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| | number = ML20150B203 | | | number = ML20150B203 |
| | issue date = 06/27/1988 | | | issue date = 06/27/1988 |
| | title = Discusses Steps Taken by Licensee to Correct Conditions at Plant Re Prompt Notification Sys & Potential for Release of Contaminated Water from Condensate Storage Tank in Response to 880523 Ltr Forwarding SM Irving Ltr.Record Copy | | | title = Discusses Steps Taken by Licensee to Correct Conditions at Plant Re Prompt Notification Sys & Potential for Release of Contaminated Water from Condensate Storage Tank in Response to Forwarding SM Irving Ltr.Record Copy |
| | author name = Stello V | | | author name = Stello V |
| | author affiliation = NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) | | | author affiliation = NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
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| | contact person = | | | contact person = |
| | document report number = NUDOCS 8807110389 | | | document report number = NUDOCS 8807110389 |
| | | title reference date = 05-23-1988 |
| | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 7 | | | page count = 7 |
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| ==Dear Senator Breaux:== | | ==Dear Senator Breaux:== |
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| I am responding to your letter dated May 23, 1988, enclosing a letter from Mr. Stephen M. Irving, an attorney in Baton Rouge, Louisiana. Mr. Irving requested that the Commission take innediate action to correct two conditions at the.Biver Bend Statinn _ Mr. Irving expressed concern regarding the necessity for manually activating the prompt notification system and the potential for the release of contaminated water from the condensate storage tank to East and West Creeks, Grants Bayou, and ultimately to the Mississippi River. | | I am responding to your {{letter dated|date=May 23, 1988|text=letter dated May 23, 1988}}, enclosing a letter from Mr. Stephen M. Irving, an attorney in Baton Rouge, Louisiana. Mr. Irving requested that the Commission take innediate action to correct two conditions at the.Biver Bend Statinn _ Mr. Irving expressed concern regarding the necessity for manually activating the prompt notification system and the potential for the release of contaminated water from the condensate storage tank to East and West Creeks, Grants Bayou, and ultimately to the Mississippi River. |
| Gulf States Utilities Company (GSU), the licensee for the River Bend Station (RBS), is taking steps to improve the prompt notification system to reduce the inadvertent emergency actuation of sirens in the Parishes that are participants in the plan. | | Gulf States Utilities Company (GSU), the licensee for the River Bend Station (RBS), is taking steps to improve the prompt notification system to reduce the inadvertent emergency actuation of sirens in the Parishes that are participants in the plan. |
| Bend Station was nomally in the automatic mode.Until recently, the emergency In this mode all the sirens in a Parish could be manually activated without the concurrence of the RBS plant staff by pressing a button in the Parish emergency operations center (E0C). | | Bend Station was nomally in the automatic mode.Until recently, the emergency In this mode all the sirens in a Parish could be manually activated without the concurrence of the RBS plant staff by pressing a button in the Parish emergency operations center (E0C). |
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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
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[ o,, UNITED STATES o
g ,a NUCLEAR REGULATORY COMMISSION WASmNG TON, D. C. 20H5
%,*****,o Juil 2 71988 The Honorable John Breaux United States Senate Washington, D. C. 20510
Dear Senator Breaux:
I am responding to your letter dated May 23, 1988, enclosing a letter from Mr. Stephen M. Irving, an attorney in Baton Rouge, Louisiana. Mr. Irving requested that the Commission take innediate action to correct two conditions at the.Biver Bend Statinn _ Mr. Irving expressed concern regarding the necessity for manually activating the prompt notification system and the potential for the release of contaminated water from the condensate storage tank to East and West Creeks, Grants Bayou, and ultimately to the Mississippi River.
Gulf States Utilities Company (GSU), the licensee for the River Bend Station (RBS), is taking steps to improve the prompt notification system to reduce the inadvertent emergency actuation of sirens in the Parishes that are participants in the plan.
Bend Station was nomally in the automatic mode.Until recently, the emergency In this mode all the sirens in a Parish could be manually activated without the concurrence of the RBS plant staff by pressing a button in the Parish emergency operations center (E0C).
This action sends a radio signal from the Parish transmitter to the siren computer transceiver located at the River Bend Station Emergency Operations Facility (EOF).
to activate the sirens in the Parish.In turn, the transceiver converted and transmitted This mode of operation was changed to minimize stren activations caused by spurious radiofrequency signals.
The computer transceiver at the EOF, now in standby mode, requires the concurrence of the RBS staff to switch it to automatic mode.
is done manually in the EOF by pressing a button. Temporarily, this After declaring switching a General Emergency, the RBS Emergency Director will notify the emergency preparedness staff to place the computer in the automatic mode.
staff is located in the same EOF building during normal shifts.The emergency preparednes a security guard stationed in the same building will be notified by radio orDuring off-shitts, telephone to do the same. We understand that both the emergency staff and the security guards have received hands-on training and have demonstrated their proficiency during drills.
By October 1988. GSU intends to install remote control hardware that will enable the Emergency Director in the Control Room to switch from standby to automatic mode.
GSU had coordinated the above changes with the Federal Emergency Manage-ment Agency, the Parishes, and the State of Louisiana.
Other modifications that have been, or will be completed by October 1988 are:
Improved shielding and grounding of the electronic equipment at the Parish EOCs; modification for the 92 sirens to reduce their susceptibility to spurious radiofrequency signals; installation of an upgraded computer with the capability to provide a fully redundant siren control and monitoring systen; and cemplete testing of the associated hardware which will provide for "safe" failure modes to prevent inadvertent siren activation. f D'
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TheiHonorable John Breaux The NRC staff concluded that these corre:tive actions should reduce the probability of spurious siren activations while providing an acceptable level of emergency notification.
The effects of the failure of the condensate storage tank and release of its contents was considered by the NRC staff during the review of GSU's application for an operating license for River Bend Station, Unit 1. The staff's evalua-tion.is contained in Section 15.7.3, Liquid Tank Failure Accident, Safety Evaluation Report related to the operation of River Bend Station, NUREG-0989, May 1984. _ The staff conducted an independent evaluation of the consequences of component failures-for radioactive-liquid-waste-components located outside the reactor containment building that could result in releases of liquid containing radioactive materials to the environs. The staff considered failure of the condensate storage tank directly after refueling, when it would contain the highest radionuclide inventory. This tank is outside and unprotected by a spill bastn; its rupture would release 600,000 gallons onto the ground. The staff concluded that the radionuclide concentrations in the tank are sufficiently low so that when the high water absorption of the soil (which reduces the amount of water entering the Mississippi River) and the high dilution capability of the Mississippi River are taken into account, the resulting "adionuclide concentrations at the nearest unrestricted drinking water source will be less than the 10 CFR Part 20 limits. Accordingly, the condensate storcqe tank wcs considered acceptable.
In view of the above discussien, Mr. Irving's concerns have been addressed and no additional action beyond that which is ongoing is deerred necessary. Mr. Irving had further requested access to information produced in connection with the complaint. Enclosed is a recent NRC inspection report that addresses inadvertent actuation of emergency sirens.
Sincerely, Victor Stello, Jr.
E cutive Director for Operations
Enclosure:
As stated DISTlintfTinN w/o enclosure:
MT.D0 cket fha ) NRC PDR w/cy of incoming Local PDR w/cy of incoming
, 7 vuuo9 E00 Reading T. Murley/J. Sniezek i
F. Miraglia M4 Reading D. Crutchfield L. Rubenstein OGC-Rockville GPA/CA V. Stello D. Mossburg, PMAS (ED0f 003769) w/cy of incoming P. Shea W. Pt.ulsoriw/cy of incoming J. Calvo P. Noonan PD4 Green Ticket File
- See previous concurrences PDIV:LA* PDIV:PM* REGIV* PDIV:D* TECH ED* OGC* f/
dield PNoonan WPaulson:kb Everett JCalvo EShoemaker DC 06/14/88 06/10/88 06/15/88 06/15/88 06/15/88 06/17/88 064B/88 AD FHi fl@iaJSniezek TMurley DDONRR DONRR ADR4*
LRubenstein ED0 VStello 0 /88 06/ /88 06/ /88 06/15/88 06/ /88
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-The. Honorable John Breaux The NRC staff concluded that these corrective actions should reduce the probability of spurious siren activations while providing an acceptable level of emergency notification.
The effects of the failure of the condensate storage tank and release of its contents was considered by the NRC staff during the review of GSU's application for an operating license for River Bend Station, Unit 1. The staff's evalua-tion is contained in Section 15.7.3, Liquid Tank Failure Accident, Safety Evaluation Report related to the operation of River Bend Station, NUREG-0989, May 1984. The staff conducted an independent evaluation of the consequences of component failures for radioactive-liquid-waste-components located outside thercactor containment building that could result in releases of liquid containing radioactive materials to the environs. The staff considered failure of the condensate storage tank directly after refueling, when it would contain the highest radionuclide inventory. This tank is outside and unprotected by a spill basin; its rupture would release 600,000 gallons onto the-ground. The staff concluded that the radionuclide concentrations in the tank are sufficiently low so that when the high water absorption of the soil (which reduces the amount of water entering the Mississippi River) and the high dilution capability of the Mississippi River are taken into account, the resulting radionuclide concentrations at the nearest unrestricted drinking water source will be less than the 10 CFR Part 20 limits. Accordingly, the condensate storage tank was considered acceptable.
In view of the above discussion, Mr. Irving's concerns have been addressed and to additional action beyond that which is ongoing is deemed necessary. Mr. Irving had further requested,_r i 'hsr-Eredum uf Infom&ti^" ^ ^t, access to information produced in connection with the complaint. T*" '"^ " ". I rv";'; request WHi now De prou:ssed ir, accordaace "ith r^ dom of l Infunnotim Act. pp,1 .e\rev4fer.sOfthetgp 7gg F M g( fY k de " " Sincerely, M dc M }
bWW y'A' Victor Stello, Jr. *
- Executive Director for Operations DISTRIBUTION Docket File NRC PDR w/cy of incoming Local PDR w/cy of incoming EDO / C03769 EDO Reading T. Murley/J. Sniezek F. Mireglia PD4 Reading D. Crutchfield f L. Rubenstein 0GC-Rockville GPA/CA ia V. Stello D. Possburg, PMAS (E00# 003769) w/cy of incoming P. Shea W. Paulsonw/cy of incoming J. Calvo P. Noonan PD4 Green Ticket File p
- See previous concurrences \) L PDIV:LA* PDIV:FM* REGIV* PDIV:D* TECH ED* (G7 DRSP:D PNoonan WPaulson:kb Everett JCalvo DCrutchfield 06/14/08 06/10/88 06/15/88 06/15/88 06/15/88 jt*h/88 06/ C6/ /88 ADP DDONRR DONRR ADR4* ED0 FMiraglia J5niezek TMurley LRubenstein VStello 06/ /88 06/ /88 06/ /88 06/15/88 06/ /88
J The. Honorable John Breaux June , 1988 The NRC staff concluded that these corrective actions should reduce the probability of spurious siren activations while providing an acceptable level of emergency notification.
The effects of the failure of the condensate storage tank and release of its contents was considered by the NRC staff during the review of GSU's application for an operating license for River Bend Station, Unit 1. The staff's evalua-tion is contained in Section 15.7.3, Liquid Tank Failure Accident, Safety Evaluation Report related to the operation of River Bend Station, NUREG-0989, May 1984. The staff conducted an independent evaluation of the consequences of component failures for radioactive-liquid-waste-components located outside the reactor containment building that could result in releases of liquid containing radioactive materials to the environs. The staff considered failure of the condensate storage tank directly after refueling, when it would contain the highest radionuclide inventory. This tank is outside and unprotected by a spill basin; its rupture would release 600,000 gallons onto the ground. The staff concluded that the radionuclide concentratiens in the tank are sufficiently low so that when the high water absorption of the soil (which reduces the amount of water entering the Mississippi River) and the high dilution capability of the Mississippi River are taken into account, the resulting radionuclide concentrations at the nearest unrestricted drinking water source will be less than the 10 CFR Part 20 limits. Accordingly, the condensate storage tank was considered acceptable.
In view of the above discussion, I see no need to take any further steps regarding Mr. Irving's request.
Sincerely, Victor Stello, Jr.
Executive Director for Operations DISTRIBUTION Docket File NRC PDR w/cy of incoming Local PDR w/cy of incoming T. Murley/J. Sniezek F. Miraglia PD4 Reading D. Crutchfield L. Rubenstein 0GC-Rockville GPA/CA D. Mossburg W. Paulson w/cy of incoming P. Noonan PD4 Yellow Ticket File V. Stello
- See previous concurrences PDIV:LA* PDIV:FM* REGIV* PDIV:D* TECH ED* DRSP:D PNoonan WPaulson:hb Everett JCalvo DCrutchfield 06/14/88 06/10/88GY0 06/15/88 06/15/08 06/15/88 06/ /88 ADP DDONRR DONRR ADR4* EDO FMiraglia JSniezek TMurley LRubenstein VStello 06/ /88 06/ /88 C6/ /88 06/15/88 06/ /88 L
4 The Honorable John Breaux June , 1988 The NRC staff concluded that these corrective actions should reduce the probability of spurious siren activations while providing an acceptable level of emergency notification.
The effects of the failure of the condensate storage tank and release of its contents was considered-by the NRC staff during the review of GSU's application for an operating license for River Bend Station, Unit 1. The staff's evalua-tion is contained in Section 15.7.3, Liquid Tank Failure Accident, Safety Evaluation Report related to the operation of River Bend Station, NUREG-0989, May 1984. The staff conducted an independent evaluatior, of the consequences of component failures for radioactive-liquid-waste-compo1ents located outside the reactor containment building that could result in releases of liquid containing radioactive materials to the environs. The staff considered failure of the condensate storage tank directly after refueling, when it would contain the highest radionuclide inventory. This tank is outside and unprotected by a spill basin; 'its rupture would release 600,000 gallons onto the ground. The staff concluded that the radionuclide concentrations in the tank are sufficiently low so that when the high water absorption-of the soil (which reduces the amount of water entering the Mississippi River) and the high dilution capability of the Mississippi River are taken into account, the resulting radionuclide concentrations at the nearest unrestricted drinking etter source will be less than the 10 CFR Part 20 limits. Accordingly, the concensate storage tank was considered acceptable.
In view of the above discussion, I see no need to take any further steps regarding Mr. Irving's request.
Sincerely, Thomas E. Murley, Director Office of Nuclear Reactor Regulation DISTRIBUTION Docket File NRC PDR w/cy of incoming local POR w/cy of incoming T. Murley/J. Sniezek F. Miraglia PD4 Reading D. Crutchfield L. Rubenstein OGC-Rockville GPA/CA D. Mossburg W. Paulson w/cy of incoming' P. Noonan PD4 Yellow T Qket File
- See previous concurr nces PDIV:LA* PDIV:PM* REGIV* PDIV:D* TECH ED* DRSP:D Mgg Everett JCalvo DCrutchfield PNoonan WPaulson: b 06/14/88 06/10/88 06/15/88 06/15/88 06/15/88 06/ /88 ADP DDONRR DONRR ADR4*
FMiraglia JSniezek TMurley LRubenstein 06/ /88 06/ /88 06/ /88 06/15/88 s
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. :The.Nonorable John Breaux- June , 1988 The NRC staff concluded that the above corrective actions should reduce the probability of spurious siren activations-and will provide dn acceptable level of emergency notification.
.The effects of the failure of the condensate storage tank and release of its contents was considered by the NRC staff during the review of GSU's application for an operating license for River Bend Station, Unit 1. . The staff's evalua-tion is contained in Section 15.7.3, Liquid Tank Failure Accident, Safety Evaluation Report related to the operation of River Bend Station, NUREG-0989, May 1984. The staff conducted an independent evaluation of the consequences of component' failures for radioactive-liquid-waste-components located outside the reactor contairarent that could result in releases of liquid containing radio-
-active materials to the environs. The staff considered failure of the conden-sate storage tank directly after refueling (highest radienuclide inventory).
This tank is cutside and unprotected by a spill basin. Tank rupture would release 600,000 gallens.onto the ground. The staff concluded that the radionu-clide concentrations in the tank are sufficiently lov so that when the high water. absorption of the soil (which reduces the encunt of water entering the Mississippi River) and the high dilution capability of the Mississippi River are .taken into acccunt, the resulting radionuclide concentratiens at the nearest.
unrestricted drinking water source will be less than the 10 CFR Part 20 limits.
Accordingly, the condensate storage tank was considered acceptable, in view of the above discussion, I see no need to take any action regarding Mr. Irving's request.
Sincerely, Thomas E. Murley, Director Office of Nuclear Reactor Regulation DISTRIBUTION Docket File NFC PCR w/cy of inccming Local PDR w/cy of incoming T. Murley/J. Sniezek F. Miraglia FD4 Readir,g D. Crutchfield L. Rubenstein 0GC-Rockville GPA/CA D. Mossburg W. Paulson w/cy of incoming P. Noonan PD4 Yellow Ticket File
- See previous concurr PDIV: *PDIV:PM e
REGIV h
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o The. Honorable John Breaux June , 1988 or will be completed by October 1908 are: Improved shielding and grounding of the electronic equipment at the Parish E0Cs; redification of the 92 sirens to reduce the susceptibility to individual actuations because of lightening strikes nearby; installation of an upgraded corputer with the hardware capabi-lity to provide a fully redundant siren control and ronitoring system; and corplete testing of the associated hardware which will provide for "safe" failure modes to prevent inadvertent siren activation.
The NRC staff finds that the above corrective actions should reduce the inadvertent siren activations and will provide an acceptable level of emergency notification.
The effects of the failure of the condensate storage tank and release of its contents was considered by the NRC staff during the review of GSU's application for an operating license for River Bend Station, Unit 1. The staff's evalua-tion is ccntained in Section 15.7.3, Liquid Tank Failure Accident, Safety Evaluation Report related to the operation of River Bend Station, NUREG-0989, May 1984. The staff conducted an independent e nluation of the consequences of component failures for radioactive-liquid-waste con.ponents located outside the reactor containment that could result in releass s of liquid containing radio-active materials to the environs. The staff consideied failure of the conden-sate storage tank directly after refueling (highest r d Wnuclide inventory).
This tank is outside and unprotected by a spill basin Tank rupture would release 600,000 gallons onto the ground. The staff cu.:1uded that the radionu-clide concentrations in the tank are sufficiently low Jo that when the high water absorption of the soil (which reduces the amount of water entering the Mississippi River) and the high dilution capability of the Mississippi River are taken into account, the resulting radicr.uclide concentrations at the nearest unrestricted drinking water source will be less than the 10 CFR Part ?0 limits.
Accordingly, the condensate storage tank was considered acceptable.
In view of the above discussion, I see no need to take any action regarding Mr. Irving's request.
Sincerely, Thomas E. Murley, Director Office of Nuclear Peactor Regulation DISTRIBUTION Docket File NRC PDR w/cy of incoming local PDR w/cy of incoming T. Murley/J. Sniezek F. Miraglia PD4 Reading D. Crutchfield L. Rubenstein OCC-Rockville GPA/CA D. Mos urg W. Paulson w/cy of incoming P. Noonan PD4 Yellow Ticket File PDIV:LA PDh. ,M REGIV PDIV:D TECH ED OGC-Rock. DRSP:D PMoonan WPaulson Everett JCalvo DCrutchfield 06/ /88 06//0 /88 06/ /88 06/ /88 06/ /08 06/ /88 06/ /08 ADP DDONRR DONRR FHiraglie JSniezek TMurley 06/ /88 06/ /88 06/ /88