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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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TEXA i UTILITIES GENERATING COMPANY P, o. box 1002 GI EN ROSE. TEXAS 76043 November 16, 1984 /:7 M
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t's. N. H. Williams Project Manager CYGNA Energy Services 101 California Street, Suite 1000 Stsa Francisco, California 94111-5894 '
COMAhCHE PEAK STEAM ELECTRIC STATION Independent Assessment Program Phase 3 Cinched U-Bolt Testing & Analyses Program Additional Information REF: 1) J. B. George (TUCCO) letter to N. H. Williams (CYGNA), dated November 1, 1984 - same subject
- 2) N. H. Williams (CYGNA) letter to J. B. George (TUCCO), " Status of Cinched U-Bolt Testing and Analyses Program", 84042.018 dated October 1, 1984
Dear Ms. Williams:
Reference i provided in its attachment the information requested by Reference
- 2. Included in the attachment as part of the answer provided to Item 2 of Reference 2 were results of a finite differetree heat transfer analysis con-ducted for an uninsulated and an insulated U-bolt configuration on a 10-inch pipe.
A rechecking of the modelling of the contact areas between the U-bolt and the pipe and the pipe and the crosspiece has indicated that the contact be-tween the pipe and crosspiece was overestimated and thac the contact between the pipe and the U-bolt had been incorrectly assumed to extend for an arc or 1800 Accordingly, we are providing in the attachment to this letter the results obtained for the uninsulated case of the pipe at 2500 F and the in-sulated case with the pipe at 350 F, where the boundary conditions of the model are changed to reflect the more realistic contact areas. We will be glad to discusr the details of the model, if CYGNA so desires.
Please call if you have any questions.
Very truly yours, TEXAS yTILITIES GENERATING COMPANY
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/ . .-. c 0 69c O' eor j Vice President / Project General Mar:ager JBG/RCI/gh 4 ;
cc: S. Burwell R. Iotti J. Van Amerongen D. Wade I f
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ATTACHMENT 1 Revision to Item 2 of Reference 1.
Please replace Item 2 response with the following:
A. The answer to this question is best worded by first restating that the choice of 2500F for the 10-irch pipe temperature is a compromise choice which bounds the majority of the systems in the plant, and where used with an uninsulated U-bolt configuration is also representative of the case where the pipe temperature may be 3500F but the U-bolt configuration is insulated.
Second, it is important to point out that there is a cingle cinched-up U-bolt which is used on the 10-inch portion of the RHR system. This is support RH-1-024-007-S22R which is on line 10-3H-1-24-601-R-2, which is connected to the outlet line of the RHR heat exchanger. The maximum normal temperature seen by the line is 2800F during initiation of RHR operation. Only under upset conditions, where component water cooling may be lost, can the maximum temperature of this line reach 3500F. There are no cinched-up U-bolts on the inlet side of the RER heat exchangers.
Third, it is germane to point out that the tests conducted on the 10-iu.h pipe specimens had a corresponding average temperature of the U-bolt equal to approximately 1500F. For the particular configuration examined here, i.e.,
stainless steel pipe and carbon steel U-bolt, the approximate 1500F represents the equilibrium temperature of the U-bolt. The following describes the tem-perature history during the thermal cycling test and the creep test for both the U-bolt and the crosspiece.
Thermal Cycle 1:
The pipe reached the test temperature of 250 F at 30 minutes, but then con-tinued to climb to over 2800F before settling back down ot 2580F. The U-bolt radius and leg stabilized around 1950F and 1500F, respectively, near the end of the cycle. See Figure 3.
Thermocouples 2, 9 and 10 on the crosspiece reached temperatures of 1290F, 136 F and 1440F, respectively, at the end of Cycle 1. These are less than the equilibrium temperatures reached during the creep test. Figure 4 shows that temperatures had not leveled off. Refer to Figure 9 for location of thermocouples.
Thermal Cycle 6:
The pipe reached an equilibrium temperature of 2500F within 20 minutes. The U-bolt radius and leg reached 18301 and 144 F, respectively, arcuad I hour.
See Figure 5.
Thermcouples 2, 9 and 10 on the crosspiece reached temperatures of 1250F, 1320F and 1390F, respectively, at the end of Cycle 6. These are less than the equilibrium temperatures reached during the creep test. Figure 6 snows that temperatures had not leveled off.
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, The pipe reached an equilibrium tecperature of 2500F in less than i hour.
The U-bolt radius stabilized at 1850F within i hour. The U-bolt leg sta-
.bilitad at 1480F within-2 hours. _See Figure 7.
Thermocouples 2, 9 and 10 on the crosspiece reached equilibrium' tempera-tures of 1380F, 1460F and 1540F, respectively, around 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. See Figure 8.
10" Specimen Summary:
With a pipe test temperature of 2500F, the U-bolt reached thermal equili-brium during each cycle of the thermal cycling test, but the crosspiece didn't. The entire assembly reached thermal equil$brium shortly into the creep test. A summary-is provided in Table 1.
Results of finite difference thermal analyses are very sensitive to the assumed area of contact between the pipe and the U-bolt and the pipe and the crosspiece.
When the U-bolt is cinched, the line contact between the pipe and the U-bolt extends for an arc which is less than 1800 , and the precise extent of which depends on the cinching force and the spacing of the bolt holes in the crosa-piece. Similarly the cinching process tends to produce a loss cf contact at some points between the crosspiece and the pipe due to-either bending cf the crosspiece or local deformation of the pipe. This loss of contact, however small, profoundly affects the heat transferred from the pipe to the crosspiece.
A heat transfer model has been executed for the uninsulated U-bolt configura-tion with the following assumptions. Heat transfer from the pipe to the U-bolt is along an are near the apex of the U-bolt. At the diametral location there is a small gap (less than 1/16") between the pipe and U-bolt. No gcps are assumed betwe(a the U-bolt and the crosspiecc (the assumpcion is believed to be inconsequential since both elements are roughly at the same temperature at that location). Heat transfer between the pipe and the crosspiece takes place through a line contact extending 2 inches along the pipe, and via gap conductance, along the circumference of th pipe and through a gap increasine t from zero to 1/128" linearly from the end of the contact area to the end of i
the place. Likewise, the heat transfer between the pipe and the U-bolt also considers the gap conductance with areas immediately adjacent to the line of contact and extending out to the U-bolt radius. This model produced results j which more closely match the results of the test.
)' Results of the analyses are shown in Figure 1 for the uninsulated case. In Figure 2 similar results are shown for the insulated case. The only difference between the latter analyses and that of the uninsulated configuration are the pipe temperature, which in the latter instance is 3500F, and the presence of j insulation.
I For the uninsulated case the average temperature of the U-bolt in the curved j portion is 175-1800F, while the straight portion is at about 150 F. For the insulated case the corresponding temperatures are approximately 3000F and j 2600 F respectively.
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Page 3 The effect of the temperature rise on the clamping forces acting on the pipe and the U-bolt for the two cases of 2500F pipe, uninsulated U-bolt and 3500F pipe, insulated U-bolt, can be estimated by comparing the relative growth of the pipe to U-bolt for the two cases, neglecting any deformation of the pipe.
Since only relative growth is pertinent here, the one-directional growth of the U-bolt due to thermal expansion given as Yi where Yi= 43 TL where L is the projected length of the U-bolt which is given as 2R and T is the temperature differential between the average U-bolt temperature and ambient (or a reference temperature), is compared to the diametral growth of the pipe, Y2 , which is given as Y2= dz AID The worst case relative expansion will occur for the stainless steel pipe and the carbon steel U-bolt. For the 10-inch pipe (10.75 OD), coefficients of thermal expansions (= 6.3 X 10-6 in/in/0F at 150-1800F or 6.6 X 10-6 at 260-300 F and d,= 9.4 X 10-6 at 250oF or 9.53 X 10-6 at 350 F and a reference ambient temperature of 700F, the relative expansion for the two cases con .
sidered, i.e., 2500F pipe with bare U-bolt, and 350 F pipe with insulated U-bolt are as follows:
- 1. 2500 F AY = 0.011755 inches
- 2. 3500F AY = 0.0137 inches i
). 3. Finite Element Analysis 3h' = 0.0141*
(* Finite Eleme.nt Analysis used 210 F.)
As seen from the above, theoretical, steadystate heat transfer analyses would predict that the case of 3500F pipe expanding against an insulated U-bolt j could result in a differential pipe expansion which would be soproximately 17%
j Jarger than could be expected for a 250 F pipe with uninsulated U-bolt. How-
, ever, the finite element analysis has been conducted in a manner that would encompass the case of 3500F insulated U-bolt. As saen from the third row of relative expansion, the finite element analysis, which used a pipe temperature of 210 F but maintained the U-bolt temperature at 700F, would yield a relative expansion which is comparable to the case of 3500 insulated.
Another point to be discussed, is that the test has provided information on the transient thermal expansion differential between the pipe and the U-bolt.
As seen from the data which is attached as Figures 3 and 5, the maximum temperature differential Fetwecn the pipe and the U-bolt occurred when the U-bolt has reached a representative temperature of about 101-1050 while the .
0 pipe had been heated to 250-255 , a difference in temperature of approximately 1500F. This difference is well simulated in the finite element analysis where there is a c',astant ditference in temperature of 140 F. It should also be remembered that for these temperature differentials, the amount of stress caused by the thermal expansion is not very significant.
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i TABLE 1 I
4 U-BOLT TilERMAL AND CREEP TEST DATA EVALUATION 4
I TIME REQUIRED TO REACll .
EQUILIBRIUM TEMPERATURE, *F EQUILIBRIUM TEMPERATURE, HOURS U-BGLT U-BOLT % U-BOLT U-BOLT ,
PIPE RADIU9 I.EGS T/C 2 T/C 9 T/C 10 PIPE RADIUS 1.ECS T/C 2 T/C 9 T/C 10 I
1 -" INSUI.ATED SPECIMEN I
TilERMAL CYCLE 1 559 498 451 * *
- I T l THERMAL CYCLE 6 560 530 440 * *
- g CREEP 564 495 451 322 340 365 2.0 2.0 2.0 3.0 3.0 3.0 y r-IIE C 250 195 150 * * * .50 1.5 1.5 * *
- TilERMAL CYCLE 6 250 183 144 * *
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CREEP 250 185 148 138 14o 154 1.0 2.0 2.0 3.0 3.0 3.0 1.I
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l THERMAL CYCLE 1 560 * * * *
- i j THERMAL CYCLE 6 560 t
j l CREEP 563 440 353 154 175 251 4.5 11.5 12.5 14.5 14.5 14.5 l - - I -
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