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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] |
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Log # TXX-6157
, File # 10010 906.2 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . eeB NOftTH OLIVE STREE"F. l R. St . DALLAS, TEXAS 763DI December 16, 1986 E.Y1".Lff.UEL Mr. Vince S. Noonan Director of Nuclear Reactor Regulation Comanche Peak Project Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 SUPPLEMENTAL INFORMATION ON CONTAINMENT C0ATINGS PERFORMANCE REF: NUREG-0797, SUPPLEMENT 9, APPENDICES L AND M.
Dear Mr. Noonan:
Attached is Texas Utilities Electric Company's (TVEC) response to your staff's request for supplemental information regarding the CPSES Coating Performance Program referenced above.
l Very truly yours,
$* hw W. G. Counsil lU By: .
,1 ~
M '-
l
'G. S. Keeley I Manager,NuclearLMensing GLB/grr Attachments (2)
CO l
I I F612310192 861216 PDR ADOCK 05000445 E PDR
4
- /
1 Attachment 1 s' TXX-6157 ' L, Page 1 of 3 l jj
-i e' PRE-AND POST-OPERATIONAL .'l '
TESTING AND SURVEILLANCE , 1,/
, e
.! The following summarizes those actions taken to date and proposed future '
, methods for assuring that protective coating work inside.the containment (s) at CPSES will reasonably maintain their integrity, without separating from the ..
sur_ faces to which they have been applied. These actions and proposals are: ..
submitted to demonstrate TUEC's compliance with the intent of NUREG-0737,SSERu i:
9,-Appendix L, Section 3.0, and 4.0 and 5.0. I m .
I. PROTECTIVE C0ATINGS APPLICATION, INSPECTION AND TESTING 1 0
. ; e Consistent with the conclusions of Supplement 9 to the Comanche Peak Safety Evaluation Report (SSER-9), containment building coating work w'as f reclassified to a Non-Safety Related Activity. . Appropriate FSAR revisions were implemented to reflect this change in Quality classification.
s
. In order to demonstrate TUEC's commitment to assuring the integrity of ;
J containment coatings throughout the life of the plant, a comprehensive '
coatings engineering inspection and documentation program was established for in-process coating work. This program was implemented June 17, 1985, and is presently implemented in accordance with a series '1 of procedures and instructions designated ECE-PC -
(Engineering / Construction Engineering - Protective Coatings). These procedures provide programmatic and operating requirements for the i implementation of the program, including:
,e A. Qualification and training of engineering inspection personnel.
l B. Inspection and testing procedures which specify:
- 1. Detailed operational methods for each inspection and test;
- 2. Inspection instruments and apparatus to be employed; 's L
- 3. Frequency of test / inspection routines; q 1
- 4. Acceptance criteria for each inspection and test; and .l
- 5. Records to be generated to document inspections and tests.
C. Verification of coatings storage and handling.
D. Calibration requirements for measuring and test equipment.
E. Reporting, disposition and tracking of deficiencies identified.
F. Completion, issuance and control of documentation.
G. Maintenance and Control of the Unit 1 Coatings Exempt Log.
l l
1
-. ~ . .. . , . . - . -_. - --_ ._-,_ - - - . - - - _., -..- ~..-_,-.
c Log # TXX-6157
, . ?, , ,
File # 10010
- n -
906.2 <
TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 488 NORTH OLIVE errREET.1.B. 88 . DAt1AS, TEXAS 75301 December 15, 1986 s
i flvt MCE Po e e#7
. Mr. Vince S. Noonan Director of Nuclear Reactor Regulation Comanche Peak Project Division of Licensing ,
U.S. Nuclear Regulatory Commission Washington, D.C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 SUPPLEMENTAL INFORMATION ON CONTAINMENT C0ATINGS PERFORMANCE REF: NUREG-0797, SUPPLEMENT 9, APPENDICES L AND M.
Dear Mr. Noonan:
Attached is Texas Utilities Electric Company's (TVEC) response to your staff's request for supplemental information regarding the CPSES Coating Performance Program referenced above.
Very truly yours, W
W. G. Counsil By:
G. S. Keeley Manager, Nuclear Licensing GLB/grr y Attachment (2) s 4
A inVssio% or TE%As LTil1TIFA FlFCTnte twerANY
, Attachment 1 '
TXX-6157 Page 1 of 3 4 -
PRE-AND POST-0PERATIONAL TESTING AND SURVEILLANCE The follow 1'hg summarizes those actions taken to date and proposed future methods for assuring that protective coating work inside the containment (s) at CPSES will reasonably maintain their integrity, without separating from the j sur_ faces to which they have been applied. These actions and proposals are '
submitted to demonstrate TUEC's compliance with the intent of NUREG-0797 SSER-9, Appendix L, Section 3.0, and 4.0 and 5.0.
I. PROTECTIVE C0ATINGS APPLICATION, INSPECTION AND TESTING Consistent with the conclusions of Supplement 9 -to the Comanche Peak Safety Evaluation Report (SSER-9), containment building coating work was reclassified to a Non-Safety Related Activity. Appropriate FSAR revisions were implemented to reflect this change in Quality classification.
In order to demonstrate TUEC's commitment to assuring the integrity of containment coatings throughout the life of the plant, a comprehensive coatings _. engineering inspection and documentation program was established for in-process coating work. This program was implemented June 17; 1985, and is presently implemented in accordance with a series of procedures and instructions designated ECE-PC (Engineering / Construction Engineering - Protective Coatings). These procedures provide programmatic and operating requirements for the implementation of the program, including:
A. Qualification and training of engineering inspection personnel.
B. Inspection and testing procedures which 'specify:
- 1. Detailed operational methods for each inspection and test;
- 2. Inspection instruments and apparatus to be employed;
- 3. Frequency of test / inspection routines;
- 4. Acceptance criteria for each inspection and test; and
- 5. Records to be generated to document inspections and tests.
C. Verification of contings storage and handling.
D. Calibration requirements for measuring and test equipment.
E. Reporting, disposition and tracking of deficiencies identified.
F. Completion, issuance and control of documentation.
p, G. MaintenanceandControloftheUnit1andUnit2)CoatingsExempt n
Logy. - -
,
TXX-6157-Page 2 of 3 At the present time all coating application work is performed in accordance with engineering approved construction procedures. These procedures contain all those operating instructions necessary for the actual coating application, and are prepared in strict accordance with project specifications and the coating Manufacturers' written instructions.
The coating application, inspection, and documentation process as outlined above will be maintained throughout the Coating Application Program inside both containments. This program, or a similar program will also be implemented for coating repairs required throughout the life of the plant, as identified in " Operational Coating Surveillance."
II. OPERATIONAL C0ATINGS SURVEILLANCE The following methods and criteria for operational surveillance for contai.nment building coating work shall be employed:
! A. The. qualification and training of engineering surveillance personnel implementing the operational program will conform to the general requirements of the qualification / training program presently in effect for the in-process inspection program detailed in procedure ECE-AD-2-1, " Qualification and Training of Coating Field Engineers." Specific training and experience requirements will be established to ensure that persor.nel are qualified to perform surveillance.
Each Coating Field Engineer (CFE) must be physically capable of performing the assigned tasks and shall have natural or corrected near distance visual acuity.
Prior to performing work, each CFE will be trained to the requirements of all applicable specifications, procedures, codes and standards pertaining to their work. Subsequent revisions to any of these documents will require the same degree of training prior to implementation. Additionally, each CFE must demonstrate proficiency in the use of test equipment and inspection techniques outlined in the applicable procedures and instructions governing this work.
The CFEs will be provided technical direction by engineering personnel with appropriate experience and training in engineering and inspection of nuclear coatings. The Lead Engineer (responsible for coating and coating surveillance) will provide the necessary technical input and will coordinate the surveillance effort during operational coating inspections and application.
B. Prior to plant operation and at each respective refueling outage, a protective coating surveillance walkdown of the Unit 1 or 2 ccatainment building will be conducted to identify and report any current or incipient coating degradation or failure. Coating surveillance walkdowns will be performed by qualified CFEs under the direction of the Lead Engineer responsible for coating and coating surveillance.
. Attachment 1 TXX-6157 Page 3 of 3 The walkdowns shall consist of visual inspection of coated surfaces throughout the containment building, in accordance with approved Engineering Procedures. This visual inspection will be accomplished using optical aids such as binoculars where required.
Temporary scaffolding and supplemental lighting will be used as required in areas of particular interest.
Particular emphasis will be placed on examining those areas of coating work which nave been added to the Coating Exempt Log. l Particular emphasis will also be placed on coating work adjacent to the sump areas at elevation 808', as failed coating in these areas have the greatest potential for migrating to the sumps under accident conditions.
Coating deficiencies or degradation identified during the walkdowns will be documented and mapped on applicable drawings. Additional inspection and testing may be required to establish the scope and severity of the deficiencies. An engineering evaluation will be performed and a determination made as to the methods, extent, and scheduling of appropriate repairs.
Concrete coating repairs, except where embedded plates exhibit corrosion may be based on a risk assessment of potential radiological exposure due to the extent of decontamination required to restore the surface. All work will be performed in accordance with ALARA guidelines for personnel performing these tasks.
All coating touchup and repairs will be performed by qualified personnel in accordance with the coating application, inspection
, and testing program previously described.
l C. The program described in SSER-9, Appendix L. paragraph 4.1.1.
recommends the use of in-situ temperature and pressure testing for coating adhesion. We believe there is no need for this test to be part of our program for the following reasons:
Adequate assurance of the acceptability of coating initial conditions will be provided through the comprehensive backfit test program and final walkdown inspections.
In-service conditions will be verified with a thorough coating surveillance and inspection program during each outage.
This type of testing is destructive (to the coating) and, in view of the other actions prescribed by the program, is considered an unwarranted hazard to testing personnel.
l
, Attachment'2 TXX-6157 Page 1 of 5 ACTIONS REOUIRED OF TUEC-SSER-9, APPENDIX M, SECTION 4.
"Although the TRT did not recommend any actions to remedy deficiencies in the coatings at CPSES, actions were required to document the status of existing coatings so that future inspection and test programs implemented to comply with SSER-9, Appendix L could.be based on known coating conditions,"
These " Actions Required" and-TUEC's response to each issue are contained in the following:
I .. BACKFIT TEST PROGRAM A. Actions reauired of TUEC Apply the Elcometer calibration correction for the 4714 adhesion tests covering 2,189 miscellaneous steel items tested to establish a more reliable estimate of.the adhesion test failure -
rate. This revised analysis should include statistical analysis showing the 95% confidence upper limit of the failure rate for all miscellaneous steel items inside the containment building.
Analyze the corrected data to establish a more reliable estimate
- of the adhesion test acceptance criterion. Enter the resultant failed areas in the Protective Coating Exempt Log. The Coating Exempt Log will be used in planning future inspections of coatings, consistent with the guidelines of Appendix L (to SSER-9).
B. TUEC's Actions and Results Regarding the Unit I containment coating, the Elcometer calibration correction data was applied to each Elcometer reading
- . obtained during the period of improper calibration. A total of
- 2,056 Protective Coating Reports (PCRs), documenting 4,882 individual adhesion test results were found to be affected, and
- were included in the analysis.
When the Elcometer calibration carrection was applied, it was determined that 490 of the 4,882 readings could have failed the minimum test criterion of 200 psi.
i An evaluation of the adhesion test results using a cluster sampling statistical analysis technique, determined that with a 4 95% confidence factor as much as 20% of the coated surface on i
miscellaneous steel inside Unit #1 Containment could have failed the minimum test criterion of 200 psi.
1 i
+
w .~ , + .,y--...r. --y-.. ,e.,, y --.,.,-,-,,--.-,.-,-.-.---m.,e , - - , . - - - . . - , . , . . . , , - - - --,-...---,----w ..w-
.t - Attachment-2
-TXX-6157 Page 2 of 5 Accordingly, thirty six thousand (36,000) square feet of coating on miscellaneous steel surfaces inside Unit #1 containment have been added to the Exempt Log.
II. TRACEABILITY
-A. Actions Reauired of TUEC CPSES Nonconformance Reports (NCRs) C-81-01724 and C-81-01673 provide "Use-As-Is" dispositions for discrepant coating materials with inadequate technical justification for the disposition.
Accordingly, provide adequate technical justification to demonstrate the acceptability of.the batches of coating materials listed in the NCRs or, alternatively, identify and quantify the areas where these batches were used and place these areas in the Coating Exempt Log. Additionally, review all other NCRs which report discrepant or irregular conditions in coating materials.
For any such NCRs which were dispositioned "Use-As-Is", identify the batches and provide adequate technical justification for their acceptance, or identify and quantify the areas where batches were used and place these areas in the Coatings Exempt Log.
The Coating Exempt Log will be used in planning future inspections of coatings, consistent with the guidelines of Appendix L to this-Supplement (SSER-9).
B. TUEC's Actions and Results A compilation was made of all containment coating Nonconformance Reports (NCRs) pertaining to discrepant coating materials which have "Use-As-Is" dispositions. These NCRs were evaluated by the CPSES Coating Engineering Manager and an independant third party
- reviewer for technical adequacy of each "Use-As-Is" disposition.
All "Use-As-Is" dispositions have been found to be acceptable.
This list, along with the technical justifiction for each disposition was submitted to the NRC on TUGC0 Letter TXX-4613, dated November 18, 1985. No further action is required.
III. C0ATINGS PROCEDURES l
A. Actions Reauired of TUEC l The TRT found deficiencies in procedures and instructions for coating work and related inspection activities during the construction phase, which rendered them inappropriate or i inadequate for determining satisfactory accomplishment of i important activities. The TRT also found that the procedure review and approval system was inadequate to detect and correct these deficiencies.
+-
l
. - Attachment 2 '
-TXX-6157 Page 3 of 5 Accordingly, make the necessary changes to the procedure review and approval system to assure review and approval by technically qualified individuals, to prevent recurrence of the types of deficiencies discussed in Coatings Category 4 (of SSER-9) and to
,_ assure that procedures are reviewed for consistency and clarity.
Apply this revised review and approval system to the .issurance and revision of all procedures which govern future coating work, inspection and testing at CPSES, consistent with the guidelines
- of Appendix L to NUREG-0797, Supplement 9.
B. TUEC's Actions and Resulb
- Pursuant to the receipt of Supplement 9 to the Comanche Peak
- Safety Evaluation Report (NUREG-0797), TUEC took those necessary actions to implement a Non-Safety Related Containment Coatings Program at CPSES, consistent with the guidelines of SSER-9 Appendix L. These actions included a complete engineering review of the technical requirements for containment building coating work, which resulted in the complete rewriting of all procedures and instructions pertaining to coating application,. inspection, testing and documentation. These procedures were prepared and reviewed by engineering personnel who are technically qualified in nuclear coating work, to assure strict compliance with all i applicable Codes, Standards, Project Specifications and the coating Manufacturer's written instructions. Specific attention was directed toward correcting those procedural deficiencies identified by the TRT in Coatings Category 4 of SSER-9, relative to the use of Non-DBA qualified coating systems and inadequate or
- inappropriate technical requirements for coating work.
In conjunction with the overall revision of the CPSES Containment Coatings Program; procedure CP-EP-6.2, " Review and Approval of Engineering Procedures for Verification of Protective coating Work Inside Containment" was developed and implemented June 13, j 1985. This procedure required technical review and approval of ,
all coating inspection and documentation procedures by the i
Coating Engineering Manager and the Unit #2 Project Civil Engineer.
i Subsequent to this procedure issuance, all coating engineering i procedures were incorporated into the TUGC0 Nuclear Engineering (TNE) Manual. At this time, the requirements of CP-EP-6.2 were incorporated into procedure TNE-AD-3, " Preparation of Procedures i and Instructions."
T l NOTE: Due to a reorganization move, the TUGC0 Nuclear Engineering Manual is evolving into the Engineering / Construction Engineering Manual.
I i
. _ . . . ~ . . _ _ _ _ _ _ . . . _ _ . _ . _ . , _ _ _ _ _ . . _ . . , - - . . - . . . _ , . . , - .__.---_...._.,_m . . . . . . . ,__ . - . -
__ _ ___ _ .. _ _ _ _ _ m l
3 - Attachment 2
- TXX-6157' Page 4 of 5 IV. C0ATINGS EXEMPT LOG (CEL) 4.
A. Actions Reauired by TUEC Provide updated estimates of the additional items, including those detailed in Coatings Category 6 to be entered in the Exempt Log. Although all coatings are now considered exempt, maintain the CEL separately to identify all items which did not meet the requirements in affect at the time the coating work was performed. The CEL will be used in planning future inspections consistent with the guidelines of Appendix L of NUREG-0797, Supplement 9.
B. TUEC's Actions and Results
- 1) Elcometer Calibration Error Based on the study performed on the affects of Elcometer adhesion tester calibration deficiencies on miscellaneous steel coatings inside the Unit I containment building, it has been determined that as much as 20% of the coating could have actually failed the adhesion test criterion.
Accordingly, thirty six thousand (36,000) square feet of coating on miscellaneous steel surfaces have been added to the Unit 1 Protective CEL.
- 2) Unsatisfactory Dry Film Thickness Based on the TRT's determination that the coating dry film thickness failure rate on miscellaneous steel surfaces in Unit I containment was as much as 8.5% for the miscellaneous steel categories, TUEC's original estimate of 5% may be low.
Accordingly, the amount of miscellaneous steel coating placed on the CEL as a result of unsatisfactory dry film thickness areas identified in NCR C-83-03103 Rev. 2, C-83-03104 Rev. 2, and C-83-03105 Rev. 2 has been increased from 8,155 square feet to 13,863 square feet.
- 3) Non-Standard Coatings
- TUEC estimated that 2,500 to 6,500 square feet of inorganic zinc coating was applied over organic topcoats in overlap
, areas that surround repairs to protective coatings over J
steel. The resultant coating system is not DBA qualified.
Accordingly, 6,500 square feet of coating has been placed l on the Unit 1 Protective CEL to document non-standard coatings.
i i
.- Attachment 2 TXX-6157 Page 5 of 5
- 4) Inaccessible or Limited Access Areas TUEC letter TXX-4262 to the NRC dated August 21, 1984, describes 6,100 square feet of coating work applied in inaccessible or limited access areas which did not meet the requirements of Specification 2323-AS-31.
Accordingly, 6,100 square feet of protective coatings have been added to the Unit 1 Protective CEL to document coating applications in inaccessible or limited access areas, where all specified requirements were not met.
4
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