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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:INCOMING CORRESPONDENCE
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 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 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999 Forwards Revised COLR, for Cycle 5 for Unit 2 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 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 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 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 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 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 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 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 ML20210S6411999-08-12012 August 1999 Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested 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 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 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 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, 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 ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 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 ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval ML20209G0721999-07-13013 July 1999 Forwards Monthly Operating Repts for June 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs of SV Occurred During Reporting Period ML20209F0681999-07-0909 July 1999 Informs That Effective 990514,TU Electric Formally Changed Name to Txu Electric.Change All Refs of TU Electric to Txu Electric on Correspondence Distribution Lists ML20209E0421999-07-0909 July 1999 Forwards Response to NRC Request for Addl Info on LAR 98-010.Attachment 1 Is Affidavit for Info Supporting LAR 98-010 ML20209B6021999-06-30030 June 1999 Submits Second Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Readiness Disclosure for Reporting Status of Facility Y2K Readiness Encl ML20195J6981999-06-15015 June 1999 Provides Addl Info Related to Open Issue,Discussed in 990610 Conference Call with D Jaffe Re ISI Program Relief Request L-1 Submitted by Util on 980220 ML20196A4921999-06-15015 June 1999 Forwards Rev 30 to Physical Security Plan.Rev Withheld,Per 10CFR73.21 ML20195J0491999-06-14014 June 1999 Submits Response to RAI Re Implementation of 1.0 Volt Repair Criteria ML20195J0651999-06-14014 June 1999 Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves 05000445/LER-1999-001, Forwards LER 99-001-00, Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures. New Licensing Commitments Identified in Attachment 11999-06-0808 June 1999 Forwards LER 99-001-00, Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures. New Licensing Commitments Identified in Attachment 1 ML20195F0091999-06-0808 June 1999 Forwards Response to RAI Re Units 1 & 2 ISI Program for Relief Requests E-1 & L-1.Communication Contains No New Licensing Basis Commitments Re Cpses,Units 1 & 2 ML20207E1921999-05-28028 May 1999 Submits Updated Request for NRC Staff to Review & Approve Certain Changes to CPSES Emergency Plan Submitted in 981015 & s Prior to Changes Being Implemented at CPSES ML20207E1711999-05-28028 May 1999 Supplements 990526 LAR 99-004 as TU Electric Believes Extingency Exists in That Proposed Amend Was Result of NOED Granted to Prevent Shudown of CPSES Unit 1 ML20207D9841999-05-26026 May 1999 Requests That NRC Exercise Enforcement Discretion to Allow Cpses,Unit 1 to Remain in Mode 1,power Operation,Without Having Performed Svc Test,Per SR 4.8.2.1d on Unit 1 Battery BT1ED2 ML20195B6351999-05-25025 May 1999 Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves TXX-9912, Forwards Txu Electric (Formerly TU Electric) CPSES Emergency Preparedness Exercise Scenario Manual for 990721-22,Graded Exercise1999-05-21021 May 1999 Forwards Txu Electric (Formerly TU Electric) CPSES Emergency Preparedness Exercise Scenario Manual for 990721-22,Graded Exercise ML20206U1981999-05-20020 May 1999 Forwards Form 10K Annual Rept,Per 10CFR50.71(b). Communication Contains No New Licensing Basis Commitments Re Cpses,Units 1 & 2 ML20196L1931999-05-20020 May 1999 Forwards MOR for Apr 1999 for Cpses,Units 1 & 2.During Reporting Period There Have Been No Failures or Challenges to Power Operated Relief Valves or Safety Valves TXX-9911, Forwards non-proprietary & Proprietary Responses to RAI Re LAR 98-010 by Incorporating Attached Changes Into CPSES Unit 2 OL NPF-89 & CPSES Units 1,OL NPF-87 & 2 TS to Increase Licensed Power.W & Caldon Proprietary Responses Withheld1999-05-14014 May 1999 Forwards non-proprietary & Proprietary Responses to RAI Re LAR 98-010 by Incorporating Attached Changes Into CPSES Unit 2 OL NPF-89 & CPSES Units 1,OL NPF-87 & 2 TS to Increase Licensed Power.W & Caldon Proprietary Responses Withheld 1999-09-03
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059K6141990-09-17017 September 1990 Submits Documentation of 900906 Telcon Re Addl Util Candidate for Licensed Operator Generic Fundamentals Exam Section ML20059G8761990-09-10010 September 1990 Forwards Rev 8 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20059F8461990-09-0404 September 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/90-22 & 50-446/90-22 on 900606-0705.Corrective action:OPT-467A Changed to Provide Addl Prerequisite Info Re Solid State Protection Sys Switch Lineup During Testing ML20059E4981990-08-31031 August 1990 Forwards Revised Radial Peaking Factor Limit Rept for Cycle 1 Per Tech Specs Through Amend 1 & ML20059E4201990-08-30030 August 1990 Forwards Objectives & Guidelines for 1990 Emergency Preparedness Exercise Scheduled for 901113 ML20028G8281990-08-29029 August 1990 Forwards Comanche Peak Unit 1 Semiannual Radioactive Effluent Release Rept,900403-0630 & ODCM TXX-9030, Forwards Endorsements 40 & 4 to Nelia Policy NF-274 & Maelu Policy M-90,respectively & Endorsements 10,11,12,13,14 & 15 to Maelu Policy MF-1311990-08-27027 August 1990 Forwards Endorsements 40 & 4 to Nelia Policy NF-274 & Maelu Policy M-90,respectively & Endorsements 10,11,12,13,14 & 15 to Maelu Policy MF-131 ML20059F4381990-08-23023 August 1990 Forwards Public Version of Revised Emergency Plan & Corporate Emergency Response Procedures,Consisting of Rev 1 to EPP-313,Rev 7 to CERP-101,Rev 7 to CERP-102 & Revised Forms.W/Dh Grimsley 900906 Release Memo TXX-9029, Responds to NRC Re Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57.Corrective Actions:Storage Facilities for Instrumentation & Control Work Packages Improved to Provide Acceptable Protection for Documents1990-08-20020 August 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57.Corrective Actions:Storage Facilities for Instrumentation & Control Work Packages Improved to Provide Acceptable Protection for Documents ML20058P0571990-08-13013 August 1990 Forwards, Comanche Peak Steam Electric Station Unit 1 Control Room Simulator 10CFR55 Certification Initial Rept ML20058N2311990-08-0909 August 1990 Forwards First Half 1990 fitness-for-duty Program Performance Data,Per 10CFR26.71(d).Point of Contact for Personnel,Random Testing Program Results & Confirmed Positive Tests Summary & Mgt Summary Included in Data ML20059A5831990-08-0404 August 1990 Responds to Info Request Made During 900802 Meeting Re Inadvertent Safety Injections on 900726 & 30 & Results of 100% Power Plateau Testing TXX-9024, Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel1990-08-0303 August 1990 Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel TXX-9022, Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station1990-07-31031 July 1990 Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station TXX-9027, Responds to NRC Re Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19.Corrective Action:Specific Activity within Tech Spec Limits.No Further Corrective Action Required1990-07-30030 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19.Corrective Action:Specific Activity within Tech Spec Limits.No Further Corrective Action Required ML20055J1571990-07-27027 July 1990 Submits Info Re Replacement of Borg-Warner/Intl Pump,Inc Check Valve Swing Arms,Per .Swing Arms in ASME Code Class 2 Check Valves Will Be Replaced During First Refueling Outage ML20056A0461990-07-24024 July 1990 Requests Regional Waiver of Compliance for Containment Pressure Transmitter 1-PT-934 During Coming Outage TXX-9023, Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. No Subj Transmitters in Existence at Facility1990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. No Subj Transmitters in Existence at Facility ML20055G6351990-07-17017 July 1990 Submits Results of Remote Shutdown Panel Environ Survey ML20055F9391990-07-13013 July 1990 Advises That Operators Have Gained Significant Experience in Operating Plant Under Wide Range of Conditions & Have Demonstrated Necessary Proficiency to Safely Operate Unit ML20055F9371990-07-13013 July 1990 Submits Info Re Revised Acceptance Criteria for THERMO-LAG Fire Barrier,Per 900705 Telcon.On Exposure to Heat Flux at Surface of Barrier,Listed Mechanisms Activated.Fire Testing Demonstrates That Panels Qualified W/Variation in Thickness ML20044A7001990-06-26026 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Util Will Implement for Unit 2 Activities Performed for Unit 1 ML20044A1411990-06-20020 June 1990 Forwards Endorsements 4 & 5 to Nelia Certificate N-90, Endorsements 5 & 6 to Maelu Certificate M-90 & Endorsements 34,35,36,37,38 & 39 to Nelia Policy NF-274 ML20043H7031990-06-18018 June 1990 Discusses Mod/Rework to Auxiliary Feedwater Sys Check Valves Mfg by Bw/Ip Intl,Inc.All But One Affected Check Valve modified.Motor-driven Auxiliary Feedwater Pump Discharge Valve Check Valve Body Replaced ML20043H2181990-06-15015 June 1990 Forwards Response to 900515 Request for Addl Info on Emergency Preparedness.Ongoing Emergency Preparedness Programs Address Concerns Raised by Citizens for Fair Util Regulation ML20043G3131990-06-15015 June 1990 Forwards Addl Info Re Pressurizer Surge Line Thermal Stratification & leak-before-break Evaluation & Nonproprietary Suppl 3 to WCAP-12247, Supplementary Assessment... & Proprietary Suppl 3 to WCAP-12248 ML20043C5671990-06-0101 June 1990 Discusses Identification of Slave Relays Tested Using Alternative Methodology,Per 900402 Commitment.Encl Tabulation Identifies Test Type,Applicable Procedures & Equipment & Impact of Improper Documentation ML20043E7131990-06-0101 June 1990 Responds to NRC 900517 Notice of Violation & Imposition of Civil Penalty in Amount of $25,000.Corrective Action:Qc Mgt Counseled Level III Inspector & QC Supervisor on Importance of Good Communications W/Receipt Inspectors ML20043C4501990-05-31031 May 1990 Advises That Util Revised FSAR Section 15.1.2 & Question/ Response 32.108,per 10CFR50.59 ML20043B5471990-05-25025 May 1990 Provides Status of Facility Design & Const Activities,Per Request.Detailed Design Work Will Resume in June 1990.Const Activities Expected to Increase Signficantly by Jan 1991 ML20043B5481990-05-23023 May 1990 Provides Clarification of 890710 Commitment Re Power Ascension Program.Cooldown Portion of Remote Shutdown Test Performed During Preoperational Testing,Per FSAR & Reg Guide 1.68.2 ML20043D1711990-05-21021 May 1990 Forwards Public Version of Revised Emergency Plan Procedures,Including Rev 8 to EPP-109,Rev 7 to EPP-112,Rev 4 to EPP-116 & Rev 6 to EPP-121.W/DH Grimsley 900604 Release Memo TXX-9018, Advises of Completion of Implementation of Requirements of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety- Related Equipment1990-05-21021 May 1990 Advises of Completion of Implementation of Requirements of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety- Related Equipment ML20043B0981990-05-15015 May 1990 Forwards Radial Peaking Factor Limit Rept for Cycle 1, Containing F(Xy) Limits for All Core Planes Containing Bank D Control Rods & All Unrodded Core Planes ML20042F2851990-05-0303 May 1990 Supplemental Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. ML20042F3861990-05-0303 May 1990 Responds to NRC 900410 Ltr Re Violations Noted in Insp Repts 50-445/90-10 & 50-446/90-10 on 900206-07 & 0226-0302. Corrective Action:Memo Issued Emphasizing That Discrepancies Should Be Brought to Attention of Site Organizations ML20042F3021990-05-0202 May 1990 Responds to NRC 900402 Ltr Re Violations Noted in Insp Repts 50-445/89-23 & 50-446/89-23.Util Does Not Believe That Circumstances Described in 900402 Ltr Constitutes Violation of 10CFR50.9(a) ML20042F3051990-05-0202 May 1990 Provides Revised Response to Generic Ltr 88-17 Re Loss of DHR ML20042E4581990-04-12012 April 1990 Responds to Inconsistencies in Terminology & Labelling Identified During NRC 890118 & 19 Audit of Facility Dcrdr. Util Believes Control Room Inventory Requirement of Suppl 1 to NUREG-0737,satisfied ML20042E0701990-04-10010 April 1990 Discusses 900305 Meeting W/Nrc in Rockville,Md Re Offsite Power Availability for Automatic Switch Co Solenoids for MSIV in Event of Nonmechanistic Main Steam Line Crack in Superpipe Region ML20012F5011990-04-0303 April 1990 Forwards Corrections to 891016 Response to Emergency Diesel Generator Engine Requirements.Lengths of Two Pairs of Bolts Above Crankpin Shall Be Measured Ultrasonically Before Detensioning & Disassembly of Bolts ML20012F3221990-04-0202 April 1990 Discusses ESF Sys Slave Relay Alternate Test Methodology. Implementation Schedule for Design Mods to Relay Will Be Submitted by 900601 ML20042D8081990-03-29029 March 1990 Forwards Proposed Change to FSAR Section 13.4 Re Station Operations Review Committee.Similar Change Submitted in 900328 Ltr for Chapter 6 of Facility Tech Specs ML20012F0411990-03-28028 March 1990 Forwards marked-up Pages of Facility Draft Tech Specs & Bases (NUREG-1381) Provided W/Low Power OL ML20012E6051990-03-27027 March 1990 Forwards Endorsements 1-4 to Maelu Certificate M-90, Endorsements 1-9 to Maelu Policy MF-131,Endorsements 29-33 to Nelia Policy NF-274 & Endorsements 1-3 to Nelia Certificate N-90 ML20012E6531990-03-27027 March 1990 Provides Final Response to Reporting Requirement 2 of NRC Bulletin 88-008, Thermal Stresses in Piping Connected to RCS, for Unit.Nde Requirements of Action 2 Not Considered Applicable to Unit ML20012E1911990-03-23023 March 1990 Forwards Comanche Peak Steam Electric Station Unit 1 Cycle 1 Startup Physics Tests Control Rod Worth Predictions Utilizing TU Electric Control Rod Swap Methodology. ML20012E1581990-03-23023 March 1990 Clarifies 880624 Response to NRC Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants. ML20012D0201990-03-19019 March 1990 Advises That Allegations Provided to NRC by Former Util Employee Unsubstantiated,Based on Investigation by Util Safeteam Organization ML20012E2181990-03-19019 March 1990 Responds to Generic Ltr 89-19 Re USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants. Util Determined That Loss of safety-related Inverters 1 or 2 Would Involve Coincidental Opening of Main Feedwater Valves 1990-09-04
[Table view] |
Text
- -- - _
, v, .
""":"""" Log # TXX-89597:.
1 .~~ File # 10010 C C- 903.9 7UELECTRIC .Ref. # 10CFR50.55(a)
. August 31, 1989 Esmtive Vue hesident U. S. Nuclear Regulatory Commission Attn: Document Control Desk
.. W ashington, D. C. 20555
SUBJECT:
C0riANCHE MAK STEAM ELECTRIC STATION' (CPSES)
DOCKET NOS. 50-445 AND 50-446-
' ADVANCE FSAR SUBMITTAL DESIGN LIMITS FOR BOLTED. PIPING SUPPORT JOINTS.
AND BOLTED FLANGE JOINTS 4-Gentlemen:
--*- This letter provides an advance copy of'a change to be included in a future FSAR amendment. ~This change allows the use of the referenced ASME code edition and addenda documented in Safety Evaluation Report Supplement 14 Section 4,1.2.2_for the design limits of bolted piping support joints and bolted flange joints.
In order-to facilitate NRC staff review of this change, the attachment is organized as follows:
- 1. Draft revised.FSAR pages, with changed portions indicated by a bar in the margin, as they are to appear in a future araendment.
- 2. A detailed description / justification for the change.
- 3. A copy of the related SER section.
- 4. A page containing the title of a " bullet" which consolidates and categorizes similar individual changes -by subject and related SER section.
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8909070111 890831
A PDC 400 North Olive Street LB B1 Dallas, Texas 7$201
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i TXX-89597 l ' August 31', 1989-Page 2 of 2-
-5. The bold /overstrikelversion of the! revised FSAR pages referenced by;
'the detailed' description / justification-for:the changes identified-above. 'The bold / overstrike version facilitates. review of the
- revision
- by highlighting each addition' of'new text in bold type font-and overstriking with a. slash'(/) the portion,of the text that ist deleted.
Sincerely..-
?$/ r1f- , ) "
William'J. Cahill, Jr.
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By OW24 b, 23' '
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R.OfWalker
. Manager, Nuclear. Licensing.
HAM /ser-Attachment
- c. Mr. R. D. Martin.. Region IV
_1 Resident Inspectors._CPSES (3) .
_m-__m__ - _ - - . - - _ _ ____m_. _ _ . _ _ ____m-a_-____ __ _ _ _ _ _ _ - __m___-______-._.- - - .m._ _ _ _m-____.-__.-_2____-_--_-________m_- - _ _ _ _ _ _ _ _ _ _ _ _._.__-__.-m__-_ ______.-__m
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'l Attachment to TXX-89597 August 31,- 1989 i
Advance FS/R Submittal Concerning .~.
'I Design Limits For Bolted Piping Support Joints And. .! '
Bolted Flange Joints -
- s .-
' Item 1-Draft Revised FSAR Pages 2,3 I Item 2- : Detailed Description / Justification 4
'l for Changes j Item 3 Related SER Sect? 5,6,7 l
~
Item 4 Bullet Title 8
' Item 5 Bold /0verstrike Version of 9,10' ;
Revised FSAR Pages J I
l i
i
- I i
)
CPSES/FSAR
.; . Attachm:nt.'to TXX-89597 Paga 2 of 10 a. Elastic analysis for the design of Class 2 and 3 p ,- .
I components in accordance with subparagraph NB 3227.6 of -
ASME B&PV Code,Section III.
p b. Limit analysis is done at a specific location when the limits on local membrane stress intensity and primary bending stress intensity do not satisfy'the limits of ASME B&PV Code,Section III, subparagraph NB 3228.2.
61-l_ l 2.- Bolts For the Code Class'2 and 3 components not.in Westinghouse *s scope, the following are the criteria for the design of bolting:
DRAFT a. Bolts for Component Supports (Other than Pipe Supports) !
0112.13 ;
40 Normal and Unset Conditions - The design limits are as per ASME B&PV Code,Section III, Article XVII-2460 and NRC approved ASME Code Cases as indicated in the specification.
0112.13
.20 Emeraency Condition - The bolt allowables are 1.33 times l
the allowable used in the normal and upset conditions. !
i 0112.13 :,
20 Faulted Condition - The bolt allowables for normal and j upset conditions are increased by a factor which is the '
lower of 1.2 (Sy/Ft) or 0.7 (Su/Ft). However, the total j allowable stress shall not exceed 0.9 Sy in any case. !
20 Sy - Yield stress j 20 Ft - Allowable tensile stress l 1
.j 20- Su - Ultimate tensile stress Draft Version 3.9B-14 1
-- - --_- -- - _ 9
b, , Attach ent to-TXX-89597 CPSES/FSAR Pag 2;3 of 10 f: 0112.13 L
L b.- Bolts for Pipe Support Joints DRAFT The design limits for bolted pipe support joints are in DRAFT accordance with the ASME B&PV Code,Section III, 1983 Edition including the Summer 1983 Addenda, paragraphs NF 3225 and NF 3324.6.
L
- c. Bolts for Flange Joints l DRAFT The design limits for bolted flange joints connecting pipe DRAFT to pipe and/or pipe to equipment are in accordance with the ASME B&PV Code,Section III, 1983 Edition, subparagraphs NC/ND 3658.2 and NC/ND 3658.3.
- d. Bolts and Components DRAFT 0112.13 Bolts for components do not exceed the Code allowable DRAFT stress limits.
66
- 3. Non-ASME Code Class Components The supplier of the mechanical components not covered by the ASME B&PV Code must demonstrate by experimental testing or calculation that the design stress limits (with use of applicable codes and standards) are sufficiently below the elastic limits to ensure operability.
3.98.2 DYNAMIC TESTING AND ANALYSIS 3.9B.2.1 Preonerational Vibration and Dynamic Effects Testina on Pinina l0112.12 The purpose of preoperationel vibration and dynamic effects tests of i
)
i 3.98-15 Draft Version l
_ . . _ . . _ - - . - - . - - . _ _ - - . - - . - . _ _ _ - . - - - - - - _ _ - _ - _ - _ - _ _ - - _ _ - - _ - - J
wa3svduaa w wewr n-
. . DETAILED DESCRIPTION
,.Atta'hment
- c to TXX-89597-
. .Page,4_cf 10 FRAR'Page
, (as amended) Group Description 3.9B-14, 15 2. ' Allows the use of design'11mits for bolted. pipe support
-joints in accordance with'ASME III, subsection 1NF, paragraphs NF-3225 and NF-3324.6 of the 1983 Edition-Summer 1983 Addenda.
Correction:
' Incorporates the design limits provided by ASME III, paragraphs NF-3225 and NF-3324.6 of the 1983 Edition -
Summer 1983 Addenda. This correction replaces.the-criteria with design limits presnted to the NRC by=
TV Electric report entitled, " Documentation of'ASME III' NA-1140 Review for Piping and Supports," revision 2 dated September 30. 1987 and subsequently. reviewed and' approved y:the NRC as documented in NUREG-0797, Supple-ment'14 to the Safety Evaluation Report, section 4.1.2;2, pages 4-6 thru 4-8.
FSAR Change Request Number: 88-569.1 Related SER Section: 3.9.3: SSER14 4.1.2.2 SER/SSER Impact: No 3.9B-14.-15 2 Allows the. usage of Design limits for the design of bolted. flange joints connecting pipe and/or pipe to equipment in accordance with ASME III, subparagraphs NC/ND 3658.2 and 3658.3 of the 1983 Edition-Summer 1983 Addenda.
Correction:
Incorporates the design limits provided by ASME III.
subparagraphs NC/ND 3658.2 and 3658.3 of the 1983 Ed.-
Summer 1983 Addenda. This correction replaces the criteria with design limits presented to the NRC by TV Electric-report entitled,
" Documentation of ASME III NA-1140 Review for Piping and Supports," revision 2,. dated September 30, 1987 and subsequently reviewed and approved by the NRC as documented in.NUREG-0797, Supplement 14 to theLSafety '[.
Evaluation Report, section 4.1.2.2, pages 4-6 thru 4-8. .;
FSAR Change Request Number: 88-569.2 Related SER Section: 3.9.3: SSER14 4.1.2.2
- SER/SSER Impact
- No o
I l
L I
, o
<, , [AttachanttoTXX-89597-
, , ,'Page.5.cf=10 4.1.2.2 Design Criteria and Methodology The CPSES pipe stress and pipe support design criteria in CPFP-7 (Reference 30) j have been oeveloped by.SWEC for the design validation of ASME Code Class 1, 2. -
and 3 pipe supports and ASPE Code Class 2 and 3 piping systems. The ,
controlling . documents for the SWEC design validation Aftert are contained in ^
Comanche Peak Project Procedures CPPP-1 through CPPP-35 (Appendix E of this l supplement). The piping stress analyses and pipe support calculations will become the CPSES analyses of record and provide assurance that the structural qualification of the piping and pipe supports within the CAP scope are in accordance with CPSES licensing commitments and the applicable requirements of
.the ASME Boiler and Pressure Vessel Code (References 27 and 28). The following sections discuss the staff review and evaluation of the CPSES design criteria and analytical methodologies used in the piping and pipe support design validation.
Review of Final Safety Analysis Report Amendment 61 In Amendment'01 (Reference 31) to the CPSES Final Safety Analysis Report (FSAR)
(Reference 32), the applicant provided the changes made to the FSAR piping design criteria as a result of the CAP design validation effort. As a result of its review of the FSAR Amendment 61 changes, the staff concludes that the changes do not si and supplements (gnificantly Reference 11)alter theinstaff except findings the areas in thetoprevious related (1) the CPSES SEP combinationofloss-of-coolantaccident(LOCA)andsafe-shutdownearthquake (SSE) Iceds (Section 3.9.2.3 of the SER) and (2) the piping system damping values (Section 3.7.1 of the SER).
The staff evaluated the combination of LOCA and SSE loads for reactor coolant system heavy component supports in its safety evaluation provided in a letter from C. I. Grimes (NRC) to W. Counsil (TU Electric) dated June 8, 1967 (Reference 33), in conjunction with the implementation of the final rule on the modification of 10 CFR SO, Appendix A, General Design Criterion 4 requirements for protection against the dynamic effects-of postulated pipe ruptures (51 Federal Register 12505, dated April 11,1986). Similarly, the staff found that the use of revised damping values per ASME Code Case N-411 (Reference 34) was acceptable for CPSES as discussed in a letter from V. Noonan (NRC) to W.
Counsil (TU Electric) dated March 13, 1986 (Reference 35).
The staff also reviewed the technical acceptability of the FSAR Amendment 61 changes and the use of later ASME Code provisions as perinitted in paragraph NA-1140(f) of the ASME Code Section III (Reference 27). The staff's review of the use of later ASME Code provisions focused primarily on the technical justifications provided in the applicant's report entitled, " Documentation of ASME III NA-1140 Review for Piping and Supports," Revision 2, dated September 30, 1987 (NA-1140 report). This report documented the applicant's review performed to ensure that the use of design criteria in CPPP-7 is in conformance with paragraph NA-1140(f) of the ASME Code and, in particular, that all related ASME. Code requirements are met. The code of record for CPSES piping is ASME
- Code Section III,1974 Eoition, including Sumner 1974 Addenda Subsections NC/ND (Reference 27). The code of record for CPSES pipe supports is the 1974 Edition including Winter 1974 AdJenda Subsection NF (Reference 28). On the basis of its review of the NA-1140 report, the staff finds that all related Comanche Peak SSER 14 4-6
,AttachCent te TXX-89597 Page 6 of 10 requirements associated with the use of specific provisions of a Ccde edition
-or addenda were met and thus . the use of later Code provisions as specified in the NA-1140 report is acceptable. The specific provisions from later Code editions and addenda reviewed and approved by the staff for CPSES are listed below:
(1) 1977 EDITION - WINTER 1978 ADDENDA Appendix 0 - Rules for Design of Safety Valve Installations (2) 1983 EDITION' i;C-3658.2 - Standard Flange Joints at Moderate Pressures and Temperatures NC-3658.3 - ANSI B16.5, Flanged Joints with High-Strength Bolting
.ND-3658.2 - Standard Flange Joints at Moderate Pressures and Temperatures ND-3658.3 - ANSI S16.5, Flanged Joints with High-Strength Bolting (3) 1983 EDITION - WINTER 1984 ADDENDA Figure NC-3673.2(b) Flexibility and Stress Intensification Factors (Do/tm less than or equal to 100)
(Branch Connections, Buttwelds, and Fillet Welds)
Figure NC-3673.2(b) Branch Dimensions Figure ND-3673.2(b) Flexibility and Stress Intensification Factors (Do/tm less than or, equal to 100)
(Branch Connections, Buttwelds, and Fillet Welds)
Figure ND-3673.2(b) Branch Dimensions (4) 1977_ EDITION - WINTER 1978 ADDENDA XVII-2211 - Stress in Tension Figure XV11-2111(c) Illustrations of Maximum Design Stress in Through Thickness Direction of Plates and Elements of Rolleo Shapes (Figure Delete 6) hF-3226 - Through Plate Thickness Tensile Limit Figure AF-3226.5 Illustrations of Maximum Design Stress in Thrcugh Thickness Direction of Plates and Elements of Rolled Shapes (Figure Deleted) i NF-33?l.1 - Design Ccnditions 1
~ Comanche Peak SSER 14 4-7
.. ,,'AttachM nt to TXX-89597
_ Page 7<of 10 (5) ;1977 EDITION - WINTER 1979 ADDEhDA NF-3391.1 - Allowable Stress Limits (Class 2 and MC Plate /Shell)
NF-3392.1 - Allowable Stress Limits (Cicss 2 and MC Linear)
.(6) 1500 EDITION hF-1133 - Intervening Elements .n Relation to Jurisdictional Bcundaries hF-1131.6 - Portion F (7) 1980. EDITION XVII-2462 - Minimum Edge Distance (8) 1983 EDITION - SUP91ER 1983 ADDENDA NF-3225 - Design of Bolting NF-3324.6 - Design Requirements for Bolted Joints (9) 1983 EDITION - SUMMER 1985 ADDENDA NF-4721 - Bolt Holes (10) 1974 EDITION - WINTER 1975 ADDENDA NC-6221 - Minimum Required Hydrostatic Test Pressure
~(11) 1^74 EDITION - WINTER 1975 ADDENDA XVII-2410 - General Requiremer.ts (for the Design of Connections and Joints (12)1960 EDITION - WINTER 1982 ADDENDA NF-3324.5 - Design Requirements for Welos (13)1974 EDITION - SUMMER 1975 ADDENDA NB-3630(d) - Exemptions for Class 1 Piping It should be noted that 10 CFR 50.55a " Codes and Standards " currently references the ASME Code,Section III, Division 1 up to the 1983 Edition including the Summer 1984 Addenda. Although the portion of 10 CFR 50.55a pertaining to ASME Code Class 2 and 3 piping is not directly applicable to CPSES, it does provide the staff position regarding the latest Code edition and addenda found suitable for use. Several provisions listed above from later Code addenda (i.e., Winter 1984 Addenda and Summer 1985 Addenda) are not referenced currently in 10 CFR 50.55a. A final rule has been developed to update 10 CFR 50.55a to incorporate by reference the Winter 1984 Addenda, Summer 1985 Adcenda. Winter 1985 Addenda, and 1986 Edition of Section III, 1
i Comanche Peak SSER 14 4-8
I . Attachpr;nt to TXX-89597 Pag 3 8 of 10-3.9.3 ASME Code Class 1. 2 and 3 Components. Component Supports and Core Sucoort Structures EMEB 20. The FSAR has extended the code usage for Class. 2 and 3 bolting for flange joints and piping support joints.
CPSES/FSAR
'Page 9 of 10 a. Elastic-analysis for the d2 sign of Class 2 and 3 components in accordance with subparagraph NB 3227.6 of
.ASME B&PV Code,Section III.
b.- Limit analysis is done at a specific location when the limits. on local membrane stress intensity and primary bending stress intensity do not satisfy the limits of ASME B&PV Code Section III, subparagraph NB 3228.2.
61-
- 2. Bolts For the Code Class 2 and 3 components not in Westinghouse's scope, the following are the critaria for the design of bolting:
- a. Bolts.for Component Supports (Other than Pipe Supports) 1 0112.13 40 Normal and Unset Conditions - The design-limits are as per ASME B&PV Code,Section III, Article XVII-2460 and NRC approved ASME Code Cases as indicated in the specification.
0112.13 20 Emeraency Condition - The bolt allowables are 1.33 times the allowable used in the normal and upset conditions.
0112.13 20 Faulted Condition - The bolt allowables for normal and upset conditions are increased by a factor which is the lower of 1.2 (Sy/ft) or 0.7 (Su/Ft). However, the total allowable stress shall not exceed 0.9 Sy in any case.
20 Sy = Yield stress 20 Ft - Allowable tensile stress 20 Su - Ultimate tensile stress Bold /0verstrike 3.9B-14 Version
~
l
.m Attachm2nt to TXX-89597 CPSESUSM Page 10 of 10 !
0112.13
- b. Bolts for Pipe Support Joints q The design limits for bolted pipe support joints are in accordance with the ASME B&PV Code,Section III,1983 Edition including the Summer 1983 Addende, paragraphs NF l 3225 and NF 3324.6.
I L
1'
- c. Bolts for Flange Joints The design limits for bolted flange joints connecting pipe i to pipe and/or pipe to equipment e m in accordance with j the ASME B&PV Code Section III, 1983 Edition, subparagraphs NC/ND 3658.2 and NC/ND 3658.3.
- d. Bolts and Components WI 5fddi & ddfi fdt pipd fiddddi Id/dd/ fMdd 24 fddMddl WMd/d J 20 fMd dddfdd p/didd/d ddd fddpd/dfdtd dd ddf didddd ISS Pif .
df 200d f dddfdtd fd fMd (d(ditddddff df Eddd didd 17dit ,
0112.13 di Bolts for components do not exceed the Code allowable 20 stress limits.
66
- 3. Non-ASME Code Class Components The supplier of the mechanical components not covered by the ASME B&PV Code must demonstrate by experimental testing or calculation that the design stress. limits (with use of applicable codes and standards) are sufficiently below the elastic limits to ensure operability.
3.95.2 DYNAMIC TESTING AND ANALYSIS j 3.9B.2.1 Preonerational Vibration and Dynamic Effects Testino on Pioino 0112.12 The purpose of preoperational vibration and dynamic effects tests of I
3.9B-15 Bold /0verstrike
~
Version j