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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
Log # TXX-6247 File # 10068 10010 clo
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RIELECTRIC w aiw c.nw January 29, 1987 Etecunve ike PreuJent U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 COMANCHE PEAK CORRECTIVE ACTION PROGRAM REF: V. S. Noonan Letter to W. G. Counsil Dated December 31, 1986 Gentlemen:
Enclosed please find the information requested in the referenced letter dated December 31, 1986, regarding the Corrective Action Programs established by TV Electric.
- 1. (Plea'se provide) a list of the discrete program components of each corrective action plan (e.g., high energy line break, systems interactions, fire protection, etc.); the organization that is conducting the work (e.g., SWEC, Ebasco, Impell, etc.); the location where the work is being performed (e.g., NY, Boston, Chicago, etc.).
Response
The information requested is provided in Attachment 1. In the attachment, the eleven major Corrective Action Programs (CAP) and Generic Issues Reports (GIR), the lead engineering organization, and the program components are identified.
- 2. (Please provide) a current schedule of completion of work for the various program components; a point of contact.
- 3. (Please provide) a list of products that will be produced as a result of the corrective action plans and documentation available to be reviewed.
Response
The information requested in items 2 and 3 is provided in Attachment 2.
Also, the current revision and issue date is indicated with the scheduled i completion date for design validation activities associated with each program element by CAP /GIR. The products to be issued by the lead organization / responsible contractor are also noted.
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TXX-6247 January 29, 1987 Page 2 The overall TU Electric point of contact for the Corrective Action Program execution is:
Mr. L. D. Nace Vice President, Engineering and Contruction CPSES P.O. B0X 1002 F.M. 56 Glen Rose, Texas 76043 (817)897-8738 The points of contact for the respective engineering organizations are as follows:
A) Stone & Webster Engineering Corporation (SWEC-CAP):
Mr. R. W. Ackley c/o TU Electric P.O. Box 1002 F.M. 56 Glen Rose, Texas 76043 (817)897-8513 B) EBASCO Services, Inc. (EBASCO):
Dr. R. C. Iotti c/o TV Electric P.O. Box 1002 F.M. 56 Glen Rose, Texas 76043 (817)897-8354 C) Impell Corporation (IMPELL):
Mr. R. W. Grubb c/o TU Electric P.O. Box 1002 F.M. 56 Glen Rose, Texas 76043 (817)897-8335 D) Stone & Webster Engineering Corp. (SWEC-PSE):
Mr. R. L. Klause 3 Executive Campus Cherry Hill, New Jersey 08034 (609)482-3352
- 4. (Please provide) plans for design verification of any design /
requalification work that may arise from recently initiated SWEC work.
Response
Design verification for any redesign / reverification work initiated by SWEC will be performed in accordance with the SWEC Engineering Assurance Program.
TXX-6247 January 29, 1987 Page 3
- 5. (Please provide) an explanation of the relationship between generic issue
- reports and issue resolution reports. It is our understanding that both are to document planned corrective actions and evaluations by TERA of
. these plans.
- _ Response
! Issue Resolution Reports (IRRs) are the vehicle used by the CPRT Design Adequacy Program (DAP) to document and communicate perceived problem areas found with design documentation. IRRs summarize DAP discrepancy issues
- reports (DIRs) into technical problem areas. These documents do not summarize'all DIRs identified by the DAP group nor consider other related CPRT TRT-ISAP or Quality of Construction (QOC) issues addrersed by'the Corrective Actions Programs. ~
TU Electric, in the Corrective Actions Program, has developed topical or discipline Generic Issues Reports (GIRs) to describe the process by which all CPRT findings (including DIRs & IRRs) and the associated generic 4 implementations thereof are addressed. In general, each IRR is discussed in an appendix to the applicable GIR.
Conceptually, the IRR was intended by the DAP group to become a self
- contained document encompassing problem identification, technical-resolution and DAP concurrence. However, because the specific resolution of any IRR (or DIR) is based upon a determination of the mar.ner in which portions of the design will be validated and associated issues will be
.1 resolved, the GIR program has superceded the conceptual DAF intent of l IRRs. Consequently, the Final Report has become the mechanism by which TV Electric and the supporting engineering organizations will document the dispositi,ons of issues.
Very truly yours,
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W. G. Counsil
, By:
D. R. Woodlan Supervisor, Docket Licensing JDS/ef '
j Attachments 1
- c - Mr. R. D. Martin - Region IV i Mr. D. L. Kelley - R. I. - Region IV Mr. H. S. Phillips - R. I. - Region IV
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1 Attachment I to TXX-6247 January 29, 1987 Page 1.1 CORRECTIVE ACTION PROGRAM (CAP) COMPONENTS & RESPONSIBILITIES GIR/ CAP Lead Responsible Work Issue Resolution Sub.iect Ora. Procram Component Contractor Location Report Mech. SWEC-CAP Seismic Qualification of Seismic Impell CPSES DAP-E-M-500 Category I B0P Equipment B0P Equipment High Energy Line Ebasco CPSES DAP-E-M-501 i Breaks-i l Overpressure Protection of Safety SWEC-CAP Boston DAP-E-M-502
- Related Piping and Equipment-Specification of Mechanical Components SWEC-CAP Boston DAP-E-M-503
. Determination of Heat Loads for HVAC Ebasco CPSES DAP-E-M-504 Equipment Sizing Control of Welding Processes SWEC-CAP Boston DAP-E-M-506 Internal and Turbine Missile Ebasco CPSES DAP-E-M-507 j Evaluations
! Fire Protection Impell CPSES DAP-E-EIC-505
! System Design SWEC-CAP Boston DAP-E-M-508 a
Systems Interaction Ebasco CPSES
- a. High Energy Line Breaks DAP-E-M-501
- b. Moderate Energy Line Breaks --
- c. Environmental & Flooding DAP-E-M-501
! d. Seismic /Non-Seismic Interaction --
(except Train "C" < 2")
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Attachment I to TXX-6247 January 29, 1987 Page 1.2 CORRECTIVE ACTION PROGRAM (CAP) COMPONENTS & RESPONSIBILITIES GIR/ CAP lead Responsible Work Issue Resolution Sub.iect Oro. Prooram Component Contractor location Report Civil / SWEC-CAP Reactor Containment Concrete SWEC-CAP Boston DAP-C/S-501 Struct. Design (Mat, Shell, Dome, Discontinuities & Penetrations)
Reactor Containment Concrete SWEC-CAP Boston DAP-C/S-502 Internals Other Seismic Category I Concrete SWEC-CAP Boston DAP-C/S-503 Structures Seismic Category I Structural Steel SWEC-CAP Boston DAP-C/S-504 Pipe Whip Restraints and Jet SWEC-CAP Boston DAP-C/S-505,526 Impingement Shields Reactor Containment Liner SWEC-CAP Boston DAP-C/S-506 Fuel Transfer Tube Support and SWEC-CAP Boston DAP-C/S-507,510 Other Liners Miscellaneous Supports (Equipment) SWEC-CAP Boston DAP-C/S-508 Penetration Sleeves and Anchorage SWEC-CAP Boston DAP-C/S-509 Concrete Anchors SWEC-CAP Boston DAP-C/S-511,514 Computer Code Benchmarking SWEC-CAP Boston DAP-C/S-513 Testing Programs SWEC-CAP Boston DAP-C/S-515 Heavy Load Drops SWEC-CAP Boston DAP-C/S-512 Generic Technical Concerns SWEC-CAP- Boston --
Seismic Analysis SWEC-CAP Boston DAP-C/S-520
Attachment I to TXX-6247 January 29, 1987 Page 1.3 CORRECTIVE ACTION PROGRAM (CAP) COMPONENTS & RESPONSIBILITIES GIR/ CAP Lead Responsible Work Issue Resolution Sub_iect Ora. Procram Component Contractor location Report Electrical SWEC-CAP Calculations SWEC-CAP Boston DAP-E-EIC-501 Electrical Independence SWEC-CAP Boston DAP-E-EIC-504 (R.G. 1.75)
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Attachment I to TXX-6247 January 29, 1987 Page 1.4 CORRECTIVE ACTION PROGRAM (CAP) COMPONENTS & RESPONSIBILITIES GIR/ CAP Lead Responsible Work Issue Resolution Sub_iect Oro. Proaram Component Contractor location Report Instru- SWEC-CAP Setpoint Calculations SWEC-CAP Boston DAP-E-EIC-502 mentation and I&C Separation and Isolation SWEC-CAP Boston DAP-E-EIC-504 Controls
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Attachment I to'TXX-6247 !
January 29, 1987 Page 1.5
- CORRECTIVE ACTION PROGRAM (CAP) COMPONENTS & RESPONSIBILITIES-t j GIR/ CAP Lead Responsible Work Issue Resolution
, Sub. lect Ora. Proaram Component Contractor location Report I
i Large SWEC-PSE Large Bore Piping and Pipe Supports SWEC-PSE CH-NJ, NY, --
! Pcre Pipe Requalification Boston, '
Supports CPSES, Houston, -
Toronto 4
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Attachment I to TXX-6247 January 29, 1987 Page 1.6 CORRECTIVE ACTION PROGRAM (CAP) COMPONENTS & RESPONSIBILITIES GIR/ CAP Lead Responsible Work Issue Resolution Sub.iect Oro. Proaram Component Contractor location Report Cable Ebasco As-Builting of Hangers and Ebasco CPSES DSAP VIII Tray Trays - Units 1 & 2 Att. 2 Hangers Design Verification of Unit 1 CTHs Impell Chicago DSAP VIII in Reactor and Safeguards Bldgs. FW, TX Att. 2 Walnut Creek, CA Design Verification of Unit 1 Ebasco NYC DSAP VIII CTHs in Other Unit 1 Bldgs. Att. 2 and all Unit 2 Bldgs.
Testing of Cable Tray Hanger Ebasco*(1) Culver DSAP VIII
& Tray System (Dynamic Analysis) (ANC0) City, CA Att. 4 Testing of Cable Trays, Fittings & Ebasco*(2) Raleigh, DSAP VIII Clamps (CCL) NC Att. 4 Modifications of Hangers Unit 1 - Impell CPSES DSAP VIII Reactor Bldg. and Safeguards Bldg. Att. 4 Modification of Hangers Ebasco CPSES DSAP VIII Other Unit 1 Bldgs. and all Att. 2 Unit 2 Bldgs.
- (l) & (2) The performance of activities will be conducted by CCL/ANCO using testing criteria and methodology provided by Ebasco.
Attachment I to TXX-6247 January 29, 1987 Page 1.7 CORRECTIVE ACTION PROGRAM (CAP) COMPONENTS & RESPONSIBILITIES GIR/ CAP Lead Responsible Work Issue Resolution Subiect Oro. Proaram Component Contractor Location Report Conduit Ebasco Design Verification and Ebasco NYC DSAP VIII Supports Preparation of Design Documents Att. 3 Trains A&B Design of Modified and Individually Ebasco CPSES/ DSAP VIII i
Train C Engineered Supports for Unit 2 NYC Att. 3
> 2" '
Preparation of Isometric for Ebasco CPSES DSAP VIII Conduit Installation - Unit 2 Att. 3 Design Verification of Unit 2 Ebasco CPSES/ DSAP VIII Isometrics NYC Att. 3 As-Builting of Unit 1 Conduit Random Ebasco CPSES DSAP VIII Sample; Thermolagged Conduits, and Att. 3 Conduits with Thermoblanket UNISTRUT Support Testing Program Ebasco *(l) Raleigh, DSAP VIII (CCL) NC Att. 4 Selected UNISTRUT and Transverse Support Ebasco CPSES DSAP VIII Replacement Program Unit 1 Att. 3 100% Design Validation of Unit 1 Ebasco DSAP VIII Conduits & Conduit Supports Att. 3
- a. As-builting & preparation CPSES
- b. Isometric design verification CPSES/NYC
- c. Validation of remaining CPSES conduits and supports Testing of Conduit Clamps Ebasco*(l) Raleigh, DSAP VIII (CCL) NC Testing of Conduit Cantilever Ebasco*(l) Raleigh, DSAP VIII Configurations (CCL) NC
- (l) The performance of activities will be conducted by CCL based upon testing criteria and methodology provided by Ebasco.
- - _ _ - -. . - _ - . _ . . . - _ _ _ . .. - ._-_ - . - ... ._. - . _. __.-. . . . - . ._ . .~
j i
! Attachment I to TXX-6247
- January 29, 1987 Page 1.8 CORRECTIVE ACTION PROGRAM (CAP) COMPONENTS & RESPONSIBILITIES GIR/ CAP lead Responsible Work Issue Resolution i Sub.iect Oro. Procram Component' Contractor Location Report l Conduit Impell Support Inspection, System Impell CPSES/ --
- Supports Interaction, Analysis, Design Walnut
! C Train Criteria Development & PIs Springs, CA i < 2" l
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Attachment I to TXX-6247 January 29, 1987 Page 1.9 CORRECTIVE ACTION PROGRAM (CAP) COMPONENTS & RESPONSIBILITIES GIR/ CAP Lead Responsible Work Issue Resolution Sub.iect Oro. Proaram Component Contractor location Report Small SWEC-PSE Small Bore Piping and Pipe SWEC-PSE CH-NJ, NY, --
Bore Pipe Supports Requalification CPSES, Supports Boston, Houston, Toronto
-Attachment I to TXX-6247.
January 29, 1987 Page 1.10 CORRECTIVE ACTION PROGRAM (CAP) COMPONENTS & RESPONSIBILITIES GIR/ CAP Lead Responsible Work Issue Resolution Sub.iect Oro. Proaram Component Contractor Location Report HVAC Ebasco Systems Engineering & Design Ebasco NYC
- a. Specifications Review & Reissue DAP-E-M-504*(1)
- b. As-built heat load capacity --
- c. Site Engineering & Construction --
Support As-Builting & Drawing Preparation Ebasco CPSES DSAP VIII
- a. Unit 1 Duct & Duct Hangers
- b. Unit 2 Duct & Duct Hangers Design Verification of Duct & Hangers Ebasco NYC DSAP VIII
- (l) Referenced in the Mechanical GIR e f r
Attachment I to TXX-6247 January 29, 1987 Page 1.'11 CORRECTIVE ACTION PROGRAM (CAP) COMPONENTS & RESPONSIBILITIES GIR/ CAP Lead Responsible Work Issue Resolution Subject Oro. Proaram Component Contractor location Report Equipment Impell Seismic Qualification Impell CPSES *(1)
Qualifi-cation Environmental Impell CPSES --
- (l) Referenced in the Mechanical GIR i
Attachment 2 to TXX-6247 January 29, 1987 Page 2.1 CORRECTIVE ACTION PROGRAM (CAP) PRODUCTS GIR/ CAP Rev. Issue ECD for Sub.iect No. Date Component Validation Product Mechanical 0 1/27/87 Seismic Qualification of 8/1/87 Design Validation Package, Resolution Seismic Category I B0P of Applicable DIRs, & Final Report *(l)
Equipment B0P Equipment High Energy 8/1/87- Design Validation Package, Resolution Line Breaks of Applicable DIRs, & Final Report *(l)
Overpressure Protection of 8/1/87 Design Validation Package, Resolution Safety Related Piping and of Applicable DIRs, & Final Report *(1)
Equipment Specification of Mechanical 8/1/87 Design Validation Package, Resolution Components of Applicable DIRs, & Final Report *(l)
Determination of Heat Loads 8/1/87 Design Validation Package, Resolution for HVAC Equipment Sizing of Applicable DIRs, & Final Report *(l)
Control of Welding Processes 8/1/87 Design Validation Package, Resolution of Applicable DIRs, & Final Report *(l)
Internal and Turbine Missile 7/1/87 Design Validation Package, Resolution Evaluations of Applicable DIRs, & Final Report *(1)
Fire Protection 8/1/87 Design Validation Package, Resolution of Applicable DIRs, & Final Report *(1)
System Design 8/1/87 Design Validation Package, Resolution of Applicable DIRs, & Final Report *(l) l
Attachment 2 to TXX-6247 January 29, 1987 Page 2.1 continued CORRECTIVE ACTION PROGRAM (CAP) PRODUCTS GIR/ CAP Rev. Issue ECD for Subiect No. Date Comoonent Validation Product Systems Interaction 6/30/87 Design Validation Package, Resolution.
High Energy Line Breaks of Applicable DIRs, & Final P.eport*(l)
Moderate Energy Breaks Environmental & Flooding 6/30/87 Design Validation Package,' Resolution Seismic /Non-Seismic of Applicable DIRs, & Final Report *(l)
Interaction
- (l) See Page 2.12 to TXX-6247 January 29, 1987 Page 2.2 CORRECTIVE ACTION PROGRAM (CAP) PRODUCTS GIR/ CAP Rev. Issue ECD for Sub.iect No. Date Component Validation Product Civil / 0 11/20/86 Reactor Containment Concrete 7/1/87 Design Validation Package, Resolution Structural Design (Mat, Shell, Dome, of Applicable DIRs, & Final Report *(l)
Discontinuities and Penetrations)
Reactor Containment Concrete 7/1/87 Design Validation Package, Resolution Internals of Applicable DIRs, & Final Report *(l)
Other Seismic Category I 7/1/87 Design Validation Package, Resolution Concrete Structures of Applicable DIRs, & Final Report *(l)
Seismic Category I Structural 7/1/87 Design Validation Package, Resolution Steel of Applicable DIRs, & Final Report *(l)
Pipe Whip Restraint and Jet 8/31/87 Design Validation Package, Resolution Impingement Shields of Applicable DIRs, & Final Report *(l)
Reactor Containment Liner 7/1/87 Design Validation Package, Resolution of Applicable DIRs, & Final Report *(l)
Fuel Transfer Tube Support 6/30/87 Design Validation Package, Resolution and Other Liners of Applicable DIRs, & Final Report *(l)
Miscellaneous Supports 8/1/87 Design Validation Package, Resolution (Equipment) of Applicable DIRs, & Final Report *(l)
Penetration Sleeves and 7/1/87 Design Validation Package, Resolution Anchorage of Applicable DIRs, & Final Report *(l)
Concrete Anchors 8/1/87 Design Validation Package, Resolution of Applicable DIRs, & Final Report *(l)
Computer Code Cenchmarking 8/1/87 Design Validation Package, Resolution of Applicable DIRs, & Final Report *(l) to TXX-6247 January 29, 1987 Page 2.2 continued CORRECTIVE ACTION PROGRAM (CAP) PRODUCTS GIR/ CAP Rev. Issue ECD for Sub.iect No. Date Component Validation Product Testing Programs 4/30/87 Design Validation Package, Resolution of Applicable DIRs. & Final Report *(l)
Heavy Load Drops 8/1/87 Design Validation Package, R,salution of Applicable DIRs, & Final Report *(l)
Generic Technical Concerns 8/1/87 Design Validation Package, Resolution of Applicable DIRs, & Final Report *(l)
Seismic Analysis 8/1/87 Design Validation Package, Resolution of Applicable DIRs, & Final Report *(l)
. to TXX-6247 January 29, 1987 Page 2.3 CORRECTIVE ACTION PROGRAM (CAP) PRODUCTS GIR/ CAP Rev. Issue ECD for Subiect No. Date Component Validation Product Electrical 0 12/17/86 Calculations 8/1/87 Design Validation Package, Resolution of Applicable DIRs, & Final Report *(l)
Electrical Independence 8/1/87 Design Validation Package, Resolution (R.G. 1.75) of Applicable DIRs, & Final Report *(l)
Attachment 2 to TXX-6247 January 29, 1987 Page 2.4 CORRECTIVE ACTION PROGRAM (CAP) PRODUCTS GIR/ CAP Rev. Issue ECD for Sub.iect No. Date Component Validation Product Instrumen- 0 1/5/87 Setpoint Calculations 8/1/87 Design Validation Package, Resolution tation and of Applicable DIRs, & Final Report *(l)
Control I&C Separation & Isolation 8/1/87 Design Validation Package, Resolution of Applicable DIRs, & Final Report *(l)
Attachment 2 to TXX-6247 January 29, 1987 Page 2.5 CORRECTIVE ACTION PROGRAM (CAP) PRODUCTS GIR/ CAP Rev. Issue ECD for Subiect No. Date Component Validation Product Large 0 6/27/86 Large Bore Piping and Pipe 7/1/87 Design Criteria Bore Pipe Supports Requalification Walkdown Reports Supports Project Procedures Pipe Stress Calcs Pipe Support Calcs High Energy Line Break Calcs Moderate Energy Line Crack Calcs Fluid Transients Calcs Other Related Pipe Stress & Support Calcs and Generic Calcs FSAR Changes Resolution of Applicable DIRs Issue Final Report
Attachment 2 to TXX-6247 January 29, 1987 Page 2.6 CORRECTIVE ACTION PROGRAM (CAP) PRODUCTS GIR/ CAP Rev. Issue ECD for Sub.iect No. Date Component Validation Product Cable Tray 1 1/21/87 As-Builting of Hangers 1/30/87*(2) As-Built Drawings for each hanger,
, Hangers Resolution of Applicable DIRs &
Issue Final Report r
As-Builting of Trays 1/30/87*(2) Tray Span Drawings, Resolution of Applicable DIRs &
Issue Final Report Design Verification of 6/1/87 Design Criteria Guidelines, CTH System Instructions & Calculations, Resolution of Applicable DIRs &
Issue Final Report Testing 6/1/87 Test Reports, Resolution of Applicable DIRs &
Issue Final Report Modification of Hangers 6/1/87 As-Built Drawings of Modified Supports, Resolution of Applicable DIRs &
Issue Finzl Report
- (2) See Page 2.12 to TXX-6247 January 29, 1987 Page 2.7 CORRECTIVE ACTION PROGRAM (CAP) PRODUCTS GIR/ CAP Rev. Issue ECD for Sub.iect No. Date Component Validation Product Conduit 0 10/16/86 Design Verification & 12/31/87 Design Criteria Guidelines, Supports Preparation of Design Instructions & S-0910 and Trains A&B & Documents S2-0910 Drawing package, Train C > 2" Resolution of Applicable DIRs &
Issue Final Report Design or Design Verification 12/31/87 Individual drawings per of Modified & Individually support & design verified Engineered Supports As-Built Isometrics for each U2 Conduit Run, Resolution of Applicable DIRs &
Issue Final Report Testing Programs 7/1/87 UNISTRUT Test Report, Clamps Test Report, Cantilever Conduit Test Report, Resolution of Applicable DIRs &
Issue Final Report to TXX-6247 January 29, 1987 Page 2.8 CORRECTIVE ACTION PROGRAM (CAP) PRODUCTS GIR/ CAP Rev. -Issue ECD for Sub.iect No. Date Component Validation Product Conduit 1 10/15/86 Support Inspection, System 7/19/87 Walkdown documents, Cales, Supports Interaction Analysis, Design Review Documentation, Technical Train C < 2" Maintenance, Criteria Reports of Project Instructions, Development & Project Resolution of Applicable DIRs &
Instructions Issue Final Report
Attachment 2 to TXX-6247 January 29, 1987 Page 2.9 CORRECTIVE ACTION PROGRAM (CAP) PRODUCTS GIR/ CAP Rev. Issue ECD for Sub_iect No. Date Component Validation Product Small 0 12/S/86 Small Bore Piping and Pipe 9/1/87 Small Bore Generic Issues Bore Pipe Supports Supports Requalification Report Supports Generic Technical Issues Report Design Criteria Walkdown Reports Project Procedures Pipe Stress Calcs Pipe Support Calcs High Energy Line Break Calcs Moderate Energy Line Crack Calcs Fluid Transients Calcs Other Related Pipe Stress &
Support Calcs and Generic Calcs FSAR Changes Resolution of Applicable DIRs Issue Final Report
Attachment 2 to TXX-6247 January 29, 1987 Page 2.10 CORRECTIVE ACTION PROGRAM (CAP) PRODUCTS GIR/ CAP Rev. Issue ECD for Sub.iect No. Date Component Validation Product HVAC 0 12/15/86 Systems Engineering & Design 4/30/87 Design Basis Documents for HVAC serving Safety Specifications for Systems Related Structures & & Equipment Equipment flow Diagrams i As-Built Heat Load Calculation Resolution of Applicable DIRs Issue Final Report As-Builting and Drawing 3/21/87 As-Built & Design Verified Preparation drawings for Individual Hangers & Duct Segments Resolution of Applicable DIRs Issue Final Report Design Verification of 9/30/87 Design Criteria, Guidelines, Ducts & Hangers Instructions & Calculations l Resolution of Applicable DIRs Issue Final Report l
_ _ _ _ _~_. _ _ _ _ .
to TXX-6247 January 29, 1987 Page 2.11 CORRECTIVE ACTION PROGRAM fCAP) PRODUCTS GIR/ CAP Rev. Issue ECD for Sub.iect No. Date Component Validation Product Equipment 0 12/29/86 Seismic Qualification 7/I/87 EQ Master List Qualifi- Resolution of Applicable DIRs cation Issue Final Report Environmental Qualification 7/1/87 Design Validation Package Resolution of Applicable DIRs Issue Final Report 4
to TXX-6247 January 29, 1987 Page 2.12 CORRECTIVE ACTION PROGRAM (CAP) PRODUCTS NOTES
- (1) Each Design Validation Package (DVP) will identify and contain the following items related to the scope of that package:
Design Basis Documents (DBDs) which serve as the basis of the package evaluation Design Documents (Drawings, Diagrams, Specifications, Calculations, etc.)
Design responsibility interfaces will be identified and cross-referenced among interfacing organizations in each DVP. Boundaries of validated design will be identified and documented.
A distinction should be made between DVPs and DBDs. The DBD describes the plant design criteria. The DVP contains the design basis, production, construction, testing, operations and licensing documents which exist as proof that CPSES design complies with its criteria commitments.
- (2) Excludes cable spreading room frame. These installations will be validated as part of the Civil / Structural CAP.