|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7681999-10-19019 October 1999 Forwards Insp Rept 50-458/99-12 on 990822-1002.Four Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy RBG-45125, Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams1999-10-18018 October 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams ML20217J3751999-10-15015 October 1999 Informs That Applicable Portions of NEDC-32778P, Safety Analysis Rept for River Bend 5% Power Uprate, Marked as Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) IR 05000458/19990071999-10-0505 October 1999 Refers to Util Ltr Re Apparent Violations Described in Insp Rept 50-458/99-07 Issued on 990804 & Forwards Nov.Insp Described Two Apparent Violations Related to River Bend Station Division I EDG RBG-45123, Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required1999-09-30030 September 1999 Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required RBG-45124, Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl1999-09-24024 September 1999 Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl RBG-45122, Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-471999-09-23023 September 1999 Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-47 RBG-45113, Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp1999-09-21021 September 1999 Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp ML20212D8901999-09-16016 September 1999 Discusses 6 Month Review of Plant Midcycle Ppr.Advises of Plans for Future Insp Activities.Forwards Historical Listing of Plant Issues,Referred to as PIM ML20216F7881999-09-15015 September 1999 Forwards Insp Rept 50-458/99-10 on 990830-990903.No Violations Noted.Insp Covered Licensed Operators Requalification Training Program & Observation of Requalification Activities 05000458/LER-1998-003, Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents1999-09-0909 September 1999 Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents ML20211Q7721999-09-0909 September 1999 Expresses Appreciation for ,In Response to NRC 990702 Re Denial of Notice of Violation Cited in Concerning Insp Rept 50-458/98-16.Reply Found to Be Responsive to Concerns Raised in NOV RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted1999-09-0808 September 1999 Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted ML20211Q3921999-09-0808 September 1999 Forwards Insp Rept 50-458/99-08 on 990711-0821.One Violation Being Treated as Noncited Violation ML20211Q5541999-09-0808 September 1999 Discusses Meeting Conducted on 990830 in St Francisville,La Re Overall Performance Issues During 990403-0703 Refueling/ Maintenance Outage.Due to Proprietary Nature of Some Subject Matters,Meeting Closed to Public.Attendance List Encl ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) RBG-45095, Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status1999-09-0707 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status RBG-45097, Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves1999-08-31031 August 1999 Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves RBG-45094, Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation1999-08-25025 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation ML20211E2071999-08-23023 August 1999 Discusses Insp Rept 50-458/99-07 in Which 2 Violations Were Identified & Being Considered for Escalated Enforcement Action.Response Should Be Submitted Under Oath or Affirmation ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 RBG-45093, Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept1999-08-17017 August 1999 Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept ML20211A9291999-08-17017 August 1999 Forwards Insp Rept 50-458/99-11 on 990719-23.Areas Examined Included Portions of Licensee Physical Security Program. No Violations Noted ML20210T8881999-08-16016 August 1999 Forwards Replacement Pages 9-18 for Insp Rept 50-458/99-09, Issued on 990730 IR 05000458/19980101999-08-13013 August 1999 Forwards Summary of 990805 Mgt Meeting with Licensee in Arlington,Tx Re Radiological Control Problems Noted in Insp Repts 50-458/98-10 & 50-458/99-04.With Attendance List & Licensee Presentation ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210U3751999-08-12012 August 1999 Informs That Info Contained in Presentation, River Bend Station Fuel Recovery Project,Dtd 990622, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20210Q7691999-08-11011 August 1999 Forwards Request for Addl Info Re Licensee River Bend Individual Plant Exam External Events,Under GL 88-20,suppl 4,dtd 910628 ML20210R4591999-08-10010 August 1999 Ack Receipt of Which Transmitted Plant Emergency Plan,Rev 20 Under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required,Based on Determination That Changes Does Not Decrease Effectiveness of EP ML20210N1641999-08-0404 August 1999 Forwards Insp Rept 50-458/99-07 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210K4641999-08-0303 August 1999 Forwards SE Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Power-Operated Gate Valves, Issued on 950817 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K1351999-07-30030 July 1999 Forwards Insp Rept 50-458/99-09 on 990510-28 with in-office Insp Until 990701.Three Violations Being Treated as Noncited Violations ML20210J9691999-07-30030 July 1999 Discusses 990719 Meeting with Util in Arlington,Tx Re Region IV Staff Findings of Root Cause Investigation Into Fuel Cladding Failures That Occurred During Recent Cycle 8 Operation.List of Attendees & Organization Chart Encl RBG-45072, Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL1999-07-23023 July 1999 Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL ML20210E9001999-07-23023 July 1999 Informs That as Result of Staff Review of Licensee Responses to GL 92-01,rev 1,Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 RBG-45073, Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl1999-07-20020 July 1999 Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl RBG-45071, Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl1999-07-19019 July 1999 Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl 05000458/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 11999-07-15015 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 1 ML20196L0501999-07-0606 July 1999 Informs That NRC Insp Rept 50-458/99-03 Issued on 990519 with Errors in Tracking Numbers Assigned to Seven Noncited Violations & Error Re Actual Location of SRO During Refueling Activities.Revised Pages 2 & 4 Encl ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl ML20196K6851999-06-30030 June 1999 Ack Receipt of & Denial of NOV in Response to Transmitting NOV & Insp Rept 50-458/98-16.Listed Info Documents Results of Review of Response to Violation Re fire-induced Circuit Faults ML20196K0671999-06-30030 June 1999 Forwards Insp Rept 50-458/99-04 on 990412-16 & 28-29.Five Violations of NRC Requirements Occurred & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy.Meeting Scheduled for 990726 RBG-45048, Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept1999-06-29029 June 1999 Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept RBG-45047, Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output1999-06-29029 June 1999 Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output ML20196H5171999-06-21021 June 1999 Requests Withholding of Info Being Presented in Meeting of Entergy,General Electric & NRC Staff.Licensee Requested Meeting with NRC to Present Info on Recent Anomalous Conditions Found During Insp of Fuel Bundles.W/Affidavit 05000458/LER-1999-012, Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form1999-06-21021 June 1999 Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form RBG-45035, Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld1999-06-21021 June 1999 Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld ML20196E0601999-06-18018 June 1999 Forwards Insp Rept 50-458/99-05 on 990418-29.Four Violations Identified & Being Treated as Noncited Violations 05000458/LER-1999-011, Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-06-0909 June 1999 Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARRBG-45125, Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams1999-10-18018 October 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams RBG-45123, Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required1999-09-30030 September 1999 Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required RBG-45124, Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl1999-09-24024 September 1999 Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl RBG-45122, Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-471999-09-23023 September 1999 Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-47 RBG-45113, Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp1999-09-21021 September 1999 Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp 05000458/LER-1998-003, Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents1999-09-0909 September 1999 Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted1999-09-0808 September 1999 Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted RBG-45095, Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status1999-09-0707 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) RBG-45097, Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves1999-08-31031 August 1999 Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves RBG-45094, Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation1999-08-25025 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 RBG-45093, Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept1999-08-17017 August 1999 Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept RBG-45072, Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL1999-07-23023 July 1999 Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL RBG-45073, Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl1999-07-20020 July 1999 Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl RBG-45071, Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl1999-07-19019 July 1999 Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl 05000458/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 11999-07-15015 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 1 ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl RBG-45047, Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output1999-06-29029 June 1999 Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output RBG-45048, Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept1999-06-29029 June 1999 Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept ML20196H5171999-06-21021 June 1999 Requests Withholding of Info Being Presented in Meeting of Entergy,General Electric & NRC Staff.Licensee Requested Meeting with NRC to Present Info on Recent Anomalous Conditions Found During Insp of Fuel Bundles.W/Affidavit RBG-45035, Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld1999-06-21021 June 1999 Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld 05000458/LER-1999-012, Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form1999-06-21021 June 1999 Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form 05000458/LER-1999-011, Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-06-0909 June 1999 Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl 05000458/LER-1999-010, Forwards LER 99-010-00 for River Bend Station,Unit 1 IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-05-28028 May 1999 Forwards LER 99-010-00 for River Bend Station,Unit 1 IAW 10CFR50.73.Commitments Identified in Rept,Encl RBG-45021, Informs That Cycle 9 Operation Will Remain within MCPR Safety Limits Approved in Amend 105 to TS Issued by NRC in1999-05-26026 May 1999 Informs That Cycle 9 Operation Will Remain within MCPR Safety Limits Approved in Amend 105 to TS Issued by NRC in 05000458/LER-1999-009, Forwards LER 99-009-00 IAW 10CFR50.73.Commitments Contained in Ltr Are Identified on Commitment Identification Form1999-05-24024 May 1999 Forwards LER 99-009-00 IAW 10CFR50.73.Commitments Contained in Ltr Are Identified on Commitment Identification Form RBG-45017, Informs NRC of Addition of ASME Boiler & Pressure Vessel Code,Section Xi,Code Case N-496-1 to RBS Inservice Insp Program.Commitment Made by Util,Encl1999-05-14014 May 1999 Informs NRC of Addition of ASME Boiler & Pressure Vessel Code,Section Xi,Code Case N-496-1 to RBS Inservice Insp Program.Commitment Made by Util,Encl ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 05000458/LER-1999-007, Forwards LER 99-007-00 IAW 10CFR50.73.Commitments Identified in LER Are Noted in Attachment 11999-05-10010 May 1999 Forwards LER 99-007-00 IAW 10CFR50.73.Commitments Identified in LER Are Noted in Attachment 1 05000458/LER-1999-006, Forwards LER 99-006-00 Re Unplanned Automatic Standby Svc Water Initiation,Due to Procedure Inadequacy.Commitments Identified in Rept Noted in Attachment 11999-05-0606 May 1999 Forwards LER 99-006-00 Re Unplanned Automatic Standby Svc Water Initiation,Due to Procedure Inadequacy.Commitments Identified in Rept Noted in Attachment 1 05000458/LER-1999-005, Forwards LER 99-005-00 IAW 10CFR50.73(a)(2)(i).Commitments Identified in LER Are Noted in Attachment 11999-05-0303 May 1999 Forwards LER 99-005-00 IAW 10CFR50.73(a)(2)(i).Commitments Identified in LER Are Noted in Attachment 1 RBG-44993, Forwards RBS Annual Individual Monitoring Rept for Jan-Dec 1998,per Requirements of 10CFR20.2206(b).File Info Listed. Without Encl1999-04-30030 April 1999 Forwards RBS Annual Individual Monitoring Rept for Jan-Dec 1998,per Requirements of 10CFR20.2206(b).File Info Listed. Without Encl RBG-44998, Informs of Missing Documentation Re Examination Results Reported in RBS Owners Activity Report Forms Submitted to NRC on 9802241999-04-30030 April 1999 Informs of Missing Documentation Re Examination Results Reported in RBS Owners Activity Report Forms Submitted to NRC on 980224 ML20206E7811999-04-29029 April 1999 Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested 05000458/LER-1999-003, Forwards LER 99-003-00,per 10CFR50.73.Commitments Identified in Rept Are Noted in Attachment 11999-04-23023 April 1999 Forwards LER 99-003-00,per 10CFR50.73.Commitments Identified in Rept Are Noted in Attachment 1 RBG-44968, Submits Addl Info Re 981008 LAR 1998-02 Re Implementation of Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long- Term Solution.Clarifies Certain Aspects of Proposed Ts,Per 990406 Telcon with NRC1999-04-15015 April 1999 Submits Addl Info Re 981008 LAR 1998-02 Re Implementation of Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long- Term Solution.Clarifies Certain Aspects of Proposed Ts,Per 990406 Telcon with NRC RBG-44965, Responds to 990324 Telcon RAI Re SLMCPR Calculation Method for RBS Cycle 9 Slmcpr,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits. Proposed TS Pages, Encl1999-04-0808 April 1999 Responds to 990324 Telcon RAI Re SLMCPR Calculation Method for RBS Cycle 9 Slmcpr,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits. Proposed TS Pages, Encl RBG-44959, Withdraws 981120 LAR 1998-20,allowing Adjusting Control Pattern for Plant Startup If Outage Had Occurred Before Planned Refueling Outage.No Plant Outage Was Conducted & Plant Is Now in Eighth Refueling Outage1999-04-0808 April 1999 Withdraws 981120 LAR 1998-20,allowing Adjusting Control Pattern for Plant Startup If Outage Had Occurred Before Planned Refueling Outage.No Plant Outage Was Conducted & Plant Is Now in Eighth Refueling Outage ML20205F1781999-03-31031 March 1999 Forwards Consolidated Entergy Submittal to Document Primary & Excess Property Damage Insurance Coverage for Nuclear Sites of Entergy Operations,Inc,Per 10CFR50.54(w)(3) RBG-44939, Forwards Rbs,Unit 1 Annual Occupational Radiation Exposure Rept for 1998, Per TS 5.6.1.Rept Consists of Tabulation of Exposure for Personnel Receiving Exposures Greater than 100 Mrem Per Yr1999-03-31031 March 1999 Forwards Rbs,Unit 1 Annual Occupational Radiation Exposure Rept for 1998, Per TS 5.6.1.Rept Consists of Tabulation of Exposure for Personnel Receiving Exposures Greater than 100 Mrem Per Yr ML20196K7101999-03-26026 March 1999 Submits Reporting & Recordkeeping for Decommissioning Planning,Per 10CFR50.75(f)(1) RBG-44899, Provides Notification of Termination of Licensed Operator, AA Rouchon,License OP-42416-1,due to Resignation.Reactor Operator License Data,Listed1999-03-25025 March 1999 Provides Notification of Termination of Licensed Operator, AA Rouchon,License OP-42416-1,due to Resignation.Reactor Operator License Data,Listed ML20204G8701999-03-15015 March 1999 Responds to NOV Described in NRC Correspondance to Util ,expressing Disappointment in NRC Determination That AD Wells Deliberately Provided Incomplete & Inaccurate Info to NRC During Meeting on 971015 RBG-44925, Responds to NRC Re Violations Noted in Investigation Rept 4-97-059.Corrective Actions: Mgt Expectations for Communicating with NRC Issued to Site Personnel on 980212,by RBS Vice President,Operations1999-03-15015 March 1999 Responds to NRC Re Violations Noted in Investigation Rept 4-97-059.Corrective Actions: Mgt Expectations for Communicating with NRC Issued to Site Personnel on 980212,by RBS Vice President,Operations RBG-44924, Informs That Util Response to NOV Re Investigation Rept 4-97-059,will Be Issued by 990315,as Extended by NRC Ltr .Encl Check for $55,000 Is for Payment of Civil Penalty IAW Instructions in .Without Check1999-03-0505 March 1999 Informs That Util Response to NOV Re Investigation Rept 4-97-059,will Be Issued by 990315,as Extended by NRC Ltr .Encl Check for $55,000 Is for Payment of Civil Penalty IAW Instructions in .Without Check RBG-44912, Responds to Violations Noted in Insp Rept 50-458/98-13. Corrective Actions:Matls & Training Were Provided to Expedite Implementation of Existing Procedural Guidance to Supply Compressed Air1999-03-0303 March 1999 Responds to Violations Noted in Insp Rept 50-458/98-13. Corrective Actions:Matls & Training Were Provided to Expedite Implementation of Existing Procedural Guidance to Supply Compressed Air RBG-44904, Informs NRC of Date Change Re Commitment Made in Response to NOV 50-458/98-05-01.New Commitment Date 9912161999-02-25025 February 1999 Informs NRC of Date Change Re Commitment Made in Response to NOV 50-458/98-05-01.New Commitment Date 991216 RBG-44384, Submits Response to Fuel Cladding Defect Issues Raised in 10CFR2.206 Petition.Clear Technical Basis Exists in Info Provided by River Bend Station to Deny Petition1999-02-11011 February 1999 Submits Response to Fuel Cladding Defect Issues Raised in 10CFR2.206 Petition.Clear Technical Basis Exists in Info Provided by River Bend Station to Deny Petition ML20203C4201999-01-25025 January 1999 Submits Denial of NRC Request for Advance Info Re Concerns Raised by Ucs in 10CFR2.206 Petitions on River Bend & Perry Plants.Petitioners Were Not Required to Provide NRC with Info in Advance of Informal Public Hearings 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARRBG-33517, Responds to NRC Re Violations Noted in Vendor Interface & Procurement Team Insp Rept 50-458/89-200. Corrective Actions:Maint Instruction Index for Diesel Engine Reviewed1990-09-10010 September 1990 Responds to NRC Re Violations Noted in Vendor Interface & Procurement Team Insp Rept 50-458/89-200. Corrective Actions:Maint Instruction Index for Diesel Engine Reviewed RBG-33466, Responds to Deviations Noted in Insp Rept 50-458/90-16 on 900709-19 Re Suppression Pool Water Level.Corrective Actions:Operator Aids Will Be Developed to Inform Control Room Operators of Actual Instrument Range1990-08-30030 August 1990 Responds to Deviations Noted in Insp Rept 50-458/90-16 on 900709-19 Re Suppression Pool Water Level.Corrective Actions:Operator Aids Will Be Developed to Inform Control Room Operators of Actual Instrument Range RBG-33460, Forwards Certified Cash Flow Statements for Guarantee of Funds in Event of Retrospective Call Under Secondary Financial Protection Program,Per 10CFR140.211990-08-28028 August 1990 Forwards Certified Cash Flow Statements for Guarantee of Funds in Event of Retrospective Call Under Secondary Financial Protection Program,Per 10CFR140.21 RBG-33496, Advises That KT Allbritton No Longer Needs to Maintain License for Facility Due to Termination of Employment1990-08-28028 August 1990 Advises That KT Allbritton No Longer Needs to Maintain License for Facility Due to Termination of Employment RBG-33450, Forwards Rev 3 to River Bend Station Updated Fsar. Rev Covers Period 890301-9003011990-08-28028 August 1990 Forwards Rev 3 to River Bend Station Updated Fsar. Rev Covers Period 890301-900301 RBG-33424, Requests That Proposed Tech Spec 3.0 & 4.0,when Approved,Be Issued as Effective Immediately W/Implementation to Be Completed by 9009291990-08-22022 August 1990 Requests That Proposed Tech Spec 3.0 & 4.0,when Approved,Be Issued as Effective Immediately W/Implementation to Be Completed by 900929 RBG-33372, Forwards Semiannual Rept on fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d).No Weaknesses in Program Identified1990-08-10010 August 1990 Forwards Semiannual Rept on fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d).No Weaknesses in Program Identified RBG-33310, Responds to NRC Re Exercise Weaknesses Noted in Insp Rept 50-458/90-06.Corrective Actions:Computer Clock Synchronized to Correct Time & Logic Changed for Making Location Addresses in Retransmission of Messages1990-08-0101 August 1990 Responds to NRC Re Exercise Weaknesses Noted in Insp Rept 50-458/90-06.Corrective Actions:Computer Clock Synchronized to Correct Time & Logic Changed for Making Location Addresses in Retransmission of Messages RBG-33300, Forwards Schedule for Submittal of Repts Re Reactor Physics Methods & Reactor Transient Analysis Methods Rept,Per 900712 Meeting1990-07-30030 July 1990 Forwards Schedule for Submittal of Repts Re Reactor Physics Methods & Reactor Transient Analysis Methods Rept,Per 900712 Meeting RBG-33294, Forwards Decommissioning Trust Agreement for River Bend Unit 1 & Nuclear Decommissioning Trust Fund Agreement Between Cajun Electric Power Cooperative,Inc & Hibernia Natl Bank1990-07-26026 July 1990 Forwards Decommissioning Trust Agreement for River Bend Unit 1 & Nuclear Decommissioning Trust Fund Agreement Between Cajun Electric Power Cooperative,Inc & Hibernia Natl Bank RBG-33196, Forwards Rev 0 to River Bend Station,Cycle 3 Core Operating Limits Rept Jul 1990. Use of Core Operating Limits Rept in Lieu of cycle-specific Parameters in License Amend Request Approved W/Amend 42 to License,Per Generic Ltr 88-161990-07-13013 July 1990 Forwards Rev 0 to River Bend Station,Cycle 3 Core Operating Limits Rept Jul 1990. Use of Core Operating Limits Rept in Lieu of cycle-specific Parameters in License Amend Request Approved W/Amend 42 to License,Per Generic Ltr 88-16 RBG-33150, Responds to NRC Re Violations Noted in Insp Rept 50-458/89-11.Corrective Actions:Implementation of New Computerized Tagging Sys Being Developed1990-07-0202 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-458/89-11.Corrective Actions:Implementation of New Computerized Tagging Sys Being Developed RBG-33143, Addresses Progress of Procurement & Evaluation Activities for Sys to Meet Reg Guide 1.97 Neutron Monitoring Requirements.Bid Spec to Incorporate NRC & BWR Owners Group Guidance Will Be Issued Prior to Fourth Quarter 19901990-06-29029 June 1990 Addresses Progress of Procurement & Evaluation Activities for Sys to Meet Reg Guide 1.97 Neutron Monitoring Requirements.Bid Spec to Incorporate NRC & BWR Owners Group Guidance Will Be Issued Prior to Fourth Quarter 1990 RBG-33132, Suppls Response to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Will Reverify Switch Settings on Initial Surveillance Interval of 5 Yrs1990-06-28028 June 1990 Suppls Response to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Will Reverify Switch Settings on Initial Surveillance Interval of 5 Yrs RBG-33120, Responds to 900621 Request for Addl Info Re Effects on Containment Dynamic Loads Which Will Result from Increasing Suppression Pool Temp from 95 F to 100 F.Original Design Basis of 100 F Included in Steam Condensation Loads1990-06-26026 June 1990 Responds to 900621 Request for Addl Info Re Effects on Containment Dynamic Loads Which Will Result from Increasing Suppression Pool Temp from 95 F to 100 F.Original Design Basis of 100 F Included in Steam Condensation Loads RBG-33114, Requests Withdrawal of 900202 Application for Amend to License NPF-47,revising Div I & II Diesel Generator Crankshift Insp Scheduling,Per 900529 Telcon1990-06-26026 June 1990 Requests Withdrawal of 900202 Application for Amend to License NPF-47,revising Div I & II Diesel Generator Crankshift Insp Scheduling,Per 900529 Telcon RBG-33113, Requests Implementation of Generic Ltr 87-09 Wording for Bases for Spec 4.0.3 Re Reporting Requirements of 10CFR50.73 for Missed Surveillances to Enable NRC to Continue Review of 880930 Application for Amend to License1990-06-26026 June 1990 Requests Implementation of Generic Ltr 87-09 Wording for Bases for Spec 4.0.3 Re Reporting Requirements of 10CFR50.73 for Missed Surveillances to Enable NRC to Continue Review of 880930 Application for Amend to License RBG-33100, Requests Waiver of Compliance W/Tech Spec 3/4.6.3.1 Until Exigent Processing of Tech Spec Change Request LAR 90-08 Completed.Change Revises Max Temp for Suppression Pool to 100 F to Avoid Limiting Plant Operation in Jul & Aug 19901990-06-22022 June 1990 Requests Waiver of Compliance W/Tech Spec 3/4.6.3.1 Until Exigent Processing of Tech Spec Change Request LAR 90-08 Completed.Change Revises Max Temp for Suppression Pool to 100 F to Avoid Limiting Plant Operation in Jul & Aug 1990 ML20043G2211990-06-14014 June 1990 Responds to 900509 Request for Addl Info Re 900209 Response to Violations Noted in Insp Rept 50-458/89-41.Procedure Being Developed to Provide Guidelines for Future Troubleshooting of Recirculation Flow Control Valve Sys ML20043G8191990-06-12012 June 1990 Forwards Rev 5A to Pump Valve Inservice Testing Plan,For Review.Rev Provides Addl Info & Clarification for Requests for Relief Noted in Rev 5 ML20043E6531990-06-0606 June 1990 Forwards Addl Info Re 880930 Application for Amend to License NPF-47 to Implement Generic Ltr 87-09 Requirements Re Preplanned Use of Addl Operating Flexibility ML20043F9801990-06-0606 June 1990 Forwards Response to NRC 890731 Request for Addl Info Re Util 890731 Application for Amend to License NPF-47 to Implement Generic Ltr 87-09.Justifications for Use of Proposed Tech Spec 3.0.4 Will Be Submitted Separately ML20043D5591990-06-0101 June 1990 Provides Status of Actions Re Insp Rept 50-458/89-45 Which Dealt W/Dual Coil Solenoid Operated Valves Used to Control MSIVs ML20043D5421990-06-0101 June 1990 Forwards Addendum to River Bend Station - Unit 1,Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989. ML20043D5401990-06-0101 June 1990 Provides Update to 900125 & 0315 Responses to Insp Rept 50-458/89-200.Util in Process of Performing Retrofit Review of in-stock Items Purchased Between 850101-900101 ML20043D2371990-05-31031 May 1990 Provides Suppl to 890929 Response to Violations Noted in Insp Rept 50-458/89-31.Safety Tagging Administrative Procedure Being Revised to Make Clearance Program Easier to Understand & Follow ML20043C8011990-05-29029 May 1990 Forwards Rev 12 to Physical Security Plan.Rev Reflects Current Activities of Plant Security Programs.Rev Withheld (Ref 10CFR73.21.) ML20043B4231990-05-21021 May 1990 Forwards Rept Re Investigation Involving Unsatisfactory Performance Test Result by Dhhs Certified Lab Under Contract to Util to Perform Drug Screen Testing Under 10CFR26, Fitness-For-Duty Program. ML20043A4271990-05-14014 May 1990 Forwards Authorization of Util Board of Directors for Tf Plunkett & Wh Odell to Sign Ltrs to NRC Transmitting Amends to OL or Responses to Insp Repts ML20042G7031990-05-0909 May 1990 Responds to NRC 900405 Ltr Re Weaknesses Noted in Insp Rept 50-458/90-06 on 900220-23.Corrective Action:Software in Simulator Changed to Duplicate Software in Control Room & More Training Time on Computers Given to Operators ML20042F9741990-05-0707 May 1990 Responds to Violations Noted in Insp Rept 50-458/90-02 on 900122-26.Corrective Actions:Electrical Power Removed from Valves,Safety Assessment of Spurious Opening Performed & QA Performed on Energized Valves ML20042G2521990-05-0404 May 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants.' ML20042E3781990-04-0606 April 1990 Responds to Violations Noted in Ofc of Investigations Rept 4-88-027,per Enforcement Action 90-043.Corrective Actions: Util Auditing self-screening Contractor Programs to Assure Compliance & Audit Will Be Evaluated for Acceptability ML20042D8351990-03-30030 March 1990 Submits Supplemental Info Re Util Response to Station Blackout Rule & Advises That Results of Plant Evaluations Demonstrate Ability to Cope W/Station Blackout for Proposed 4 H Duration W/O Reliance on Ac Power Sources ML20042E3501990-03-30030 March 1990 Forwards Evaluation of Unsatisfactory Performance by Dhhs Certified Lab Performing Drug Testing ML20012F1571990-03-28028 March 1990 Requests Extension Until 900601 to Submit Changes to Facility Tech Specs Re Leak Detection & Inservice Insp Program,Per Generic Ltr 88-01 ML20012F1551990-03-28028 March 1990 Suppls 890411 Response to Violations Noted in Insp Rept 50-458/86-04.Operations QC Instructed QC Planners & Lead Inspector to Include Hold Point of Electrical Maint Work Request for Category I Electrical Equipment Panels ML20042D7041990-03-21021 March 1990 Forwards Results of Ultrasonic Testing Conducted on N4A-2 Feedwater nozzle-to-safe End Weld During mid-cycle Outage at Plant.Circumferential Indication Identified in Buttered Area on Safe End Side of Weld During Second Refueling Outage ML20012E0001990-03-20020 March 1990 Forwards Marsh & Mclennan 900313 Ltr Containing Summary of Property Insurance Coverage for Facility,Per 10CFR50.54(w)(2) ML20012C7901990-03-16016 March 1990 Forwards Response to Violations Noted in Insp Rept 50-458/89-39.Response Withheld (Ref 10CFR73.21) ML20012C9931990-03-15015 March 1990 Forwards Duke Engineering & Svcs,Inc 900105 Ltr to BC Fichtenkort Re Proposed Crankshaft Insp Variation & Recommends Variation Be Presented to Clearinghouse Members at 900111-12 Meeting ML20012C7881990-03-15015 March 1990 Provides Updated Status for Corrective Actions Being Taken for Discrepancies Identified in Insp Rept 50-458/89-200. Thirty-six Items identified.Twenty-eight Items Completed. Three of Eight Remaining Items Require Evaluation of Stock ML20012C0381990-03-0909 March 1990 Advises That Senior Reactor Operator License 43188-1 & Reactor Operator License 42087-2 for a Middlebrooks & DG Looney,Respectively,Expired on 900105 & 900201 ML20012A4431990-03-0101 March 1990 Requests Addl Clarification to Prepare Response to Generic Ltr 90-01 Re Survey of Time Spent by Key Nuclear Power Plant Managers in Responding to Various Operational Insps & Audits ML20012B3001990-03-0101 March 1990 Forwards Fitness for Duty Program Rept 90-F-02 Re Investigation of Unsatisfactory Performance Test Result by Certified Lab Under Contract to Util to Perform Drug Screen Testing,Per 10CFR26 ML20012A9161990-02-28028 February 1990 Forwards Response to Inspector Followup Item Noted in Insp Rept 50-458/89-42 on 891113-17.Corrective Actions:Rev to Procedure EDP-AA-10 Re Issuance of Training Matrix on Semiannual Basis Will Be Issued to Remove 2-yr Rereading ML20011E8431990-02-0909 February 1990 Responds to Violations Noted in Insp Rept 50-458/89-40. Corrective Actions:All Prestaged Matl Removed from Containment & Radiation Protection Personnel Cautioned on Placement of Matl on 95-ft Elevation of Containment ML20011E6741990-02-0909 February 1990 Responds to Violation Noted in Insp Rept 50-458/89-41 on 891101-15.Corrective Actions:Procedure Which Would Provide Guidelines for Future Troubleshooting of Recirculation Flow Control Valve Sys Being Developed ML20011E1531990-01-29029 January 1990 Provides Currently Identified Outage & nonoutage-related Activities to Update NRC of Util Licensing Activities in Order of Priority ML20006C0061990-01-25025 January 1990 Forwards Notification of Nuclear Liability Insurance Coverage for Facility 1990-09-10
[Table view] |
Text
GULF STJETES UTILITIES COMPANY POST OFPtCE Bo*295i a OsAUvoNT. TEAAS 77704 D I AREA cooE 713 938-3G43 4 June 2h, 1981 l
/ /[ f u\
n3G- 10,612
,7 U u,4/ 30 bS4 File No. G9.11 ,,klg /gg Mr. Darrell G. Eisenhut, Director Nuclear Reactor Regulation v/t -
g/Q s
j U. S. Nuclear Regulatory Co==ission -
Washington, D. C. 20555 2 ear Mr. Eisenhut:
Gulf States Utilities Co=pany (GSU) has reviewed your letter of December 22, 1980 concerning the " Control of Heavy Loads." The informa+1on provided documents the results of our reviev and actions being taken.
In you2 letter you requested that submittals concerning our re-viev af heavy loads be made in tvc parts. Part cne, included herein, includes a review of Section 2.1 in your Enclosure 3, " Request for Additional Information on Centrol of Heavy *. cads." Part two vill include Sections 2.2 and 2.3 af Enclosure 3 and will be submitted oy September 22, 1931.
.v River Send Station's plant procedures, training program, inspection and maintenance programs vill be developed in accordance with Section 5.1 of :."JREG-0612. A polar crane load drop analysis is currently being performed and vill be incorporated into Section 9.1.h.3 of the Final Safety Analysis Report in a future amendment (see Section 2.1.1, Page 1 of Attachment).
Gulf States Utilities Ccm.;any has projected a Fuel Load date of October, 1983 Any concerns related to NUREG-0612 vill be addressed prior to our Fuel Load date and incorporated in the design, construction and operation of the River Bend Station.
Sincerely,
( , '
E. L. Draper, J .
Vice President Nuclear Technology ELD /RJK/kt -
g Attachment hG 8107010273 810624 j PDR ADOCK 05000458 7 IA ' 11 A PDR
1 of 2 Attachment 1 Enclosure 3 2.1.1 The only overhead handling system from which a load drop may result in damage to safe shutdown or decay heat removal equipment is the reactor building polar crane (RBPC). The equipmentofconcernwithregardtotgeRBPCarecontainment el 162'3") , hydroger. mixing fans unitcoolers(1HVR*UCIA,y;hydrogenrecombiners (1 CPM *FNIA,B; el 162'3") ,3 .
(1HCS*RBNRIA,B; el 186'3") , and various containment atmosphere monitoring isolation valves and their respective
?.ines. A polar crane load drop analysis is currently being performed and will be incorporated into the FSAR in a future amendment, as per FSAR Section 9.1.4.3.
, 2.1.2 The definition of heavy load, "a load whose-weight is greater
- than the combined weight of a single spent fuel assembly and f
its handling tool," as promulgated by NUREG-v612 precludes the consideration of: jib crane located adjacent to the containment fuel storage pool; channel handling boom; and various containment cranes including the refueling and auxiliary platforms and the fuel building's fuel handling platform. All cranes mentioned above are not expected to carry loads heavier than a spent fuel assembly. The fuel building bridge crane (FBBC,15 ten) and the spent fuel cash trolley (SFCT, 125 ten) carry no loads over safe shutdown or decay heat removal equipment and are prec'aded from consideration (the attached FSAR text and fi;ures elaborate).
The radwaste building overhead crane, turbine building cratie, and intake structure gantry crane do not carry heavy loads over safe shutdown or decay heat removal equipment.
4 2.1.3 (a) Attached ar figures locating spent fuel and safety-related equpment. Safe load paths will be defined pending the completion of the polar crane load drop analysis.
(b) Having defined safe load paths after due consideration of the results of the polar crane load drop analysis, measures ensuring observance of these paths will include operator training and written procedures.
1 Safety-related. equipment.
l 300RORGIML
2 of 2 (c) Loads handled by the RBPC will include:
Lifting Load .Egt. Device Egt.
Drywell Head 52 tons dryer / separator 4 tons strongback RPV Head 64 tons head /strongback 20 tons carousel dryer /
separator Steam Dryer 32 tons strongback 4 tons Steam Separator 45 tons dryer / separator 4 tons strongback Portable Refueling 20 tons (est.) undetermined Shield i
RPV Head Insula- 11 tons (est.) d ryer/sepa ra to r 4 tons tion & Support Frame strongback Procedures covering the handling of these heavy loads 4
will be written prior to fuel load.
(d) ANSI N14.6-1978 and ANSI B30.9-1971 do not pertain to the RBPC, the dryer / separator strongback, or the head /strongback carousel. Any use of slings will comply with ANSI B30.9-1971.
(e) Inspection, testing, and maintenance procedures will comply with Chapter 2-2 of ANSI B30.2-1976.
(f) The RBPC design includes the applicable design requirements of AWS D1.1, NEC Article 610, NEMA MG1-18.501 through MG1-18.518, and CMAA Specification No. 70 as a Service Class A-1 crane. The RBPC is designed to Seismic Category I requirements. 29CFR17, Part 1910.179. .
(including amendment dated July 1, 1973) and ANSI B30.2.0 are also incorporated into the crane design.
(g) The guidelines of ANSI B30.2-1976 will be followed, where applicable, with respect to operator training, qualification, and conduct.
I
i l
RBS FSAF to detect a low pool water level,'and adequate makeup water is available to assure that the fuel is not uncovered should a leak occur.
Sines the fuel storage racks are made of noncombustible mator:..a1 and are stored under water, there is no potential fire nazard. The large water volume also protects the spent fuel storage racks from potential pipe breaks and associated jet impingement leads.
9.1 2.3.3 Protection Features of Spent Fuel Storage facilities
- 1. The layout of the fuel handling areas around the fuel pool in the fuel building (Fiq. 1.2-20 and 1.2-22) is desioned such that the traversing of any heavy obiects over stored scent fuel is precluded. The scent fuel cask cool and the scent fuel cask trolley are chysically outside the boundaries of the fuel pool, with the only interconnection being a fuel transfer slot which is sealed by a watertight gate. Therefore, the spent fuel i cask handling crane, which passes over the cask storace area, cannot in any way be traversed over any cortion of the fuel pool.
(
In addition, the scent fuel cask trolley has a fixed main hoist. i.e., the hoist centerline is fixed between the runwav rails with no capability fcr traversing between the runways. This arrangement crecludes an off-center lowering of the spent fuel cask, and a vertical cask drop cannot impinge upon spent fuel racks.
, The fixed main hoist arrangement also makes a cask drop at an angle unlikely. The consequences of a cask drop, at an angle or vertically, may result in local yielding and possible rupture of the cask pool liner. The i watertignt gate which is in the sealing position during
- cask transfer operations prevents loss cf water from the spent fuel pool and no damage to the spent fuel results.
No satety-related equipment is located near the spent fuel cask pool or near the scent fuel cask handling area.
During all cask handling operations, the watertight gate is cicsed, thus restricting any water loss resulting l
from the consequences cf a cask drop accident and i postulated damage to the cask storage area. Even in the abnormal event of the gate being open during cask handling operations, breaching of the cask area liner due to a' cask drop would only lower the fuel pool water 9.1-14 _.
I l - - -
RBS FSAF level to the bottom of the fuel transfer slot. The design of the slot is such that this level is a sufficient height above the top of the spent fuel racks so as to maintain the stored < fuel totally submerged in water (Fig. 9.1-7) . Thus, the gate may be replaced and the fuel pool water level restored with no threat of damage to stored spent fuel bundles or to personnel.
- 2. Any high levels of radioactivity released in the fuel building are detected in the fuel building ventilation exhaust. Automatic controls are provided to divert thiJ exhaust through the fuel building charccal filtration system prior to release to the atmosphere. For further details see Section 9.4.2.
- 3. Administrative procedures require periodic sampling of the leak test system on the spent fuel pool liner.
Little cr no leakage is expected during ncrmal operating conditions.
Should ' sampling cf a drainage-monitoring tap indicate water leakage out of the spent fuel pool, the leakage ficw rate is determined at the sampling station using a measured container and stopwatch. Since the leak test system is divided into several zcnes and each tap k monitors drainage f rom one of these zcnes, the general lccation of the leak is determined. The introduction of pressurized air into the drainage-monitoring tap causes air bubbles to escape into the fuel pool water through the leaking seam, thus enabling precise location of the leak.
Secticn 9.1.2.1.1.1 discusses additional protection features for the spent fuel storage facility.
9.1.2.4 Inspection and Testing Bequirements 9.1.2.4.1 containment Fuel Storage Ins containment spent fuel storage racks require no periodic special testing or inspection for nuclear safety purposes.
9.1.2.4.2 Fuel Building Fuel storage A poison surveillance program will be conducted throughout the life of the spent fuel stcrage racks to ensure that the neutron-absorbing material is not deteriorating or altering in any way which would not be expected based cn the poison material qualification tests. Foison ccupons are situated in the pool in areas'that are expected to see the scst
' 9.1-15
. RBS FSAR C servicing equipment and address safety aspects of the design where applicable.
9.1.4.2.1 Spent Fuel Shipping Cask The design of the spent fuel shipping cask storage and handling facilities is based upon a cask with the approximate dimensions of 12 ft in diameter and 18 ft in length, with a maximum loaded weight of approximately 125 tons.
These large casks are shipped to and from the site on a specially designed rail car. Smaller casks are shipped on a flatbed trucx equipped with suitable cask hold-down devices and heat exchangers as required. Design of the casks and transport vehicles conform to the rules and regulations for packaging and transportation of radioactive materials (10CFR71 and 49CFR171-178) .
9.1.4.2.2 Cverhead Eridge Cranes 9.1.4.2.2.1 Spent Fuel Cask Trolley The arrangement of the spent fuel cask handling system is shown in Fig. 9.1-9.
The SFCT, located at the eastern end of the fuel building, is an overhead electric trolley with an auxiliary bridge.
The trolley (Fig. 9.1-10) travels in a north-south direction on a straight runway and houses the 125-ton main hoist whose hook position is fixed laterally at the midpoint of the trolley span. The auxiliary bridge consists of two wide flange double beam girders and is permanently fixed to the main trolley. The auxiliary bridge is not provided with a separate drive, but is driven hy means of the main trolley drive. The auxiliary trolley rails are mcunted on the centerlines of the auxiliary bridge girders and span their entire length. The auxiliary trolley houses the 15-ton auxiliary hoist and moves in a plane of travel perpendicular to the main runway.
The primary function of the main hoist and trolley is to upend and transfer the spent fuel shipping cask. For the performance of this function, the SFCT has been designed for service in the outside environment. It is used to service the transporting vehicle and the fuel transferring mechanism in the fuel transfer canal. The SFCT rails do not extend over any portion of the spent tuel pool; thus, the cask cannot be transported over the spent fuel.
km ,9.1-29 l
RBS FSAB The SFCT is operated from an operator's cab located beneath the main trolley and the auxiliary bridge. Controls for the main hoist and trolley, and auxiliary, hoist and trolley are fully magnetic,. reversible, with five steps of variable speed. The load control for the main hoist is provided by an eddy current control brake for hoisting and lowering motions. In addition to this electric brake, the main hoist has two independent shoe-type holding brake # which are automatically applied to the hoist motor shaft when the motor is de-energized. The main trolley rovement is controlled by a self-adjusting brake, hydraulically operated and actuated by a foot lever in the cab. Additionally, the main trolley is provided with an electric parking brake which engages only when the magnetic main line disconnect is open.
Due to the precise handling requirements for upending the spent fuel shipping cask, both the main hoist and main trciley are provided with an inching device. These devices provide a continuous maximum speed nct greater than 0.5 fpm regardless of load for both the main hoist and main trolley.
Each hoist is provided with limit switches to stop the hoist in its highest and icwent safe position. In addition, the main hoist is equipped with a slack cable limit switch to prevent hoisting and lcwering against a slack cable and with (
a centrifugal limit switch to apply the holding brakes in (,
the event of an overspeed. Each hoist is alsc provided with a load-limiting device that senses an overload on the hoist and stops the hoisting motion. This cutoff switch interrupts the hoisting motion, but does not affect the lowering circuit. Upon lowering and removing the load, the load-limiting device autcmatically resets and peraits hoisting operations to continue.
9.1.4.2.2.2 Fuel Building Bridge Crane The fuel building bridge crane is a welded box girder, overhead crane that travels in an east-west direction in the fuel building. The trolley houses the 15-ton hoisting assembly and travels laterally on its rails which are mounted on the centerlines of the girders (see Fig. 1. 2-21) .
The crane is controlled by a pendant control box suspended from the bridge and independent of the trcliey location.
The primary function of the bridge crane is the handling of new fuel between the receiving area and the new fuel inspection stand and/or the new fuel storage vault. During construction the crane rails extend over the spent fuel pool so that the crane can be used for placement of the high density fuel racks (HDFR). This extension is controlled with intericcks (physical blocks) after placement of the 9.1-30 -
- -. . _ . . ._ .. 2
t RBS FSAR
~
HDFNs so that the crane is prevented from crcssing over the ~
scent fuel pool.
controls for the bridge, hoist, and trolley motors are fully magnetic reversible with five steps of variable speed. The hoist is equipped with an eddy current control brake for hoisting and lowering motions. Accompanying the control trake are two independent holding brakes which are automatically applied to the hoist motor shaft when the motor is de-energized. Cne hciding trake is the dc-rectified type; the other a motor-mounted disc brake.
The bridge motor is equipped with an electric shoe trake that automatically and immediately is applied to the bridge
. motor shaft ir. the event of loss of power. The trolley traverse motor has an ac disc brake that respcnds to a loss of power in the same manner as the bridge brake.
9.1. 4. 2. 2. 3 Reactor Building Polar Crane The RDPC ccr.sists of two girders and a trolley. The crane, shown in Fig. 1.2-12, is of welded box girder construction with the girders ccnnected by end ties at the left and right ends of the girders. This bridge assembly rests on circular runway rails (el 214 ft 3 in) which provide for 360-deg 3 rotation of the crane girders. The runway rails are mounted
) on a circular support structure welded to the containment vessel. The trolley travels laterally on its rails mounted on the crant jirders and serves as the platterm for the main (100-ton) ano auxiliary (5-ton) hoisting mechanisms. The crane can te operated from either the bridge-mounted cab or frcm a pendant control suspended from the bridge.
The REPC is used to move the portable refueling shield, drywell head, reactor vessel head, steam dryer, steam separator, and reactor vessel head insulation and support frame. Curing the construction phase, the crane is used for the lif ting and placement of major machinery and equipment.
The REFC is not used for handling of fuel.
Controls for the bridge, auxiliary hoist, and trolley motors are fully magnetic reversible with five steps of variable speed. Controls for the main hoist are of the variable, stepless direct current static type. The vain hoist is provided with phase loss and phase reversal protection to prevent hoist brakes from being released until the motor field is energized and armature current is flowing. The load control for the auxiliary hoist is provided by eddy-current braking for hoisting and lowering motions. The main hoist has dynamic control with an euergency feature which automatically lowers the lead at a safe rate in the 9.1-31 1 ?003BRFIM
9 i=. .*
' " ?.:".::
..r. n'
~~..
.i'"" \
h, /..l :7{I' .
a J
7;;*. " .::"::'." .;"
~
. ." g\ , tj (f [/ 3.:."."
.. .y4 / . . . . ~ .
- ,.f"
. ,_ y~h% Q- .
~ '\ k- .- .
, =w
.,.3 ^~
ql}
- ~ . -
1
= j -D
?
=s' . ..
% .b' , . i -
--a.a
/ & f Q.,k .4.. gf Y"O ~f' p u.'
y */' *, w . ' " ' t y,\ ' k~ . ~
l- C
~'
. :::v. ,/ ,
' J ',
- h. A \
4 h' } ,'
4
.:: , .k. : y
, '..". 0 %
,2 yp, -(3p. /' d.~f
.{ . t 7'/
1 .m jun. ,_ _t g /
...x.-...
- r
. I n. 4, ,, ,,,., ,, . . . . . . .
//.. e .
<* a W 1a
~ .'
e
'a1 y h, *r. . .
3 ., ,
,- , , ~ .
i .'s
,\
.Z'T. .
/ iN(g
,,,d I
- 1L ;
j -[-)i
.-.; 7. g
.I 1 14 p
.____.-G t. __ r..
7~a~~.,,,,, g ' ;;*n 4 L_"" J 1; g_
tt . ;"n~. ' _ u- atti~r M~ =.t. m. ~~i a.V:yl . ;;;qr..jf
.p m~ ."= ..;
===ia
-.- j .L. 1 . . -
[h.. .!)l.r- ' ,
,J,
{_m e ,.-a iw. .
r
. , . . ,h ,:":t f- "-] n., C ;
g
' ,2A,,
, , i -
rJ , .
c I - - -
~,
= r*" ~ .;;;; ;.,r a o '; .J.. . , , , -'I. , w(L
i, q .. !
,t y'k2. .h.y.!; y .. L.. ~r -
i l u.
[ :--jp} s
't_ .c .i
&- _- ~ ~ - B a <;_
ji ( 3 .-} 3
~~-~
lq }:.-im .
u .. . -
- Qy . . . .
- -4
/
+ , I
~~*
.f.
Qg,., , ,.2, .
i
_...\ h.tch-
{ + ,,,,
!::p, ?
A'- .-.yT
g / . . . . .
g l
.,*L -- d
~-~*
~. $ . i
'11 1a
$ L -- _ . ~ m_. _N z { - _ pf[ / -- :f':--
.aa 1- y
. . ;, ;.,.~.-
\.\ y ' ~ ~ i.s. ' -
--; m,1-- r ~ ~ ~ - 3 .
p '* = *4..~7 --- ~=:-r-]V** _._,, ' -l. , I -a 'cp.. ,
9._ mJ 1.,- ,..<s
' .j .. . .-- efI- . .
~ ~ \ g..,V-*
, . 4...... i g';;*.'*. ;: A3 }. . - .. . . r.# , ""A* '
2
~~',.--.g:
'g ' yt. . u,i
. ,u=_ o r. e g -4[ - .- , .e q_
\,. .
, %,. i
/
9 ,em
- - j' ,-
~ */
-g[ g g
.i. N.--- < ga e n--
p ,, ' ***
.I. ,,/ ' .
7ri ,,'
-llj/;;1 ,
l y
,. 1 ,
1 y ,.g --
t r-
j$'/L .,- , .f.
e
* {f,- l-i p.. .p , f ],y , . . . , ,.;,; ,,; m.
,y}2 .
-)' - ,b / f ';. , $~ 2!~..; I
.i. ~.Vs 1
3, , .,
, f. ,-G .,
.. /
~.
... %,c, ..
1, .-m. .,
~}-~.-
e j.r,. ..
. :;;n
-~.-.~-
y
< - . . .. -./ .. . .
_ g \
, / ..... N U +-- .; .,
.- "x y
, , , , , , , , .. .ut ;;;,7;. ,
' ' ' ~...-r
~~ .d -
N.,.,,,,,,,, . . . . . . 1 O .< .. 4
===.' l 7.7 Q
m :gs
.,.. . . s. , : . : : :
me.a e s . .. sc=s esse FIGURE L2-9 gg g,,,,, GENERAL ARRANGEMENT .
REACTOR BUILDING
.,..g PLANS EL 16 2*-3 & 186' a %e 3 SOURCE = 12210* E M-2 A
- REV 6 RIVER BEND STATION FNAL SAFETY ANALYSS REPORT
) . -
4
\'7,.,,r- _ _ JW. -
M I ._ . , s--.~-
'l *j' p i,r -
'N N (
i . 's V D%
l'f ?
' ~~
/ EA - -
/- 'D 4hp . .
a/-~
h "di- s.
_,,,,,C. .-. -
3 , .,,,,a ::==- % y p ,,, ' '~. T*.* :"-
i N .- gg _; J.,
L. ;, '.l" :*J ,- .';." O~'~*' ~
^
}.. i_TJ. I ii ii il I! II II IiI 'l 1 *.".*e L F~{hf
^
.g
- 1,$$4/ UI'~ I - i-[i' U.L T" '~~ 1
! l; f1 - - - " - ~ ~ ~
m~ T 4
'2'----
l- -
l ~ ~ ~
.z - ;
'\ /
- - - - - . ,1 _,
i
{l -Z, ~ gI ff.t'f 4 ,k
{ & i ...dl .t,;;; '.a4' g '.2 * ~1 r h. :;:.',..: ,.h . , ) p(_
5 w - p- . ,, . .,y
,. .m 9,1 {,1, d.. .. . . .
;; g . .
g .
e
(
. \ ..
-,\ -
f - j r[ -i~.r _ lv, ,
,- uai i, a 4 ,
g-
, k_ . :--4; - - - p ::" .q i
...v. r; ; ,
'd
- . .. . .-t- -
-i
- - .~
' " ~ ' *
--~I O
- t d
+- -/
f .. . .~ ,
i,
. . . _ _ ~
.uesas. c 2 .' ..a s
-~
=*I f I [..- - - - -! , f . s* .! ,
' I -
-). rt ' '
e EC
.ny=
- ...e c 4 r -.. : 4 3 == rc ) . ,; .,)4 - s ,j , - .-- u a 4 cc, ,
~ tq";'- .
g' Y- _
- . . ..1,;:,
, a....
}. @
C.. .i, _.*
~
i r1. *-* * .-
4 **
-+ l 3 s . It ~. ,, s "l _ ,-
t,'...
4, ,
i
- g. , , 1
{ . .. /+_
. 3. .
1 .
. 1; i-4-
2 , . .
4 g y
=='~~N
& Y
~ ,
,)
. ... : =-
4 * *' { '~ "~~;&('< E d h cu u lG=.:..
. u I D
.u.."*" e. - i e.. . .
- q. _
J.
uy . .
P & ~ M,p.y&E '., -ann ,
, " ' " " ' " '3 L.CMWDM@,r . M v .. h - .r. ~~l
'~~* -<{l{s i . .
L' i
n;
..~
l 1 -
s I h}.
a s
(.
l . . . , . _ . -.,.::.::. / :
,l-: ",
k sf
~
w*
'[.--4IC.Jt' -
i . o) t'.=t -
- ' '..., d' II.' . . .
' ' - " ~ ' ' ' '
- - - - p> -. , . . . ,
.....t --
'mt i:
m..
j g '! ~ g Wc ! -l
( l 7
aj i +..
- t__
i g
- b gpp s r
_*-- f',, ,' d 4,. f tt ' gr_
f 4 m,,,, = - +
'd'/ _ . . <
u , . ,
> n-ai a '6. . e ~ - a 1y y.lf1 PITY e
- -"! -- =.:. L. . , ' . --. .n .
;;;;n::, - *, t--- -
l t
Y,,f 16'. * * * ,; .._ , - ' - ,' ' 3".
{
- lI.: f '(y1, {u- 4 j~~ -
m .-
t^. *'"' 3 t,7, , --
[ --'-*;,
- j. ,j . y-4 :,, 3 y. 'f . .' *
3:J -
c... '
y .. ,. ' i. g l - '
[
g ,
. d , .. ~ _ , , , , c 7 ,_,
l
/m... _ . _ . _ _ . _ . _ . _ . - - - -
FIGURE 1 2-12 g e.a . GENERAL ARRANGEMENT REACTOR BUILDING -
j SECTIONS 1-1 & 2-2 h
C)
SOURCE:12210, EM- 2D.REV 6 RIVER BEND STATION ft4AL SAFELY ANALYSIS HEPORT
> 3 : y. -
f , a u .r p. 9 a I '
I
]'
l'q 7 l
I' i
. . 'J jj i r'; ,
i
._i --
t" ' [N Q
... .. I .gn O :
i -
~
u A.'
e -_lir _. _.7 t!
s p
.~g tda -U'hitf;=.z....<
.s...- .
-. -}* '
.6 9 t' r; -
--f- 1 i- --
' W *--* 8 '
{~ }q(.)[
g . ., l! fL.'L:,h'-}
q% - . 1. - -+ .
7.-
4 y--- 7 i.
#= 'il
[lk ll1 ll? '
gg e _
i i
_..'1
~rz a' I
, j ,
.p,_Iani tt j ame e at- '*"'., m.. w.
{ ,, i ea .
dm i ....
l 4 ;. -.
\ ' \ :i2
("*""' .. (D.
J.
A h.k I~ I.h. .g \ '
ow o 1
f,,y es a
,.,s,, r)e]((q[;olM l t k* db.O 4 b \- s _.
../l,,
j'
"- y g? f ! ?-- --. %
s / m ,, -; - JP' q
-" .. y
- c. .T.N. g..,.
.m. I .7 a w-. --/
, ' '- 7' 7 kI v'/
~
c)I q'- i ya c
- .1'.P t y\'*
i G. q \ i.,:g---
v L. (//
pr I @L
(,.ii=x%[- .
M.J*. 7.T. sn a
u i
a.. ,p =,-
,f
--n ,u . . .
yll L_
. - ,- I 1 -
Q' r -
Q/ I 1;
J r.1 iT } -
h
'i t II W d.~ - 4** .:. t. 4. W
' t- *_ .
- a. ! L cJ'- - }' t
, .~ .
I L.. 'J .
spm :3 SJ_ ' (m2- d.: . L.)g".
}.R x. D' .',j q,.
g
- w. <
.g..o-----.-,,
g,y . . .
._ i i l r , --
T :
.- < _ . .. .h,,,{u.-~
"5 .s **7','
't- n p: .6.*. f/,
,B
- f-[
.: toe-.<'. . ,c
,'. " - n **
ch I $7 C --- .'
,,o s t. 4, "-. . M.
"", .7.
'"- =
~~.b~ H:
l 9 --
\'
i.y
,Q t
*P t
1 7
h-( r[ g;,+- 7 ' rl . r ' -vw5,b}3 *@gf g r
. . . . . . . . f ;. <q 2
- .r:2.'= :.rr I. ,
i c } Py .
16 I --_, 4..,\.\3 .
.:-.,' x .- . - - -
g , _ . , b, . [3 .
;, . V if -. . . . , .. ise
. . - },...
t.
=.. . . . _rj. o gjpr ..
{l.r h,i
. .: 11.h,..
li y y y' g, 9 y'(s.Y '" ~
v '[. [ .j. l l} g, "
1 .* ' h . ~ . # l g [..ju{f.M.? . ' ., _ te-y , *.,*.
; rr ..'
j .. . {1 w .j .. ..., ._. .
g
%,b.y .. . .j y. -, ; <- . :. . .t L N ,
g t*-** ! ['
f z w.,
i-m --
,, ,. g ~ 4 j[, '[,[ie ; 7 1 , ,W4 4 t.
.gm, r. :-.. e j
--aTl j i
.p%.
.' . 'i !
- r. -
..ap ,.-j
~
~
t._ ;. '. . .6 .':-: .: -< ' . . .
.M,d . . . ,.
.f _- --
i ty ,F, pg ;4 '
i l '68 ***'"'
- Y- ~-%j - -.,. ,- Nis,a .Ft .' , yg.
t
- ,, 7 ,,-
, i1 ', ,..
. a tt ; ] 3 .,. @ .
- .:, = . ji
.w->> .I I
i - -- . _; y.-_ w e FOURE 12 20 1 1 l
.l l .
I r.m? , .
i
! _ i: :-' } _ . . _ - -
- '~
GENERAL ARHANGEMENT -
i *j i
~ ~ ~
FUEL BUILDt4G
.wr . -~
n.. e. o RIVER BEND STATION FINAL SAFETY ANALYSIS REPORT
)
e e o e ce s ce mm g>
4 s e a mr-1 S
I.. .__ w.u~
._ ~._ \
,. r~"//~ . .
-l . -
6 . .- - ment =: 5==K , p =* w . . i_wpt' y -
3 i
e
,}[-_
~ - -
1- - -"
. t_ g ... m l;
, .w.
l /
g :. .
>} . .m - ,. . g f --
g e ,
. , . . 9.. . .,. r 3; If {_w p%~'gO-7 @3; . _ . . .
r
\ -~
w.
zt_ 9 ., - . . . ,
. --% -=-y W, . . . ... , r i. . .. -
g ta k' "-@v..y
_s..
R(
7., c::-- g,,.,2..
0-- 25= . . .T ~ ; ' $ : r, -, ,
"I 3 0 ,' i.7.** ... l }
9 - - .. _. -
l l
L
- a. ,.,-];j -j -
. 9 -- --- -- - _-
[ }
6 --
g~ . _ . _ . _
' i-i
--- [ gLa-y!}._[ } .. ,l. J_._.1
'= 7. ; -
UlI{f~
~
N*[' l*
, -.s.
~ * * *
, 3:,t ; e-
- - pu
.1.4 "". T. T. * ./,T t g .
__. s -
7'
,..._-. .- . --; -._- . ._,~ .
. f.: M - I .. . I il E13:
(l st--
.LT _ , a t~. J
['~) j.{'
[ .-....,-
-t5 A
-.J.,.,- ,
l * 'en e
$D sans==*'**
.. ~ .
,* .' "* ' 7****"' ..; ; ; ;
()
- J*
statt eear
"[ , , FIGURE 12-21
""""'**~0' GENE 81AL ARRANGEMENT I '
FUEL DUILDING RIVER BEND STATION j FINAL SAFETY ANALYSIS REPORT
'i 1
e s, o -
o 99 , o .
.j- 7 .pi 7 ,
i :
- 1i m.: _ . 1 j i :
1'4 f ~ -~ ~
. J :.ca . i l ,. . .. . .
! I f
'Wt t- 11 l
. . .- .~.jp @g<
t..: _2 4 ..
J). ...
t As
<*x ef' * -
! tj .ir.
i wr1 1 <
q rc ^ :2-
; q p=s,1. 2' i
i r. .=-g, ' -.q
. .. IdI T f_ _l M3 H I -
s-.
[ !
s *3 h Yv. _ap , p. rw u
..: _'su j .h+l+A m .s r+ w -
}
n i J ,
T ', .h E,f .O c.' ,11 h Y i., ';+- '4 =
C"'lr,b .y J A j- I' .-
7 b,"I.N';h.,f'. a.. w; i? p3 !
l .I' w-At h,, ; $ g 3 331; *I ?
c3/4 .s -
a %g 2id. , ,
na ,
, Q M ,y
. . .- t s . , .
f.
;3 :_
if ,,e u?, } . ig- -
ul e w,yQ>Jr;.' .j.
+
, ,. / '
m.
-7 , l ..
~v
%,.s.#
,N -
gF m y '
.j.
J .
l
- -- - l"' a; ' _ -J<.,i) .
.. L I, e, at
,i
=> .4 1 / l6 I ;: ,
i
@ i.. E1
._1:.
- ii l , '! '
. . j ". ; _ _. -
[ :* , _ .
( -- r --- - l 7
.a r.:-
} )i -}
g g; - .
y y e. . . .. ..' .. ..
I . I '
' ' l . ^._
r
'I j
t-:.
,. *i
. .r.. .
_r; . . . .
( < a
{sT ,-
Tr rr r 41 e_--
.. 7
;. ;iii4 - - - - - - - ~ -
_.. l ]
iXfiM }j y
~~
J
+ -
s=
2 -. ,
-3
,J __ _
l qr 3
~~ '~' '
leN:W i')I b !il h.
~~j- -i-a-g, . .. - - - -- 4 , ,- ;. it, t 1 x !.
L- --
F--
!p ! LTt i I
~[ r44 y . .:
L.. f' 7 x jh' "'*--w
- . . . 4.
., :. I Um
.s..
e-.-.-
, ff a- m . " l Le}. ,
I 7, Q f I '_ ' V l l l~ 7
. . _ , t
~
L $1 - 3 b Y ll,
- . .; \
Y.
.c
-t,; a, Jli~
y I
7 L
t =
Y-
-n i.'
m N -
_ d . I ' 'i i - r._ [ ,?
., 3 .i.'
g.j8 --
'!in 4,- !'2 )) ,1 1 J .~.= , n
. 4-- t .i : ,O .. r -- ~
'd ;3 ' , [ ,j ; 71
= "l' q ,,,g ,{
7
. e[, ! I .L'.! 'h' :
'l
) FIGURE 12-22 I- i
'g*' d.,,1-h
, i...
k'- 'a 1, s:l II iei
.- A' -
,j l jlJ'i 1
,j"l GENERAL ARRANGEMENT
- .. _! FUEL BUILDING
[
RIVER BEND STATION Fr4AL SAFETY ANALYSIS REPORT I
e
""' i c.',.Q ~ ~ , ", ,,. " ;."-- ;;~ :- - ~~
"**. ~~ < T"' ' 'q-..
%-rMas g my v =1n '% rn e--n_' =e- i==
* - y k_,. _f 47 wy i
.c m
- 7. 3 ipic :: .xxg :a. -
~s 6 e; .
* ""* ~
a ** * ' . . . .
3 s
) " ' ,;- j r;'
7.O ** .g p_ ~ ,:j Lqx t
w
,1 ;
- n. .< _. .: *A j} [. 1..~.Q.
,.y j
_r j -
l ps .......
7- /
>j 1
g 3
Q,ps, .r 4 a g j 3- 7
; q_- -.ya q_ .+ ,_hr 1).
c.
q==
r - "
b g,
3,
= a;.
"~~""
.. q) _
~
g_q ,nf
,,y ,7 ,,
gfr.--
p r
h Lc... - - - - - - -
HJ 1 ,"
4 r
=. F.-Fi - .- _ ,q / g. c k,, ,
. i
- ,=, . n _ ${p e.
y -- - <o, m .. .. _ ,,,,.y.
r 3
. e.m_.- ,
l
.,. ag a { l -
"'.=eT..'*vi e i
gt. w.F-' ;-*,,-f
/ u%
i f
* - " =
- o.pJ _ . I a,,
'.t ,.
%. f----) , . .
~
l
**********-- J q_l ,,-...u t
.a. c e 4 .- /
ij i
; "~ ' () h .,,,
m .y cL L.
== v J Ql&
{e'.. g rx g_ . . ~ , gy-1
-wp , . , g. m- , - E ,) . ____ _ -p.< gd,gygg-- , ~. , y i ,
, , , , _. _. I , - + '. ee.- ..% =L p=- = *a u ~ .- I --.-a .1 ,. -
y' l"./ a' *.gel de ma g,, g f,.
t***! " ** *:
- g. . v, :, .
. . c .. n Q .
%",,; - " l y
. P l'*
-rf f/ ~. y! e .) *
" ' " ' , ' , . * , ' ' ' % '" y* 8 T. * (' a.= m aa r l[ l
,,i, P_ .
- _. . . ,o, ; r, :
y fC .,
j -m. . . - . :
M]
. , ~ ,
, g l ta .
~h, O E I.- 7'1 M,#.3 e'
..)
^ ~~
Ir ". !'.Z -
O t.; .
. ,1 .,
[-'
1 a l2v' Y
.23. .. An . .m. pio
*b\ e _
q' ,- .. .v
,a- w. \
l .- .. <;
u s e, . -
l * ~ - s c, l
\ 3. s .
- ~ .. ,-.
n' :
j.3j f 1 ., ub., l, :
A. s . i -
i .---,;.,.. A : ,.
_ .. . }s -
(.. u .c
- t. d
,e'
, a, I
.L
[ _.- -
l
[ ;gw ,
{'l ' . 'J. l ' i i Y! '
. . , - 4 / .e ll l; - a=
/ g. h I
pn - -
e ., , . ]' i .n( { .ig a,ht- 41 =a,,,,,.=,,,,,,,=
slpS
}L 'f .=6 A [ W' o'-@ g f, m - ..,
' q?k. g. n M q M 8.._.3 a..?_A+. n.In , < . < ._.. 4.. a+ ._
n.7f..~.~. f
. A. , , ..-.. ..
. = - . -a. . mg,. a ..
R S-S 6-6
'i$s{edY Q FGURE 12-23 OE:3 GENERAL ARRANGEMENT FUEL BUILDING d RIVER BEND STATION g FNAL SAFETY ANALYSIS REPORT M.'.'.
DC::=
r-- ,*., . 1;
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _}}