1999
Forwards LER 99-010-00 for River Bend Station,Unit 1 IAW 10CFR50.73.Commitments Identified in Rept,Encl
RBG-45021, Informs That Cycle 9 Operation Will Remain within MCPR Safety Limits Approved in Amend 105 to TS Issued by NRC in1999-05-26026 May 1999
Informs That Cycle 9 Operation Will Remain within MCPR Safety Limits Approved in Amend 105 to TS Issued by NRC in
05000458/LER-1999-009, Forwards LER 99-009-00 IAW 10CFR50.73.Commitments Contained in Ltr Are Identified on Commitment Identification Form1999-05-24024 May 1999
Forwards LER 99-009-00 IAW 10CFR50.73.Commitments Contained in Ltr Are Identified on Commitment Identification Form
RBG-45017, Informs NRC of Addition of ASME Boiler & Pressure Vessel Code,Section Xi,Code Case N-496-1 to RBS Inservice Insp Program.Commitment Made by Util,Encl1999-05-14014 May 1999
Informs NRC of Addition of ASME Boiler & Pressure Vessel Code,Section Xi,Code Case N-496-1 to RBS Inservice Insp Program.Commitment Made by Util,Encl
ML20206N1921999-05-10010 May 1999
Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1
05000458/LER-1999-007, Forwards LER 99-007-00 IAW 10CFR50.73.Commitments Identified in LER Are Noted in Attachment 11999-05-10010 May 1999
Forwards LER 99-007-00 IAW 10CFR50.73.Commitments Identified in LER Are Noted in Attachment 1
05000458/LER-1999-006, Forwards LER 99-006-00 Re Unplanned Automatic Standby Svc Water Initiation,Due to Procedure Inadequacy.Commitments Identified in Rept Noted in Attachment 11999-05-0606 May 1999
Forwards LER 99-006-00 Re Unplanned Automatic Standby Svc Water Initiation,Due to Procedure Inadequacy.Commitments Identified in Rept Noted in Attachment 1
05000458/LER-1999-005, Forwards LER 99-005-00 IAW 10CFR50.73(a)(2)(i).Commitments Identified in LER Are Noted in Attachment 11999-05-0303 May 1999
Forwards LER 99-005-00 IAW 10CFR50.73(a)(2)(i).Commitments Identified in LER Are Noted in Attachment 1
RBG-44993, Forwards RBS Annual Individual Monitoring Rept for Jan-Dec 1998,per Requirements of 10CFR20.2206(b).File Info Listed. Without Encl1999-04-30030 April 1999
Forwards RBS Annual Individual Monitoring Rept for Jan-Dec 1998,per Requirements of 10CFR20.2206(b).File Info Listed. Without Encl
RBG-44998, Informs of Missing Documentation Re Examination Results Reported in RBS Owners Activity Report Forms Submitted to NRC on 9802241999-04-30030 April 1999
Informs of Missing Documentation Re Examination Results Reported in RBS Owners Activity Report Forms Submitted to NRC on 980224
ML20206E7811999-04-29029 April 1999
Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested
05000458/LER-1999-003, Forwards LER 99-003-00,per 10CFR50.73.Commitments Identified in Rept Are Noted in Attachment 11999-04-23023 April 1999
Forwards LER 99-003-00,per 10CFR50.73.Commitments Identified in Rept Are Noted in Attachment 1
RBG-44968, Submits Addl Info Re 981008 LAR 1998-02 Re Implementation of Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long- Term Solution.Clarifies Certain Aspects of Proposed Ts,Per 990406 Telcon with NRC1999-04-15015 April 1999
Submits Addl Info Re 981008 LAR 1998-02 Re Implementation of Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long- Term Solution.Clarifies Certain Aspects of Proposed Ts,Per 990406 Telcon with NRC
RBG-44965, Responds to 990324 Telcon RAI Re SLMCPR Calculation Method for RBS Cycle 9 Slmcpr,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits. Proposed TS Pages, Encl1999-04-0808 April 1999
Responds to 990324 Telcon RAI Re SLMCPR Calculation Method for RBS Cycle 9 Slmcpr,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits. Proposed TS Pages, Encl
RBG-44959, Withdraws 981120 LAR 1998-20,allowing Adjusting Control Pattern for Plant Startup If Outage Had Occurred Before Planned Refueling Outage.No Plant Outage Was Conducted & Plant Is Now in Eighth Refueling Outage1999-04-0808 April 1999
Withdraws 981120 LAR 1998-20,allowing Adjusting Control Pattern for Plant Startup If Outage Had Occurred Before Planned Refueling Outage.No Plant Outage Was Conducted & Plant Is Now in Eighth Refueling Outage
ML20205F1781999-03-31031 March 1999
Forwards Consolidated Entergy Submittal to Document Primary & Excess Property Damage Insurance Coverage for Nuclear Sites of Entergy Operations,Inc,Per 10CFR50.54(w)(3)
RBG-44939, Forwards Rbs,Unit 1 Annual Occupational Radiation Exposure Rept for 1998, Per TS 5.6.1.Rept Consists of Tabulation of Exposure for Personnel Receiving Exposures Greater than 100 Mrem Per Yr1999-03-31031 March 1999
Forwards Rbs,Unit 1 Annual Occupational Radiation Exposure Rept for 1998, Per TS 5.6.1.Rept Consists of Tabulation of Exposure for Personnel Receiving Exposures Greater than 100 Mrem Per Yr
ML20196K7101999-03-26026 March 1999
Submits Reporting & Recordkeeping for Decommissioning Planning,Per 10CFR50.75(f)(1)
RBG-44899, Provides Notification of Termination of Licensed Operator, AA Rouchon,License OP-42416-1,due to Resignation.Reactor Operator License Data,Listed1999-03-25025 March 1999
Provides Notification of Termination of Licensed Operator, AA Rouchon,License OP-42416-1,due to Resignation.Reactor Operator License Data,Listed
ML20204G8701999-03-15015 March 1999
Responds to NOV Described in NRC Correspondance to Util ,expressing Disappointment in NRC Determination That AD Wells Deliberately Provided Incomplete & Inaccurate Info to NRC During Meeting on 971015
RBG-44925, Responds to NRC Re Violations Noted in Investigation Rept 4-97-059.Corrective Actions: Mgt Expectations for Communicating with NRC Issued to Site Personnel on 980212,by RBS Vice President,Operations1999-03-15015 March 1999
Responds to NRC Re Violations Noted in Investigation Rept 4-97-059.Corrective Actions: Mgt Expectations for Communicating with NRC Issued to Site Personnel on 980212,by RBS Vice President,Operations
RBG-44924, Informs That Util Response to NOV Re Investigation Rept 4-97-059,will Be Issued by 990315,as Extended by NRC Ltr .Encl Check for $55,000 Is for Payment of Civil Penalty IAW Instructions in .Without Check1999-03-0505 March 1999
Informs That Util Response to NOV Re Investigation Rept 4-97-059,will Be Issued by 990315,as Extended by NRC Ltr .Encl Check for $55,000 Is for Payment of Civil Penalty IAW Instructions in .Without Check
RBG-44912, Responds to Violations Noted in Insp Rept 50-458/98-13. Corrective Actions:Matls & Training Were Provided to Expedite Implementation of Existing Procedural Guidance to Supply Compressed Air1999-03-0303 March 1999
Responds to Violations Noted in Insp Rept 50-458/98-13. Corrective Actions:Matls & Training Were Provided to Expedite Implementation of Existing Procedural Guidance to Supply Compressed Air
RBG-44904, Informs NRC of Date Change Re Commitment Made in Response to NOV 50-458/98-05-01.New Commitment Date 9912161999-02-25025 February 1999
Informs NRC of Date Change Re Commitment Made in Response to NOV 50-458/98-05-01.New Commitment Date 991216
RBG-44384, Submits Response to Fuel Cladding Defect Issues Raised in 10CFR2.206 Petition.Clear Technical Basis Exists in Info Provided by River Bend Station to Deny Petition1999-02-11011 February 1999
Submits Response to Fuel Cladding Defect Issues Raised in 10CFR2.206 Petition.Clear Technical Basis Exists in Info Provided by River Bend Station to Deny Petition
ML20203C4201999-01-25025 January 1999
Submits Denial of NRC Request for Advance Info Re Concerns Raised by Ucs in 10CFR2.206 Petitions on River Bend & Perry Plants.Petitioners Were Not Required to Provide NRC with Info in Advance of Informal Public Hearings
1999-09-09
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ld G ULF 23TA TES UTILITIES COnXPANY w e .un s m.a con cur i e m nm wuuxeu 3 <
Mi A (( l( SD4 ( M thli.4 14 M $ 1 October il 1991 RilG 35756 File No. G9.5, G9.33.4 t'
U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:
River Itend Station - Unit 1 Docket Ng. 50-458 This letter provides Gulf States Utilities Company's (GSU) response to Generie Ixtter 9106 " Resolution of Generie issue A 30; Adequacy of Safety-Related DC Power Supplies". The attached detailed outline furnishes the information requested in the generie letter required to resolve this issue for River Iknd Station. Each item is directly followed by the response in a format comparable to that set forth in the generie letter.
If you have any questions or comments, please contact Mr. l.cif I.. Dietrich of my staff at (504) 381-4866.
Sincerely, I ~ ..
gd (ff ,l}I:/>f)
A W.11. Odell Manager - Oversight River Bend Nuclear Group LAE/LLD/WJ3 Attachment j 1 wumny e
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b ec:
U. S. Nuclear Regulatory Conunission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 7&J1!
NRC Resident inspector P.O. Iku 1051 St. Francisville, LA 70775 Mr. D. V. Pickett U.S. Nuclear Regulatory Cornmission 11555 Rockville Pike Rockville, MD 20852
E UNITED STATES OF AMERICA NUCLEAR REGULATORY C0KHIDDION STATE OF LOUISIANh )
FARISH OF WEST FELICIANA )
Docket No. 50-458 In the Matter of )
GULF STATED UTILITIES COMPANY )
(River Dend Station - Unit 1)
AFFIDAVIT W. H. Odell, being duly sworn, staten that he is a Manager-Oversight for Gulf Statoa Utilities Company; that he is authorized on the part of said company to sign and filo with the Nuclear Regulatory Commission the documents attached heroto; and that all such documents are true and correct to the best of his knowledge, information and belief.
if Q /
~
W. 117 Ode fl Subscribed and sworn to beforo me, a Notary Public in and for the Stato and Parish _ above named, this J111 day of 19 4( , My Commission expires wi;th Life.
Dntbbtit. _,
- SMl1A A _ /J2M.;i.d )
Claudia F. Hurst Notary Public in and for West Feliciana Pariog, Ioulaiana i
l l
AITACilhil2iI BESPONHLTD.RENERIC.111TIEIL9h06
- 1. The following informa'. ion is provided for Elver nend statio2LihilLl.
- 2. a. The numb:r of independent redundant divisions of Class IE or safety-related DC power for this plant is Thicc_G. (include any separate Class lE or safety related DC, such as any DC dedicated to the diesel generators).
The systems are: IEN!!'SWGl A Division I lENil'SWGill Division 11 lE22*PNIM)1 Division 111
- b. The number of functional safety r: lated divisions of DC power necessary to attain safe shutdown for this unit is Ont.u).
Safe suutdown can be attained provided that either the Division 1 or Division 11 DC systern is operable. Division 111 alone is not adequate to achieve safe shutdown.
3, Does the control room at this t. nit have the following separate, independently annunciated alarms and indications for each division of DC power?
- a. Alarms
- 1. 11attery disconnect or circuit breaker open? 112i Alarm 0941 "DIV I 125 VDC BAT SPLY 13RKR lENil*ACB561 OPEN" Alarm 0942 "DIV 11125 VDC llAT SPLY llRKR lENB*ACB581 OPEN" l
Alarm 2353 'DIV 111 125 VDC SYSTEM I
'IROUllLE" which alarms the following conditions:
lh11cIy.Epply_httakCLopfJi DC bus ground fault DC bus low voltage (battery discharge) 1
4
- 2. 11attery charger disconnect or circuit breaker open (both mput AC and output DC)? .YJiS Alarm 0939 "DIV i 125 VDC 11US SUPPLY AND DISTR BRKR OC TRIP" Alarm 0940 *DIV 11125 VDC 110S SUPPLY AND DISTR BRKR OC TRIP" Alarm 1062 "DIV i 125 VDC CilGR BRKR lENil'ACll560 OPEN" Alarm 1064 "DIV 11 125 VDC CilGR llRKR lENil'ACB580 OPEN" Alarm 1063 "DIV I 125 VDC llACK UP CilGR IlllKit IENil'ACD563 OPEN" Alarm 1065 "DIV 11125 VDC HACK UP CilGR BRKR 1ENB*ACftS83 OPEN" Alarm 0792 "125 VDC 11A'lTERY CilGR lENil*CifGRI A TROUlit.E" which alarms the following conditions:
AC_innutundcDrlingc DC output high voltage Charger high current Charger high temperature Alann 0798 "125 VDC llATTERY CilGR lENB'CilGRIB TROU13LE" which alarms the following conditions:
/LC.instlundervoltag DC output high voltage Charger high cunent Charger high temperaturc Alarm 2360 "DIV 111 HNITERY CilGR TROUllLE" which alarms the following conditions:
Loss of cingcLAC DC outpuLbreaker tripped _ntgn DC output high voltage i
I L :-
Alarm 0815 "125 VDC BACK UP llATTERY CHGR li1YS'CilGRID TRGU131.E" which alarms the following conditions provided that AC input breaker is closed:
AC_inp.ulleden'ellage DC output high voltage Charger high current Charger high temperature NOIE: An open AC input breaker would show up as an AC input undervoltage or loss of charger AC,
- 3. DC syr. tem ground? YM Alarm 0760 "DIV I 125 VDC IENB*SWG01 A GkOUND PAULT" Alarm 0764 "Div 11 125 VDC lENB*SWG01B GROUND FAUI,T" Alarm 2353 "DIV 111 125 VDC SYSTEM TROUBLE" which alarms the following conditions:
Battery supply breaker open D.C bus gtsmifault DC bus low voltage (battery discharge)
- 4. DC bus undervoltage? HW Alarm 0762 "DIV 1125 VDC IENB*SWGl A UV LOW" Alarm 0763 "DIV I 125 VDC IENB*SWGl A UV LOW-LOW" Alarm 0766 *DIV 11125 VDC lENB*SWGlB UV LOW" Alarm 0767 "DIV 11125 VDC IENB*SWGlB UV LOW-LOW" 3
q l
I 4
Alarm 2353 "Div 111 125 VDC SYSTEM TROUBLE" which alarms the following conditions: l Battery supply breaker open DC bus ground fault DC bus low vohags,fhaRery_diic]Dirac) l
- 5. DC bus overvoltage? XES Alarm 0792 *125 VDC llATTERY CilGR LEND *CilGRIA TROUBLE" whleh alarms the following conditionc:
AC inpJ undervoltage DC output high voltagg Charger high current Charger high temperature Alarm 0798' "125 VDC Battery CifGR lENIPCilGRIB TROUBLE" whleh alarms the following conditions:
AC input undervoltage DC_otttput high voltage Charger high current Charger high temperature Alarm 2360 "DIV Ill BA'lTERY C11GR TROUBLE" which alarms the following conditions:
Loss of charger AC DC output breaker tripped or open .
DC outp.uthigh voltage Alarm 0815 "125 VDC BACK UP BA1TERY CliGR 1BYS*CliGRID TROUBLE" whleh alarms the following conditions provided that AC input breaker is closed:
AC input undervoltage r DC output high voltagg Charger high current Charger high temperature L
l- $
l
l HQIli: Overvoltage can only occur when the charger output voltage is high. The characteristics of batteries preclude its producing a high voltage condition.
6, lhttery charger failure? 1T4 Alarm 0792 *125 VDC llNITERY CilGR lENB*CHORI A TROUBLE" which alarms the following conditions:
AC input undervoltage DC output high voltage Charger high current Charger high temperature Alarm 0798 "125 VDC BNITERY CilGR lENB*CHGRlB TROUBLE" which alarms the fo!!owing conditions:
AC input undervol: age DC output high voltage Charger high current ;
Charger high temperature Alarm 2360 "DIV III BA'ITERY CHOR TROUhLE" which alarms the following conditions:
Loss of charger AC DC output breaker tripIv:d or open
. DC cutput high voltage
- Alarm 0815 "125 VDC BACK UP BATTERY CHGR 1BYS*CHGRID TROUBLE" which alarms the following conditio..s provided that AC input breaker is clexd:
AC input undervoltage DC output high voltage Charger high current Charger high temperaltre
- 7. Battery discharge? HQ*
- See answer to question 5 for explar ation.
o Alarm 0762 "DIV i 125 VDC IENB*SWGI A UV l LOW" L Alarm 0766 "Div 11125 VDC IENB*SWGlB UV LOW" 5
L 1
l
Alarm 0792 "125 VDC RA'lTERY CliGR lENB*CHGRIA TROUBLB" which alarms the following conditions:
AC input undervoltage DC output high voltage ChartrLhltlLclintlit Charger high temperature Alarm 0798 *125 VDC BA'lTERY CilGR lENB*CilGRIB TROUBLE" which alarms the following conditions:
AC input undervoltage DC output high soltage Charger higluatncnl Charger high temperature Alarm 2353 "DIV 111 125 VDC SYSTEM TROUBLB" which alarms the following conditions:
Battery supply breaker open DC bus ground fault D.C bjjijow voltage (ballrIX.di$chalEC) b, Indications
- 1. Battery float charge current? HQ*
- See answer to question 5 for explanation.
Ammeter IENB*A02-A for IENB* BAT 01 A (connected to IENB*SWG01A)
Ammeter lENB*B02-A for IENB'BA'IT)lB (connected to IENB*SWG01B)
No batteries arc directly cot.nected to back up DC switchgear IBYS*SWG01D.
Ammeter lENB*C02 A shows discharge cwrent only.
2, Battery circuit output current? .YES Ammeter IENB*A02 A for lENB* BAT 01 A (connected to iENB*SWG01 A)
- Ammeter lENB*B02-A for J ENB' BAT 01B (connected to IENB*SWG01B)
Ammeter IENB*CO2-A for IE22*S001 BAT (connected to lE22*PNLSOGI) 6
- 3. Battery discharge? XES Ammeter lENB*A02 A for IENB* BAT 01A (connected to IENB*SWG01 A)
Ammeter IENB*B02 A for IENB* BAT 01B (connected to IENB*SWG01B)
Ammeter IENB*CO2-A for lE22*S001 BAT ,
(connected to IE22*PNLS001)
- 4. Bus voltage? .YES Voltmeter IENB*A03-V for IENB* BAT 01 A (connected to lENB*SWG01 A)
Voltmeier IENB'B03-V for IENB* BAT 01B (connected to IENil*SWG01B)
Voltmeter 1ENB*C03 V for IE22*S001 BAT (connected to IE22*PNLS001)
- c. Does the unit have written procedures for response to the above alums and indications? _YES SOP-0049 "125 VDC SYSTEM" ARP-601 16 "P601-16 ALARM RESPONSE" ARP 808 87 "P808-87 ALARM RESPONSE"
- 4. Does this unit have indication of bypassed and inoperable status of circuit breaken or other devices that can be used to disconnect the battery and battery charger from its DC bus and battery charger from its AC power source during maintenance? X13$
Alarm 1062 'DIV I 125 VDC CHGR BRKR lENB*ACB560 OPEN" Alarm 1064 "DIV 11125 VDC CHGR BRKR lENB*ACB580 OPEN" Alarm 1063 "DIV i 125 VDC BACK-UP CilGR BRKR lENB*ACB563 OPEN" Alarm 1065 "DIV 11125 VDC BACK-UP CliGR BRKR lENB*ACB583 OPEN" Alarm 0792 "125 VDC '8AlTERY CHOR lENB*CHGRI A TROUBLE" which alarms the following conditions:
AC_itimtLit'1durllagc DC output high voltage Charger high current Charger high temperatuce 2
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1
}
4 Alarm 0798 "125 VDC BATTERY CilGR 1ENB*CilGRill TROUBLE" which alarms the following conditions:
AC input undmolkgg DC output high voltage Charger high current Charger high temperature Alarm 2360 "DIV III BATTERY CllGR TROUBLE" which alarms the following conditions:
Loss of charger AC DC outout bredetgpInLorceen DC output high voltage Alarm 0815 "125 VDC BACK UP BATTERY CHGR 1BYS*CHGRID TROUBLE" which alarms the following conditions provided that AC input breaker is glay:d:
AC inout undervoltage DC output high voltage Charger high current Charger high temperature Alarm 0941 "DIV I 125 VDC BATTERY SPLY BRKR 1ENB*ACB561 OPEN" Alarm 0942 "DIV 11125 VDC BA1TERY SPLY BRKR lENB*ACB581 OPEN" Alarm 2353 "DIV III 125 VDC SYSTEM TROUBLE" which alarms the following conditions:
Batterv supply breder open DC bus ground fault DC bus low voltage (battery discharge)
MDIf: An open AC. input brcaker would show up as an AC input undervoltage or loss of charger AC. On a loss of power to one of the busses, the " control power available" lights for all equipment controlled from the failed bus will extinguish. Additionally, the associated " system inop" alarms will energire.
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- 5. If the answ:r to any part of Questions 3 or 4 is NO. then provide information justifying the existing design features of the facility's safety reiated DC system.
Question 3.a.7 was answered ILQ because there are no direct alarms which indicate that a battery is dlKharging, The batteries will discharge whenever the DC system load is greater than the charger capacity. This occurs when either the load increases (i.e., during a plant transient) or when the charger capacity decreases (i.e., charger failure).110th of these events will be annunciated uy the
" charger trouble
- alarms. Undervoltage alarms indirectly annunciate a ' battery dishared" condition.
Q1cstion 3.b.1 was answered N0 because ammeter lEN11*C02-A for IE22*S001DAT only indicates battery current in the dishugg direction. The charging current for the IIPCS batteries (as well as for the other batteries) is checked twice a day at the charger under OSP-0012.
Due to the above conditions, the alarms and instrumentation for the safety related battery systems are considered adequate.
- 6. (1) Have you conducted a review of maintenance and testing activities to minimize the potential for human error causing more than one '
DC division to be unavailabic? XM (2) Do plant procedures prohibit rnaintenance or testing on redundant DC divisions at the same time? XM Tech Spec 3/4.8.2
-SOP-0049 "12SVDC SYSTEM"
- 7. Are maintenance, surveillance and testing procedures regarding station hatteries conducted routinely at this plant? Specifically:
- a. At least once per 7 days are the following verified to be within acceptable limits:
l (1) Pilot cell electrolyte level? XM (2) Specific gravity or charging current? XUS (3) Float voltage? XM
'4) Total bus voltage on float charge? XM (5) Physical condition of all cells? XM L
9
Tech Spec 4.8.2.1 (a)
PMP-1030 " STATION 11ATTERY WEEKLY MAINTENANCE" STP 3051100 " BATTERY WEEKLY SURVEILLANCE TEST FOR BATTERY lENil* BAT 01 A" STP-305-Il01 " BATTERY WEEKLY SURVEILLANCE TEST FOR BATTERY lENB' BAT 01B" STP 2031102 " BATTERY WEEKLY SURVEILLANCE TEST FOR BATTERY lE22*S001 BAT"
- b. At least once per 92 days or within 7 days after a battery discharge, overcharge, or if the pilot ecil readings are outside the 7 day surveillance requirements are the following verined to be within acceptable limits:
(1) Electrolyte level of each cell? X13 (2) _ The average specific gravity of each cell? Ils (3) The specine gravity of each cell? XES (4) The average electrolyte temperature of a representative number of cells? X11S (5) The float voltage of each cell? 115 (6) Visually inspect or measure resistance of terminals and connectors (including the connxtors at the DC bus)? .YES Tech Spec 4.8.2.1 (b)
PMP-1031 " STATION BATTERY QUARTERLY SURVEILLANCE TEST" STP-3051300 " BATTERY lENB* BAT 01A QUARTERLY SURVEILLANCE TEST" STP-3051301 " BATTERY lENB' BAT 01B QUARTERLY SURVEILLANCE TEST" STP-2031302 " BATTERY lE22*S001 BAT QUARTERLY SURVEILLANCE TEST"
- c. At least every 18 months are the following verified:
(1) Low resistance of each connection (by test)? XIIS (2) Physical condition of the battely? XIiS (3) Battery charger capability to deliver rated ampere output to the DC bus? XIH (4) The capability of the battery to deliver its design duty cycle to the DC bus? XIiS 10
i
, i The 18 month frequency for this Tech Spec was chosen to coincide with scheduled refueling outages and is considered to be adequate due to the above described conditlens.
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L a
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4 9 (5) Each individuai cell voltage is within acceptable limits during the service test? YES Tech Spec 4.8.2,1 (c) & (d)
PhtP 1034 " STATION BA'ITERY SERVICE DISCllARGII TEST" STP-305-1600 "BA'iTERY LEND *BA11)l A 18 hiONTH INSPECTION" STP-305-1601 "BA'ITERY lENB*BNIIllB 18 htONTli INSPECTION" STP 203-1602 " BATTERY lE22*S001 BAT 18 htONTil INSPECTION" STP-3051603 " BATTERY CilARGER lENB*CilGRi A 18 htONTil LOAD TEST" STP 305-1604 " BATTERY CHARGER lENB*CilGRIB 18 hiONTil i LOAD TEST" STP-305-1605 " BATTERY CHARGER lE22*S001CHGR 18 h10 NTH LOAD TEST" STP 3051606 "IIATTERY IENil* BAT 01 A 18 hiONTH SERVICE DISCif ARGE TEST" STP-3051607 "BA1TERY lENB*ITAT01B 18 MONTli SERVICE DISCHARGE TEST" STP-2031608 " BATTERY 1E22*S001 BAT 18 MONTH FERVICE DISCHARGE TEST"
- d. At least every 60 months, is capacity of each battery vert:ed by perforrnance of a discharge test? lliS Tech Spec 4,8,2,1 (e)
PMP-1033 " STATION BA1TERY PERFORhfANCE DISCIIARGE TEST" STP-3051700 " BATTERY IENB*llATOI A 60 MONTil PERFORMANCli DISCHARGE TEST" .
STP-305-1701 "BNITERY lENB* BAT 01B 60 MONTH PERFORMANCE DISCilARGE TEST" STP-305-1702 " BATTERY lE22*S00lllAT 60 MONTil FERFORMANCE DISCHARGE TEST"
- e. At least annually, is the battery capacity verified by performance discharge test, if the battery shows signs of degradation or has reached 85% of the expected life? HQ* ,
- See answer to question 9 for explanation.
Tech Spec 4,8.2,I (f)
PMP-1033 " STAT!ON BATTERY PERFORMANCE DISCHARGE TEST" STP-3051700 " BATTERY lENB* BAT 01 A 60 MONTli PERFORMANCE DISCilARGE TFST" 11
STP 3051701 "IlNITERY lENil* BAT 0ll! 60 MONTil PERFORMANCE i DISCllARGE TEST" i STP-305-1702 "BA*tTERY lE22*S001 BAT 60 MONTil PERFORMANC11 DISCIIARGE TEST
- 8. Does this plant have operational features such that following loss of one safety-related DC power supply or bus:
1
- a. Capability is maintained for ensuring continued and adequate !
reactor cooling? YES l
- b. Reactor coolant system integrity and isolation capability are maintained? YES The plant is designed to meet single failure and electrical separation criteria per IEEE-308 and IEEE 384. Safe shutdown can be attained provided that either the Division 1 or Division 11 DC system is operable.
1
- 9. If the answer to any part of Questions 6,7, or 8 is MQ, then provide your basis for not performing the maintenance, surveillance and test described and/or tbc bases for not including the operational features cited.
A HQ answer was given for Question 7.c because the River llend Tech Spec surveillance frequency for the condition in question is 18 months, rather than tmnually. Tech Spec 4.8.2.l(f) reads as follows:
"At least once per 18.anenths, during shutdown, performance discharge tests of battery capacity shall be given to any battery that shows signs of degradation or has reached 312E of the service life expected for the application. Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests or is below 90% of the manufacturer's rating" The expected life for batteries IENB' BAT 01 A and IENB* BAT 01B is 20 yars.
Since 85% of the expected life is 17 years and EQMSR 244.521-1 requires replacement of these batteries every 15 years, it is expected that the 85% criteria will never be exceeded. Similarly, battery 1E22*S001 BAT has an expected life of 20 years with a replacement frequency of 13.5 years.
Weekly and quarterly surveillance tests and maintenance procedures are designed to identify battery problems and correct them in a timely manner. Any cells which are identified as unsatisfactory by these tests are replaced in accordance with CMP-1030.
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