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Category:CORRESPONDENCE-LETTERS
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999 Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span ML20217M5711999-10-20020 October 1999 Forwards Insp Repts 50-445/99-15 & 50-446/99-15 on 990822- 1002.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999 Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred ML20217E7951999-10-12012 October 1999 Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5 ML20212L2891999-10-0101 October 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals. Purpose of GL Was to Obtain Info That Would Enable NRC to Verify That Condition of Licensee SG Internals Comply with Current Licensing Bases TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999 Forwards Revised COLR, for Cycle 5 for Unit 2 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps ML20212G0721999-09-24024 September 1999 Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site ML20212H0461999-09-24024 September 1999 Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820 ML20212F7481999-09-24024 September 1999 Forwards SER Authorizing Relief from Exam Requirement of 1986 Edition ASME Code,Section XI Pursuant to 10CFR50.55a(a)(3)(ii) for Relief Request A-3 & 10CFR50.55a(g)(6)(i) for Relief Requests B15,16,17 & C-4 ML20212F1041999-09-23023 September 1999 Requests That NRC Be Informed of Any Changes in Scope of Y2K System Deficiencies Listed or Util Projected Completion Schedule for Comanche Peak Steam Electric Station,Units 1 & 2 ML20212E6661999-09-21021 September 1999 Advises That Info Contained in Application & Affidavit, (CAW-99-1342) Re WCAP-15009,Rev 0, Comache Peak Unit 1 Evaluation for Tube Vibration Induced Fatigue, Will Be Withheld from Public Disclosure ML20212D9111999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of CPSES & Did Not Identify Any Areas in Which Performance Warranted Insp Beyond Core Insp Program.Core Insp Plan at Facility Over Next 7 Months.Insp Plan Through March 2000 Encl ML20212A7601999-09-14014 September 1999 Forwards Insp Repts 50-445/99-14 & 50-446/99-14 on 990707-0821.Four Violations Occurred & Being Treated as Ncvs.Conduct of Activities Was Generally Characterized by safety-conscious Operations & Sound Radiological Controls TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999 Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC ML20211P3761999-09-0707 September 1999 Ack Receipt of Ltr Dtd 990615,transmitting Rev 30 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20211L9871999-09-0303 September 1999 Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999 Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl ML20211K2231999-08-31031 August 1999 Forwards Txu Electric Comments of Rvid,Version 2 ML20211J3801999-08-27027 August 1999 Forwards Corrected TS Page 3.8-26 to Amend 66 to Licenses NPF-87 & NPF-89,respectively.Footnote on TS Page 3.8-26 Incorrectly Deleted ML20211G7301999-08-26026 August 1999 Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively ML20211G1081999-08-26026 August 1999 Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure ML20211G3441999-08-25025 August 1999 Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2 ML20211B2861999-08-18018 August 1999 Forwards Insp Repts 50-445/99-13 & 50-446/99-13 on 990720- 23.No Violations Noted.Insp Included Implementation of Licensee Emergency Plan & Procedures During Util Biennial Emergency Preparedness Exercise ML20211C4661999-08-18018 August 1999 Discusses Proprietary Info Re Thermo-Lag.NRC Treated Bisco Test Rept 748-105 as Proprietary & Withheld It from Public Disclosure,Iaw 10CFR2.790 ML20210U3981999-08-17017 August 1999 Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred ML20211C0991999-08-17017 August 1999 Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety ML20211C4571999-08-16016 August 1999 Forwards Omitted Subj Page of Contractor TER TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999 Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802 ML20210R6561999-08-13013 August 1999 Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS 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 ML20210S6411999-08-12012 August 1999 Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested ML20210R2221999-08-12012 August 1999 Forwards Insp Repts 50-445/99-10 & 50-446/99-10 on 990510-0628.Violations Noted & Being Treated as Ncvs, Consistent with App C of Enforcement Policy ML20210N1101999-08-0404 August 1999 Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request 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 ML20210J2301999-08-0202 August 1999 Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2 ML20210J6071999-08-0202 August 1999 Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2 TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999 Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727 TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999 Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20210K2321999-07-29029 July 1999 Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted ML20210G5861999-07-29029 July 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999 ML20210J0121999-07-27027 July 1999 Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999 Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES ML20210F3121999-07-26026 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, ML20210D8231999-07-23023 July 1999 Forwards Safety Evaluation of Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 ML20210C2931999-07-21021 July 1999 Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval ML20210C3331999-07-16016 July 1999 Forwards Exam Repts 50-445/99-301 & 50-446/99-301 on 990618- 24.Exam Included Evaluation of Six Applicants for Senior Operator Licenses ML20209H2551999-07-16016 July 1999 Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230 1999-09-07
[Table view] Category:EXTERNAL CORRESPONDENCE
MONTHYEARTXX-9914, Responds to 990525 RAI Re Renewal of Tpdes Permit Number 01854.Explanation & Response to Each Item,Listed1999-06-16016 June 1999 Responds to 990525 RAI Re Renewal of Tpdes Permit Number 01854.Explanation & Response to Each Item,Listed ML20206E7271999-04-29029 April 1999 Submits Original & Four Complete Copies of Application for Renewal of Permit to Discharge,Deposit or Dispose of Wastes Into or Adjacent to Water in State. with Three Oversize Drawings ML20045D3451992-06-16016 June 1992 Discusses Util Review of 920603 Ltr Outlining Thermal Science,Inc Field Surveillance of Application of Thermo-Lag 330 Fire Barrier Sys on Util Test Assemblies at Omega Poing Labs.Supporting Documentation Encl ML20091Q2891992-01-27027 January 1992 Forwards Rev 7 to Quarterly Plant Performance & Other Indicator Data for Fourth Quarter of 1991 & Gross Heat Rate Data Form for 1991 ML20070T7651991-04-0101 April 1991 Forwards 910327 License Amend Request 91-001 Re Addition of Spec 3/4.7.12 & Bases 3/4.7.12 for Safety Chilled Water Sys ML20073D1051991-03-29029 March 1991 Comments on Final Rept Addressing Scaling for Unit 1,dtd Feb 1991 Per Insp Repts 50-445/90-47 & 50-446/90-47.Concerns Raised That Util Selected Criterion XI Re Test Control as Sole Mgt Std to Control safety-related Activities ML20066A5711990-12-19019 December 1990 Forwards Update to ASME Section Iii,Div 1 Code Control Program Documents for Incorporation Into State of Tx Dept of Licensing & Regulation Controlled Manual CCPM-15,authored by Ebasco ML20056B3741990-08-21021 August 1990 Forwards Update to ASME Section Iii,Div 1 Code Control Program Documents for Incorporation Into State of Tx Dept of Licensing & Regulation Controlled Manual CCPM-15 ML20011E1521990-01-27027 January 1990 Forwards Addl Case Concern Repts 89-0025 Re Apparent Substandard Shop Applied Welds Internal to Secondary Side of Steam Generators & 89-0034 on Specific Wiring & Connection Method Damaging safety-related Electrical Wiring ML20248D0661989-09-21021 September 1989 Notifies Util of Case Position on Concerns & Problems in Scaling Calculation Program at Plant.Documentary Info Supporting Util Position on Aspect of Dispute Should Be Provided ML19332C7971989-09-14014 September 1989 Forwards Offsite Portion of Annual Emergency Preparedness Independent Review & Status of Corrective Actions Initiated, Per 10CFR50.54(t) ML19332E0011989-09-14014 September 1989 Forwards Offsite Portion of Annual Emergency Preparedness Independent Review Per 10CFR50.54(t) ML19332D4781989-09-14014 September 1989 Forwards Offsite Portion of Annual Emergency Preparedness Independent Review to Be Conducted Every 12 Months.Review Must Include Evaluation for Adequacy of Interfaces W/State & Local Govts ML19332C8171989-09-14014 September 1989 Forwards Offsite Portion of Annual Emergency Preparedness Independent Review & Status of Corrective Actions Initiated, Per 10CFR50.54(t) ML20246A0421989-08-18018 August 1989 Advises That S&W Notified by Util That Responsibility for Facility Code Control Program Will Be Terminated Effective on 890823.EBASCO Svcs,Inc Selected to Assume Responsibility for Code Control Program Effective on 890824 ML20247R7291989-07-28028 July 1989 Advises That Status of Suspect molded-case Curcuit Breakers, Identified in Initiative Element One Will Be Provided by 890815.Util Estimates That 750 nonsafety-related Breakers in Warehouse Stock Examined as Part of Initiative Element Two ML20247D2491989-07-12012 July 1989 Forwards Communications Repts Associated W/Design Control Review ML20247A9261989-05-11011 May 1989 Forwards State of Tx & Local Govt Objectives for Graded Exercise Scheduled for 890725-26 ML20245J3341989-04-0707 April 1989 Forwards Summary of Points of Agreement Reached at 890308 Meeting.Agreements Will Be Subj to Further Discussion Among Parties.W/Certificate of Svc.Served on 890427 ML20246H4791989-03-0606 March 1989 Forwards Communications Repts Associated W/Corrective Action Programs for Plant Independent Assessment Program Phases ML20206F7201988-11-14014 November 1988 Forwards Communications Rept Transmittal 47 Re Independent Assessment Program on All Phases of Conduit Support Design Review ML20151X2621988-08-19019 August 1988 Forwards Rev 4 to Independent Assessment Program:Conduit Support Design Review Issues List for Comanche Peak Electric Station - Unit 1 ML20154H6281988-05-21021 May 1988 Requests to Be Advised at Earliest Opportunity Whether Projected Schedule for Issuance of Phase IV Rept Available. Related Correspondence ML20147G2941988-03-0303 March 1988 Forwards Communication Repts Re Cable Tray Audits,Per Independent Assessment Program ML20147F8911988-03-0303 March 1988 Forwards Communications Repts Associated W/Piping/Pipe Support Audits ML20147H4891988-03-0303 March 1988 Forwards Communications Repts Associated W/Independent Assessment Program Conduit Audits ML20147G2261988-03-0303 March 1988 Forwards Communications Repts Associated W/Civil/Structural Audits ML20196F7451988-02-23023 February 1988 Forwards Surveillance Repts Associated W/Phase 4 Independent Assessment Program Obtained During Util Review ML20196D4541988-02-0909 February 1988 Forwards Rev 4 of Mechanical Review Issues List (Ril). Rev Includes Review Issue 10 Re Component Cooling Water Sys Butterfly Valve at Outlet of Residual Heat Removal Hx.Rev of Ril Reflects Info That Cygna Gained Prior to Dec 1987 ML20236X2701987-11-25025 November 1987 Forwards Communications Repts on Independent Assessment Program,Phase 4 Re Cable Tray,Civil/Structural & Conduit Audits ML20236S1281987-11-13013 November 1987 Forwards Communications Repts Associated W/Civil/Structural Audits.List of Communications Repts Encl ML20236R9531987-11-13013 November 1987 Forwards Communications Repts Associated W/Cable Tray Audits.List of Communication Repts Encl ML20236S3231987-11-13013 November 1987 Forwards Communications Repts Associated W/Conduit Audits. List of Communications Repts Encl ML20236R9361987-11-13013 November 1987 Forwards Communications Repts Associated W/Piping/Pipe Support Audits.Repts Also Listed in Attachment ML20236M3131987-11-0909 November 1987 Forwards Communications Repts Associated W/Cable Tray Audits,Per Communication Repts Transmittal 33 for Independent Assessment Program - All Phases.List of Encl Communication Repts Provided on Attachment 1 TXX-6932, Advises That Value of 7.43 Ph Units Reported in Performance Evaluation Rept DMR-QA Study 7 Re 1987 NPDES QA Program Incorrect Due to Clerical Error.Reported Value Should Have Been 8.43 Ph Units,Which Is within Acceptable Range1987-11-0606 November 1987 Advises That Value of 7.43 Ph Units Reported in Performance Evaluation Rept DMR-QA Study 7 Re 1987 NPDES QA Program Incorrect Due to Clerical Error.Reported Value Should Have Been 8.43 Ph Units,Which Is within Acceptable Range ML20235W3331987-10-10010 October 1987 Forwards Communications Repts Re Civil/Structural Audits,Per Independent Assessment Program,Phase 4 ML20235V4691987-10-10010 October 1987 Forwards Communications Repts Re Cable Tray Audits,Per Facility Independent Assessment Program,Phase 4 ML20235R4941987-09-30030 September 1987 Notifies of Confirmation That Util Given Extension Until 871026 to Respond to Case Motion to Compel Applicants to Supply Complete Answers to Consolidated Intervenors Interrogatories & Request for Production of Documents ML20235R1961987-09-18018 September 1987 Forwards Rev 4 of Pipe Support Review Issues List. Any Procedural Control Issues Associated W/Author Original Pipe Support Reviews of Gibbs & Hill Being Processed as Part of Ongoing Design Control Assessments ML20235R0571987-09-18018 September 1987 Forwards Communications Repts Re Cable Tray Audits ML20234B1451987-09-16016 September 1987 Forwards Rev 4 to Pipe Stress Review Issues List (Ril).All Technical Issues Associated W/Discipline Closed.Still Waiting for S&W Calculation 15454-NZ(B)-GENX-035,Rev 2 to Verify Completion of Commitments Associated W/Ril 11 TXX-6718, Forwards Listed Outstanding Documents Requested Through Audits of Ebasco Svcs,Inc1987-09-0404 September 1987 Forwards Listed Outstanding Documents Requested Through Audits of Ebasco Svcs,Inc ML20238E5591987-09-0303 September 1987 Confirms That Brazos Understanding of Phrase,As Set Forth in Objections & Responses of 870814,essentially Correct. Related Correspondence ML20237K7081987-09-0101 September 1987 Forwards Communications Rept Transmittal 28,transmitting Cable Tray Audits Re Independent Assessment Program - Phase 4 for Plant.Delay in Processing Telcons Noted Due to Word Processing Sys Conversion.W/O Encl ML20237K7931987-09-0101 September 1987 Forwards Communications Rept Transmittal 29,transmitting Piping/Pipe Support Audits for Independent Assessment Program Phase 4.W/o Encl ML20237J9981987-09-0101 September 1987 Forwards Communications Rept Transmittal 27,transmitting Conduit Audits Re Independent Assessment Program - Phase 4 for Plant.Delay in Processing Telcons Noted Due to Word Processing Sys Conversion.W/O Encls ML20237K0091987-08-11011 August 1987 Memorializes Recent Conversations & Resulting Agreement Re Extension of Time Until 870908 for Filing Case & M Gregory Response to Applicant 870713 Motion for Reconsideration of Board 870622 Order.Related Correspondence ML20237J1281987-08-10010 August 1987 Forwards Rev 14 of Cable Tray Supports Review Issues List. Rev Based on Info Provided in Util Rev 2 to Generic Issues Rept for Cable Tray Hangers,Transcripts of Public Meetings & Results of Cynga Audits Through 870731 ML20236D3271987-07-22022 July 1987 Forwards Rev 0 to Civil-Structural Review Issues List, Based on Ref Info,Transcripts of Public Meetings,Documents Provided by Util & Results of Cygna Audits Through 870613 1999-06-16
[Table view] Category:EXTERNAL LETTERS ROUTED TO NRC
MONTHYEARML20056B3741990-08-21021 August 1990 Forwards Update to ASME Section Iii,Div 1 Code Control Program Documents for Incorporation Into State of Tx Dept of Licensing & Regulation Controlled Manual CCPM-15 ML20011E1521990-01-27027 January 1990 Forwards Addl Case Concern Repts 89-0025 Re Apparent Substandard Shop Applied Welds Internal to Secondary Side of Steam Generators & 89-0034 on Specific Wiring & Connection Method Damaging safety-related Electrical Wiring ML20248D0661989-09-21021 September 1989 Notifies Util of Case Position on Concerns & Problems in Scaling Calculation Program at Plant.Documentary Info Supporting Util Position on Aspect of Dispute Should Be Provided ML19332E0011989-09-14014 September 1989 Forwards Offsite Portion of Annual Emergency Preparedness Independent Review Per 10CFR50.54(t) ML19332D4781989-09-14014 September 1989 Forwards Offsite Portion of Annual Emergency Preparedness Independent Review to Be Conducted Every 12 Months.Review Must Include Evaluation for Adequacy of Interfaces W/State & Local Govts ML19332C8171989-09-14014 September 1989 Forwards Offsite Portion of Annual Emergency Preparedness Independent Review & Status of Corrective Actions Initiated, Per 10CFR50.54(t) ML19332C7971989-09-14014 September 1989 Forwards Offsite Portion of Annual Emergency Preparedness Independent Review & Status of Corrective Actions Initiated, Per 10CFR50.54(t) ML20246A0421989-08-18018 August 1989 Advises That S&W Notified by Util That Responsibility for Facility Code Control Program Will Be Terminated Effective on 890823.EBASCO Svcs,Inc Selected to Assume Responsibility for Code Control Program Effective on 890824 ML20247R7291989-07-28028 July 1989 Advises That Status of Suspect molded-case Curcuit Breakers, Identified in Initiative Element One Will Be Provided by 890815.Util Estimates That 750 nonsafety-related Breakers in Warehouse Stock Examined as Part of Initiative Element Two ML20247D2491989-07-12012 July 1989 Forwards Communications Repts Associated W/Design Control Review ML20247A9261989-05-11011 May 1989 Forwards State of Tx & Local Govt Objectives for Graded Exercise Scheduled for 890725-26 ML20245J3341989-04-0707 April 1989 Forwards Summary of Points of Agreement Reached at 890308 Meeting.Agreements Will Be Subj to Further Discussion Among Parties.W/Certificate of Svc.Served on 890427 ML20246H4791989-03-0606 March 1989 Forwards Communications Repts Associated W/Corrective Action Programs for Plant Independent Assessment Program Phases ML20206F7201988-11-14014 November 1988 Forwards Communications Rept Transmittal 47 Re Independent Assessment Program on All Phases of Conduit Support Design Review ML20151X2621988-08-19019 August 1988 Forwards Rev 4 to Independent Assessment Program:Conduit Support Design Review Issues List for Comanche Peak Electric Station - Unit 1 ML20154H6281988-05-21021 May 1988 Requests to Be Advised at Earliest Opportunity Whether Projected Schedule for Issuance of Phase IV Rept Available. Related Correspondence ML20147F8911988-03-0303 March 1988 Forwards Communications Repts Associated W/Piping/Pipe Support Audits ML20147G2941988-03-0303 March 1988 Forwards Communication Repts Re Cable Tray Audits,Per Independent Assessment Program ML20147H4891988-03-0303 March 1988 Forwards Communications Repts Associated W/Independent Assessment Program Conduit Audits ML20147G2261988-03-0303 March 1988 Forwards Communications Repts Associated W/Civil/Structural Audits ML20196F7451988-02-23023 February 1988 Forwards Surveillance Repts Associated W/Phase 4 Independent Assessment Program Obtained During Util Review ML20196D4541988-02-0909 February 1988 Forwards Rev 4 of Mechanical Review Issues List (Ril). Rev Includes Review Issue 10 Re Component Cooling Water Sys Butterfly Valve at Outlet of Residual Heat Removal Hx.Rev of Ril Reflects Info That Cygna Gained Prior to Dec 1987 ML20236X2701987-11-25025 November 1987 Forwards Communications Repts on Independent Assessment Program,Phase 4 Re Cable Tray,Civil/Structural & Conduit Audits ML20236S3231987-11-13013 November 1987 Forwards Communications Repts Associated W/Conduit Audits. List of Communications Repts Encl ML20236S1281987-11-13013 November 1987 Forwards Communications Repts Associated W/Civil/Structural Audits.List of Communications Repts Encl ML20236R9531987-11-13013 November 1987 Forwards Communications Repts Associated W/Cable Tray Audits.List of Communication Repts Encl ML20236R9361987-11-13013 November 1987 Forwards Communications Repts Associated W/Piping/Pipe Support Audits.Repts Also Listed in Attachment ML20236M3131987-11-0909 November 1987 Forwards Communications Repts Associated W/Cable Tray Audits,Per Communication Repts Transmittal 33 for Independent Assessment Program - All Phases.List of Encl Communication Repts Provided on Attachment 1 TXX-6932, Advises That Value of 7.43 Ph Units Reported in Performance Evaluation Rept DMR-QA Study 7 Re 1987 NPDES QA Program Incorrect Due to Clerical Error.Reported Value Should Have Been 8.43 Ph Units,Which Is within Acceptable Range1987-11-0606 November 1987 Advises That Value of 7.43 Ph Units Reported in Performance Evaluation Rept DMR-QA Study 7 Re 1987 NPDES QA Program Incorrect Due to Clerical Error.Reported Value Should Have Been 8.43 Ph Units,Which Is within Acceptable Range ML20235V4691987-10-10010 October 1987 Forwards Communications Repts Re Cable Tray Audits,Per Facility Independent Assessment Program,Phase 4 ML20235W3331987-10-10010 October 1987 Forwards Communications Repts Re Civil/Structural Audits,Per Independent Assessment Program,Phase 4 ML20235R4941987-09-30030 September 1987 Notifies of Confirmation That Util Given Extension Until 871026 to Respond to Case Motion to Compel Applicants to Supply Complete Answers to Consolidated Intervenors Interrogatories & Request for Production of Documents ML20235R1961987-09-18018 September 1987 Forwards Rev 4 of Pipe Support Review Issues List. Any Procedural Control Issues Associated W/Author Original Pipe Support Reviews of Gibbs & Hill Being Processed as Part of Ongoing Design Control Assessments ML20235R0571987-09-18018 September 1987 Forwards Communications Repts Re Cable Tray Audits ML20234B1451987-09-16016 September 1987 Forwards Rev 4 to Pipe Stress Review Issues List (Ril).All Technical Issues Associated W/Discipline Closed.Still Waiting for S&W Calculation 15454-NZ(B)-GENX-035,Rev 2 to Verify Completion of Commitments Associated W/Ril 11 TXX-6718, Forwards Listed Outstanding Documents Requested Through Audits of Ebasco Svcs,Inc1987-09-0404 September 1987 Forwards Listed Outstanding Documents Requested Through Audits of Ebasco Svcs,Inc ML20238E5591987-09-0303 September 1987 Confirms That Brazos Understanding of Phrase,As Set Forth in Objections & Responses of 870814,essentially Correct. Related Correspondence ML20237K7931987-09-0101 September 1987 Forwards Communications Rept Transmittal 29,transmitting Piping/Pipe Support Audits for Independent Assessment Program Phase 4.W/o Encl ML20237J9981987-09-0101 September 1987 Forwards Communications Rept Transmittal 27,transmitting Conduit Audits Re Independent Assessment Program - Phase 4 for Plant.Delay in Processing Telcons Noted Due to Word Processing Sys Conversion.W/O Encls ML20237K7081987-09-0101 September 1987 Forwards Communications Rept Transmittal 28,transmitting Cable Tray Audits Re Independent Assessment Program - Phase 4 for Plant.Delay in Processing Telcons Noted Due to Word Processing Sys Conversion.W/O Encl ML20237K0091987-08-11011 August 1987 Memorializes Recent Conversations & Resulting Agreement Re Extension of Time Until 870908 for Filing Case & M Gregory Response to Applicant 870713 Motion for Reconsideration of Board 870622 Order.Related Correspondence ML20237J1281987-08-10010 August 1987 Forwards Rev 14 of Cable Tray Supports Review Issues List. Rev Based on Info Provided in Util Rev 2 to Generic Issues Rept for Cable Tray Hangers,Transcripts of Public Meetings & Results of Cynga Audits Through 870731 ML20236D3271987-07-22022 July 1987 Forwards Rev 0 to Civil-Structural Review Issues List, Based on Ref Info,Transcripts of Public Meetings,Documents Provided by Util & Results of Cygna Audits Through 870613 ML20216D1721987-06-20020 June 1987 Ack Receipt of .Clarifies Agreement Made During Telcon Re Date for Case to File Initial Supplementary Responses Deferred Until 870706.Necessary Discovery & Response Should Be Completed Also.Related Correspondence ML20215D7141987-06-0303 June 1987 Informs All Concerned W/Facility Independent Assessment Program of Address Correction ML20214S0641987-05-26026 May 1987 Ack Receipt of Applicant 870518 Fifth Progress Rept.Requests That Recipient Notify of When Substantive Matls Will Be Made Available So Case May Decide on Course of Action Re Comanche Peak Response Team Adequacy Issues.Related Correspondence ML20234C6731987-05-0101 May 1987 Forwards Communications Repts Associated W/Cygna Audits of S&W Civil/Structural Action Plan Re Plant Independent Assessment Program - Phase 4 ML20234C4401987-05-0101 May 1987 Forwards Communication Repts Re Cygna Audits of S&W Piping & Pipe Support Verification Activities,Per Phase 4 of Independent Assessment Program.Submittal Constitutes Communications Rept Transmittal 23 TXX-6361, Forwards Receipt to Ack Part 21 Rept Re Qualification Test Rept F-C5205-3, Nuclear Qualification - Terminal Blocks1987-03-23023 March 1987 Forwards Receipt to Ack Part 21 Rept Re Qualification Test Rept F-C5205-3, Nuclear Qualification - Terminal Blocks ML20205C0741987-03-18018 March 1987 Forwards Comments & Questions on Ebasco & Util Procedures & Criteria Re Responses to Conduit Support Review Issues List for Upcoming 870324 & 25 Conduit Support Meetings Per Rev 0 to Generic Issues Rept 1990-08-21
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- BISHOP, LIBERMAN, COOK,-PURCELL & REYNOLDS i2oo sevcNrccNrw sincer, s.w. 'N .N EW vo R a g4gg WAS H I N GrO N, D. C. 2O O 3 6 USMC es swCP, u BCRM AN & COOM -
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cc.4Eitte .s :t- . I <2om>857-9837 December 3, 1984 Mrs. Juanita ElIis President, CASE 1426 South Polk Street Dallas, Texas 75224 Subj: Texas Utilities Electric Company, et al.
(Comanche Peak Steam Electric Station, Units 1 & 2); Docket Nos. 50-445 and 50-446el,
Dear Mrs. Ellis:
Enclosed is a copy of a letter Applicants transmitted to the boaff regarding Applicants' analysis of the steam generator upper lateral restraints. This letter responds to certain questions raised by the NRC Staff during the November 13, 1984, meeting with Applicants on that topic.
Sincerely,
) I' f .
,h William A.V krin
. W Counsel for Applicants cc: w/o encl. Remainder of Service List 8412040286 841203 '
PDR ADOCK 05000445 g PDR D SO3.
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-TEXAS UTILil 3 GENElGTl:u , OJ.MIRNY
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DEC 021984 November' 21, 1984 Geary Mizuno,' Esquire
'U. S. Nuclear Regulatory Commission
'7735 Old Georgetown Road Room 10107 Bethesda, Maryland 29814 -
Subj: Texas Utilities Electric Company.(Comanche Peak Steam Electric Station, Units 1 and 2);
Docket Nos. 50-445 and 50-446
Reference:
- 1) Gibbs & Hill letter GTN-69363 dated August 21, 1984
- 2) Transcript of Meeting of November 13, 1984 in Bethesda, Maryland between Applicants, the NRC and NRC Consultants On November 13, 1984 a meeting was held between the NRC and representatives of the Applicants, to discuss Applicants analyses employed in the justifi-cation of the adequacy'of the steam generator upper lateral support (see Applicants' Motion'for Summary Disposition Regarding Upper Lateral Restraint Beam and accompanying Affidavit of R. C. Iotti).
At the conclusion of the meeting Appligants were requested to provide written statements on several items as listed below: ,
- 1. A justification of the approach taken in the analyses of the upper lateral restraint beam proper and the concrete to which it is attached,
- 2. A configuratinn of the maximum calculated MSLB temperature and of the temperature used in the, Affidavit analyses,
- 3. A confirmation of waich of the load cases examined JLn the Affidavit analyses is addressed by the calculations shown on page 60 of Reference 1, ;
4, A clarification and nodification of the statement appearing as item 5.b(3) on page 4 of the minutes of the meeting transmitted by Reference 1, ;
- 5. A clarification and m<dification of item 6C on page 5 of the same minutes,
- 6. A clarification of how shear loads and stresses are handled at the fixed boundary chosen for the structural model executed for the case of the
-concrete tensile strengtn equal to zero, and
- 7. A confirmation that the NASTRAN program employed in the Affidavit analyses has been used exclusively for these analyses, and has not been used in any other analysis or design at Comanche Peak.
Accordingly we provide the follewing: .
- a. Applicants used a dual approach to determine the adequacy of the upper lateral restraint beam proper and of the concrete to which it is attached.
The dual approach consists of two beundine analyses. As stated in the Affidavit at 4, the first analysis provides the upperbound on the physical
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G. Mizuno effects on concrete walls (i.e., wall deformation and cracking). For this analysis no credit is given to the tensile capacity of concrete. This analysis overestimates cracking in the concrete but underestimates its real restraining effects on the upper (and lower) lateral restraint beam thermal cxpansion, since the lesser the extent of cracking is, the stiffer is the concrete wall.
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As such, this analysis underestimates the real loads that would occur in the lateral restraints when they thermally expand.
To assess and bound the maximum load on the beam and stresses in rein-forcement, the second analysis assumed that the concrete would have a tensile capacity of 450 psi (see Affidavit at 5).
The extent of cracking, its distribution, and therefore, the capacity of the concrete to resist applied loads, including the beams' thermal expansion j loads for accident conditions, as predicted by the NASTRAN program with the i concrete tensile strength at 450 psi, has been questioned by the NRC and its consultants, because the program does not reproduce experimental results at high applied loads. '
Experimental results discussed in the meetings refer to tests of simple concrete beams loaded in the center. The NASTRAN program would predict failure of the beams at higher loads than experiments have shown, where high tensile strength is employed. However, it predicts results similar to experiments when low tensile strengths, i.e., below 120 psi, are used. Consequently, the extent of cracking as predicted by the NASTRAN program is less than that which actually takes place.
The effect of this underprediction is to overestimate the concrete resis-tance (stiffness) to an applied load. In terms of the analyses performed .
8 for the upper (and ' lower) lateral restraint beams, the overprediction of the concrete stiffness would lead to a conservative evaluation of the loads ex-perienced by the beams themselves, i.e., the NASTRAN program would predict higher loads for the beams than would actually occur. ~
- To ascertain the possible conservatism inherent in the analytical predic-tions stemming from the NASTRAN program, Applicants have determined the finite -
elements in which the in-plane shear loads would be sufficiently large that the program may incorrectly predict no crack formation. In plane shears in excess of 120 psi accompanied by principal tensile stresses of comparable magnitude are indicative of conditions where experimental data suggests cracking might initiate and likewise where NASTRAN does not predict cracking if the concrete =
tensile strength is assumed to be 450 psi. Applicants found that relatively few elements in the vicinity of the beam embedments fall in this category.
Had the NASTRAN program predicted that these elements cracked more exten-sively, the resistance of the concrete would have been lower and the beams' load would have been less than reported in Tables 1 and 2 of the Affidavit under the columns labelled " Concrete Tensile Strength = 450 psi". -
Applicants therefore conclude that the dual approach taken to examine the worst conditien for concrete (zero tensile strength) and the worst loading for the upper la eral restraint (made even worse by the overprediction of concrete resistance by NASTRAN) provide assurance that the upper lateral restraint and the concrete are adequately designed for the loading condit ions examined.
1 '
Iage13
- G. Mizuno 4
'. iThere is some confus' ion as to the values calculated or used for'the Affi .
. b-davit analyses of the Main Steam Line Break accident consequences on the 3 lateral restraints and concrete. Part of the confusion stems from the fact 5
. that Applicants utilized 'a conservative peak figure of. 3700F in said analy- if-sis (see Affidavit at 10 and Appendix I Figure 2) rather than the peak il values actually calculated for the uppersand lower lateral restraint from the RELAP 4, HEATING 5 analyses (thermo-hydraulic and heat transfer, respectively) have,been reported in the Affidavit.as being approxima'tely. .
3550F at approximately 300 seconds (Affidavit at 10). In addition, on p
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page 6 of-the. Minutes of the Meeting attached to Reference 1, temperature values calculated for the upper and lower. lateral restraint have been re- -
ported as 3400F and 3500F respectively at 324 seconds. ,
.5 The reason for the apparently conflicting information is the lack' of a ~
clarifying explanation on these latter values on page 6 of the minutes of the meeting. Whereas 3550F represents the approximate average of the maximum temperature of both beams-(and 370 F was actually used in the analy-ses), the temperatures quoted of 3400F and 3500F are the temperatures of the two beams at'the time when the largest difference in temperature exists between the two. .They are not the maximum calculated beam temperatures.
These temperatures were used to respond to the NRC question which requested an assessment of the effects on the walls of using actual simultaneous beam temperatures rather than maximum temperatures used in the Af fidavit analyses. The maximum effect on walls from differences in temperatures between the two-beams obviously results where the difference is maximum, and this is why those two temperatures were used. ,
- c. The load case analyzed on page 60 of the calculations attached to Reference 1, is the load combination of nominal differential pressure across the com-
.partment walls of 1 psi, plus peak temperature in the beams ~which repre-sents-the worst condition for the case of the Main Steam Line Break. It ~
corresponds to the case reported under the column labelled "Concret'e Ten-
-- sile Strength - 450 psi" of the Main Steam at 324 seconds. .
To further clarify this, we are including a modified sheet No. 60 and a ,
page of pertinent computer output as Exhibit 1. One can verify the corre-
"- ;" - sponden~ce-of'the case with Table 1 attached, where the axial stress is -
; _ reported as 13.3 ksi.
- d. The statement appearing as Item 5.b(3) on page 4 of the minutes of the meeting transmitted by Reference 1 could be misleading. Accordingly, the
'following statement should be substituted.
"The NRC pointed out'during the audit that the boundary condition used by Gibbs & Hill in the analyses along the z-direction is' incorrect in thr.t it .
does not: reflect the freedom of the structure to move. Gibbs & Hill acknow-ledged that strictly speaking this is true. However, use of a fixed boundary condition in the z-direction permitted a considerable simplifica-tion ~1n the analysis by allowing use of a symmetric model, and based on -
the fact that the' seismic stress in the compartment walls obtained from the' previous analysis using a' full model is relatively small, Gibbs & Hill concluded that the boundary condition used in the analysis has little effect on'the result. NRC concurred that the results would be acceptable provided.
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.G.'Mizuno that Gibbs & Hill calculations demonstrated that the seismic loads were -
only a small_ fraction of the total load. Gibbs & Hill is to submit calculations."
Gibbs & Hill has submitted such calculations in Reference 1, calculation set SRB-4C3, Set 2-16 sheets,
- e. The statement made in the minutes of the meeting attached to Reference 1 3 on page 5, Item C, requires'some clarification.
In the ASLB Hearings, the only case discussed was the LOCA case. The MSLB case has been introduced by Applicants in their Affidavit. Conse-quently, the LOCA case had been the only case which had received attention and for which loads had been computed under the assumption that- the com-partment waM s are infinitely rigid. -In the minutes of the meetings Gibbs & Hill repeated the same calculations and stated that the beam stresses computed from these calculations (page 55 of calculations attached to Reference 1) are below the yield point. In fact, they would be below 0.9 Fy = 45 ksi since they are 39.36 ksi. The Gibbs & Hill calculations, however, do not address the case of the Main Steam Line Break. For this case, if one were to consider the unrealistic condition that the walls are infinitely rigid, one would compute a beam stress equal to 55.8 ksi, which is in excess of the yield point. ,
Both calculations, however, are extremely ' conservative, and not representa-tive of the real stresses resulting in the beams. Nevertheless for the J purposes of accuracy, the statement on page 5 Item C is revised as follows:
"c. Calculations were developed and reviewed for the LOCA case, based on the assumption that the beam restraints (compartment walls) are ,
infinitely rigid. These showed beam stresses below the yield point.
Gibbs & Hill stated that this upper bound case, although unrealistic because the structure is not rigid, had also been discussed during -
the 1983 ASLB hearings. An equivalent calculation for the MSLB has not been" performed, as that case had not been discussed in the hearings, and would have no merit, considering the detailed analysis
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that has been perfor.ned. In fact, the LOCA case was done because -
'W Cibbs & Hill felt it had been requested by t.he NRC. Had the calcu- _ ;
lation with infinitely rigid walls been performed for the MSLB, stresses computed in the beam would be above yicid."
- f. 'To clarify how shear loads (and stresses) are handled at the fixed boundary of the base of the structural model used in the analyses, the result for one of the finite elements at the base of the model, together with explana-tion sheets is indicated as an example in Exhibit 2. A similat table is l available ror each finite element at the base. The particiilar plate being 1 exemplified by sheet 89 is element 861, which is at the base of S.G.
compartment 1, and which can be seen-in Figure 3 of Appendix IV of the Affidavit.
- g. Applicants have used the NASTRAN program with the cracking concrete feature
- only in two instances for Comanene Peak. The one instance is the analyses of the load distribution and cracking pattern in the concrete walls and lateral heams performed to provide the inf ormation supt lied in the Appli-cants' Af fidavit regarding the L'pper Lateral Restraint Beam, k'e twe i l
Page 5' G. Mizuno subsequently identified another instance where use was made of the
-cracked concrete versionLof NASTRAN; 1his instance was for the analyses Lof 'a similar steel beam expansion between two concrete beams, which also utilized the boundary cases of 0 and 450 psi tensile strength. This later analysis was employed for evaluation of the loads on concrete beams from support FW-1-097-018-C62R expanding between concrete beams B-13 and B-14 at Elevation 885'-6" in the containment Building. Its results, however, have not been directly used in preparation of the Affidavit and Motion regarding 'bif ferential Displacements of Large-Framed, Wall-To-Wall and Floor-To-Ceiling Pipe Supports", which include this support but have been used to verify the adequacy of design of the concrete beams.
It is to be noted thct in this latter case, in-plane shear stresses for all the elements are well below 100 psi. Hence, the NASTRAN predictions even at the higher tensile strengths are expected-to be accurate.
'Briefly discussed during the meeting was also the appropriateness of a heading used in the minutes of the meeting of. Reference 1, on page 6, wherein a designa-tion "As Designed" was used. A better term would be "As Analyzed" since those values refer to the temperatures employed in the analyses performed for the Affidavit.
We trust to have provided all information that we agreed to provide during the 11/13/84 meetings. Please call if you liave any questions.
Very truly yours, TEXAS UTILITIES GENERATING COMPANY El
[#[ J . B. George / ,
Vice-President / Project General Manager JBC/RCI/cp [
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cc: W. Ilorin R. C. Iotti
= J. Eichler M. Reich S. Burwell
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- Tables 1&2 in Affidavit of Robert C. Iotti Regarding Upper Lateral Restraint Beam, May 20, 1984
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.-------------_--,==---= --------------------------------------=----------------------------~~------------------
LEGEND - IDAD COMBINATIONS .
P1 = Peak Pressure M1 = Peak mechanical loads -
o? - Nominal (1 psi) pressure SO = No Seismic loads vt u Peak Temperature S1 = Maximum Seismic (incl. primary system seismic)
T2 = Associated Temperature at given time S2 = Maximum Seismic (w/o primary system seismic)
MO = No mechanical' loads S3 = Maximum Seismic (incl. primary a stem seismic added separately)
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