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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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_.7 August 4,1994 AUG , 9 U.S. Nuclear Regulatory Commission Document Control Desk M/S PI-37 Washing an, DC. 20555
Subject:
Reply to NRC Notices of Violation and Notice of Deviation IR 94-12 River Bend Station - Unit 1/ Docket No. 50-458 File No.: G9.5, G15.4.1 j RBG-40782 Gentlemen:
Pursuant 10CFR2.201, please find attached Entergy Operation's response to two notices of l violation and one notice of deviation described in NRC Inspection Report (IR) 94-12. The i mspection was performed by Messrs. Ward Smith and Chris Skinner April 24 through June 4, 1994.
In the inspection report, you raised concerns regarding procedure inadequacies, compliance with the radiation protection plan, and implementation of commitments made to the NRC.
River Bend Station (RBS) management understands the significance of the issues that you have identified and, as communicated previously, has initiatives underway which will result l in improvements in these key areas. We are confident that the actions we have l implemented will effectively resolve your concerns.
The focal point of this improvement effort is the long Term Performance Improvement Plan (LTPIP) which will be completed over a three year period. The LTPIP includes initiatives to address the issues identified in your inspection report, in that they include programs to improve the overall quality and effectiveness of site procedures and improve human performance. Although these initiatives will not immediately resolve all issues, the programs that are beginning to address your concerns and improvements have been noted.
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Reply to NRC Notices of Violation )
and a Notice of Deviation IR 94-12 l August 4,1994 j RBG-40782 Page 2 of 2 i i
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Regarding RBS procedure quality, interim procedure improvement initiatives are being ;
developed as a subset of the long term Procedures Upgrade Project (PUP) Plan to provide an immediate focus on improvement of site procedures. 'Ihe interim impmvement j initiatives focus on those procedures most important to continued safe operation and i establish the foundation for implementation of the PUP. Both the PUP and the interim !
procedure improvement initiative will include activities which will verify implementation of l regulatory commitments. l Regarding the failure to comply with the mdiation protection program, Entergy Operations ,
recognizes the importance of radiological work controls and understands the significance of a failure to comply with pmgram requirements. Again, the LTPIP includes initiatives which are expected to result in improvements in this important area. l l
In summary, RBS management shares your concerns about these issues and has taken l
immediate corrective measures and initiated long term actions to ensure resolution. In addition, as described above, we have implemented long term corrective actions that will ' -
- resolve the underlying causes and provide permanent improvement in the areas of procedure i quality and human performance. '
Should you have any questions, please contact Mr. T.W. Gates at (504) 231-4866.
i Sincerely, i
ames J. Fisicaro Director - Nuclear Safety I JJF/jr '-
enclosure xc: U.S. Nuclear Regulatory Commission, Region IV NRC Sr. Resident Inspector
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ATTACHMENT 1 .
l REPLY TO NOTICE OF VIOLATION l l
Note: For the sake of clarity, each of the five examples will be treated separately. l l
VIOLATION 9412-01 MMPLE 1)
Technical Specification 6.8.1.d states, in part, that written procedures shall be established, implemented, and maintained covering surveillance and test activities of safety-related equipment. j Contrary to the above, a procedure was not appropriately maintained in that Surveillance Test hocedure (STP)-256-3302, " Division II Standby Service Water Valve Operability Test,"
Revision 7, contained an ambiguous note, which should have been a procedure step, prior to Step 7.18.1 and the ambiguity resulted in an inadvertent engineered safety feature actuation.
REASON FOR THE VIOLATION Entergy Operations admits this example of the violation and believes that the root cause of the condition was that STP-256-3302 was not appropriately human factored because the procedure used terminology which suggested that the initial conditions for the test required that the Standby Service Water system be in a " standby" alignment when, in fact, the system in question should have been operating in a specific configuration.
Specifically, the Note indicated, in part, that if a certain other STP was not to be performed, then "both divisions of Standby Service Water System shall be lined up for Manual Operation per SOP-0042." Given that a later step of the STP included a requirement to " Start a Division II Standby Service Water Pump (if not already running)," the personnel performing this procedure interpraed the Note to mean that the SSW system should be aligned in a standby :
configuratior, with the pumps secured. In fact, the term " Manual Operation" has a specific :
meaning in the context of System Openting Procedure SOP-0042, " Standby Service Water System." In that procedure %nual Operation" means that the SSW system is isolated from the Normal Service Water sfitem with pumps operating. ,
If an SSW pump had been running at the start of this procedure in accordance with SOP-0042, the ESF actuation would not have occurred.
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CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVED -
STP 256-3302 has been revised to include proper step sequencing and clear operating instructions.
Operating crews have been briefed on this event and the lessons learned. l CORRECTIVE STEPS TO BE TAKEN TO AVOID FURTHER VIOLATIONS No additional specific corrective action is required.
i Regarding RBS procedure quality, interim procedure improvement initiatives are being l developed as a subset of the long term Procedures Upgrade Project (PUP) Plan to provide an i immediate focus an improvement of site procedures. The interim improvement initiatives focus on those procedures most important to continued safe operation and establish the foundation for implementation of the PUP. Both the PUP and the interim procedure improvement initiative will include activities which will verify implementation of regulatory commitments.
DATE WHEN FUII COMPI.TANCE WTII. BE ACHIEVED River Bend Station is in full compliance. However, long term corrective actions are being implemented and will continue to address problems associated with the adequacy of RBS site procedures. These are long term plans and will be completed in accordance with the schedules outlined in the LTPIP.
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'S VIOLATION 9412-01 (EXAMPLE 2)
Technical Specification 6.8.1.d states, in part, that written procedures shall be established, j implemented, and maintained covering surveillance and test activities of safety-related equipment.
Contrary to the above, a procedve was not appropriately maintained in that STP-302-1604, ,
" Division m HPCS Bus Undervoltage 18 Month Channel Calibration," Revision 7, Step l 7.4.6, required lifting a lead from a terminal containing two leads without specifying what to j do with the second lead. Consequently, both leads were lifted and taped together, resulting in l an unexpected Division m bus trip and automatic start of the Division m diesel generator.
REASON FOR VIOLATION Entergy Operations admits this example of the violation and believes that the root cause of the condition was inadequate technical review of a 1986 change to STP-302-1604. It should be noted that the resulting Division m bus trip did not cause an automatic start of the Division m diesel generator because it was in the maintenance mode.
Through Revision 3 of STP-302-1604, the test was performed by lifting lead A30, which was a combination of two wires, one of which was to defeat the trip function ( RSE8 ) and the other was the trip lead from the auxiliary cubicle to the breaker cubicle. This method proved to be inadequate because it would not prevent the tripping of auxiliary cubicle breaker (ACB)-
- 04. As a result, temporary change notice (TCN) 86-1759 was written against Revision 3 of the STP to require that the technicians lift wire 30.
TCN-86-1759, written in November 1986, appears to be inadequate because it does not distinguish between the two wires (Wires 101A12 and RSE8) that are terminated at terminal A30 in ACB-102. Specifically, step 7.6.6 of TCN 86-1759 to Revision 3 of the STP incorporates the requirement that the technician "LiR Wire 30 from terminal block A30 in ACB-102 to prevent tripping ACB-04." This procedural step was incorporated in Revision 4 to the procedure and has existed essentially unchanged since that time.
Herefore, the root cause of the inadequate procedure appears to be inadequate technical review of TCN 86-1759. A contributing factor in this event was inadequate technical review of Revisions 4 through 7 of the STP.
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. CORRECTIVE STEPS TAKEN AND RFRULTS ACHIEVED l
The two wims landed at terminal block A30 in ACB-102 have been assigned specific identifiers.
Change Notice 94-1160 was written to address and correct the inadequacies identified in STP-302-1604.
CORRECTIVE STEPS TO BE TAKEN TO AVOID FURTHER VIOLATIONS <
1 No additional specific cormctive action is required. I 1
1 Regarding RBS procedure quality, interim procedure impmvement initiatives are being developed as a subset of the long term Procedures Upgrade Project (PUP) Plan to provide an immediate focus on improvement of site procedures. The interim improvement initiatives l focus on those pincedures most important to continued safe operation and establish the .,
foundation for implementation of the PUP. Both the PUP and the interim procedure i improvement initiative will include activities which will verify implementation of mgulatory commitments.
DATE WHEN FUT1 COMPI.TANCE WITL BE ACHTEVED River Bend Station is in full compliance. However, long term corrective actions are being implemented and will continue to address problems associated with the adequacy of RBS site procedures. These air long term plans and will be completed in accordance with the schedules outlined in the LTPIP.
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I VIOLATION 9412-01 (EXAMPLE 3) s Technical Specification 6.8.1.d states, in part, that written procedures shall be established, implemented, and maintained covering surveillance and test activities of safety-related equipment.
Contrary to the above, a procedure was not appropriately established in that safety-related, air-operated valve SWP*AOV51B was gagged shut by applying a nitrogen pressure source and no procedural controls were implemented to provide overpressure protection for the valve. As a result, the nitrogen pressure regulator drifted to a pressure of 60 psig, which overpressurized the air operator above the manufacturer's recommended limit of 50 psig.
REASON FOR THE VIOLATIOR Entergy Operations admits this example of the violation and believes that the root cause of the condition was that neither personnel nor procedures recognized the potential for overpressurizing components while the temporary motive gas supply was installed and thus did not specify that measures be taken to prevent overpressurizing the SWP*AOV51B valve .
operator.
Administrative Procedure ADM-0027, " Protective Tagging," includes, at Step 7.2.3, a section entitled " Valve Practices" which provides guidance on the use of air-operated valves for equipment isolation. The procedure indicates that the use of air-operated valves as a clearance boundary should be avoided if possible and provides guidance on precautions to be observed if such a valve must be used as a clearance boundary.
Guidance is included in Step 7.2.3 regarding the use of an air-operated valve that cannot be gagged or blocked in position. Specifically, the step indicates that plant air may be used to maintain the valve in the desired position provided that special precautions are stated in the applicable maintenance work order (MWO) package. These precautions include briefing workers on the risk, establishing communications with the Control Room and tagging the -
supply air header isolation valves open.
Although the existing guidance appears to be appropriate, it assumes that the normal plant air system will be used to supply motive gas to the valve. It does not specifically recognize that temporary motive gas sources can be and are used occasionally to maintain an air-operated valve in the closed position. Since the use of a temporary motive gas supply creates some ,
potential for overpressuriring components, additional precautions are warranted for this condition and should have been included in the work instructions.
l CORRECTIVE STEPS TAKFN AND RFRULTS ACHIEVED )
Immediate steps were taken by Operations to mduce the actuator pressure from 60 psig to 25 psig. ;
Valve ISWP*V3319 was added downstmam of valve ISWP*AOV51B to eliminate the need l for these valves to act as isolation valves. Valve ISWP*V3319 is a manual valve and will l eliminate the need for connecting regulated nitmgen to the actuator of valve ISWP*AOV51B, thereby eliminating any chance for repetition of this specific event. A similar modification was made to the other train.
CORRECTIVE STEPS TO BE TAKEN TO AVOID FURTHER VIOLATIONS i An engineering evaluation concluded that damage to valve ISWP*AOV51B was not likely because of this event. However, to be conservative, MWO Request 201040 was initiated to completely disassemble and inspect valve ISWP*AOV51B and its actuator for any signs of damage. This will be completed by September 28,1994.
Operations will evaluate the processes in place to establish appropriate controls for temporary -
plant conditions. This evaluation will be completed by October 1,1994. Subsequent corrective action will be dependent on the results of this evaluation.
Regarding RBS procedure quality, interim pmcedure improvement initiatives are being developed as a subset of the long term Procedures Upgrade Pmject (PUP) Plan to provide an immediate focus on impmvement of site procedures. The interim improvement initiatives focus on those procedures most important to continued safe operation and establish the foundation for implementation of the PUP. Both the PUP and the interim procedure I
improvement initiative will include activities which will verify implementation of regulatory commitments.
I DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED River Bend Station is in full compliance. However, long term corrective actions are being )
implemented and will continue to address problems associated with the adequacy of RBS site !
procedures. These are long term plans and will be completed in accordance with the schedules j outlined in the LTPIP.
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7 VIOLATION 9412-01 (EXAMPLE 4)
Technical Specification 6.8.1.d states, in part, that written procedums slull be established, implemented, and maintained covering surveillance and test activities of safety-related ,
equipment.
Contrary to the above, a procedure was not maintained in that Surveillance Test Procedure STP-403-0201 did not provide instructions for placing the standby gas treatment system in standby after completion of the surveillance test.
I REASON FOR THE VIOLATION 1 l
Entergy Operations, admits this example of the violation and believes that the root cause of the condition was that, although it was intended to be performed in conjunction with other procedures, STP-403-0201, " Annulus Mixing System Monthly Operating Test," did not include steps which linked it to those procedures. In the absence of such links, STP-403-0201 was not a " stand-alone" document since it did not include certain initiating or restoration steps.
STP-403-0201 is performed concurrently with either STP-257-0201 (A train) or -0202 (B train), " Standby Gas Treatment System Filter Train A(B) Monthly Operability Test." These tests are usually performed concurrently since the annulus is normally used as a source of supply air for the standby gas treatment system (SBGTS) test.
STP-403-0201 should have included all of the necessary procedural steps or, conversely, clear precautions and limitations which specified that the procedure be performed only in conjunction with the SBGTS monthly operating test.
CORRECTIVE STEPS TAKEN AND RFRULTS ACTITEVED STP-403-0201 has been revised to provide the twc-y instruction to ensure that the decay heat removal fan has been started and that the SBGTS is properly placed in standby after completion of the test.
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CORRECTIVE STEPS TO BE TAKEN TO AVOID FURTHER VIOLATIONS I
No additional specific corrective action is required.
Regarding RBS procedure quality, interim procedure improvement initiatives are being developed as a subset of the long term Procedures Upgrade Project (PUP) Plan to provide an immediate focus on improvement of site procedures. The interim improvement initiatives focus on those procedures most important to continued safe operation and establish the foundation for implementation of the PUP. Both the PUP and the interim procedure improvement initiative will include activities which will verify implementation of regulatory commitments.
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'i f DATE WHEN FUIL COMPT.IANCE WILL BE ACHIEVED River Bend Station is in full compliance. However, long term cormctive actions are being implemented and will continue to address problems associated with the adequacy of RBS site procedums. These are long term plans and will be completed in accordance with the schedules outlined in the LTPIP.
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l VIOLATION 9412-01 (EXAMPLE 5) i Technical Specification 6.8.1.d states, in part, that written procedures shall be established, implemented, and maintained covering surveillance and test activities of safety-related equipment.
Contrary to the above, a procedure was not appropriately maintained in that preventive i maintenance pmcedure (PMP)-1001, " Preventive Maintenance of Egar Power Line Conditioners," Revision 5, Step 8.4.5, was not achievable because the installed circuit connguration was not considered when instmetions were provided for insulation resistance testing. As a msult, unsatisfactory results were obtained, requiring a change to the pmcedure.
REASON FOR THE VIOLATION Entergy Operations admits this example of the violation and believes that the mot cause of the condition was inadequate technical review of Revision 5 of PMP-1001. Either the engineer that prepared Revision 5 or the technical reviewer should have identified the deficiencies in the pmcedure revision before the STP was approved.
CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVED PMP-1001 has been revised to correct the identified deficiencies. On May 2.0, the power line conditioners for reactor protective system channels A&B were successfully tested using the revised procedure. ,
CORRECTIVE STEPS TO BE TAKEN TO AVOID FURTHER VIOLATIONS No additional specific corrective action is required. !
Regarding RBS procedure quality, interim procedure improvement initiatives are being developed as a subset of the long term Procedures Upgrade Pmject (PUP) Plan to provide an immediate focus on improvement of site procedures. 'Ihe interim improvement initiatives focus on those procedures most important to continued safe operation and establish the foundation for implementation of the PUP. Both the PUP and the interim procedure t improvement initiative will include activities which will verify implementation of regulatory commitments.
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1 7-DATE WIIFN FUIL COMPLLdLNCE WIII BE ACIHEVED Riser Bend Station is in full compliance. However, long term corrective actions are being implemented and will continue to address problems associated with the adequacy of RBS site procedures. These are long term plans and will be completed in accortlance with the schedules outlined in the LTPIP.
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L A'ITACHMENT 2 REPLY TO NOTICE OF DEVIATION DEVIATION 458/9412-02 During an NRC inspection conducted on April 24 through June 4,1994, a deviation of your Updated Safety Analysis Report was identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Action," 10 CFR Part 2, Appendix C, the deviation is listed below: '
A. Update Safety Analysis Report, Revision 4, Section 9.1.2.3.3 states, " Administrative ;
procedures require periodic sampling of the leak test system on the spent fuel pool liner. Little or no leakage is expected during normal operations."
Contary to the above, from initial licensing on November 20,1985, until May 20,1994, there was no documentation or other evidence to show that periodic sampling of the leak test system on the spent fuel pool liner had been implemented.
REASON FOR THE DEVIATION Entergy Operations admits this deviation and believes that the root cause was personnel error i on the part of the individuals who were responsible for the initial development of certain station operating procedures.
A scarth of the commitment database revealed that tracking item 01017 specified the requirement to sample the leak test system on the spent fuel pool liner to identify any leakage through the liner. Documentation associated with the tracking item further indicated that the commitment was implemented by two River Bend Station procedures: general operating procedure (GOP)-0001, " Plant Startup," and administrative procedure (ADM)-0047, "Ieakage Reduction and Monitoring Program." 'Ihe database indicated that these commitments had been incorporated in these procedures on December 2,1985. However, neither the commitment text, the commitment number, nor the associated FSAR section were referenced by either of the current procedures or an earlier revision.
It appears that this condition was caused initially by an' oversight by the individuals responsible for the initial procedure writing effort since they failed to incorporate the commitment requirements or to reference commitment 01017 in either of the two procedures.
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f A contributing cause was identified in that, despite several revisions to GOP-0001 and ADM-0047, the individuals revising the procedures failed to perform an adequate review of the commitment dataham to ensure that commitments were appropriately implemented. Such a review is required by RBNP-0001.
CORRECTIVE STEPS TAKEN AND RFRULTS ACHIEVED Operations section procedure (OSP)-0029, " Daily Img Report; Reactor Auxiliary, and Fuel Buildings," has been revised to require a leak check of the spent fuel pool liner on a monthly basis. This is an interim measure which is intended to develop a baseline from which to establish an appropriate long-term sampling periodicity.
ADM-0047 has been revised to include a reference to Commitment 01017 and a current description of the leak test methodology and required frequency.
Commitment 01017 has been revised such that it references the correct implementing document.
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_ ORRECTIVE STEPS TO BE TAKEN TO AVOID FURTHFR DEVIATIONS To ensure that no similar conditions exist, both the Procedure Upgrade Program and the interim procedure improvement initiative (extensively discussed in previous correspondence) will include activities that will verify implementation of regulatory commitments. As elements of the LTPIP, these activities will be completed over a three year period.
DATE WHEN FULL COMPr.IANCE WITL BE ACHTEVED River Bend is in full compliance. Additional assurance of full compliance will be gained through the Procedure Upgrade Program and the interim procedure improvement initiative as discussed above.
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.1 ATTACHMENT 3 REPLY TO NOTICE OF VIOLATION
' VIOLATION 458/9412-03 ;
Txhnical Specincation 6.11.1 states, in part, that pmcedures for personnel radiation prttection shall be adhered to for all operations involving personnel radiation exposure.
Riv':r Bend Nuclear Procedure (RBNP)-024, " Radiation Protection Plan," Revision 4, Section 4.9.4, requires radiation workers to adhere to the radiological work permit requirements.
Contrary to the above, on May 11,1994, a contact quality control inspector failed to adhere to the requirements of procedure RBNP-024 in that the inspector logged on radiological work permit 94-7007 and proceeded to enter the radiologically controlled area without reading and understanding the requirements delineated by the permit.
REASON FOR THE VIOLATION Entergy Operations admits this violation and believes that the root cause of the event was personnel error by the contract quality control inspector. The contact inspector was knowledgeable of station requirements for accessing a radiological controlled area (RCA) but -
failed to comply with procedural requirements or management expectations for radiation workers.
On May 11,1994, a contract quality control (QC) inspector logged onto the self-access computer under radiation work permit (RWP) 94-7007, without reading his RWP requirements, and entered the RCA. This action was in direct violation with the radiation protection responsibilities of workers. RBNP-0024, " Radiation Protection Plan," requires workers to comply with the requirements and instructions given in the RWP. 'Ihis requirement is stressed in general employee taining.
During a subsequent interview, the QC inspector indicated that he was aware that logging in on the self-access computer served as an acknowledgment that he had read and understood the ,
RWP requirements. 'Ihe QC laWor had become accustomed to entering the RCA with j other radiation workers and reviewing the applicable RWP at the same time that they did. ;
However, in this instance the inspector logged on to the RWP but did not review it. )
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CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVFB , ,
The contract QC inspector was terminated.
QC inspectors were given trainmg on the importance of reading RWPs before logging onto the self access computer.
A self accessing survey was conducted by quality assurance personnel; all individuals surveyed had read and were generally knowledgeable of their RWPs.
CORRECTIVE STEPS TO BE TAKEN TO AVOID FURTHER VIOLATIONS To emphasize the importance of compliance with radiation protection plan requirements, steps will be taken to reinforce programmatic mquirements and management expectations regarding self-accessing into the RCA. This will be completed by September 30,1994.
DATE WHEN FULL COMPLIANCE WHL BE ACHIEVED River Bend Station is in full compliance.
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