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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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9ENTERGY l"'feTJ"J" "*' '""
PO Box 220 i
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l January 18,1994 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 i
Subject:
Response to NRC Notices of Violation IR 93-27
Reference:
River Bend Station - Unit 1/ Docket 50-458/93-27
( File Nos.: G9.5, G15.4.1 RBG-39921 Gentlemen:
Pursuant 10CFR2.201, please find attached Entergy Operation's respons to notices of violation described in NRC inspection Report (IR) 93-27. The inspection was performed by Mr. Ward Smith and other Region IV inspection personnel during September 25 through November 6,1993, of activities authorized by NRC Operating License NPF-47 for River Bend Station - Unit 1 (RBS).
Should you have any questions, please contact Mr. D. N. Lorfing at (504) 381-4157.
Sincerely, gmw %
James J. Fisicato Manager, SA&QV 4
)
JJF/jr enclosures cc: U. S. Nuclear Regulatory Commission, Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Resident inspector
- P. O. Box 1051 St. Francisville, LA 70775 1
0en,-.
9401310155 940118-PDR ADOCK 05000458 f ,
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9 ATTACHMENT 1 REPLY TO NOTICE OF VIOLATION 50-458/9327-02 BEFERE E F, Notice of Violation - Letter from A. B. Beach to John R. McGaha dated December 17,1993 YLQLA_TIOR Failure to Condufet Post Maintenan_co Testirig 10 CFR Part 50, Appendix B, Criterion XI, " Test Control," states, in part, that a test program shall be established to assure that all e ting required to demonstrate the structures, systems, and components will perform satisfactorily if service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design document.
Contrary to the above, on October 27,1993, the licenseo performed maintenance on the power supply breaker for Residual Heat Removal (RHR) B shutdown cooling suction Valve 1E12*F006B by adjusting the instantaneous overcurrent trip setting under Maintenance Work Order R172573; however, no post maintenance test was specified to verify and document that the breaker would trip within design tolerances.
REASON FOR THE VIOLATION On 10/27/93 at approximately 1600, Operations was attempting to open valvo 1E12*MOVF0068, (RHR "B" shutdown cooling suction valve) per Surveillance Test Procedure (STP)-204-6304 " Loop B RHR Valve Operability Test" when the supply breaker (1EHS*MCC2FF BRK 3A) tripped. Maintenance Work Order (MWO) R172573 was issued by Operations to investigate and repair or rework the valve as required.
When an MWO package is generated for troubleshocting a condition or problem, the maintenance planner incorporates the applicable documents and procedures into the work package. involved in this process are the post maintenance test requirements which are the specific test procedures performed as required by Operations, Maintenance, System Engineering and other groups such as the motre operated valva (MOV), in-service test (IST) and local leak rate test (LLRT) groupt When planning is completed, the MWO package is routed to the applicable departments for their review. Each department reviews their specific section of
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i the MWO package for accuracy, completeness, and determination of proper rotest requirements.
The work package for the residual heat removal 'B' shutdown cooling suction valve 1E12*F0068 provided the instructions to the technicians to adjust the trip coil setting por Drawing BE200A. The drawing allows for an increase of the trip coil setting to prevent " Nuisance" breaker trips and does not require a retest of the coil for adjustments made within the specifications listed. The reason for the ,
violation is past maintenance practice did not require a retest as long as the adjustment was within the set specifications. This was a failure to recognize the need for a retest in the job plan for an adjustment of the setting. ;
Retests included in the MWO package addressed operability of the valve via the in-service test (IST) STP and Corrective Maintenance Procedure (CMP) 1253, "Limitorque Motor Operated Valves" which requires a stroke and time test. The package contained a retest for the replacement of the trip coils which would have tested them por Preventive Maintenance Procedure (PMP)-1020 had the coils been ,
replaced. No rotest was specified nor performed for an adjustment of a trip coil within the allowable range set forth in Drawing BE200A.
In order to address the NRC's concern expressed in the transmittal letter of IR 93- '
27 on the corrective action taken in response to a similar event which took place February 24,1993 (see response to Notice of Violation IR 9305-01 dated June 16,1993), a comparison of the two events was made. The 9305-01 event deals with the failure to perform the proper rotest after the replacement of solenoid operated valve (SOV) lAS*SOV36A. The MWO listed STP-122-6301 " Instrument ;
Air Valvo Operability Test" as the retest for the SOV. This was determined using the maintenance planning guide and the in-service inspection (ISI) pump and valve index. The STP contained both a stroke time test and a local stroke verification.
.The system engineer, during his review for IST applicability, determined that only a stroke time test was required for retest. Thus, retest requirements were changed from those specified in the plan.
This violation (9327-02) deals with the failure to specify retest requirements for an adjustment of a trip coil on an RHR breaker. Past practices had been not to perform a retest as long as the adjustments performed were within predetermined specifications. This past practice resulted in personnel failure to recognize a need for a retest.
In summary, in 9305-01, STP-122-6301 was originally listed in the job plan but was later incorrectly Jeleted by the systems engineer when he determined a stroke test only was required. In the 9327-02 event, an adequate retest (PMP-1020) for trip coil adjustment was not specified. The corrective action for violation 9305-01 was to review any procedures that supplied rotest instructions that could be '
applied as post maintenance retests and list those rotests in maintenance planning.-
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The corrective action for NOV 9305-01 would not have prevented the omission of a retest that occurred in Violation 9327-02, although both violations address the failure to perform an adequate retest.
CORRECTIVE STEPS THAT HAVE BEEN TAKEN AND THE RESULTS ACHIEVED A successful retest was performed on 1E12*MOVF006B (RHR "B" shutdown cooling suction valve) using PMP-1020 after the retest requirement was identified.
This retest was accomplished during the performance of MWO R155357 which was written to perform additional maintenance checks for determining the cause of the breaker trip.
The maintenance planning supervisor, during the regular planning staff meeting, instructed the electrical planners to ensure the use of PMP-1020 for retest on any breaker work which involved the changing of a trip coil setting.
. CORRECTIVE STEPS THAT WILL BE TAKEN TO AVOID FURTHER VIOLA.T_ IONS A review of the maintenance retest program is being conducted comparing it to INPO good practices, NMAC guidelines, and processes in use at other nuclear plants. This review will be completed by February 18,1994. Once this review is complete, River Bend will incorporate the necessary changes into the retest program. Changes will be incorporated by April 15,1994.
CMP-1026 " Corrective Maintenance of MCC Starters and Circuit Breakers" will be revised to list the proper retest within the body of the procedure instead of using PMP-1020 " Preventive Maintenance of Thermal Overload Relays, Unitized and Molded Case Circuit Breakers". The procedure revision will be completed by '
February 28,1994.
A document change notice (DCN) will be issued to add a statement to Drawing BE200A specifying that after adjusting the trip coil, the breaker shall be tested to '
verify performance as specified. The DCN will be issued by January 24,1994.
An evaluation will be performed to determine impact on other breakers which have ')
, been adjusted and not rotested. Should any additional action be required, a supplement to this report will be provided. The evaluation will be completed by February 28,1994. I DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED.
Full compliance was achieved upon rotest of the RHR valve. Additional actions will be completed as listed above.
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ATTACHMENT 2 REPLY TO NOTICE OF VIOLATION 50-458/9327-03 LEVELIV REFERENCE Notice of Violation - Letter from A.B. Beach to J.R. McGaha dated 12/17/93 ,
VIOLATION Technical Specification 6.8.1.d requires, in part, that written procedures shall be implemented covering surveillance and test activities of safety-related equipment.
Licensee Administrative Procedure ADM-0015, Station Surveillance Test Program, Section 8.1, Revision 14, requires surveillance test procedure steps to be performed in sequential order unless specifically stated otherwise in the surveillance test procedure.
Contrary to the above, the following are two examples of where procedures were not followed in the prescribed sequential order.
Examole 1 :
On October 20,1993, during surveillance testing in accordance with Surveillance Test Procedure STP-309-0203, " Division ill Diesel Generator Operability Test," ,
Revision 9A, the operator skipped from Step 7.3.2.13 to Step 7.3.7 without first completing Steps 7.3.2.14 through 7.3.6.5.
g_xample R On October 27,1993, during surveillance testing of the Division ll low pressure '
core spray line fill pump in accordance with Surveillance Test Procedure STP-204- -
6302, " Division ll LPCI (RHR) Pump and Valve Operability Test," Revision 4, the i operator went out of sequence while placing test gauges into service, failing to properly check an equalizer valve open and to properly elevate the differential pressure gauge as required by Section 7.5 of the procedure.
[N RESPONSE TO EXAMPLE 1: -
i fLEASON FOR THE VIOLATION A procedural non-compliance occurred in the performance of Surveillance Test Procedure (STP)-309-0203. The diesel had been placed into maintenance mode at Step 7.3.5.12 to perform prestart filter inspection and remained in maintenance mode until Step 7.3.7.6 at the completion of the barring evolution. Steps 7.3.5.14 and 7.3.7.1 were not performed in order to maintain the diesel in
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' maintenance mode for both evolutions, instead of performing them independently as prescribed by the STP. Total time in maintenance mode was 17 minutes (1420 until 1437) as documented in the short term LCO log and main control room log.
STP-309-0203, Rev 9A was approved on 01/27/93. This revision required the placement of the diesel into maintenance mode on two separate occasions in the i diesel prestart preparation section of the procedure. These steps were not performed "as written" in accordance with ADM-0015, " Station Surveillance Test Program," Section 8.0. '
The operator performing these steps believed he had the option to modify the ;
sequence of prerequisite steps in an STP. These steps were in the body of the '
procedure, entitled "Prestart Preparation"; therefore, both assumptions were incorrect. In addition, the operator failed to discuss this decision with the on-duty -
shift supervisor (SS) or control operating foreman (COF). Upon completion of the ;
STP, the operator discovered while transferring initials from a field copy of the STP +
he could not sign off the omitted steps. At this point, he questioned his previous !
decision and brought it to the attention of the SS/COF.
1 The steps omitted did not impact the STP acceptance criteria or Division 111 diesel operability. '
Root cause of this violation was attributed to poor work practice. Contributing i factors included training deficiencies related to operator's knowledge of ADM- ,
0015 requirements and format deficiencies in STP-309-0203 requiring maintenance mode to be entered twice during prestart preparation.
CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVED I Condition Report 93-0632 was generated by the operator to address the procedural non-compliance. I i
STP.309-0203 has been revised to provide better " Human Factoring." The j prestart checks, requiring the mode switch to be placed in the maintenance mode, :
are now accomplished within a single mode switch change. j An OSP-0018, " Operations Accountability Review," meeting was conducted to determine corrective actions needed to prevent recurrence.
Disciplinary action was administered by Operations management.
A training request form (93-052) was completed by Operations and submitted to the Training Department to provide training on CR 93-0632 and the applicable
_ requirements of ADM-0015, " Station Surveillance Test Program," to the current requalification training module. Training was completed on January 03,1994.
CORRECTIVE STEPS WHICH WILL BE TAKEN TO AVOID FURTHER FINDINGS All corrective steps to avoid further findings have benn completed as described above.
DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance has been achieved.
IN RESPONSE TO EXAMPLE 2:
[LEASON FOR THE VIOLATION During the performance of STP-204-6302, Rev. 4C, the STP performer failed to close the manifold equalizing valve as required in the note prior to Step 7.5.11, causing incorrect data to be entered. Original data taken with the manifold equalizing valve open was 7.0" H2 0. When this procedure violation was brought to the performer's attention, the STP performer re-performed the step correctly, obtained a reading of 21" H2 O and corrected the data to read 21" H2 0.
The note prior to Step 7.5.11 in STP-204-6302, Rev. 4C stated:
NOTE 4-way Instrument Manifold valve should have equalizing valve in the full closed position prior to taking measurements.
The performer failed to read the note preceding Step 7.5.11. The original reading recorded appeared to be too low to the performer. The performer investigated and found the equalizing valve to be open. He closed the valve and corrected the previous entry. The correction was accomplished prior to moving on to the next stop.
Step 7.5.3 requires the performer to open the equalizing valve when installing the test gauge. No other step requires the performer to close the equalizing valve.
The use of a note to ensure that the valve is closed is unsatisfactory and not in accordance with Operations Station Procedure OSP-0005, " Operations Procedure Review and Revision," and ADM-0003, " Development, Control and Use of Procedures."
OSP-0005, Attachment 5, "STP Procedure Review Checklist," provides the following guidelines:
Item 10 - Are NOTES, CAUTIONS and WARNINGS free of action steps?
River Bond Nuclear Procedure (RBNP)-0001, Attachment 6, " Procedure Review Checklist", provides the following guidelines:
Items 11,12 - Are NOTES, CAUTIONS and WARNINGS free of action ;
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The failure to set the test rig at the proper elevation was due to the performer's lack of experience and attention to detail. The procedure directed where the test gauge should be locateJ, but the performer failed to road the step carefully, thus causing confusion on gauge location. Operator inexperience contributed to the cause of this event.
The instrument test kit did not specify what hoses were to be used with each instrument. The two hoses used with the differential pressure (d/p) instrument were too short to fulfill the installation height requirement (i.e., install test instrument at same height as permanent instrument). The performer was
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attempting to compensate for this by trying the instrument in different positions.
After trying several different heights and positions, the performer determined that the height requirement was not applicable for this type of instrument. During this process the performer had made several entries with different readings on this I step. The correct reading was finally entered prior to moving on to the next step.
The procedure was inadequate in that it did not provide specific instructions on test rig installation, venting and valve alignm'ent required to obtain correct data.
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.l The root causes for this incident are: '
- 1. Installed plant gauges are not calibrated. The performer has to connect j temporary calibrated test instruments instead of using the installed ;
instruments. The installed instruments are not kept calibrated and their 1 instrument ranges are not acceptable for IST testing. I
- 2. No formal training is conducted for the IST/ OPS test group on installing test instruments and breaching contaminated systems.
- 3. Procedures are inadequate. Test procedures do not provide sufficient detail for a first time user to perform correctly. Test performers rely on basic
" Tool-box skills" during gauge installation and removal.
C_OjlRE_CTIVE STEPS THAT HAVli BEEN TAKEN AND RESULTS ACHIEVED l
Although System Engineering and Operations walk down IST/STPs prior to performing the test, there has been a lack of consistency in the methods used in the walkdown. To correct this inconsistency, a checklist has been developed to 1 guide future IST/STP procedure walkdowns. The checklist requires the individual i to answer many questions, one of which concerns whether there is sufficient detail to allow efficient performance of the procedure. Also:
- 1. STP-204-6302, " Division ll LPCI (RHR) Pump and Valve Operability Test",
has been revised to incorporate the findings of the violation event:
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a) Detailed instructions have been provided on installation, venting and valve manipulations of the test equipment.
b) The calculations required in performance of Section 7.5 have been arranged in succeeding steps.
r c) The note concerning the equalizing valve position has been made into a procedure step with a sign-off.
- 2. Operations has provided a list of gauges that need calibrating to the I&C-Department. This will eliminate approximately 90% of the test instrument installations currently required by the procedures.
- 3. The I&C Department has provided interim awareness training in the form of shop demonstrations to the IST/STP performers on the installation, venting and removal of test instruments.
CORRECTIVE STEPS WHICH WILL BE TAKEN TO AVOID FURTHER VIOLATIONS .
The Training Department has been requested to provide training to IST/STP performers on the proper methods of breaching contaminated systems and installing test instruments. The training will be completed by April 30,1994.
The I&C Department will maintain the list of gauges, provided by Operations, calibrated in support of IST/STP testing. The list will be completed by April 6, 1994.
A modification request will be developed by Engineering and reviewed by the Change Review Board to determine the need for revising instrument range requirements for IST/STP testing. The review will be completed during the first quarter of 1994.
DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance has been achieved. Additional corrective action is scheduled as stated above.
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': l ATTACHMENT 3 REPLY TO NOTICE OF VIOLATION 50-458/9327-04 LEVELIV REFERENCE Notice of Violation - Letter from A.B. Beach to J.R. McGaha dated 12/17/93 VIOLATION Technical Specification 6.8.1.d requires, in part, that written procedures shall be -
implemented covering surveillance and test activities of safety-related equipment.
Contrary to the above, on October 27,1993, Surveillance Test Procedure STP- l 204-6302, " Division 11 LPCI (RHR) Pump and Valve Operability Test," Revision 4, !
was found to be inadequately maintained, in that Step 7.5 did not provide instructions for venting of test gauges, and restoration of independent verification Step 7.5.32 failed to restore Valves 1RHS*V53 and *S4 to the locked condition.
BEASON FOR THE VIOLATION During the performance of STP-204-6302, Rev. 4C, procedure inadequacies were observed. Step 7.5.32 provides incorrect instructions for pressurizing the test differential pressure (d/p) instrumentation which may affect calibration of the test equipment.' The installed plant gauges are not calibrated, therefore the performer has to install temporary calibrated test instruments instead of using the installed equipment. The test procedure was inadequate in that it did not provide sufficient detail to install and properly vent the test rig. The performer relied on basic skills during installation, testing and removal.
Step 7.5.14 and 7.5.15 require suction and discharge pressure to be recorded; however, nineteen steps further into the STP Step 7.5.34 requires a calculation of the difference of these pressures to determine compliance with acceptance criteria. The performer chose to calculate the d/p to be acceptable prior to continuing the test. This was out of sequence with the procedure. Verification of the d/p was not required for the nineteen subsequent steps. The performer compensated for the inadequacies of the procedure in an effort to reduce radiation exposure.
1 Section 4.0, " Required Equipment," does not provide a specific list of equipment, tools and consumables required to satisfactorily complete the testing. The I procedure was deficient in not providing a list of specific equipment to allow testing. The root cause of this deficiency can be attributed to not having a l checklist specifically designed to aid in the procedure walkdown process that !
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would cause the performer to consider the equipment necessary to support test performance.
CORREC_T_IVE STEPS TAKEN AND RESULTS ACHIEVED Management expectations for strict adherence to procedures have been continually reinforced during the last quarter of 1993. The number of procedure changes (162) processed since September 1,1993 provides evidence that the majority of Operations Department employees understand the significance of this '
commitment. In addition, the Operations Department /IST Group is reviewing / revising proceW es to improve the quality of the procedures. As a result, sixty-eight (68) p ocvure revisions have been completed, with 107 change notice revisions completed The management observation program currently in place will aid the Operations Department in identifying those individuals who have not fully accepted their individual responsibility for procedure compliance. OSP-0018, " Operations Accountability Review," meetings will be conducted for those incidents identified and appropriate actions taken accordingly. ;
This event pointed out several areas requiring upgrade and improvement. STP-204-6302, " Division 11 LPCl (RHR) Pump and Valve Operability Test," was revised to incorporate the findings identified by this report. Precise instructions are i provided for installing and venting the test gauges. The locked valves (1RHS*V53 and 54) require verification and initiating of the locked condition. A checklist has been developed specifically to guide the procedure walkdown process that will cause the performer to address all areas of the procedure.
l The calculation of pump d/p and recording of the data is in succeeding procedure steps. Section 4.0, " Required Equipment," has been enhanced to provide a full list i of equipment requirements for performing the test.
Operations has provided a iist of gau;;es for calibation to the I&C Dencrtment.
This will eliminate approximately 90% of the test instrument installations currently l required by the procedures. ;
in the interim until the IST/STP performers have been properly trained, the Instrumentation and Control (l&C) Department is providing shop demonstration training on how to install and remove all temporary calibrated test instruments.
The operators working in the IST/STP program have received this training.
The results of these immediate corrective actions have brought an added awareness to IST/STP testing. Emphasis has been placed on procedures being completo and workable.
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CQBRECTIVEE_EPS WHICH WILL BE TAKEN TO AVOlD FURTHER VIOLATIONS The l&C Department will provide shop demonstration training as required and as requested by Operations on how to install and remove all temporary calibrated test instruments to personnel performing IST tests. The I&C Department will maintain the identified gauges calibrated per MSP-0003, to be completed by April 6,1994.
A modification request will be developed by Systems Engineering ~and reviewed by the Change Review Board to determine the need for revising instrument range requirements for IST/STP testing. The review will be completed during the first quarter of 1994, i The Training Department will provide training to IST/STP performers on the proper methods of breaching contaminated systems and installing test instruments. The training will be completed by April 30,1994.
Testing has boon modified to incorporate a three way valve to permit venting after the test gauge is installed. This item is completed.
DATE WF.EN FULL COMP _LIANQ_E WILL BE A_CHIEVED Full ccmpliance has been achieved. Additional corrective action will be completed as stated above.
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