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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
_-.
l w ]
') l M Log #:TXX-6895.
== File # 10130 L . -~
- IR 84-32 l
-Z _ IR 84-11
- ' # * I RIELECTRIC November 6, 1987
, William G. Counsil Executive Vice Presuknt j U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 REQUEST FOR ADDITIONAL INFORMATION REGARDING INSPECTION REPORT: 50-445/84-32 AND 50-446/84-11
Reference:
- 1. Letter from D. R. Hunter (NRC) to M. D. Spence (TUGCo) dated February 15, 1985
- 2. .TXX-6144 from W. G. Counsil (TVEC) to R. D. Martin (NRC),
dated February 2, 1987 Gentlemen:
On' July 15, 1987, TV Electric representatives met with your R. F. Warnick and
. members of his staff to discuss the subject inspection report (Reference 1) and our response to the attached Notice of Violation , Item 1 and 2 (Reference ;
2). As .a result of that meeting, the following additional information '
relative.to our response to these items is provided.
For convenience, the alleged violation from the subject report and our initial response has been provided, followed by the additional information.
Very truly yours, G. G. Q W. G. Counsil By:D D. R. Woodlan Supervisor, Docket ,
Licensing l RDD:tgj j c- Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) 8711160067 871106 !
PDR ADOCK 05000445 l G PDR p
400 Noah Olive Street LB 81 Dallas, Texas 73201 (
Attachment lto TXX-6895
. November 6, 1987
] '
Page 1 of 10 Alleaed Violation
- 1. Failure to Reaularly Review the Status a1d Adecuacy of the 0A Procram Criterion II of Appendix B to 10CFR50, as implemented by the Preliminary Safety Analysis Report (PSAR) and the Final Safety Analysis Report (FSAR),
Section 17.1, " Quality Assurance Program," and ANSI N45.2-1971, requires that the quality assurance program shall provide for the regular review by the management participating in the pragram, of the status and adequacy of the part of the quality assurance program for which they have designated responsibility.
Contrary to the above, the applicant did not establish quality assurance procedures to regularly review the status and adequacy of the construction quality assurance program; nor did the applicant appear to have reviewed the status and adequacy of the construction quality assurance program.
(445/8432-02;446/8411-02)
TUGC0 RESPONSE TUGC0 acknowledges that procedures were not established for the regular review of the status and adequacy <af the construction quality assurance (QA) program. Notwithstanding this lack of procedures, it is TUGCO's view that managers and corporate offict:rs by virtue of their day to day involvement were aware of the status and adequacy of the construction QA program. That awareness was based on various practices employed by TUGC0 managers and officers during the history of CPSES to evaluate the QA program. Those practices includttd the use of quality committees, documented management review, and independent evaluations. In addition, these managers and officers routinely received a variety of reports ;
concerning the adequacy of the construction QA program such as TUGC0 QA internal audit reports and reports produced by independent personnel from outside of the TUGC0 organization.
- 1. Corrective Action and Results Achieved TUGC0 recognizes that regularly scheduled QA program assessments and reviews serve to focus management's attention on program adequacy and effectiveness. Accordingly, the Quality Assurance Overview Committee was l formed and has met regularly since September 1985. The original charter for this committee was contained in Procedure DQP-CQ-5. The duties and responsibilities of this committee are currently described in the following policies and procedures:
o NE0 Policy Statement Number 2, " Quality Assurance Program" (Revision 0 dated June 23,1986): Requires the NE0 Vice Presidents to meet periodically to assess the status and adequacy of the QA program and at least annually to provide a written assessment of the overall effectiveness of the program to the Executive Vice President, NE0. The Executive Vice President, NE0 will assure that an annual {
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Attachment.to TXX-6895.
. November 6, 1987 ~
Page 2 of 10 independent assessment of the TUGCO audit program is' performed and the results reflected in the Vice Presidents' annual assessment.
o NE0 Procedure 2.20, " Senior Management QA Overview ;
Program" (Revision 2, dated October 13,1986): Defines '
the methodology employed by the NE0 Vice Presidents in meeting their responsibilities as-defined in HE0 Policy l Statement No. 2. This procedure establishes a committee !
which meets at least quarterly to evaluate the status and i adequacy of the TUGC0 QA program.
o NE0 Procedure 2.08, " Joint Utility Management Audit Program" (Revision 0 dated June 23,1986): Provides'a method which the Executive Vice President, NE0 may utilize to perform the independent assessment of the TUGC0 audit
. program as delineated in NE0 Policy Statement No. 2.
- 2. Corrective Steps to Avoid Recurrence The corrective acticns described above are considered sufficient to !
prevent further violations.
- 3. Date When in Full Compliance Full compliance was achieved June 23, 1986.
ADDITIONALINF03 MAT 10N The lack of procedures resulted in a lack of documented reviews of the status and adequacy of ttie construction quality assurance program. This condition represented a weakness in the construction quality assurance program.
Based on the NRC finding, it was determined that specific formal controls to address this area were recuired. This, in part, resulted in the issuance of a j memorandum from the Presicent of Texas Utilities which called for development l of policies and procedures to ensure that the "Overall effectiveness of the l quality assurance program. . .be regularly reported to Corporate Management. . .". j Subsequently, Nuclear Engineering and Operations (NE0) Policy Statement Number '
2 was issued, detailing this policy and causing the development of (
implementing NE0 procedures 2.20, " Senior Management QA Overview Program," and i 2.08, " Joint Utility Management Audit Program".
The lack of established procedures to regularly review the status and adequacy !
of the construction quality assurance program concern was addressed in issue Specific Action Plan (If;AP) VII.a.5. " Periodic Review of QA Program." The ISAP evaluated the new procedural controls implemented based on the i requirements of ANSI N45.2-1971 and 10CFR50 Appendix B, as well as applicable criteria from the Institute for Nuclear Power Operations and the applicable sections of the NRC Standard Review Plan, NUREG-0800. Because of the similarity of the criteria in these documents, the ISAP criteria were developeu to closely reflect and expand upon the criteria contained in the .
Standard Review Plan. The ISAP review reached the following conclusions:
I
. Attachment to TXX-6895 1 November 6, 1987
. Page 3 of 10' ' J
..n o The program now provides for a regular assessment of the status ,
and adequacy of the QA program, o The program defines the management positions responsible for the
' periodic review of the QA Program.
o The program describes the methodology for performing the program assessments and their frequency.
o The program describes the methodology for reporting, tracking and follow-up of the results of the periodic review of the QA Program.
o Regular program review meetings are being held in conformance with the new procedures.
o Meetings are focusing effectively on identified problems in the QA program, o Refinements are being made to improve the implementation and documentation of the procedural controls which govern the review.
Based on the above described actions, we believe that the concerns identified in the violation have been thoroughly addressed. These actions will assure that the QA Program remains in compliance with the specified requirements.
Alleged Violation
- 2. Failure to Establish and Implement a Comprehensive System of Planned and Periodic Audits Criterion XVill of Appendix B to 10CFR50, states, in 3 art, "A comprehensive system of planned and periodic audits siall be carried out to verify compliance with all aspects of the quality assurance program and to determine the effectiveness of the program." The requirements are addressed in the pSAR and FSAR, Section 17.1, " Quality Assurance Program,"
which references Regulatory Guide 1.28 (ANSI N45.2) and ANSI N45.2.12 (Draft 3, Revision 4). Those commitments require that a comprehensive system of planned audits be performed on an annual frequency.
Contrary to the above, the following examples were identified which demonstrate the failure to establish and implement a comprehensive system of planned and periodic audits of safety-related activities as required, as noted below:
- a. Annual audits were not adequately addressed by the audit implementation procedures.
o TUGC0 Procedure DQP-CS-4, Revision 0, dated August 9, 1978, only required two audits of vendors fabricating reactor coolant pressure boundary components, parts and
Attachment to TXX-6895
!- Page 4 of 10 i i
l- equipment; one audit of vendors fabricating engineered l safeguards components, parts, and equipment; and audits of balance of plant (safety-related) as required by the quality assurance manager.
o TUGC0 Procedure 00P-CS-4, Revision 2, dated April 16, i 1981, required only that organizations will be audited on '
a regularly scheduled basis.
o TUGC0 Procedure 00P-CS-4, Revisions 2 and 10, did not specify auditing frequencies for design, procurement, construction, and operations activities, o TUGC0 Procedure DQP-CS-4, Revision 10, based audit requirements on Regulatory Guide 1.33, Revision 2, February 1978. This commitment did not fully address the requirements of the construction quality assurance program.
The above procedure and subsequent revisions failed to describe and require annual audits in accordance with commitments and requirements. Earlier audit procedures were not available to determine if they met requirements.
- b. Planning and staffing to perform 1983 audits was inadequate to assure that a comprehensive system of audits was established and implemented to verify compliance with all aspects of the quality assurance program, in that, of 656 safety-related procedures (which control safety-related activities) the NRC review revealed 3 that the applicant sampled only 165, or 25 percent, during the l 1983 audit program. Consequently, significant aspects of the i safety-related activities were not adequately audited.
I
- c. The Westinghouse site organization, established in 1977 to perform Nuclear Steam System Supply (NSSS) engineering services, was not audited by TUGC0 during the years of 1977, 1978, 1979, 1980 and 1981.
- d. Audit of vendors that manufacture or fabricate parts, components, and equipment for reactor coolant pressure boundary and engineered safeguards systems have not been conducted annually dating back to August 9, 1978. (445/8432-03; 446/8411-03)
TUGC0 RESPONSE The number and scope of audits conducted each year by TUGC0 over the history of the CPSES project reflect the evolution of the TUGC0 audit program from an initial overview function to the present role in which TUGC0 has assumed primary audit responsibility. The TUGC0 audit program was initially described in the CPSES QA Plan and beginning in 1978 in Procedure CQP-CS-4. (The procedure identification was changed to DQP-CS-4 in 1982.) The TUGC0 QA Department audit responsibilities described in the
Attachment to TXX-6895 L
t November 6, 1987 Page 5 of 10 SAR were formalized in Revision 0 (dated August 29,1978) of this procedure which established an audit plan. Consistent with TUGC0's initial overview role as outlined in PSAR Table 17.1-1, a minimum number of audits were planned and conducted for those organizations whose QA programs were described in the SAR. As TUGC0 assumed direct responsibility for site construction and engineering activities, the audit responsibilities of the QA Department expanded commensurately.
Accordingly, procedure CQP-CS-4 was revised to address these responsibilities by providing for regularly scheduled audits of these i activities and organizations and for the generation of an annual audit plan.
TUGC0 believes that the audit planning and scheduling practices employed by TUGC0 and its principal contractors over the history of the project collectively provided adequate audit coverage of the construction QA program. The conclusions of the CPRT independent review regarding audit planning and scheduling, as described in the Results Report for ISAP VII.a.4, was that " Audit planning and scheduling, though in the past not in compliance regarding frequency and not formally systemized until recently, did appear to be well thought out in the centext of the TUGC0 concept of the audit program requirements at any particular time".
Our response to each of the examples is set forth below.
ADDITIONAL INFORMATION To address the concerns of this violation, Issue Specific Action Plan (ISAP)
VII.a.4 was developed. This plan had the specific task of evaluating and considering the implications of these concerns on construction quality, determining the root cause of the findings and any generic implications, addressing the collective significance of the deficiencies, and proposing an action plan which would ensure that such problems do not recur. Input to the ISAP included the NRC Notice of Violation,10CFR50 Appendix B, SSER 11, the applicable portions of NUREG 0800, and various regulatory guides and standards.
l The ISAP VII.a.4 Results Report states: "The overall effectiveness of the audit program has been less than fully adequate. Specific examples are: it has failed to identify and cause corrective action of inadequacies in such areas as QC inspector training, qualification, and certification; and control of non-conforming items and corrective action. It is concluded, from the evidence observed that the failure to identify and cause corrective action in these two areas was due primarily to the practice of auditing to existing procedures while not performing verification of the adequacy of existing procedures to implement program requirements. It is further concluded that the cause of the deviations and weaknesses in the QA audit program which have been identified in this report are the result of inadequate procedures."
The ISAP Results Report also states: "Although audit program deviations and weaknesses related to construction activities were identified, it has been determined that no action is required beyond that specified in ISAP VII.c,
Attachment to TXX-6895 November 6, 1987 I
. Page 6 of 10 which addresses all areas of safety-related hardware and is intended to provide confidence that any currently unidentified concerns related to the quality of construction of the CPSES hardware will have been identified, evaluated and resolved."
TUGC0 RESPONSE TO EXAMPLE 2.a j l
TUGC0 has committed to meet the provisions of ANSI N45.2.12, " Requirements for Auditing of Quality Assurance Programs for Nuclear Power Plants,"
Draft 3, Revision 0 (vice Revision 4 as stated in the Notice of l Violation), dated May 2, 1973. We acknowledge that the TUGC0 audit '
implementation procedures did not explicitly establish an annual audit frequency for all organizations or activities. However, the preplanned audits conducted each year by TUGC0 and its principal contractors provided audit coverage of the involved organizations and the activities of design, construction, procurement and others, as applicable.
- 1. Corrective Action and Results Achieved Procedure DQP-CS-4, " Procedure to Establish and Apply a System of Preaward Evaluations, Audit and Surveillance", was revised in November 1984 to specifically require that applicable elements of the construction QA program be audited by TUGC0 annually or at least once within the life of .
an activity, whichever is shorter. Procedure DQP-CS-4 has subsequently '
been re-identified as DQP-QA-15.
- 2. Corrective Steos to Avoid Recurrence The corrective actions described above are considered sufficient to avoid further violations.
- 3. Date When in Full Comoliance Full compliance was achieved in November 1984.
ADDITIONAL INFORMATION ITEM 2.a ISAP VII.a.4 evaluated the audit program performance based on records of the audits performed. The evaluation concluded that the failure to perform vendor audits on an annual frequency resulted in no adverse affect on the audit
, program because of the additional activities implemented by the QA organization to supplement the audits which did occur. These additional activities included joint inspection / audits during which auditors would accompany inspectors on release inspection trips to investigate specific problems, and requests for corrective action sent to vendors for specific, identified problems that did not warrant an audit investigation or did not appear to indicate an adverse trend.
1 As stated in the response to a recent NRC request for additional information regarding this ISAP (Reference TXX-6656, dated August 14, 1987), "when the ISAP VII.a.4 Results Report was prepared...there were no 'known problems with
Attachment to TXX-6895 November 6, 1987 Page 7 of 10 vendor supplied material' which were attributed to the failure to perform I
' vendor audits on an annual basis. In other words, no procurred hardware problems were known that could have been identified and corrected through audits or other vendor compliance activities. Subsequent to issuance of the ISAP VII.a.4 Results Report, the scope and methodology of ISAP VII.a.9 has been revised to include hardware inspections which may identify problems which might have been identified in an audit program. Information pertinent to the adequacy of the audit program that is gathered during implementation of ISAP VII.a.9 and other ISAPs will be evaluated during the collective evaluation process and described in the Collective Evaluation Report."
TUCC0 RESPONSE TO EXAMPLE 2.h TUGC0 denies the allegation of a violation for the reasons that follow.
With respect to staffing levels, a designated audit group staff was established in 1979 which increased in strength each year through 1983; however, the number of qualified personnel who actually performed audits during those years also included members of the QA organization other than those assigned to the audit group. It is TUGC0's view that the total number of QA personnel who performed audits during 1983 represented an adequate staffing level. The CPRT independent review resulted in the same conclusion as documented in the Results Report for ISAP VII.a.4.
With respect to audit planning, TUGC0 has reviewed the 1983 audit plan against those safety-related procedurm for activities which were being more than minimally performed during 1983. Those procedures were grouped by activity groups which were then compared to the scopes of the audits conducted during 1983. All but three of the sixty activity groups identified were subject to audit during 1983. Of the three activity groups not subjected to a specifically scoped audit during 1983, two received ancillary coverage as a result of the 1983 auditing activities and one (Protective Coatings QC Inspection) was excluded from the 1983 audit program due to the extensive review by the NRC of that area which was ongoing during 1983.
TUGC0 believes that the 1983 audit program coverage of the design and construction phase of CPSES was adequate. This conclusion was also reached by the CPRT independent review as described in the Results Report for 1 SAP VII.a.4. However, TUGC0 concluded that some of its administrative practices in scheduling audits should be formalized in a procedure or instruction. Accordingly, Instruction DQI-AG-1.7, "CPSES Construction Phase Audit Program", was issued June 27, 1985. (This instruction has since been re-identified as Procedure DQP-AG-4.) A similar procedure for the scheduling of operations phase audits has been issued as DQP-AG-3, "CPSES Operation Phase Audit Program."
ADDITIONAL INFORMATION ITEM 2.b No additional information was requested.
Attachment to TXX-6895 l: ' Novemb r 6, IF87
, Page 8 of 10
]
1 TUGC0 RESPONSE TO EXAMPLE 2.c TUGC0 denies the allegation of a violation for the reasons that follow.
TUGC0 did not perform audits of the Westinghouse site organization because this organization is not and has never been responsible for the performance of safety-related activities. This was verified by TUGC0 during Westinghouse audits TWH-23 and TWH-24 conducted in 1982. However, subsequent to the NRC inspection TUGC0 performed an audit in November 1984 (audit number TWH-30) of the Westinghouse site activities which confirmed that the Westinghouse site organization was not responsible for the performance of safety-related work activities. Therefore, there is and was no requirement to audit this organization. The CPRT independent ,
review resulted in the same conclusion as documented in the Results Report l for ISAP VII.a.4.
To assure that we remain cognizant of the scope of work for the i Westinghouse site organization, the Westinghouse Division responsible for the Westinghouse site organization has been identified on the vendor audit i schedule and the TUGC0 Approved Vendors List (AVL). This assures that an '
annual evaluation of that Division's activities will be performed.
ADDITIONAL INFORMATION ITEM 2.c The CPRT review of this issue examined the scope of activities for which Westinghouse was responsible during the period in question. This review determined that between 1977 and 1981, the Westinghouse site organization provided support to the Westinghouse home office through involvement in the transmittal of Field Change Notices (FCNs) and engineering dispositions of Field Deficiency Reports (FDR) to TU Electric. Based on this, it was determined that the Westinghouse site organization did perform activities subject to 10CFR50 Appendix B Criterion VI, ' Document Control."
This activity was performed by Westinghouse personnel in accordance with procedures OPR 210-2 for FDRs and OPR 305-4 for FCNs. These procedures are in turn implemented in accordance with the requirements of the Westinghouse '
Nuclear Service Division Quality Assurance Program Plan WCAP 9245. As a result of this, the site organization was subject to audit by Westinghouse per WCAP 9245, and was audited six times in the period from January 1978 to October 1986.
For this activity, the requirements of ANSI 45.2.12 were met by TV Electric's audits of the Westinghouse parent organization for compliance with 10CFR50 Appendix B Criterion XVIII.
TUGC0 RESPONSE TO EXAMPLE 2.d 2
TUGC0 assumed responsibility for the vendor audit program from Gibbs &
Hill beginning in January 1978. To assure the most effective utilization of audit resources, TUGC0 QA management scheduled vendor audits based on the following:
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o Vendor Activity; I o Evaluation ratings determined from reviews of source o release inspection trip reports; o Receipt, installation or test problems communicated to the audit group from the site; o The last audit date.
This practice assured the application of audit resources to a vendor during active fabrication or when source or receipt inspections or other information indicated potential quality problems.
There were occasions when vendors were not audited annually due to satisfactory vendor ratings or lack of activity at the vendor facility.
However, it is our view that our practices resulted in an adequate vendor audit program and were equivalent to the practices endorsed by the NRC in Regulatory Guide 1.144, Revision 1. The CPRT independent review of this violation concluded in the Results Report for ISAP VII.a.4 that the failure to perform audits of all TUGC0 vendors on an annual frequency did not result in any adverse effects on the audit program because of the ,!
additional activities implemented by the QA organization to supplement the audit activity.
- 1. Corrective Action and Results Achieved Following the NRC Special Review Team inspection conducted in early 1984, TUGC0 determined that the FSAR description of its external audit program i needed clarification. Consequently, in August 1984 TUGC0 revised FSAR l Table 1A(B) to adopt a commitment to paragraph C.3(b), " External Audits",
of Regulatory Guide 1.144, Revision 1. This commitment requires the performance of annual evaluations and triennial audits of active vendors.
TUGC0 Procedure DQP-CS-4, " Procedure to Establish and Apply a System of Pre-award Evaluations, Audits and Surveillance," was revised in November 1984 to incorporate this commitment. (This procedure has since been re-identified as DQP-QA-15, "TUGC0 QA Audit Program.") Evaluations for all active vendors on the AVL which were last audited during or before 1983 were completed in the first quarter of 1985. As of January 1,1986 all active vendors on the AVL were within their annual evaluation and triennial audit frequency.
- 2. Corrective Ste.ps to Avoid Recurrence The corrective actions described above are considered sufficient to prevent recurrence of this violation.
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- 3. Date When in Full Compliance Full compliance was achieved 'as of January 1,1986.
ADDITIONAL INFORMATION IT[M 2.d A CPRT review was performed based on the audit index for the period, which determined that the audits were not performed in accordance with the ;
applicable requirements for timeliness or frequency. The review determined j that a number of mitigating activities were performed during this period. '
These included:
o A vendor rating program was used to adjust the scheduling of inspections and audits. Some of the audits which were reviewed by the CPRT were noted to have been performed in response to !
unsatisfactory inspection results.
o In mid-1979, a joint inspection / audit program was instituted l whereby auditors would accompany inspectors on release inspection trips to investigate specific program areas based on problems identified during previous source inspections.
o TV Electric QA used " Request (s) for Corrective Action" which were correspondence with the vendors requesting corrective action for i specific, identified problems when it was concluded that the problems did not warrant an audit investigation or did not appear to indicate an adverse trend.
o Internal documents known as " Yellow Flag Sheets" were also utilized by the TV Electric QA Staff to ensure that applicable QA personnel were aware of status and/or problems with particular i vendors (e.g., a hold placed on shipments from a vendor until after an audit was performed).
While source inspections and limited scope audits were not intended to serve ;
as substitutes for a regularly scheduled program of audits, they did provide data which was used by TV Electric to evaluate the effectiveness of vendor QA programs.
As discussed in the response to NRC's request for additional information !
related to this ISAP (TXX-6656 dated August 14, 1987), " Subsequent to the issue of the ISAP VII.a.4 Results Report, the scope and methodology of ISAP VII.a.9 has been revised to include hardware inspections which may identify ,
l problems which might have been identified in an audit program. Information pertinent to the adequacy of the audit program...will be evaluated during the collective evaluation process and described in the Collective Evaluation Report."
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