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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7681999-10-19019 October 1999 Forwards Insp Rept 50-458/99-12 on 990822-1002.Four Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy RBG-45125, Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams1999-10-18018 October 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams ML20217J3751999-10-15015 October 1999 Informs That Applicable Portions of NEDC-32778P, Safety Analysis Rept for River Bend 5% Power Uprate, Marked as Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) IR 05000458/19990071999-10-0505 October 1999 Refers to Util Ltr Re Apparent Violations Described in Insp Rept 50-458/99-07 Issued on 990804 & Forwards Nov.Insp Described Two Apparent Violations Related to River Bend Station Division I EDG RBG-45123, Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required1999-09-30030 September 1999 Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required RBG-45124, Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl1999-09-24024 September 1999 Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl RBG-45122, Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-471999-09-23023 September 1999 Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-47 RBG-45113, Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp1999-09-21021 September 1999 Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp ML20212D8901999-09-16016 September 1999 Discusses 6 Month Review of Plant Midcycle Ppr.Advises of Plans for Future Insp Activities.Forwards Historical Listing of Plant Issues,Referred to as PIM ML20216F7881999-09-15015 September 1999 Forwards Insp Rept 50-458/99-10 on 990830-990903.No Violations Noted.Insp Covered Licensed Operators Requalification Training Program & Observation of Requalification Activities 05000458/LER-1998-003, Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents1999-09-0909 September 1999 Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents ML20211Q7721999-09-0909 September 1999 Expresses Appreciation for ,In Response to NRC 990702 Re Denial of Notice of Violation Cited in Concerning Insp Rept 50-458/98-16.Reply Found to Be Responsive to Concerns Raised in NOV RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted1999-09-0808 September 1999 Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted ML20211Q3921999-09-0808 September 1999 Forwards Insp Rept 50-458/99-08 on 990711-0821.One Violation Being Treated as Noncited Violation ML20211Q5541999-09-0808 September 1999 Discusses Meeting Conducted on 990830 in St Francisville,La Re Overall Performance Issues During 990403-0703 Refueling/ Maintenance Outage.Due to Proprietary Nature of Some Subject Matters,Meeting Closed to Public.Attendance List Encl ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) RBG-45095, Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status1999-09-0707 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status RBG-45097, Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves1999-08-31031 August 1999 Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves RBG-45094, Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation1999-08-25025 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation ML20211E2071999-08-23023 August 1999 Discusses Insp Rept 50-458/99-07 in Which 2 Violations Were Identified & Being Considered for Escalated Enforcement Action.Response Should Be Submitted Under Oath or Affirmation ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 RBG-45093, Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept1999-08-17017 August 1999 Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept ML20211A9291999-08-17017 August 1999 Forwards Insp Rept 50-458/99-11 on 990719-23.Areas Examined Included Portions of Licensee Physical Security Program. No Violations Noted ML20210T8881999-08-16016 August 1999 Forwards Replacement Pages 9-18 for Insp Rept 50-458/99-09, Issued on 990730 IR 05000458/19980101999-08-13013 August 1999 Forwards Summary of 990805 Mgt Meeting with Licensee in Arlington,Tx Re Radiological Control Problems Noted in Insp Repts 50-458/98-10 & 50-458/99-04.With Attendance List & Licensee Presentation ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210U3751999-08-12012 August 1999 Informs That Info Contained in Presentation, River Bend Station Fuel Recovery Project,Dtd 990622, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20210Q7691999-08-11011 August 1999 Forwards Request for Addl Info Re Licensee River Bend Individual Plant Exam External Events,Under GL 88-20,suppl 4,dtd 910628 ML20210R4591999-08-10010 August 1999 Ack Receipt of Which Transmitted Plant Emergency Plan,Rev 20 Under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required,Based on Determination That Changes Does Not Decrease Effectiveness of EP ML20210N1641999-08-0404 August 1999 Forwards Insp Rept 50-458/99-07 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210K4641999-08-0303 August 1999 Forwards SE Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Power-Operated Gate Valves, Issued on 950817 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K1351999-07-30030 July 1999 Forwards Insp Rept 50-458/99-09 on 990510-28 with in-office Insp Until 990701.Three Violations Being Treated as Noncited Violations ML20210J9691999-07-30030 July 1999 Discusses 990719 Meeting with Util in Arlington,Tx Re Region IV Staff Findings of Root Cause Investigation Into Fuel Cladding Failures That Occurred During Recent Cycle 8 Operation.List of Attendees & Organization Chart Encl RBG-45072, Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL1999-07-23023 July 1999 Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL ML20210E9001999-07-23023 July 1999 Informs That as Result of Staff Review of Licensee Responses to GL 92-01,rev 1,Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 RBG-45073, Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl1999-07-20020 July 1999 Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl RBG-45071, Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl1999-07-19019 July 1999 Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl 05000458/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 11999-07-15015 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 1 ML20196L0501999-07-0606 July 1999 Informs That NRC Insp Rept 50-458/99-03 Issued on 990519 with Errors in Tracking Numbers Assigned to Seven Noncited Violations & Error Re Actual Location of SRO During Refueling Activities.Revised Pages 2 & 4 Encl ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl ML20196K6851999-06-30030 June 1999 Ack Receipt of & Denial of NOV in Response to Transmitting NOV & Insp Rept 50-458/98-16.Listed Info Documents Results of Review of Response to Violation Re fire-induced Circuit Faults ML20196K0671999-06-30030 June 1999 Forwards Insp Rept 50-458/99-04 on 990412-16 & 28-29.Five Violations of NRC Requirements Occurred & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy.Meeting Scheduled for 990726 RBG-45048, Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept1999-06-29029 June 1999 Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept RBG-45047, Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output1999-06-29029 June 1999 Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output ML20196H5171999-06-21021 June 1999 Requests Withholding of Info Being Presented in Meeting of Entergy,General Electric & NRC Staff.Licensee Requested Meeting with NRC to Present Info on Recent Anomalous Conditions Found During Insp of Fuel Bundles.W/Affidavit 05000458/LER-1999-012, Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form1999-06-21021 June 1999 Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form RBG-45035, Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld1999-06-21021 June 1999 Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld ML20196E0601999-06-18018 June 1999 Forwards Insp Rept 50-458/99-05 on 990418-29.Four Violations Identified & Being Treated as Noncited Violations 05000458/LER-1999-011, Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-06-0909 June 1999 Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARRBG-45125, Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams1999-10-18018 October 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams RBG-45123, Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required1999-09-30030 September 1999 Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required RBG-45124, Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl1999-09-24024 September 1999 Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl RBG-45122, Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-471999-09-23023 September 1999 Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-47 RBG-45113, Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp1999-09-21021 September 1999 Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp 05000458/LER-1998-003, Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents1999-09-0909 September 1999 Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted1999-09-0808 September 1999 Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted RBG-45095, Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status1999-09-0707 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) RBG-45097, Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves1999-08-31031 August 1999 Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves RBG-45094, Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation1999-08-25025 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 RBG-45093, Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept1999-08-17017 August 1999 Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept RBG-45072, Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL1999-07-23023 July 1999 Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL RBG-45073, Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl1999-07-20020 July 1999 Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl RBG-45071, Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl1999-07-19019 July 1999 Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl 05000458/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 11999-07-15015 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 1 ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl RBG-45047, Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output1999-06-29029 June 1999 Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output RBG-45048, Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept1999-06-29029 June 1999 Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept ML20196H5171999-06-21021 June 1999 Requests Withholding of Info Being Presented in Meeting of Entergy,General Electric & NRC Staff.Licensee Requested Meeting with NRC to Present Info on Recent Anomalous Conditions Found During Insp of Fuel Bundles.W/Affidavit RBG-45035, Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld1999-06-21021 June 1999 Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld 05000458/LER-1999-012, Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form1999-06-21021 June 1999 Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form 05000458/LER-1999-011, Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-06-0909 June 1999 Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl 05000458/LER-1999-010, Forwards LER 99-010-00 for River Bend Station,Unit 1 IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-05-28028 May 1999 Forwards LER 99-010-00 for River Bend Station,Unit 1 IAW 10CFR50.73.Commitments Identified in Rept,Encl RBG-45021, Informs That Cycle 9 Operation Will Remain within MCPR Safety Limits Approved in Amend 105 to TS Issued by NRC in1999-05-26026 May 1999 Informs That Cycle 9 Operation Will Remain within MCPR Safety Limits Approved in Amend 105 to TS Issued by NRC in 05000458/LER-1999-009, Forwards LER 99-009-00 IAW 10CFR50.73.Commitments Contained in Ltr Are Identified on Commitment Identification Form1999-05-24024 May 1999 Forwards LER 99-009-00 IAW 10CFR50.73.Commitments Contained in Ltr Are Identified on Commitment Identification Form RBG-45017, Informs NRC of Addition of ASME Boiler & Pressure Vessel Code,Section Xi,Code Case N-496-1 to RBS Inservice Insp Program.Commitment Made by Util,Encl1999-05-14014 May 1999 Informs NRC of Addition of ASME Boiler & Pressure Vessel Code,Section Xi,Code Case N-496-1 to RBS Inservice Insp Program.Commitment Made by Util,Encl ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 05000458/LER-1999-007, Forwards LER 99-007-00 IAW 10CFR50.73.Commitments Identified in LER Are Noted in Attachment 11999-05-10010 May 1999 Forwards LER 99-007-00 IAW 10CFR50.73.Commitments Identified in LER Are Noted in Attachment 1 05000458/LER-1999-006, Forwards LER 99-006-00 Re Unplanned Automatic Standby Svc Water Initiation,Due to Procedure Inadequacy.Commitments Identified in Rept Noted in Attachment 11999-05-0606 May 1999 Forwards LER 99-006-00 Re Unplanned Automatic Standby Svc Water Initiation,Due to Procedure Inadequacy.Commitments Identified in Rept Noted in Attachment 1 05000458/LER-1999-005, Forwards LER 99-005-00 IAW 10CFR50.73(a)(2)(i).Commitments Identified in LER Are Noted in Attachment 11999-05-0303 May 1999 Forwards LER 99-005-00 IAW 10CFR50.73(a)(2)(i).Commitments Identified in LER Are Noted in Attachment 1 RBG-44993, Forwards RBS Annual Individual Monitoring Rept for Jan-Dec 1998,per Requirements of 10CFR20.2206(b).File Info Listed. Without Encl1999-04-30030 April 1999 Forwards RBS Annual Individual Monitoring Rept for Jan-Dec 1998,per Requirements of 10CFR20.2206(b).File Info Listed. Without Encl RBG-44998, Informs of Missing Documentation Re Examination Results Reported in RBS Owners Activity Report Forms Submitted to NRC on 9802241999-04-30030 April 1999 Informs of Missing Documentation Re Examination Results Reported in RBS Owners Activity Report Forms Submitted to NRC on 980224 ML20206E7811999-04-29029 April 1999 Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested 05000458/LER-1999-003, Forwards LER 99-003-00,per 10CFR50.73.Commitments Identified in Rept Are Noted in Attachment 11999-04-23023 April 1999 Forwards LER 99-003-00,per 10CFR50.73.Commitments Identified in Rept Are Noted in Attachment 1 RBG-44968, Submits Addl Info Re 981008 LAR 1998-02 Re Implementation of Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long- Term Solution.Clarifies Certain Aspects of Proposed Ts,Per 990406 Telcon with NRC1999-04-15015 April 1999 Submits Addl Info Re 981008 LAR 1998-02 Re Implementation of Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long- Term Solution.Clarifies Certain Aspects of Proposed Ts,Per 990406 Telcon with NRC RBG-44965, Responds to 990324 Telcon RAI Re SLMCPR Calculation Method for RBS Cycle 9 Slmcpr,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits. Proposed TS Pages, Encl1999-04-0808 April 1999 Responds to 990324 Telcon RAI Re SLMCPR Calculation Method for RBS Cycle 9 Slmcpr,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits. Proposed TS Pages, Encl RBG-44959, Withdraws 981120 LAR 1998-20,allowing Adjusting Control Pattern for Plant Startup If Outage Had Occurred Before Planned Refueling Outage.No Plant Outage Was Conducted & Plant Is Now in Eighth Refueling Outage1999-04-0808 April 1999 Withdraws 981120 LAR 1998-20,allowing Adjusting Control Pattern for Plant Startup If Outage Had Occurred Before Planned Refueling Outage.No Plant Outage Was Conducted & Plant Is Now in Eighth Refueling Outage ML20205F1781999-03-31031 March 1999 Forwards Consolidated Entergy Submittal to Document Primary & Excess Property Damage Insurance Coverage for Nuclear Sites of Entergy Operations,Inc,Per 10CFR50.54(w)(3) RBG-44939, Forwards Rbs,Unit 1 Annual Occupational Radiation Exposure Rept for 1998, Per TS 5.6.1.Rept Consists of Tabulation of Exposure for Personnel Receiving Exposures Greater than 100 Mrem Per Yr1999-03-31031 March 1999 Forwards Rbs,Unit 1 Annual Occupational Radiation Exposure Rept for 1998, Per TS 5.6.1.Rept Consists of Tabulation of Exposure for Personnel Receiving Exposures Greater than 100 Mrem Per Yr ML20196K7101999-03-26026 March 1999 Submits Reporting & Recordkeeping for Decommissioning Planning,Per 10CFR50.75(f)(1) RBG-44899, Provides Notification of Termination of Licensed Operator, AA Rouchon,License OP-42416-1,due to Resignation.Reactor Operator License Data,Listed1999-03-25025 March 1999 Provides Notification of Termination of Licensed Operator, AA Rouchon,License OP-42416-1,due to Resignation.Reactor Operator License Data,Listed ML20204G8701999-03-15015 March 1999 Responds to NOV Described in NRC Correspondance to Util ,expressing Disappointment in NRC Determination That AD Wells Deliberately Provided Incomplete & Inaccurate Info to NRC During Meeting on 971015 RBG-44925, Responds to NRC Re Violations Noted in Investigation Rept 4-97-059.Corrective Actions: Mgt Expectations for Communicating with NRC Issued to Site Personnel on 980212,by RBS Vice President,Operations1999-03-15015 March 1999 Responds to NRC Re Violations Noted in Investigation Rept 4-97-059.Corrective Actions: Mgt Expectations for Communicating with NRC Issued to Site Personnel on 980212,by RBS Vice President,Operations RBG-44924, Informs That Util Response to NOV Re Investigation Rept 4-97-059,will Be Issued by 990315,as Extended by NRC Ltr .Encl Check for $55,000 Is for Payment of Civil Penalty IAW Instructions in .Without Check1999-03-0505 March 1999 Informs That Util Response to NOV Re Investigation Rept 4-97-059,will Be Issued by 990315,as Extended by NRC Ltr .Encl Check for $55,000 Is for Payment of Civil Penalty IAW Instructions in .Without Check RBG-44912, Responds to Violations Noted in Insp Rept 50-458/98-13. Corrective Actions:Matls & Training Were Provided to Expedite Implementation of Existing Procedural Guidance to Supply Compressed Air1999-03-0303 March 1999 Responds to Violations Noted in Insp Rept 50-458/98-13. Corrective Actions:Matls & Training Were Provided to Expedite Implementation of Existing Procedural Guidance to Supply Compressed Air RBG-44904, Informs NRC of Date Change Re Commitment Made in Response to NOV 50-458/98-05-01.New Commitment Date 9912161999-02-25025 February 1999 Informs NRC of Date Change Re Commitment Made in Response to NOV 50-458/98-05-01.New Commitment Date 991216 RBG-44384, Submits Response to Fuel Cladding Defect Issues Raised in 10CFR2.206 Petition.Clear Technical Basis Exists in Info Provided by River Bend Station to Deny Petition1999-02-11011 February 1999 Submits Response to Fuel Cladding Defect Issues Raised in 10CFR2.206 Petition.Clear Technical Basis Exists in Info Provided by River Bend Station to Deny Petition ML20203C4201999-01-25025 January 1999 Submits Denial of NRC Request for Advance Info Re Concerns Raised by Ucs in 10CFR2.206 Petitions on River Bend & Perry Plants.Petitioners Were Not Required to Provide NRC with Info in Advance of Informal Public Hearings 1999-09-09
[Table view] Category:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC
MONTHYEARML20244B0011989-03-0808 March 1989 Lists Facts to Consider for Action to Fix or Close GE Reactors Once & for All ML20205D2541988-10-17017 October 1988 Comments on Failure of Rev 1 to Updated SAR for Facility to Comply w/10CFR50.71(e)(5).Corrective Action Re Potential Jeopardy of Intent & Usefulness of Rept Requested ML20150F9251988-02-21021 February 1988 FOIA Request for All Documents Re Insp Rept 50-458/87-30 Conducted During Dec 1987 ML20213C7931986-09-12012 September 1986 FOIA Request for Documents Re Western Piping & Engineering Pipe Clamps Furnished to Perry 1 & 2 & Van Meter 820607, 0721,0818 & 840125 Complaints to NRC Re Design Deficiencies at River Bend ML20211C5631986-09-12012 September 1986 FOIA Request for Three Classes of Documents Re Use of Western Piping & Engineering Clamps at Perry Nuclear Power Plant & All Complaints/Correspondence Involving Deficiency Complaint at River Bend Plant ML20214D5661986-08-30030 August 1986 Suppls 850717 FOIA Request for Addl Info Re Tech Specs & for Documents Re Disposition &/Or Resolution of Staff Concerns & Request for Investigation ML20141N2611985-10-0101 October 1985 FOIA Request for Documents Exchanged Between Gulf States Utils Board of Directors & NRC Since 1978 ML20134P1001985-08-31031 August 1985 Expresses Concern Re Testing of Newly Installed Emergency Siren Notification Sys at Facility.Transcript of West Feliciana Parish Police Jury 850611 Meeting Encl ML20134P2371985-07-17017 July 1985 FOIA Request for All Info Re Tech Specs for Facility ML20134L4791985-07-17017 July 1985 FOIA Request for Biographical Data on Region III Resident Inspector,H Livermore & SALPs for Listed Plants for Specified Time Frames ML20096C5821984-05-30030 May 1984 Alleges Poor Traceability of Matl Used in Thermocouple Extension Wire Conductors,Faulty Testing of Onsite Cable Repairs,Nonqualification of Replacement Cable Trays & Lack of Adequate Flood Protection for Critical Components ML20081B6951983-09-0101 September 1983 Appeals Partial Denial of FOIA Request for Four Categories of Info Re Caseload Forecast Panel 830330-31 Meeting & Site Visit ML19339A9621980-10-0808 October 1980 FOIA Request for Repts & Correspondence Re Choice & Actuality of Facility Becoming BWR ML19351D5321980-10-0606 October 1980 Responds to 800905 Ltr Re Halt of Const at Facility.Forwards Comments from Concerned Individual Regarding Suspension of Const at Facility ML19320B7081980-06-15015 June 1980 FOIA Request for Documents Re Three Mar 1980 Violations Occurring at Facility ML20147D8231978-11-0101 November 1978 Forwards Stone & Webster Progress Rept.Expresses Concern Re Alligator Bayou Study & NRC Site Audit 1989-03-08
[Table view] |
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4 Il Oil Of Concensso ScismTisTs October 6, 1980 Victor Stello, Jr., Director Office of Inspection E.nd Enforcsment U.S. Nuclear Regulatory Commission i
Washington, D.C. 20555 i
Dear Mr. Stello:
This is in response to your letter cf September 5, 1980 concerning the River Bend facility which UCS received on September 10, 1980. You will recall that on July 21, 1980, UCS,' acting on behalf of an individual who wishes to remain l anonymous, requested a halt of construction at the River Bend '
facility.
As discussed by telephone with member of your staff on September 2, 1980, we sent a copy of Instiction Report 80-08 to the individual on September 12, 1980. Ths individual's ,
comments are enclosed exactly as received excipt that they H have been retyped and information that could lead to identi-fication of the individual has been deleted.
Some of the comments contain information a tsic6 NRC's jurisdiction. Therefore, we are sending a copy t) Mr. Stephen Irving of the Public Law Utilities Group in Batol Rouge, Louisiana so that he may bring these matters to tue attention of the Louisiana Public Utilities Commission if he believes such action is appropriate.
UCS wishes to add to the individual's comments the following three points:
First, your stated basis for declining to suspend construction at the River Bend facility is completely at odds with the nature of the licensing process and makes a nullity of the requirement )
that applicants demonstrate a strong-quality assurance program as a requisite to issuance of a construction permit. In your l
letter of August 18, 1980, you state that " suspension of cor.- g l struction is not warranted at this time as this project is in 0 its very early stages of construction." " Consequently, the Yl\ t, f ,
allegations questioning the adequacy of certain construction '
practices do not presently bear on public health and safety as j i Il 7 23 4 ','4 5 5 A ,' i+:: A #" w
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operation of'the facility is yet some-years away." Extens' ton i 4
of that " logic" would lead to the conclusion that there is i no need for any safety review by NRC at the construction permit e stage. However, the principal purpose of reviewing an applicant's quality assurance program prior to_CP issuance is to ensure that l 4
the plant will be constructed properly. i 1
i As you are certainly aware, your inspectors cannot and do j i not attempt to verify the adequacy of each safety related part ,
of a plant.'. Instead, you rely on the licensee's quality assurance j program during construction to ensure that the plant is properly
. constructed and does not " unduly" jeopardize public health and :
safety when operation begins. In recognition of this, quality I i assurance is often cited as the cornerstone of reactor safety.
. Therefore, to argue as you do that an inadequate quality assurance program is not sufficient grounds to halt construction is contrary I to the Commission's reasons for requiring an acceptable quality l assurance program at the CP stage. Moreover, the stage at which quality assurance deficiencies are discovered is completely l irrelevant. Whether at the beginning or the end of construction, l when discovered they must be corrected.
4 Second, your investigation to date has evaded the main thrust of the individual's concerns. The original complaint noted explicitly that suspension of construction was needed to l remove the pressure which is contributing to the lax practices
! and the fact that, once constructed, both investigation and .
. correction of mistakes become more expensive and, hence, much !
j less likely. Furthermore, as the individual notes in the attached comments, several allegations of construction deficiencies i
, have in fact been confirmed. The fact that the utility is in !
2 the process of correcting those deficiencies confirms the
- accuracy of the allegations. The remaining question, still
- unanswered by your investigation, is whether the quality assurance program is adequate to assure that other construction deficiercies do not exist.
Third, Inspection Esport 80-08 states that Regulatory Guide 1.131, dated August 1979 is only issued for comment. The fact is that Regulatory Guide 1.131 was first issued for comment in August 1977. Thus, the implication that-Stone & Webster promptly l accepted the guidance is not accurate.*/ Furthermore, the i
- Please note the individual's request for a copy of Stone & Webster's December 12, 1979, position statement on Regulatory Guide 1.131.
Please send UCS a copy to forward to the individual.
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important question is not whether Stone & Webster accepts the Regulatory Guide, but whether the licensee, Gulf States Utilities, accepts it. The Inspection Report states that Gulf States Utilities still has not decided; thus the allegation is shown -
to be correct.
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If you desire any further intx ution from the individual, please let us know promptly.
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Rok.s it D. Pollard
dcluar Safety Engineer m s Ellyn R. Weiss Harmon & Weiss 1725 I Street, N.W.
Suite 506 Washington, D.C. 20006 cc: w/ enc 1.
Stephen Irving Anne Plettinger commissioner John Ahearne Commissioner Peter Bradford
, Commissioner Victor Gilinsky J
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Sept. 27, 1980 4
Ms. EllynDWeiss
. Harmon & Weiss 1725 I St., N.W. .
Suite 506 Washington, D.C. 20006 Dear Ms. Weiss w; )
Thanks for your letter of Sept.'12. I have at last had a I chance to look it over. Some of the NRC responses to the L allegations are pretty evasive. Other responses acknowledge ;
the truth of the allegation, and then draw a conclusion that i there is no safety related result. I must disagree.
Before going into the r.pecifics of the matter, I'd draw your attsntion to tha list of GSU personnel who were present 4 at the NRC audit. Included are Jim Hudson and Ernie Troncilliti, both of whom were fully conversant with the problems... Thus, it is true that GSU was aware of numerous l deficiencies in their cables and cable trays, and was under-taking to find answers, but this does not change . the fact l that the deficiencies existed; the material was not in con-formance with the criteria. Therefore, it does not behoove the NRC to say it was.
Now, regarding the allegations:
a) If the 600 V power cable is not to be shipped until after August 25,1980, ' then the schedule must have been changed.
Also, we.are told that test results will not be available
, until early in 1981. Will Okonite be permitted to ship before satisfactory test 5results are available? If not, then there is a serious impact in the construction schedule, l which shows a cut over 50 months from date of commencement. i
- Are saa to believe that GSU will accept these kinds of delays?
l Also, if'the' site activities only involve splice identification, then how will they go about qualifying these splices, or are we to believe that they plan to single out those lengths of cable that contain splices for "non-Q" application only? l l
- b) -We are told that S&W has issued a position statement on
, Reg Guide 1.131 on December 12, 1979. I have been unaware until now that such a statement exists. I'd te interested in seeing a copy. If S&W, indeed, accepts with no exceptions, Reg Guide 1.131, which was issued some years af ter the PSAR was issued, are we to believe that GSU and itt. agents accept
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with no objection ex post facto rule-making?
c) Regarding the matter of thermocouple extension wire and 300 volt instrument cable, NRC' acknowledges that ,the vendor, i indeed, violated the spec, and that Stone & Webster subse-quently revised the spec to accommodate.the vendor. Is this procedure acceptable to the.NRC? Also, if NRC plans to take no action until the licensee can assure trace-ability through the certificate of conformance, will Rockbestos be permitted to ship this cable? If the cable does not have a clear pedigree, then if a failure occurs while the plant is in operation, how are we'to effect a correction? Surely the temperature readings carried by j the thermocouple extension wire are important enough to warrant very special efforts, beyond merely adjusting the specification for the convenience of the vendor. After all, we must assume that the vendor bid on the job with his eyes open, and had every opportunity to take the necessary exceptions before any contracts were signed.
d) We are told that some 17,000 pieces of cable tray have been shipped to the field, all of which is aluminum. We are further told that a number of N&D's (Ncnconformance
& Disposition Reports) have been issued against some of
-these trays, the last of which being dated June 18, 1980.
The NRC report says that this last report has not yet
,- been dispositioned, and yet the NRC report is dated August 19, over two months after the issuance of the NED.
Does Stone & Webster routinely take over two months to disposition an N&D? If Stone & Webster's Engineering Assurance Procedures, and their River Bend Procedures Manual, which govern their operations on the River Bend
- Project, have been approved by the NRC, do these documents permit a two month delay in answering an NED? Does the NRC truly believe that Stone & Webster's Operations Center kept the field waiting with nonconforming cable for over
, two months with no answer? Also, how can the licensee
' assure that these nonconforming trays will not be used as is? And how do they propose to deal with post-installation damage?
e) It.is true that Husky's seismic design calculations were reviewed'by the. cognizant engineers at S&W before shipment 7' took place, k'at the NRC report acknowledges that the first
, shipment of cable tray,.in December of 1979, took place some five months before Husky received PE signoff on their A
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r design. Thus the allegation is shown to be correct.
The relevant question is, why isn't the operation monitored closely enough to cover this kind of sloppy activity? Are there other items on the site that are similarly uncovered by PE signoff, despite spec requirements?
f) [I] must respectfully disagree with the NRC's statement that the use of two different types of cable in the same circuit at River Bend's run to the makeup water structure does not violate good engineering practice. I suggest that they will be hard pressed to find a competent cable engineer
, to endorse such a practice. For one thing: in the case in question, the ground braids used on the two cables are made of different materials, which is definitely not a recommended practice. The main rationale behind the decision to use two different sizes of cable for the run to the makeup water structure was to save money, and it is highly doubtful that this design had the endorsement of Stone & Webster's cable specialist.
g) We are told that Stone & Webster's electrical installation spec allows a rung to be removed to allow the necessary bending radius. This does not answer the allegation, as it does not prove that such tray is seismically qualified.
The tests that were performed on the tray did not have any rungs removed. Husky can pr6ve the seismic capabilities of their tray with a rung removed either by analysis or by test, but if they do it by analysis, then that, too, should
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be signed off by a PE. Also, if they have seismically proven their straight cable trays, how do we know that the fittings would meet the sama criteria? Finally, if Addenduni 5 to Spec 241.320 deleted the requirement that ;
a PE sign off on the seismic design requirements in a COC i i prior to shipment, did the NRC approve of this deletion?
Was a change taken to the PSAR?
One more thing; we are told that cable tray began arriving
- at the jobsite in December of 1979, and none has been installed '
to date (which would be August 19, 1980). Are we to believe that GSU has had cable tray in inventory at the site for eight months, without any attempt .to install it? Was any inquiry made about this waste by the Louisiana Public Utilities commission? Will GSU deny.that they paid Huskiy nearly
$10,000 in overtime to obtain early delivery of the cable trays?
4 h) . I must regretfully state that the NRC's answer to the question about the spec that sizes the SkV and 15kV i
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cinsulated power cable is a lie! Any comparison between what in called out in Calculation E46H and what is nca '
ordered on Anaconda in the spec, and all addenda, as well as tables of reel assignments, will show that E46H is totally obsolete, and that the cables have been ordered 2 l- to conform to E120. 346H was done several years ago, and ~y ~
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was correct when it was done, but since that time, the circuit length estimates have changed, the loads have changed, and, indeed, even the cable impedance tables have changed. Thus, S&W's contention that they are using an obsolete calculation to order 5kV and 15kV power cable is totally in error. They are using the best i information they have to date, which is in E120. Which brings us back to the original contention, that S&W does not challenge, namely, Calculation E120 has not been approved.
i i) The NRC's answer does not address to the allegation.
For starters, if there are no Category I applications for 15kV power cable at the site, then why is it ordered in i- Specification 241.232, on whose cover sheet appears the words "I Nuclear Safety Related"? Does GSU just like to spend money? Also, has the NRC actually examined the ;=<r" table of insulated 15kV power cable sizes contained -in*""-
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Design Criteria 241.100 and found 250=MCM= copper cable?
If it does appear in that,tableffwas it r'ecently added, via the latest revisidh?~ I doubt that the 250 MCM cable that was ordered was covered in the Design criteria as of
! the time it was ordered.
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The NRC states that no fabrication of cable has been i initiated. And yet the cable tray, on which the cable is to be supported, was delivered in December of 1979, but not installed. Are we to believe that the cable vendors have accepted these delays without insisting on massive price adjustments? Also, how do they propose i to meet the 400,000 BTU /hr flame test requirement, and when? If the test must be made on a " production run of
- cable"'and they are not yet into production, it would seem that they have something of a problem. And what if their cable fails the flame test. If it's in production, are we to believe that they will throw out a whole pro-duction run? or is the test itself strictly pro forma, eyewash that proves nothing? If so, then why run it?
Anaconda stated last June that they were, in fact, ' in production on the cable, and .nat they planned to deliver it to the jobsite shortly after the August 25 field 4
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Ns required date. Now they .tell the.NRC that they are not
- in production. Perhaps a call to their.Marion, Indiana plant would be fruitful.
The key to the problem would seem to be GSU's construction' schedule. They tell their vendors and others that they are on a 50 month construction schedule, and yet they tell 4 the NRC that they have not begun to install either cable or cable tray months after this activity was to be well under way if'their schedule was to be met.- We know that the cost
, of the plant has escalated from an estimated $400 million-at design inception to an estimated $1.7 billion now, 4 and that they are down from two units to one unit and that they have invited minority interests to share in the power plant. At current interest rates, a delay of a few months in incredibly expensive for GSU. They have a tremendous financial incentive to meet their fifty month
. construction schedule; thus - their assurances to the NRC that they have delayed construction, or that they have delayed installation of the 600 volt power cable, lacks credibility.
i Finally, I have a problem with the last statement in the NRC report, "No items of noncompliance or deviations have been identified." That contradi~ cts the body of their own report, to wit: :
(1) Allegation: " Factory reworked areas of 600 volt power and control cables have not been qualified..."
Inspection Results: . . . Qualification work...is in
- proc ress. . .a fabrication hold has been in effect. . .Eecause of c eficiencies. . . Activities at the site involve identification 4
of cable splices, not qualification..."
t (2) Allegation: " ...there will be no direct traceability (of) the (thermocouple extension wire and the 300 volt instrument cable)"
Inspection Results: " . . . traceability is made from the conductor to the reel through the resistance test reports...
No action will be taken until the-licensee can assure traceability..."
(3) Allegation: ...the conductor tests will be performed on a bulk basis..."
Inspection Results: "For the instrument cable, conductor testing is performed on the ccmpleted cable...
A specification revision is in process...Rockbestos has requested a change. . .to supply a (COC) in lieu of actual test reports..."
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G (Al Allegations- "Large amounts of cable tray have been damaged in the field..." 4 Inspection Results: ".. 82 trays nave been identified l as being damaged...N&D has not been dispositioned"
(.5) / Allegations "
...none of the repairs proposed have met the' seismic qualification criteria."
Inspection Results: ...the dispositioning is awaiting...
approval of Husky recommendations ~and seismic calculations...
these recommendations are in the review cycle; thus, no repairs will be initiated until it can be assured that the seismic qualification criteria will not be violated."
(61 Allegation: "Large (amounts) of cable tray have been shipped.without Husky...having complied with the... requirement that their seismic qualification criteria must be approved by a professional engineer."
Inspection Results: ."...the first shipment of cable
, tray to the (jobsite) (was) in December, 1979. The required l certificate of compliance was signed on May 20, 1980 by the responsible Husky professional engineer..."
(.7) Allegation: "Tne power run to the makeup water structure is done with two entirely different type (s) of cable...".
Inspection Results: ...there are two types of cables -
a single conductor for cable tray and conduit applications and a three conductor cable for direct burial applications..."
NOTE: .The single conductor cable is actually being used in an underground duct bank application.
(8) Allegation: "...it is (sometimes) necessary to remove a rung (in the cable tray) . (This) has not\been proven to be seismically qualified."
" ... atone & Webster is currently Inspection Results:
reviewing the seismic acceptability of removing a rung..."
Thus, within the body of the NRC's own report we find eight items of noncompliance that they acknowledge.c And, as stated above, if.we were to examine the files, we'd find that Anaconda, indeed, stated that they had commenced pro-1 duction,vdespite S&W's claim.that they had not. In fact,
, it would'belinatructive to review S&W's job book against S&W's Expediting Department records in this regard.
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Indeed, the body of the NRC's report alludes to the existence i
, of "N&D's" on the job, which.are defined as "Nonconformance !
and-Disposition Reports." Thus, mere conversance with the English language would indicate that nonconformances exist, at least in the opinion of S&W's field people. 1 I'd strongly recommend that we petition the NRC to amend "
their report to correct the concluding statement to read "Certain items of noncompliance or deviation'have, indeed,
- been identified, with the following resp 6ns~e~by'the licensee;..."
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