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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:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 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 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 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 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 ML20196E0601999-06-18018 June 1999 Forwards Insp Rept 50-458/99-05 on 990418-29.Four Violations Identified & Being Treated as Noncited Violations ML20195G3121999-06-0909 June 1999 Ack Receipt of Re Changes to River Bend Station Emergency Plan,Rev 19.No Violations of 10CFR50.47(b) Were Identified ML20195G3671999-06-0909 June 1999 Ack Receipt of Ltr Dtd 981016,which Transmitted River Bend Station Emergency Plan,Rev 18 Under Provision of 10CFR50, App E,Section V.No Violations of 10CFR50.54(q) Identified During Review ML20195D6041999-06-0303 June 1999 Discusses EOI Request That Attachment 4,NEDC-32549P, Safety Review for River Bend Station Cycle 7 Final Feedwater Temp Reduction, Rev 0,be Withheld from Public Disclosure. Determined Info Proprietary & Will Be Withheld DD-99-08, Informs That to Extent That Union of Concerned Scientists Requests Commission Undertake Formal Review of DD-99-08 & Hold Meeting to Directly Receive View on Decision,Request Denied.With Certificate of Svc.Served on 9905211999-05-20020 May 1999 Informs That to Extent That Union of Concerned Scientists Requests Commission Undertake Formal Review of DD-99-08 & Hold Meeting to Directly Receive View on Decision,Request Denied.With Certificate of Svc.Served on 990521 ML20206U4321999-05-18018 May 1999 Forwards Notice of Withdrawal of Licensee 961106 Request for Approval of Deviation from Approved Fire Protection Program to Extent Program Incorporated Technical Requirements of Section III.G.2 of App R to 10CFR50 ML20206U6081999-05-18018 May 1999 Forwards Insp Rept 50-458/99-03 on 990307-0417.Eight Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20207A8051999-05-15015 May 1999 Forwards Insp Rept 50-458/99-06 on 990419-23.No Violations Noted.Inservice Insp Activities at River Bend Station Were Being Implemented in Accordance with ASME Code & Regulatory Requirements ML20206N7081999-05-12012 May 1999 Informs That NRC Ofc of NRR Reorganized,Effective 990328. Reorganization Chart Encl ML20206N8811999-05-12012 May 1999 Forwards Notice of Withdrawal of 981120 Amend Request for License NPF-47.Proposed Amend Would Have Established New TS 3.10.9, Control Rod Pattern - Cycle 8, Added to Section 3.10, Special Operations ML20206H9191999-05-0707 May 1999 Informs That on 990407,NRC Administered Generic Fundamentals Exam Section of Written Operators Licensing Exam.Facility Did Not Participate in Exam,However Copy of Master Exam with Key Encl.Without Encl NUREG-1434, Discusses Licensee 960418 Request for Amend for Plant That Would Permit Addl Method of Fuel Movement & Loading in Core Upon Removal of Control Rods from Defueled Core Cells.Nei TSs Task Force Process Will Be Used to Review TSTF-2261999-05-0505 May 1999 Discusses Licensee 960418 Request for Amend for Plant That Would Permit Addl Method of Fuel Movement & Loading in Core Upon Removal of Control Rods from Defueled Core Cells.Nei TSs Task Force Process Will Be Used to Review TSTF-226 ML20206J2291999-05-0303 May 1999 Discusses Responding to NOV Issued on 990105.NOV Was Based on NRC Conclusions That Licensee Provided NRC Inspector with Info Licensee Knew Was Inaccurate & Incomplete ML20206E6381999-05-0303 May 1999 Ack Receipt of 990305,990315 & s Responding to NOV & Proposed Imposition of Civil Penalty, .EOI Paid Civil Penalty & Requested Withdrawal of NOV & Civil Penalty for Reasons Stated.Finds NOV & Civil Penalty Appropriate ML20206E4531999-04-27027 April 1999 Discusses Request That Attachment 4, Final Calculation of RBS Cycle 9 SLMCPR (Safety Limit for Mcpr), Submitted with 981216 License Amend Request,Be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20206A2031999-04-21021 April 1999 Discusses EOI Second 10-year IST Program for River Bend Station Submitted on 980106 & 980910 Which Included One Pump Relief Request & Two Valve Relief Requests.Forwards SE Authorizing Pump Relief Request & One Valve Relief Request ML20205N7251999-04-13013 April 1999 Forwards Summary of 990408 Meeting with EOI in Jackson, Mississippi Re EOI Annual Performance Assessment of Facilities & Other Issues of Mutual Interest.List of Meeting Attendees & Licensee Presentation Slides Encl ML20205J5331999-04-0606 April 1999 Ack Receipt of Denying Request from NRC That Addl Info Be Provided Prior to Informal Public Hearing Held on 990222 Re River Bend Station & Perry Nuclear Power Plant 10CFR2.206 Petitions ML20205K0681999-04-0505 April 1999 Submits Summary of 990325 Meeting Re Engineering Performance at Site & Assessment of Organization Strengths & Opportunities for Improvement.List of Attendees & Matl Used in Presentation Enclosed ML20205A4531999-03-26026 March 1999 Forwards Insp Rept 50-458/98-10 on 990222-26.Violation Noted & Being Treated as Non-Cited Violation.Concludes That Radiation Work Permit Program Poorly Implemented Until July 1998 Because of Inadequate Program Implementing Procedures ML20205D7691999-03-26026 March 1999 Forwards Insp Rept 50-458/99-02 on 990124-0306.One Violation Identified & Being Treated as non-cited Violation.Licensee Conduct of Activities During Insp Generally Characterized by safety-conscious Operations & Sound Engineering ML20205D5361999-03-26026 March 1999 Forwards Ser,Accepting Util 980107 Request for Alternative to Augmented Reactor Pressure Vessel Exam Requirements for Plant,Unit 1 Pursuant to 10CFR50.55a(g)(6)(ii)(A) for First 10-year Insp Interval.Technical Ltr Rept Also Encl ML20204G8081999-03-24024 March 1999 Refers to 990303 Reply to NRC NOV & Proposed Imposition of Civil Penalty .Since Licensee Paid Civil Penalty & C/A Found Responsive to NRC Concerns,Matter Considered Closed ML20205A4021999-03-23023 March 1999 Forwards Insp Rept 50-458/99-301 on 990222-0303.No Violations Noted.Insp Included Evaluation of Three Applicants for Senior Operator Upgrade & for Senior Operator Instant & Eight Applicants for Reactor Operator License ML20205F3131999-03-19019 March 1999 Advises of Planned Insp Effort Resulting from River Bend PPR Review,Which Was Completed on 990211.Performance of River Bend Staff During Assessment Period Was Acceptable 1999-09-09
[Table view] |
See also: IR 05000458/1998005
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611 RYAN PLAZA DRIVE, SUITE 400
ARLINGTON, TEXAS 76011-8064
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JUN 301998
John R. McGaha, Vice President - Operations
River Bend Station
Entergy Operations, Inc.
P.O. Box 220
St. Francisville, Louisiana 70775
SUBJECT: NRC INSPECTION REPORT 50-458/98-05
Dear Mr. McGaha:
Thank you for your supplemental letter of June 18,1998, in response to our letter and
Notice of Violation dated April 17,1998, concerning deficiencies with the Environmental Design
Criteria of the standby gas treatment system. We will review the implementation of your
corrective actions during a future inspection to determine that full compliance has been achieved
and will be maintained.
.
Thomas P. Gwynn, irecto
Division of Reactor rojec
Docket No.: 50-458
License No.: NPF-47
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Executive Vice President and jf
Chief Operating Officer I i
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Entergy Operations, Inc.
P.O. Box 31995 f
Jackson, Mississippi 39286-1995
Vice President
Operations Support
Entergy Operations, Inc.
P.O. Box 31995
Jackson, Mississippi 39286-1995
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9807070019 990630
PDR ADOCK 05000458
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Entergy Operations, Inc. ' 2-
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l Plant Operations i
River Bend Station
Entergy Operations, Inc.
P.O. Box 220
St. Francisville, Louisiana 70775
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Director- Nuclear Safety
River Bend Station
Entergy Operations, Inc.
l P.O. Box 220
St. Francisville, Louisiana 70775
Wise, Carter, Child & Caraway l
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P.O. Box 651
Jackson, Mississippi 39205
Mark J. Wetterhahn, Esq.
Winston & Strawn
1401 L Street, N.W.
Washington,~ D.C. 20005-3502
Manager- Licensing
River Bend Station
Entergy Operations, Inc.
P.O. Box 220
St. Francisville, Louisiana 70775
' The Honorable Richard P. leyoub
Attorney General
Department of Justice
State of Louisiana -
P.O. Box 94005 -
Baton Rouge, Louisiana 70804-9005
-H. Anne Plettinger
3456 Villa Rose Drive
Baton Rouge, Louisiana 70806
President of West Feliciana
Police Jury
[ P.O. Box 1921
St. Francisville, Louisiana 70775
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Entergy Operations, Inc. -3-
! Wdliam H. Spell, Administrator
L Louisiana Radiation Protection Division
P.O. Box 82135
Baton Rouge, Louisiana 70884 2135
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DOCUMENT NAME: R:\_RB\RB805AK2.GDR
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OFFICIAL RECORD COPY
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June 18,1998
AN 2 2
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U.S. Nuclear Regulatory Commission i
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ATTENTION: Document Control Desk, OP-17 l
Washington, D.C. 20555
Subject: Reply to Notice of Violation in inspection Repoit 50-458/98 05
River Bend Station - Unit i
License No. NPF-47
Docket No. 50-458
File Nos.: G9.5, G15.4.1
RBG-44548
RBF1-98-0167
Ladies and Gentlemen:
Pursuant to the provisions of 10CFR2.201, Entergy Operations, Inc. (EOI) is
submitting as Attachment i to this letter the response to the Notice of Violation
described in NRC Inspection Report (IR) 50-458/98-05. This inspection was
conducted February 22 through April 4,1998.
We value the insights that we have gained from the subject inspection and believe it
has resulted in an increased knowledge of the Standby Gas Treatment System. The
insights and perspectives acquired from interface with the Commission, research and
testing, and modification feasibility evaluations will allow us to further improve our
system's performance. The commitments contained in this document are identified on
Attachment 2. Should you have any questions, please contact Mr. David Lorfing of l
my staff at (504) 381-4157.
Sin trely,
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Reply to Notice of Violation in 50458/98-05
June 18,1998
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RBG 44548
RBF198-0167
Page 2
cc: Regional Administrator
U.S. Nuclear Regulatory Cnmmission
Region IV
611 Ryr : Plaza Drive, Suite 400
Arlington, TX 76011
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NRC Sr. Resident Irispector
P.O. Box 1050
l St. Francisville, LA 70775
David Wigginton
NRR Project Managei
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U.S. Nuclear Regulatory Commission
WS OWFN 13-H-3'
Washington, D9 20555
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Reply to Notice of Violation in S0-458/98-05
June 18,1998
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RBF198-0167
Page 3
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ATTACHMENT 1
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REPLY TO NOTICE OF VIOLATION 50-458/9805-01
Violation
During a routine NRC Resident inspection conducted FebnJary 22 through Apri! 4,
1998, a violation of NRC requirements was identified. In accordance with the
" General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-
1600, the violation is listed below:
10 CFR Part 50, Appendix B, Criterion 111 (Design Control), requires that measures be
established to assure that applicable regulatory requirements and the design basis,
as defined in 10 CFR 50.2 and as specified in the license application, are correctly
translated into specifications, drawings, procedures, and instructions. These
measures are required to include provisions to assure that appropriate quality
standards are specified and included in design documents and that deviations from
such standards are controlled.
The Updated Safety Analysis Report, Section 3.11.1.2, states 'The indoor
environmental design basis conditions which have been used to establish the design
basis for RBS [ River Bend Station) are specified for normal, abnorinai, and accident
conditions. The environmental data for temperature, pressure, humidity, and radiation
are defined for each building zone."
" Environmental Design Criteria, Document Number 215.150, for River Bond Station -
Unit I," Revision 4, specifies, in part, that auxiliary building pressure is between -1/4
and -1/2 inch water gauge (W.G.) under accident conditions.
Contrary to the above, established measures did not assure that deviation from the
Environmental Design Criteria was controlled, in that, since initial construction,
excessive standby gas treatment system induced pressure would have resulted,
under accident conditions, in auxiliary builoing pressure less than -1/2 W.G. (-4.0"
W.G. as currently configured).
Reason for the Violation
The primary root cause of this violation was River Bend Station personnel did
not exhibit a comprehensive level of sensitivity to the complex design and
licensing requirements for the Standby Gas Treatment System and Auxiliary
Building pressures.
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June 18,1998
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System and Design engineers were constrained by their assumption that the
original design of the Standby Gas Treatment system was capable of meeting
the diverse requirements placed on it. In fact, later review and balardng
attempted during Forced Outage 98-01 demonstrated that the design
configuration simplicity of the system compounded by a very leak-tight
secondary containment will not allow it to meet all system requirements; such
as: drawdown requirements, maintain a flow rate of 12,500 cfm in both the
containment purge and the Loss of Coolant Accident snode, and result in long
term Auxiliary Building negative pressures between 1/4 in. Water Gage (W.G.)
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and 1/2 in. W.G.
l River Bond Station personnel were focused on the safety functions of the
Secondary Containment and the Standby Gas Treatment System (SGTS) to -
contain, dilute, and hold up fission ;;oducts that may leak from the primary
containment following a Design Basis Accident. It was understood the SGTS
must meet the Technical Specification drawdown times to assure the
performance is within the assumptions of the offsite dose calculations.
Personnel developed the assumption that a higher long term negative pressure
would only help to assure that air exhausted from the Annulus and Auxiliary
Building was filtered and adsorbed by the SGTS. Although Specification
216.300, " Air Conditioning and Ventilation Systems - Hydronic Balancing, was
referred to in the investigation and disposition of Condition Report (CR' 97-
0526A, it was believed the pressure criteria contained in the specification j
applied only to initial system balancing done at startup and did not constitute '
design requirements for the system. River Bond Station should have
recognized the need to reconcile the nonconformances with design and i
licensing bases documentation at this time. Additionally, the relationship !
' between recirculation line alignment, Auxiliary Building pressure, and filter train l
flow requirements was not recognized; although, the individual requirements ;
were known, i
Background
The Standby Gas Treatment System (SGTS) is designed to ensure all
radioactivity leaking from the primary containment and Auxiliary Building is
collected and filtered prior to discherge to the atmosphere following an
- accident. The SGTS consists of two identical 100% capacity redundant,
parallel, physically separated charcoal filtration assemblies (GTS-FLT1 A and
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B), related ductwork, dampers, controls, and centrifugal fans of 12,500 cubic
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June 18,1998
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feet per minute each (cfm). Following an emergency,2,500 cfm is exhausted
from the annulus to maintain a 1/4"-1/2" W.G. negative pressure relative to the ,
Auxiliary Building and 10,000 cfm is exhausted from the Auxiliary Building to l
l maintain it at 1/4"-1/2" W.G. negative pressure relative to the outside !
l atmosphere. The system is also used (manually) to purge the containment and
drywell. Upon a receipt of a Loss of Coolant Alarm, high annulus radiation
signal or loss of Annulus Pressure Control flow, the SGTS is automatically
started and annulus air and exhaust air from the shielded compartments in the i
Auxiliary Building is divertad through the filter trains. A recirculation flow path is .
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provided between the suchon of each filter train and discharge of each exhaust
fan with associated ductwork, backdraft dampers (GTS-DMP4A/B), manual i
balancing dampers (GTS-DMP5A/B), automatic air operated dampers (GTS- )
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AOD22A/B) and their associated instrumentation and controls to recirculate and
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facilitate flow balancing of the air.
Discussion j
During the period of April 1986 through May 1997, SGTS operated with various
recirculation duct da nper (GTS-AOD22A/B and GTS-DMP5A/B) configurations.
! These configurations resulted in the recirculation line being unable to reduce
pressure in the Auxiliary Building during post accident system operation. The
Standby Gas Treatment System was more than able to perform its safety
function; however, access to the Auxiliary Building was difficult. In May of
1997, the recirculation duct was restored to a functional status by placing GTS-
AOD22A/B in automatic and by throttling open GTS-DMP5A/B. This action
restored the as <lesigned system lineup. Testing demonstrated that for a single
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running train of SGTS, access to the Auxiliary Building would still be more '
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difficult than desired.
An engineering evaluation was performed and concluded that the higher
pressures experienced did not/would not adve sely impact equipment,
components or structures. Soon thereafter,it was recognized that access to
the Auxiliary Building would be necessary with two trains of SGTS sunr667 A i
temporary device was designed and installed on Auxiliary Building Door PW-
95-02. The device would ensure a operator access through the door.
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In March 1998, the need to update the Environmental Design Criteria was
rewgnized. A condition report (CR 98-0230) was written to address this issue.
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l Subsequently, a root cause evaluation (CR 98-0230) was performed to address
L the high negative pressures in the Annulus and the Auxiliary Building. It was
discovered that restoring the damper lineup to the design configuration in May
of 1997, produced SGTS Filter Train flows in excess of design values. This
- restoration lineup required the filter train recirculation dampers, GTS-AOD 22A
and B to be placed in automatic so that they would open upon an initiation
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signal. However, this resulted in filter train flows of 15,360 cfm exceeding the
12,500 cfm * 10% Technical Specification reference flow. This higher flow also ;
exceeded the filter unit design flow of 12,500 cfm and charcoal maximum face l
l velocity of 40 fpm given in Specification 225.220, " Standby Gas Treatment
Units.' High GTS filter train flows were evaluated as part of the interim
disposition for CR 98-0437 and the suppoding operability evaluation. The filter
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train individual components, the fans, the dampers and the associated !
' ductwork were found to be undamaged by the high flows and capable of
performing their safety functions with these high flows.
Contributing Factors: ;
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- The balancing instruction,s containedin Spect6 cation 216.300 lead to a
system alignment where Riter flow may exceed system design tiow rate of
12,500 cim.
l The specification states, "The (SGTS) bypass loop dampers,
l 1GTS*AOD 22A, 228, must be closed.' The inlet damper is then
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adjusted for a flow rate of 12,500 cfm and suction paths established to l
the SGTS from the Auxiliary Building and Annulus via Annulus Mixing. l
Then, the specification directs the user to, "Open (SGTS) filter train
bypass loop damper 1GTS*AOD22A or 22B, and adjust and set the
pressure for the Auxiliary Building with manual dampers 1GTS*DMP5A
or 58." This results in filter train flows substantially different frem, and ;
higher then, the 12,500 cfm obteined during the prerequisite balancing. i
e Previous history of accepting high negative pressure in the Annulus and
Auxiliary Sunng with a primary focus of action toward achieving draw down
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timesAfttration fancinon.
Pre-operational test 1-PT 400-2, completed on September 7,1985,
recorded Annulus pressure of -4.2 ' W.G. and Auxilis:y Building
pressure of -0.91" W.G. after one hour of operation. Mceptance
criterion in section 10.12.1 was given as, "The annulus and auxilisty
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Reply to Notice cf Viriation in 50-458/98-05
June 18,199s
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RBG 44548
R8F 1-98-0187
Pa0e 7
building pressure is maintained at a minimum -112 inches W.G. and -1/4
inches W.G. respectively (relative to outside atmosphere) during a Loss
of Coolant Accident."
Condition Reports 88-0101, 93-0403, and 94-1109 documented high
negative pressure and or difficulty in accessing the Auxiliary Building
when SGTS is in operation. In each case, no nonconformance with
Specification 216.300 or Environmental Design Criteria Specification
215.150 was recognized or identified.
- The disposition and review of CR 97-0526A became nanowly focused on
the goal of reducing Auxiliary Building negative pressure while still meeting
the drawdown times containedin the Technical SpectMcations.
The disposition of CR 97-0526A focused efforts at the resolution of the
access problem created by excess negative pressures in the Auxiliary
Building. Given the system design, a solution was to open the
recirculation dampers and throttle the manual dampers as necessary to
achieve drawdown times. With this accomplished, the goal appeared to
have been met without sufficient consideration given to the effects of this
alignment on other system requirements such as flow rate and peak
positive pressure period.
Corrective Actions That Have Been Taken
e As a result of the high negative pressure condition in the Annulus and
Auxiliary Building, design change documents implemented after May 11, !
1997, were reviewed to identify any modifications that may not have been !
evaluated for high negative pressure in the Annulus and Auxiliary Building.
None were found.
. In response to the flows in excess of Technical Specification values, both SGTS
trains were declared inoperable. An evaluation and inspection of the effects of
higher flows on systems, structures and components was performed. It was ,
determined that no adverse effects on equipment or structures did or would be l
expected to exist. The trains were rebalanced to obtain flows within Technical
Specification limits and surveillance tests were performed to assure compliance ,
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with drawdown times. The final system configuration resulted in lower flows from
the Auxiliary Building than assumed in the original positive pressure period
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analysis. This in turn affected the Loss of Coolant Accident dose analysis.
River Bond performed a dose analysis (Interim Disposition to CR 98-0437)
using the existing filter train flows, containment leak rate data from 10CFR50,
Appendix J leak rate testing and historical filter efficiency test data. The results
of this analysis were acceptable and determined conservative relative to
historical test data. Additionally, the charcoal beds were analyzed to evaluate
the effects of increased flow. The analysis results on the charcoal indicated no
adverse effects.
Corrective Actione That Will Be Taken to Avoid Further Violationa
e River Bond will perform a review of the design and licensing bases of the
Standby Gas Treatment system and secondary containment prior to plant startup
following Refueling Outage 8.
- Complete the System Design Criteria review for Standby Gas Treatment and
update licensing bases documentation prior to plant startup following Refueling
Outage 8.
- Evaluate the options, design, and implement modification (s) that will allow
Auxiliary Building access under all modes of SGTS operation without the use of
temporary devices. Actions will be completed by November 30,1998.
. Update Specification 216.300 and c'larify Environmental Design Criteria 215.150
to reflect maximum negative pressures and correct the inaccuracies in the
balancing instructions that contributed to the high flow situ.ation prior to plant
startup following Refueling Outage 8.
- Brief Engineering Department personnel on the specific lessons learned from i
this issue including recognizing the importance of both high and low limits for
design ranges; and the proper use of configuration control change mechanisms,
interim Statue !
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River Bend Station Engineering has conducted feasibility evaluations to determine the
most 6ppropriate solution to Auxiliary Building access difficulties. One of the most
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promising solutions to the access condition is the modification of Auxiliary Building
I doors to enable the installation of a mechanical assist device. The device being
considered, has been used by others in alleviate similar problems with doors. River
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Reply to Notice of Violation in 50-458/88-05
June 18,1996
- RBG-44548
RBF1-96-0167
Pege 9
Bend is in the process of acquiring these devices. These devices may provide a
possible solution to the secondary containment access conditions.
! River Bend Station is continuing to evaluate solutions to system performance
requirements (such as drawdown), system configuration and permanent access
solution alternatives.
Date When Full Compliance Will Be Achieved
Full compliance will be achieved prior to startup from Refueling Outage Eight.
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ATTACHMENT 2 ;
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Commitment identification Fonn
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COMMITMENT ONE-TIME CONTINUING
ACTION COMPLIANCE
Review the design and licensing bases of the Standby Gas Treatment X i
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System and Secondary Containment. Additionally, RSS will complete
the Standby Gas Treatment System Design Cdteria review and update ,
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the 1.icensino and Desen Bases documentation
implement modification (s) that will allow Auxiliary Building accesa in all X
modes of operation without use of temporary devices.
Brief Design and System Engineering personnel on the specific X
lessons loamed from this issue including recognizing the importance of
both high and low limits for design ranges and the proper use of
configuration control chenge mechanirms.
Update Specification 216.300, ' Air Conditioning and Ventilation X
Systems - Hydronic Balancing * and clarify Environmental Design
Criteria 215.150 to reflect maximum negative pressures and correct
the inaccuracies in the balanc!ng instructions that contributed to the
high flow situation. ,
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