FOIA Request for Documents Concerning Tech Specs Changes, Operating Procedures,Personnel Training & Physical Plant ChangesML20214N993 |
Person / Time |
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Site: |
River Bend |
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Issue date: |
09/11/1986 |
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From: |
Guste W LOUISIANA, STATE OF |
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To: |
NRC |
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References |
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FOIA-86-687 NUDOCS 8612040040 |
Download: ML20214N993 (3) |
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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:STATE/LOCAL GOVERNMENT TO NRC
MONTHYEARML20236F3121987-07-0202 July 1987 FOIA Request for GE Nuclear Reactor Study & Related Subtask Force Repts,Generally Known as Reed Rept.Info for Use in Current Ratemaking Proceeding Before PSC of La for River Bend Plant ML20214N9931986-09-11011 September 1986 FOIA Request for Documents Concerning Tech Specs Changes, Operating Procedures,Personnel Training & Physical Plant Changes ML20215M5191986-09-11011 September 1986 Expresses Concerns Re NRC Employee Allegation That Util Apparently Concealed Knowledge of Serious & Pervasive Errors & Misstatements in Facility Tech Specs ML20098F4111984-09-20020 September 1984 Forwards Act 825 for Inclusion in Author Rept to Aslb. Related Correspondence ML20093N2451984-07-24024 July 1984 Requests That Wj Guste & Id Lindsey Be Removed from Svc List ML20093E5501984-07-0606 July 1984 Ack Receipt of to ASLB Outlining Evolution of Regulations Re Development & Distribution of Board Notification.Related Correspondence ML20093E5091984-07-0606 July 1984 Ack Receipt of Correspondence Referenced in LS Dewey .Board Notification 84-062 Re Core Thermal Hydraulic Stability & Svc List Should Have Been Sent to Aslb.Related Correspondence ML20091J4741984-05-31031 May 1984 Discusses 840518 Meeting Re Emergency Planning Contentions. Amends Will Be Developed to Address Issues Raised in 12 Listed Contentions.Certificate of Svc Encl.Related Correspondence ML20084M6781984-05-0909 May 1984 Requests That Wj Guste & Jd Lindsey Be Removed from Svc List & That State Agency Be Added as Listed ML20084M6701984-05-0404 May 1984 Notifies of 840518 Meeting in Baton Rouge,La to Discuss Contentions Re Emergency Response Plan.Certificate of Svc Encl.Related Correspondence ML20082Q1621983-12-0505 December 1983 Notifies That State of La Has Reviewed Rept on Transmission Line Const Activities within Port Hudson Natl Historic Landmark. Archeological Investigation Underway at Magnolia Plantation Sugar Mill ML20040D0651981-12-29029 December 1981 Comments on NRC Geologic & Seismologic Questions Re FSAR Review.Comparison of Util & NRC Remote Sensing Lineament Analyses Requested ML20039E4111981-12-29029 December 1981 Requests Comparison of Gulf States Utils Co Interpretation of Remote Sensing Lineament Analysis for 5-mile Radius,W/Nrc Analysis Using Duplicate Photos.Monitoring of Groundwater Usage & Pumpage Strongly Urged ML19350B6171981-02-23023 February 1981 Expresses Disappointment That D Hood,Project Manager,Unable to Make Expected Insp Visit to Plant Due to Budget Cuts. Urges That Decision Be Reversed ML19327A4821980-08-0404 August 1980 Forwards Memorandum of Agreement for Nrc/Gulf States Utils Co Project at Port Hudson Natl Historic Landmark,East Feliciana Parish,La.Concurs W/Stipulations in Agreement 1987-07-02
[Table view] |
Text
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. Spfate of Tauisiana DEPARTMENT OF JUSTICE
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ATTOe**ET Ogestaat 3-3 4 LOYOL A SUILDING September 11, 1986 FREEDOM OF INFORMATON ACT REQUEST forJ-26-u 7
Admiral Lando Zech, Chairman Nuclear Regulatory Commission Cf 9~/7-((
U.S.
Washington, D.C. 20555 This letter contains a Freedom of Information Act Request -
5 U.S.C. Sec. 532 et seq. -
Dear Admiral Zech:
I have been startled to read documents obtained from a Louisiana citizen in response to a Freedom of Information Act request in which an NRC official expressed the belief that Gulf States Utilities Company had apparently concealed knowledge of serious aad pervasive errors and misstatements in the River Bend Technical Specifications.
The NRC official, Mr. Dean Houston, has expressed his misgivings, not only about the concealment, and the prevalence of errors in the technical specifications, but also about what he evidently considered to be an unwise policy decision by NRC to accelerate its review of the technical specifications.
Mr. Houston's memo of May 1st refers to the fiasco to which, in his view, a similar policy led with respect to Grand Gulf.
I am not sure of the extent of the fiasco over Grand Gulf to which Mr. Houston refers; I am painfully aware, however, that only days after that plant had been declared in commercial service, and therefore, Middle South Energy's customers had become responsible for its capitol costs, the plant was shut down for an extended period, to accomplish by l retrofit compliance with NRC requirements which had been deferred until that time.
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Quite apart from the safety implications of Mr.
I Houston's revelations, which, I trust, you will examine l .
i 8612040040 FOIA 860911 PDR l Pbgo sTE86-687
A Admiral Lando Zech, Chairman U.S. Nuclear Regulatory Commission September 11, 1986
- Page Two thoroughly, I am concerned about their significance for economic regulation of Gulf States Utilities Company by the Louisiana Public Service Commission. The Louisiana Commission, like its counterpart in Texas, has before it the
, question of whether River Bend has "gone commercial" and, if so, when.
The company has suggested that River Bend was placed in commercial service on June 16, 1986.
I should be grateful if you would cause'your staff ~to send me whatever.information NRC may have that may be relevant to that determination, including, but not' limited to, any
- ~ documents containing any information concerning changes made in the technical specifications, the operating procedures, the training of personnel, and the physical plant itself, 1 - subsequent to June 16, 1986; whether decisions to make those changes have been made or are under contemplation, and whether
- such changes will cause or extend any shutdown of the plant, or any operation at reduced power.
I should further like to ask you, Admiral, in a spirit of comity, and apart from the specific requirements of j the Freedom of Information Act, to advise me of any NRC requirements, or contemplated requirements, or indeed to advise me of anything of which your agency has knowledge, (apart from normal fuel consumption) which may affect the capacity factor performance of River Bend.
I trust that you will direct your staff to respond to this request in keeping with the spirit as well as the letter of the Freedom of Information Act.
Inasmuch as this information is sought for use by a state government -- actually two state governments, since we will share it with our Texas counterparts -- in the economic regulation of a public utility company, a use which primarily benefits the general public, I request that you direct your 4
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Admiral Lando Zech, Chairman U.S. Nuclear Regulatory Commission September 11, 1986 Page Three agency to waive or substantially reduce the fees it is authorized to charge for compliance 'th this request.
Very truly ou ,
WILLIAM . USTE, .
Attorn eneral WJG,JR./vpf Enclosures cc: Members, U.S. Nuclear Regulatory C6mmission FOIA. Office, U.S. Nuclear Regulatory Commission Members, Louisiana Public Service Commission Louis S. Quinn, Secretary, Louisiana Public Service Commission Secretary, Public Utilities Commission of Texas James Boyle, Office of Public Utility Counsel r
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Note To: E. Butcher, Group Leader TSRG, DL From: D. Houston, TSRG, DL
Subject:
Concerns About River Bend Technical Specification Development l l
Initial feedback from Region IV auditors and NRR reviewers in regard to River Bend Tech Spec review would indicate that: (1) this draft of Tech Specs has I some serious problems to be resolved. (2) numerous deficiencies in plant pro-cedures exist in about all areas wher. compared against this draft and (3) the plant itself will not be ready for licensing before September,1985. It would appear that our accelerated review schedule is inappropriate and our " Final Draft" questionable. Therefore. I feel that the future development of RBTS should be reassessed upon the conclusion of the current review, on or about May 15,1985, and see if a normal schedule (enclosed) would not be the better way to proceed. .
The licensing process for River Bend follows that for Grand Gulf during the last year of review. Grand Gulf was always to be ready for licensing in the next month or two from November 1981 to June 1982. Due to this anticipated action, technical reviews and Tech Spec development could not be performed under ideal conditions.
We are all aware of the problems that surfaced afterwards on GGTS but yet it appears to me that we have ignored some of the lessons learned from the GG case by accelerating the RSTS development, thus giving reviewers less time to perform their review and eitminating some logical steps in our established procedure.
On River Bend, the basic problem with the review is that the utility has failed to pursu[ solution of numerous issues in a timely manner. When confronted with the restr' citons on containment purge, their licensing contact said they were pre-paring a submittal for next week to address the problem that has been known to exist for months. Currently, the LPM carries 67 open items for resolution in the i SER and SSERs. This resolution in many cases depends upon future FSAR amendments, not just the ones in the past few weeks which have yet to be reviewed. As of now, ASB.CSB.EQB.ICSB,PSB andRSB branches are looking at or are awaiting information, all of which might affect RB Tech Specs. Compare this to Perry which expects a license in June-July,1985, only a total of 21 items remain open.
From the Regiyal Audit viewpoint, we have turned the Audit Team loose with a cet m m MJech Specs right off the press. On a normal schedule, they would have had the TS for 5 weeks to review, comment and resolve outstanding items prior to their audit function. The utility would also have had 5 weeks to review their procedures before the audit. By accelerating the schedule, both the Region and the utility a're poorly prepared for this important step in the TS process.
The same can be said for our consultant review and for the utility certification.
All of these functions were again an aftemath of the Grand Gulf fiasco and we have lessened the review. ~~
Due to the uncertainties associated with the current safety review, I would rec-omend that the TS situation be reassessed in the near future and a realistic schedule be set. If many problems exist or are still to be resolved, a nomal schedule ending in August should be adopted. Obviously, with current and future TSRG resources available, my participation in the realistic schedule should not -
be required and a near-future depar.ture to ACRS can be arranged. Please inform me of a ' suitable transfer date. t
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D. Houston, TSRG' DL
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1 MEMORANDUM.FOR: Edward J. Butcher, Group Leader Technical Specification Review Group Division of Licensing FROM:
M. Dean Houston, Reactor Engineer Technical Specification Review Group Division of Licensing
SUBJECT:
DEFICIENCIES IN REGARD TO GSU CERTIFICATION OF RIVER BEND .
TECHNICAL SPECIFICATIONS (FINAL DRAFT)
By letter dated May 2,1985. Gulf States Utilities (GSU) was requested to review the final draft of River Bend Technical Specifications and submit by May 13, 1985, a certification under oath and affinnation that .the final draft accurately reflects the FSAR, SER and as-built configuration of the plant. By letter dated May 6,1985 GSU submitted their certification, under oath and affirmation, of the final draft of River Bend Tech Specs.
Included in their submittal were: (1) identified editorial changes (173 items), (2) proposed changes to the Tech Specs (38 items), (3) proposed revisions to the SER (7 items) and (4) identification of FSAR sections to be revised with some proposed FSAR revisions (55 areas).
In my review of their submittal, numerous deficiencies, acts of emission and conynission, have been identified. Examples of editorial errors that were not identified by GSU are presented in Enclosure 1. The attached pages are from the GSU submittal, some with their markup, and the errors that were not detected are circled. These errors take many forms - typos, missed l
headings, non-existent trip signals, nomenclature, etc. While misspelled
- words can be properly interpreted, many of the other unidentified errors f
' would have contributed to operator confusion. The enclosure is not intended to be a complete compilation of overlooked errors but does establish that the GSU review process was less than thorough. Approximately 20% of the
! errors in the final draf t were not detected during their review. This is an unacceptable level by any standard and their review process for certi-fication at licensing must be improved.
Examples of deficiencies by acts of comission are presented in Enclosure 2.
Two of these are editorial errors and one is based on a possible false statement regarding their as-built plant.
(1) GSU proposed changes to page 3/4 8-5 of the River Bend ,
Tech Specs as shown. As proposed, the change was to be inserted between 10 and seconds. On page 3/4 8-6 of the I
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Edward J. Butcher May 17, 1985
, same submittal, GSU properly proposed an identical change with the clause to be inserted after 10 seconds. As pr.oposed on 3/4 8-5, the revision makes no sense and would confuse the operator.
{2) In Attachment B of the GSU submittal of May 6, 1985, Item 29 reouests a deletion of a surveillance requirement because -
"There are no valves in the flow path of any PGCC subsystem."
In past discussions, GSU has resisted this requirement on the basis that the valves did not have a position indicator although, in fact, the valves do have a trip indicator. A copy of FSAR Figure 9.5-13 is enclosed which shows numerous solenoid operated valves as well as a cou;1e of check valves
, , in the flow path. Therefore, the GSU statement of "no valves in the flow path" appears to be a false representation.
(3) Also, in Attachment B, item 30 refers to adding a footnote to TS 3/4.7.6.4, Table 3.7.6.4-1. This is in error as the proposed footnote,was identified with TS 3/4.7.6.5 Table 3.7.6.5-1. -
In' addition to the deficiencies noted above, I would like to comment briefly on other uncertainties associated with the River Bend Tech Spec review.
GSU has submitted a listing of 55 areas in the FSAR that need revision to support Tech Spec. sections. Amendment 19 to the FSAR was delivered on May 14, 1985 and only 12 of these areas were addressed. Therefore, in the other 43 areas, the NRR Technical Reviewer has not seen the necessary documentation to support the current Tech Spec section or a proposed revision to a section. There is also the potential for additional FSAR revisions resulting from the reviewer's evaluation. This lack of timely information will impact the accelerated schedule for issuance of the Tech l
Specs with the River Bend license in June,1985.
There seem to be some values in the FSAR and Tech Specs that are constantly being changed. For example, the DBA activity release to the environment following a LOCA (used for containment Tech Spec review) were revised in Amendment 18 to the FSAR dated April 1985 and revised again (increased) in Amendment 19 on May 13, 1985. In the Tech Specs, GSU has proposed that the water level for r4 Ultimate Heat Sink be 112'4" (2nd Draft),108"6" (Final Draft) and 111'10" (current revision). Changes of this frequency would indicate that the utilities review process has not settled down.
All of the above matters should be given due considerations when discussing comitments and completion schedules for the River Bend Tech Specs.
. h A- @Lb M. Dean Houston, Reactor Engineer Technical Specification Review Group Division of Licensing -
cc: D. Crutchfield R. Benedict S. Stern l
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- a Edward J. Butcher May 17,1985
' same submittal, GSU properly proposed an identical change with the clause to be inserted after 10 seconds. As proposed on 3/4 8-5, the revision makes no sense and would confuse the operator.
(2) In Attachment B of the GSU submittal of May 6,1985, Item 29 requests a deletion of a surveillance requirement because -
"There are no valves in the flow path of any PGCC subsystem."
In past discussions, GSU has resisted this requirement on the basis that the valves did not have a position indicator although, in fact, the valves do have a trip indicator. A copy of FSAR Figure 9.5-13 is enclosed which shows numerous solenoid operated valves as well as a couple of check valves in the flow path. Therefore, the GSU statement of "no valves
_- , in the flow path" appears to be a false representation.
(3) Also, in Attachment B. Item 30, refers to adding a footnote to TS 3/4.7.6.4, Tab.le 3.7.6.4-1. This is.in error as the proposed footnote was' identified with TS 3/4.7.6.5, Table 3.7.6.5-1.
In addition to the deficiencies noted above, I would like to comment briefly
! on other uncertainties associated with the River Bend Tech Spec review.
GSU has submitted a listing of 55 areas in the FSAR that need revision to I
support Tech Spec sections. Amendment 19 to the FSAF was delivered on May 14, 1985 and only 12 of these areas were addressed. Therefore, in the other 43 areas, the NRR Technical Reviewer has not seen the necessary documentation to support the current Tech Spec section or a proposed
, revision to a section. There is also the potential for additional FSAR revisions resulting from the reviewer's evaluation. This lack of timely information will impact the accelerated schedule for issuance of the Tech Specs with the River Bend license in June, 1985.
There seem to be some values in the FSAR and Tech Specs that are constantly being changed. For example, the DBA activity release to the environment following a LOCA (used for containment Tech Spec review) were revised in Amendment 18 to the FSAR dated April 1985 and revised again (increased) in A.mendment 19 on May 13, 1985. In the Tech Specs, GSU has proposed that the water level for the Ultimate Heat Sink be 112'4" (2nd Draft),108"6" l (Final Draft) and 111'10" (current revision). Changes of this frequency would indicate that the utilities review process has not settled down. -
All of the above matters should be given due considerations when discussing i
commitments and completion schedules for the River Bend Tech Specs.
i Original signed by M. Dean Houston, Reactor Engineer Technical Specification Review Grooi Division of Licensing cc: D. Crutchfield TSRG:DL Distribution -
R. Benedict DHouston:jc Docket File *TSRG File S. Stern 5//p/85 e
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- May 21, 1985 Mr.MORANDUM FOR: Edward J. Butcher, Group Leader Technical Specification Review Group, DL FROM: R. A. Benedict, Reactor Engineer Technical Specification Review Group, DL SU3 JECT: MORE DEFICIENCIES IN REGARD TO GSU CERTIFICATION OF RIVER BEND TECHNICAL SPECIFICATIONS (FINAL DRAFT) ,
Further to Dean Hous' ton's May 17, 1985 memorandum to you on this same subject, there are an additional 38 pages in which editorial errors were not identified by GSU. The missed errors are circled on the enclosed pages.
All told, 79 pages .out of 509 had editorial errors that GSU missed.
R. A.. Benedict, Reactor Engineer Technical Specification Review Group, DL
Enclosure:
As stated cc: D. Crutchfield D. Houston S. Stern 5
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% s., ,/ July 9, 1985 Docket No. 50-458 l
NOTE TO FILE:
SUBJECT:
RIVER BEND TECHNICAL SPECIFICATIONS
~
On July 8,1985, a highly reliable source with professional ties to Gulf States Utilities remarked in the presence of another TSRG member and myself that the River Bend staff was aware of many errors, discrepancies and problems in the current River Bend Technical Specifications. He further said that GSil management had apparently instructed their staff to not pursue resolution of these items at this time since Jt would be time consuming and hold up the issuance of a license. They have detemined that the plant can live by the current Tech Specs and changes will be pursued after licensing.
This philosophy is identical to that of MP&L or Grand Gulf and we are all too aware of the disastrous results of that case. Ancther reason that GSU.would not want to pursue resolution at this time is that changes to Tech Specs will result in changes to operating procedures. With some 900 procedures to re-review and modify, if necessary, more time will be lost toward licensing.
If the above is true, CAUTION should be the mode for TSRG, technical reviewers, Region IV and EG&G in the final audit and review of Appendix "A" to the license. GSU has already demonstrated their inability to identify all errors in the certification of the
" Final Draft." I would expect that their final certification will be perfomed in the same haste and will definitely not identify all problems if the above instructions are true.
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Dean Houston, Reactor Engineer Technical Specification Review Group Division of Licensing -
cc: R. Benedict t M. Virgilio D. Crutchfield e
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July 15, 1985 '
Docket No. 50-458 i
NOTE TO: File 7 FROM: Dean Houston, TSRG:DL SU8 JECT:
RIVER JULY BEND TECHNICAL SPECIFICATION NOTE OF 9, 1985 In my note of July 9,1985, I made reference to errors, discrepancies and were time constraints. known to GSU staff members but were not pursue asked about details no specific examples were furnished. concerning these areas p and the questio
.The basis for my concern is that GSU has the Final already demonstrated a weakness. in their certification (under oath) of Draft.
Following that certification, Bob Benedict and I issued memorandums, dated May 17 and 21, 1985, respectfully, in which we identified numerous errors that were not uncovered in their review (Enclosu To the best of my knowledge, I am unaware of specific details that would indicate errors, deficiencies, or problem areas in the curren't Technical Specifications.
However, it would not surprise me if there were. For example, in Amendment 20 to the FSAR, that has been the basis of our review dated identified latefor June 1985, the first time. eight new ventilation systems and one new building w While it may be true that these systems did not truly not affectreflected the Technical the as-built Specifications, plant. it is an indication that the FSAR has safety systems, the Technical Specificatiens could be in error.If similar discrepa i
Technical Specifications, note the differences between
- certified (Enclosures copy dated 3 and 4). April 26, 1985, and a markup dated June 28, 1985
' Three key instru:nentation setpoints for the HPCS system were before?changed, hopefully the last set is correct but why wasn't the matter ca One Fuel Handling. area that has previously been discussed and w As written, all primary containment penetrations required to be closed during accident conditions are closed by some mechanism. GSU had i
informally status ratherrequested than closed.that some of these penetrations be put into operable i some time to review and approve, that we should forget it.Their reques Since pytting valves into other than a closed category would have reopened the review of this area, we did not grant the change or pursue it further.
There is some principle, but may not work in the real world. indication n that the should be pursuing now. This may be an area that GSU i .
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File July 15, 1985 The extent of errors and discrepancies is not known other than noted above.
& af & ,. r;a Dean Houston Technical Specification Review Group, OL Er. closure:
As stated cc: D Crutchfield M. Virgilio um B
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- W A SHING T ON, 0. C. 20555 h . ,',. . July 18, 1985 MEMORANDUM FOR: Robert D. Martin, Regional Administrator Region IV FROM: Harold R. Denton, Director Office of Nuclear Reactor Regulation
SUBJECT:
REQUEST FOR AN INVESTIGATION The purpose of this memo is to request your assistance in investigating an allegation of wrongdoing by Gulf States Utilities, the applicant for River Bend.
By memo dated July 9,1985, Mr. Dean Houston, a Reactor Engineer in the Division 1 of Licensing, NRR, informed us of an allegation regarding the quality of certain licensing documents. In Mr. Houston's presence, an individual with professional ties to the applicant stated that the applicant's staff is aware of many errors, l discrepancies and problems in the River Bend Technical Specifications. He further stated that Gulf States Utilities' management had instructed their staff not to pursue corrections at this time since it would hold up issuance of a license. As Enclosure 1. I am providing a copy of Mr. Houston's July 9,1985 memo.
i Mr. Houston believes the alleged activities likely occurred. This is based _
on his assessment of the applicant's perfomance throughout the Technical Specification development process. As Enclosure 2. I am providing a second memo on this subject from Mr. Houston dated July 15, 1985. This memo was written at our request to document relevant background infomation.
Mr. Martin Virgilio of the Technical Specification Review Group DL, has been j designated as office contact for this action. Mr. Virgilio can be reached at !
492-8947.
H o d R. Denton ir to O e of Nuclea Rea to regulation
Enclosures:
As stated cc: J. Taylor - ,
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