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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:LEGAL/LAW FIRM TO NRC
MONTHYEARML20055E2741990-05-0101 May 1990 FOIA Request for Investigation Rept 4-89-008 ML20042E3291990-04-10010 April 1990 Advises That Due to Clerical Error,Author Ltrs to NRC Re Insp Repts 50-445/90-05 & 50-446/90-05 Not Served.Repts Will Be Served to All Parties on Attached List ML20042E3311990-03-31031 March 1990 Advises That Open Issues Re Thermo-Lag Insulation Matl & Harassment & Intimidation of QC Inspector Not Addressed in Insp Repts 50-445/90-05 & 50-446/90-05.CASE Questions Whether Formulas to Mfg Thermo-Lag Changed ML20042E3351990-03-28028 March 1990 Requests Listed Info or Basis for Specific Action Re C Grimes 900208 Ltr to J Cahill Re Issuance of License NPF-28,specifically Why Temporary Exemption from Schedular Requirements Granted ML20042E4301990-03-26026 March 1990 Lists Questions Based on Review of Insp Repts 50-445/89-88, 50-446/89-88,50-445/88-88 & 50-446/88-88,including Contamination Problems Found Inside Namco Switches in 1989 & Aircom Fasteners ML20043B7341990-03-0202 March 1990 FOIA Request for Records Re Insp Performed by C Williams on 900207-0302 Concerning ASME Section III Compliance Review & Weld 12A ML20011F0091990-02-0808 February 1990 Certifies That Util Covered for Decontamination Liability & Excess Property Insurance,Effective on 900208 ML20012D6361990-02-0505 February 1990 Responds to Util 891221 Ltr to NRC Re thermo-lag Dispute ML20012D5951990-02-0505 February 1990 FOIA Request for Documents & Records Relevant to & Generated in Connection W/Insp Repts 50-445/90-05 & 50-446/90-05 on 900131 Re Therm-o-Lag Issues ML20005G5381990-01-10010 January 1990 Urges Resolution of Issues in Dispute & Matters of Concern to Case Prior to Fuel Load Decision.Issues Include, Auxiliary Feedwater Check Valve & Pending Enforcement Action & Station Svc Water Sys Enforcement Action ML20005G5481990-01-0909 January 1990 Forwards Analytical Evaluation of Station Svc Water Sys for Facilities by Case Consultant J Doyle Dtd 891231.Rept Submitted to Document Events Re Removal of Plastite Liner in Station Svc Water Sys in Spring 1988 ML19354D7631990-01-0909 January 1990 Forwards Rev 0 to Case Final Rept, Analytical Evaluation of Station Svc Water Sys,Comanche Peak Nuclear Power Station. Rept Contains Conclusions Applicable to Issues of Regulatory Character & Competence of Util to Manage & Operate Plant ML20005G6951990-01-0909 January 1990 Corrected Ltr Discussing K Doyle Rept, Analytical Evaluation of Station Svc Water Sys for Comanche Peak. Rept Concludes That Probable Cause of Failures of Sys Due to Inability of Util Personnel to Perform Accurate Analysis ML20005G6751989-12-12012 December 1989 FOIA Request for Documents Re Insp Repts 50-445/89-23 & 50-446/89-23 on 890405-0502 ML20006B8811989-12-0505 December 1989 Appeals Denial of FOIA Request for App B Records ML19332F4911989-12-0101 December 1989 Discusses NRC 891027 Ltr to B Brink Re Citizens for Fair Util Regulation 891016 Request for Stay.Nrc Must Be Consistent in Application of NRC Procedures Re Probing of Allegations.Improprietaries Should Be Sought from Case ML20005G5441989-11-29029 November 1989 Requests That NRC Independently Conduct Insp/Investigation of Dispute Between Case & Util Re Thermo-Lag & Thermo Science,Inc Qc/Qa Breakdown.Util 891116 Ltr to Case Re Results of Investigation of Inspector a Concerns Encl ML20011D1221989-11-20020 November 1989 Discusses Concerns Re Integrity of Regulatory Process as Affecting Plant ML19332D7371989-10-0606 October 1989 FOIA Request for Records Re Chronology of Events Beginning 1985 ML19332F3141989-09-27027 September 1989 FOIA Request for Documents Re 890908 Insp Repts 50-445/89-38 & 50-446/89-38 ML20247R0381989-09-23023 September 1989 Advises of Case Position Re Need for Regulatory Enforcement Action in Response to Mgt Process & Administrative Control Failures Evidenced by 890505 Event at Facility ML20248C2711989-09-23023 September 1989 Requests Reclassification of Violations Noted in Insp Rept 50-445/88-47 & 50-446/88-42 on 880707-0802.Informs Case Believes Further Insp & Enforcement Review Appropriate ML20245J9341989-06-30030 June 1989 Forwards Util Response to Cap Rock Electric Cooperative,Inc Request for Order Modifying Antitrust License Conditions ML20248D6571989-06-16016 June 1989 Ofc of Inverstigations Subpoena to Jj Macktal,Nrc Investigation 4-89-008.* Requests Leave of 5 Days to Respond to Request Filed for Enforcement of Subpoena & to Brief Commission on Issues Re Subpoena ML20246K3781989-05-22022 May 1989 Requests Status of NRC Determination of Pending Fee Waiver Requests for FOIAs 89-47 & 89-52 ML20245A0381989-05-12012 May 1989 Forwards Request from Cap Rock Electric Cooperative,Inc for Order Enforcing & Modifying Antitrust License Conditions & Certificate of Svc.W/O Request ML20244D8701989-04-0606 April 1989 Forwards Endorsement 27 to Nelia NF-274 ML20246K3621989-03-30030 March 1989 Responds to Responding to Appeal of Denial of Fee Waivers for 890301 FOIA Requests.Justification for Fee Waiver Provided ML20246K3401989-03-0101 March 1989 Appeals Denial of Two Requests for Fee Waivers Re FOIAs 89-47 & 89-52 on Behalf of Jj Macktal & SM Hasan.Purpose of Requests to Examine Process Utilized by EDO & NRC for Revoking Confidentiality of Allegers ML20244D8771989-01-26026 January 1989 FOIA Request for Records Re Settlement Negotiations & Agreements in Licensing Proceedings Effectuated During Jul 1988 ML20246K2061989-01-25025 January 1989 FOIA Request for Records Re Revocation of Confidentiality on 890123 by V Stello & Requests for Info by Third Parties Which Concerns SM Hasan or Jj Macktal &/Or Respective Allegations About Facility ML20205D1401988-10-14014 October 1988 Forwards State of Tx Public Utils Commission Substantive Rule 23.66 Re Wheeling for Cogenerators ML20151U5971988-08-0808 August 1988 Requests Withdrawal of Portion of 860131 Filing Re Case Request for Imposition of Fine,For Suspension of Const Activities & for Hearing on Application to Renew CP ML20150E1411988-07-12012 July 1988 Forwards Suppl Filing of Response of Applicant to Motions to Stay,To Intervene & for Sua Sponte Relief Filed by Various Parties ML20150E2061988-07-10010 July 1988 Clarifies Relevant Issues Raised in LC Clark Re Recent Filings by J Doe.W/Supporting Info & Certificate of Svc ML20150D5031988-07-0808 July 1988 Forwards Motions to Intervene & for Sua Sponte Filed on Behalf of Citizens for Fair Util Regulation & Individual Residents ML20150D5091988-07-0707 July 1988 Forwards Substitute Pleadings of Petitioner J Doe ML20150D5261988-07-0606 July 1988 Forwards Motion for Permission to Withdraw Pleadings W/O Prejudice & W/Leave to File Substitute Pleadings within 48 H ML20151Y6221988-04-29029 April 1988 Forwards Wg Counsil Transmitting Errata to Project Status Repts for Mechanical Suppl a - Sys Interaction & Mechanical Suppl B - Fire Protection. Related Correspondence ML20151T7141988-04-26026 April 1988 Forwards Applicants Answers to Board 14 Questions Re Action Plan Results Rept VII.a.9.Checklists Used for Reinsp/ Documentation Review for 81 Items of Equipment & Matl Not Included W/Answers Due to Vol Amounting More than 1,000 Pp ML20151E9771988-04-0808 April 1988 Informs That Applicants Notified Board & Parties of Availability in TU Electric Document Room of Matls Ref in NRC Sser 14.W/Certificate of Svc ML20148M0221988-03-30030 March 1988 Forwards Exhibit 18 Introduced to Record by Counsel for co-owners During Williams 880218 Deposition & Pages 190-195 & 464-465 of Transcript,Representing Entire Contents of Deposition Re Exhibit.W/Certificate of Svc ML20148K3681988-03-24024 March 1988 Forwards Excerpts from Form 10-K Filed by Util W/Security & Exchange Commission.Excerpts Contain Financial Disclosures Re Facility.Info Provided to Keep Board Apprised of Matters Re Facility ML20150D0151988-03-21021 March 1988 Forwards Transcripts of Meeting Held on 871217-18 & 880218 Between Case & Util.W/O Encl.W/Certificate of Svc ML20150D0201988-03-18018 March 1988 Informs That on 880314,CASE Filed Tenth Progress Rept W/ Board & Urged Board to Review Transcript of Public Meetings Held Between Case & Applicants in Which Walsh/Doyle Issues Discussed.W/Certificate of Svc.Related Correspondence ML20148G1411988-03-17017 March 1988 Forwards Ltr of Even Date from Util to NRC Which Transmits Copies of Errata Prepared for Project Status Rept Re Cable Tray & Cable Tray Hangers & Conduit Supports Train C 2 Inch Diameter & Less ML20150D0381988-03-14014 March 1988 Forwards Util Informing That Licensee Still Collecting Documents for Files Containing Documentation for Result Rept VII.a.9 ML20196D5001988-02-0808 February 1988 Forwards Wg Counsil Transmitting Project Status Rept for Civil/Structural, Rev 0.Related Correspondence ML20195J0621988-01-15015 January 1988 Forwards Wg Counsil to Nrc,Transmitting Project Rept for Electrical, Rev 0.Rept Also Sent to J Ellis & Cygna.Related Correspondence ML20147D5771988-01-14014 January 1988 Forwards Util Form 8-K,current Repts, & 1214,filed W/Securities & Exchange Commission.Documents Forwarded as Part of Parties Efforts to Keep Board Apprised to Matters Re Facility.Related Correspondence 1990-05-01
[Table view] |
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TRIAL LAWYERS FOR Pusuc JUSTICE. P.C.
COUN5tuCRS ATtAW SUITE 611 .
2000 P STREET. NORTHWEST
, ANTHONY E ROtSMAN VASHINGTON. D.C. 20036 B6CKETED (202W3m U" " D'"'C' "
USNRC ARTHUR BRvANT STAFF ATTORNtY .
5 W ,5 M" '85 NJG 20 A!0:58 August 15, 1985 1- : e.
Mr'. Darrell Eisenhut U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Vince Noonan U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Sirs:
The Comanche Peak Response Team (CPRT) Program Plan and the Issue Specific Action Plans were submitted to the NRC on June 28, 1985. The objective of the plan is to insure that the Comanche Peak nuclear power plant receives an operating license. In order to receive a license the Nuclear Regulatory Commission must find that there is reasonable assurance-that the facility, as built, does not endanger the public health and safety.
It is the position of the Citizens Association for Sound Energy (CASE) that such a finding can only be made after (1) the completion of a 100% reinspection of the plant, (2) a complete design review analysis, and (3) the successful implementation of an acceptable corrective action program.
The CPRT Program Plan, even if successfully implemented, lacks significant programmatic controls, and is substantively deficient in a number of key areas. The process and substance deficiencies identified in the document submitted to date are described in this document. Since the CPRT itself is not complete (i.e. the QA/QC program for the plan has not yet been submitted, the inspection attributes are missing, the checklists for retraining are missing, etc.) these comments are not defini-tive. Further comments will be submitted after receipt and review of the other portions of the plan.
i 8500200693 850015 PDR ADOCK 05000445 G PDR
4 It should be noted that it is CASE's position that the plan itself should be litigated before the ASLB, and that additional hearings should be held on the adequacy of implementation of the reinspection effort, as well as the appropriateness of the pro-posed corrective action plan and the implementation of the corrective action program. It is also CASE's position that the ambiguity in the plan is so great that approval should not be granted prior to discovery on the program elements. It is our belief that the Applicant's commitments are not the actual program plan.
Finally, CASE objects to the proposition that the Staff's view of the questions raised in this letter (and the review of TUEC's response to Staff questions) will ime committed to an SSER prior to a public meeting on the final proposed program plan.
1 The efforts of the public and the whistleblowers to review TUEC's final program plan will be meaningless without providing for public review and comment on the CPRT.
We look forward to meeting with the Staff on these matters in the near future.
Sincerely,
$k I Billie Pirner Garde cc: Service List
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PRELIMINARY REVIEW OF THE COMANCHE PEAK RESPONSE TEAM PROGRAM PLAN (DOCKET 2)
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PRELIMINARY CRITIQUE OF THE PROGRAMMATIC
' ASPECTS OF THE CPRT PROGRAM PLAN This critique contains observations on the following aspects of the CPRT program plan:
- 1. Overall inadequacy of the proposed approach.
- 2. Programmatic deficiencies with the third party efforts proposed.
- 3. Programmatic deficiencies in the integration of the various overviews, reinspections, evaluations, and ongoing work activities.
- 4. . Programmatic deficiencies in methodologies.
- 5. Programmatic deficiencies in scope, i.e. the depth'and breadth of the review.
'
- 6. Programmatic deficiencies in the sampling techniques.
- 7. Programmatic deficiencies in the ISAP/DSAP approach to "
External Source Issues.
I- 8. Missing elements of proposed program.
- 9. Comparison of CASE proposal and the CPRT.
In each of these categories there are both specific and general observations. These comments however are not definitive.
There is no attempt to address the specific inadequacies of various ISAPs/DSAPs, nor is there any attempt to guess the inadequacy of the CPRT QA/QC program. Several charts have been attached as Exhibit 1 to this document to demonstrate the missing elements of the proposed program. (We have taken the liberty of modifying the charts contained in the progam plan submitted by the Applicant for illustrative purposes.)
,, - r -
OVERALL INADEQUACY OF THE PROPOSED APPROACH The most significant defect in the CPRT Program Plan is that e
it perpetrates the iterative process of design and construction failures. TUEC has chosen to " push ahead" with the reinspection and corrective action program, and only incorporate retro-spectively any rework or reinspection requirements which result from the conduct of the CPRT.
According to the CPRT-Program Process (Rev.2, p.15), the scope of the actual work of the reinspection program, as outlined in the ISAPs/DSAPs "will be based on a preliminary assessment of the root cause and potential generic implications of the identi-fied deviations...Accordingly, most of the ISAPs and DSAPs will utilize iterative or phased implementation approaches that include an initial phase that is exploratory in nature."
Since the reinspection work has already begun it is apparent that the exploratory phase has been. completed and preliminary assessments of the root cause and potential generic implications have already been identified. Yet none of the preliminary assecaments have been disclosed, produced to the public or the NRC. Nor have they been completed using a Quality Control /
Quality Assurance program for the CPRT, since such a program has not been developed. It is not clear from a reading of the program plan whether the results of the exploratory phase have ever been - or will ever be - documented.
TUEC's inability to successfully implement the iterative design and contruction process has caused major regulatory, safety and financial problems. The choice of an iterative l
. . _ . . . . . _ _ _ _ . - _ ~ ._._;
approach to the reinspection and corrective action program is indicative of current management's inability or unwillingness to e
choose the prudent. approach to getting the Comanche Peak project under control.
It is our view that the only way to successfully approach the reinspection, reanalysis, and corrective action project is to start with a clean slate. That is, to halt construction entirely until the CPRT program plan has received the full approval of the NRC Staff and the Licensing Board. Only then will it be prudent to begin the operation through a phased approach -- first reinspection, then rework.
The second major inadequacy of the program is that it is not comprehensive in scope, breadth or depth. As submitted, the program plan results will not be able to support the reasonable assurance objective sought by TUEC. Some details of the program inadequacies have been summarized in following sections.
Most importantly the CPRT proposes that concerns are resolved at the time that "TUGCo has defined actions" which "when implemented will correct identified deficiencies and preclude similar deficiencies." (Rev. 2, p. 5) The history of implementation failures at Comanche Peak provide no basis for the Staff or the public to be able to rely on the successful ;
implementation of any corrective action. This is particularly true.since it is.TUGC], not the independent third party, that is l recommending the. corrective action in the first place. This situation makes it even more crucial that NRC hold points be i
mandated for~ review of any correction or rework effort.
6 0
, The third major inadequacy of the proposed program is that it is not controlled by third party personnel, but instead a
remains under the control and direction of TUEC. For example, TUEC controls all modifications of ongoing work in Unit II
.(Rev.2, p.4) and also the " future plant operations" (Rev 2, p.5).
The lack of independence of the third-party teams to control their work eliminates their value, adding only confusion, not credibility.
Fourth, the management team remains a mystery. It is not sufficient for TUEC to have ostensibly removed the former QA/QC executives of the Comanche Peak project and replaced them with a team of borrowed professionals who march to the beat of an unknown drummer. The current management team is a completely diversified group of consultants, loaned employees, contract employees, advisors, and others. It remains unclear what has happened to the former executives, or why,.and it is even murkier who is currently running the project - either the reinspection /.
corrective action program, or the remaining construction project.
This confusion surrounding the management personnel is a critical weakness in the current proposal.
We believe that the reinspection program and any subsequent required corrective action must be done by truly independent third parties. They must have clearly defined reporting respon-sibilities to the NRC under 10 C.F.R., as well as the responsibi-lity for drawing the conclusions about the scope of the problems.
The remaining work to be done on Unit II should be handled by a new team of TUGCO and/or prime contractor personnel who have not '
had anything to do with previous construction problems.
s - y,-r - -r-
.c The CPRT program plan also suffers from a confusing and
- p. unclear methodology being implemented by numerous separate organizations. This multiple level approach invites programmatic breakdowns and failures in implementation of even the best program plans. To illustrate, the program contains an indepen-i dent design verification program (IDVP) using the vertical slice methodology of one safety system, a horizontal review of two other systems, a sampling program (employing both a random sample and a bias sample), a 100% review of-the large bore piping, a design analysis review, and hundreds of response inspections to ISAPs and DSAPs. Each portion of the program plan is being accomplished according to a different set of criteria, a different company's quality control / quality asourance criteria, and being directed by separate management teams. The standards against which inspections are accomplished are ambiguous and open to interpretation. The organizational structure for the inter-face of the programmatic elements is either non-existent, or appears to be unworkable.
Other problems with sampling methodology, and major elements of the program which are still missing are described below.
Finally, a major fatal flaw of this program is its failure to produce the necessary level of detailed information to preclude misinterpretation. This is particularly important in this plan since there is a myriad of different personnel working on a plethora of reinspections, and the reinspection personnel are not the individuals drawing conclusions, or making recommen-dations about the findings.
Another result of having no comprehensive attribute check-list for reinspections is that there will be no meaningful way to o
assess whether adoption of a previous external inspection is appropriate.
Finally, the failure to produce detailed attribute check-lists renders paperwork reviews by third-party overviewers or the NRC virtually meaningless.
The NRC must at a minimum require the CPRT program (1) to be reorganized into a logical step-by-step process, (2) to be based on the reinspection of systems and components against detailed 3
attribute checklists, (3) to establish NRC inspection hold points at critical junctures, (4) to require an independent overview
- of the required corrective action, and (5) to remove TUEC from the task of determining the co'nsequences of generic / programmatic defects.
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PROGRAMMATIC DEFICIENCIES WITH 9
THE PROPOSED THIRD PARTY EFFORTS
- 1) None of the third parties are independent of TUEC, since all of the consultants are under the direction of the CPRT.
- 2) The third parties were selected solely by TUEC, dis-regarding the importance of.the concurrence of the public, and the nomination and approval procedures for independent third parties used by the NRC since 1982. This after-the-fact assertion does nothing to restore the confidence of the public in the " fresh perspective."
- 3) The review team leaders, issue coordinators, and advisors are primarily responsible to, c. are, in fact, TUGCO 4
personnel who have been involved in the construction project for a long time.
- 4) The asserted qualifications, reputation, and integrity of the third party consultants have not been tested through discovery or cross-examination, nor have the consultants answered questions from the public on their experience, competence, integrity, or the direction from the CPRT regarding the scope of their work.
- 5) The third party consultants, individually and organiza-tionally, are apparently not being considered a part of the normal regulatory process, and therefore not required to report all safety related information reportable under 10 C.F.R.
50.55(e) and 10 C.F.R. Part 21 to the NRC directly.
- 6) The third-party consultants can only recommend correc-tive action to TUEC/TUGCO, but they cannot control the implemen-tation of the corrective action. It is not even clear whether the third party has the autho.rity to insist on accomplishment of a particular corrective action as a caveat for any conclusions.
- 7) The SRT responsibilities, under the direction of a TUGCO Vice President, control the CPRT effort through selection of management personnel, approval of the action plans, review and approval of the " safety significant" determination, and root cause and generic implication assessment, and approval of corrective action.
- 8) The same TUGCO Senior Vice President, is also in charge of.the issues raised through the SAFETEAM, and other project activities, i.e., there is no procedure for inclusion of new issues without approval of TUGCO management.
PROGRAMMATIC DEFICIENCIES IN THE INTEGRATION OF c' THE VARIOUS OVERVIEWS, REINSPECTIONS, AND EVALUATIONS
.2
- 1) There is no status assessment of system commodities or defined baseline of items, subject to the CPRT. Without such a document the completion date or progress made can not be quantified.
I
- 2) Interfaces between the ongoing project and the program reinspection plan are almost non-existent. (Interface between the design, construction, reinspection, and corrective action aspects of the project are critical for successful implementation of the program plan.)
- 3) The use of the Collective Evaluation Reports providing information at the end of the DSAP/ISAP process precludes consi-deration of critical.information by all disciplines during the reinspection.
- 4) The circular approach to expanding issues is, as described on page 2 of revision 2, not detailed in a manner which provides confidence that the all generic implications and root causes will be extrapolated to other areas of the plant.
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PROGRAMMATIC DEFICIENCIES IN METHODOLOGY
, 1) The methodology is not supported through references to established professional codes (ASME, ANSI, AWS, etc.).
- 2) The methodology is ambiguous about commitment to' the FSAR, and provides no criteria upon which an exception will be sought.
- 3) Reporting procedures for third-party auditors exclude independent contact-with the NRC.
- 4) Issues " closed out" by the external source for whatever reason are not considered for potential root cause or generic implications.
- 5) The program plan does not include all vendors, or separate construction activities and therefore presumes that work was accomplished in accordance with regulatory requirements.
There is nothing to justify this position.
- 6) The hardware categories proposed in the self-initiated evaluation are not comprehensive. There is no explanation for how homogenous populations were selected. There is no explana-tion of how the selected populations will provide the foundation to reach the broad conclusions predicted by the CPRT.
- 7) There are no attribute checklists for inspections, or for inspectors to be retrained to.
j
- 8) There is no new retraining, recertification programs for TUEC or B&R QA/QC or craft personnel which insures that the identified failures in the training program implementation is not repeated.
- 9) The criteria for determination of defects is its " safety significance", not necessarily non-compliance with FSAR require-ments.
- 10) There is no provision for assessing deficiencies in inaccessible hardware components.
- 11) There is no provisiors for logical consideration of potential programmatic' generic defects, such as inadequate design review. All defects, deficiency reviews, etc. are going on simultaneously.
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i PROGRAMMATIC DEFICIENCY IN SCOPE, DEPTH AND BREADTH
- c. e
- 1) The program plan does not provide the breadth of review
' necessary to reach any_ conclusions about the overall design and construction of.the plant (i.e. insufficient number of systems
= proposed and a lack of attributes on the selected systems).
{. 2) No basis has been provided to justify the selection of the civil / structural, electrical / mechanical, instrumentation systems proposed.
I 3) The external source issues have identified massive specific or programmatic deficiencies. The proposed program
- - fails to accommodate the reported failures substituting instead the review of the smaller number of. systems as a first cut.
f i 4) The size of the sample of systems to be reviewed is-4 inadequate to reach any meaningful conclusions about the systems or components which are called into question by external source '
issues.
4 t 5) The information provided on the large bore piping reanalysis is insufficient to determine whether the " major j concerns about the system" are the only concerns which should be
- considered. (There are no-submitted procedures, checklists, i programmatic details about the' program.)
4 F 6) The vertical slice approach for the mechanical components is supposed to extrapolate the IDVP results to other
- systems, but.the slice is not comprehensive enough, it relies upon other inspection results to eliminate' inspection ~ attributes.
- 7) The IDVP plan should include the timely consideration and implication of the root cause of all IDVP-issues on other compo-nents and systems.
- 8) There is no justification provided to exclude the Westinghouse-designed portions of.the! plant. Since the design QA
- breakdown apparently stems from implementation failures, all j
vendors must be subjected to the design review analysis to insure the adequacy of the design for CPSES.
i
, 9) The scope of the DAP was developed by, eliminating j inspection elements by reliance on the inspection by numerous
-other external sources, which themselves were. separate from the
[ current effort and conducted according to totally different pro-cedures, and intended to discover different information.
- 10) There is no justification for the creation of arbitrary i
homogenous hardware groups to use as a base to extrapolate results of the DAP.
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_ , _ ____.__,_s_.-_.___. __. _ . . . . _ . . _ _... _ _ _,_
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- 11) Expansion criteria for components are ambiguous and-l . rely on no developed acceptability level.
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PROGRAMMATIC DEFICIENCIES IN THE SAMPLING TECHNIQUES 4
- 1) The proposed sampling approach is generally based on
- the conduct of reinspection of both bias.and random samples. The i reinspection itself is done against unknown ~ baseline criteria L (i.e. sometimes the FSAR, sometimes " safety significance,"
sometimes'an unknown attribute checklist) using a 95/5 sampling
. plan. The attributes are, a,s of yet, unidentified so there is no way to determine by: reviewing the plan whether .the reinspection
- will be of sufficiently detailed attributes to permit meaningful' conclusions about the acceptability of any one component.
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- 2) The bases for the CPRT decisions will be. engineering
- evaluations of the safety significance of design, construction,
! or process deficiencies, not raw data. Therefore, only those j defects which are judged to have any safety significance will.
i ever be used as a' basis'to reach the threshhold for expanding the j sample size.
j .
- 3) Exploratory evaluations which are not recorded are used j to identify the specific sub-p,opulation rendering the. sampling process biased from the beginning.
- 4) The sampling approach is not committed.
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1 i PROGRAMMATIC DEFICIENCIES IN THE APPROACH TO
- EXTERNAL SOURCE ISSUES AND SELF-INITIATED EFFORTS
- 1) The ISAP/DSAP approach ignores the critical need to assess the project as a whole, instead of on a piecemeal
. approach.
- 2) ISAPs are not prepared on any issues not yet identified by the NRC-TRT, including over 700 internal allegations in the SAFETEAM files.
- 3) ISAP development, done by the issue coordinators or l field consultants, do not coincide with a standard set of f
-requirements (i.e. some ISAPs use the FSAR as the acceptance criteria, some use regulatory guides, some use professional
- standards). -Therefore it is not possible to draw conclusions about compliance with the originally prescribed standards.
- 4) ISAPs do not address the history of other problems related to the specific issue (i.e. each ISAP is self-contained, except for the end-of-line review).
- 5) Each ISAP has individual close-out criteria which do not qualify acceptability.
- 6) _ There is no inspection criteria or uniform attribute checklists which can be used by QA/QC personnel, auditors, or third party reviewers to determine the adequacy of the ISAP.
- 7) The ISAPs/DSAPs do not include the results of the exploratory investigations which are used as a basis to develop the ISAP.
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MISSING ELEMENTS A
The following elements are missing entirely from the program
- 1. There is no accurate, up-to-date list of remaining work against a defined baseline of actual work necessary to complete Unit 1 and Unit II.
- 2. There are no work controls on on going work, including ongoing reinspection work and any on-going corrective action work.
- 3. There are no NRC inspection and review hold points at
' critical reinspection points.
- 4. There are no inspections attribute checklists available
, for review and analysis to insure that the reinspection effort will be comprehensive.
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- 5. There is no significant change in the organization and management personnel associated with the construction of the plant (as opposed to QA/QC).
- 6. There is no internal management analysis to i determine the root cause of the implementation failures of the initial construction and inspection effort.
- 7. There is no verifiable central control over the multiple reinspection programs to insure that the interfaces necessary for successful implementation and communication exist at the facility.
- 8. There has been no significant reduction in the con-struction activity of Unit II to accommodate' changes.
- 9. There is, to date, no quality control / quality assurance program for the reinspection program.
4 10. There is no acceptable protocol between the CPRT-SRT, TUEC, and other contractors.
- 11. There are no third party controls over the implementa-tion of the' corrective action measures.
i 12. There is no contractual independence of-the evaluators j on the SRT from TUEC management.
- 13. There is no separation between the reinspection effort and the work-completion effort.
i 14. There has been no review of the third-party organiza-
- tions or individuals (either through the hearing or through a public meeting).
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6' 15. There is no program to consider the implications of
-harassment and intimidation on the work atmosphere.
- 16. There is no program for retraining and recertifying all inspectors to new inspection criteria.
- 17. There is no justification provided for the identification of the homogenous hardware groups which are to provide the basis for the conclusions of the self-initiated evaluation.
- 18. There is no adequate plan for implementation of oversight controls on the self-initiated evaluations, or the ISAP/DSAPs.
COMPARISON OF APPENDIX A (SUGGESTED CONSTRUCTION i REVERIFICATION PROGRAM) TO THE CPRT PROGRAM PLAN 9
On February 4, 1985, CASE submitted a proposal for a comprehensive reinspection program as an attachment to their REQUEST FOR AN EVIDENTIARY STANDARD. The Board deferred final ruling on the proposal, suggesting that TUEC's proposal may be acceptable to CASE.
The key elements of CASE's proposal are listed on the left.
The right-hand column denotes which recommendations are included in the CPRT Program Plan.
l l CASE Proposal CPRT Program Plan l
I. Selection of 3rd Party:
l a) Provide for Board selection of inde- No pendent auditor to perform reinspection using following criteria: (1) indepen-dence; (2) competences (3) integrity.
b) Selection after a public No meeting about the nomination prior to staff approval.
c) Poard approval of independent No nuditor.
II. Overall Program Plan - Phase Is a) Reorganize TUEC & B&R upper management. Partial b) Reorganize site and mid-level Partial management.
c) Reorganize work force into teams. No l
d) Installation and status assessment of No current work completion.
+
. CASE Proposal CPRT Program Plan e) Establish NRC " hold points" for No review of work plans.
f) Complete revision for all procedures. No g) Issue new procedures and inspection No attribute checklists after NRC review.
h) Review documentatien and incorporate No design changes into final design.
- 1) Re-qualification of equipment. No j) Review vendor QA programs. No k) Recertify and retrain personnel. No III. Overall Program Plan - Phase II:
a) Reinspect hardware and report No results.
b) Monthly meetings on implementation. No c) Develop corrective action plan, Partial submit for review, and revise.
d) Board approval of corrective action No plan.
IV. Overall Program Plan - Phase III a) Resubmit design for NRC approval. Partial b) Work Authorization Procedure for No items requiring repair.
c) Work completion accomplished.
d) Monthly meetings to review progress. No
r 4
a CASE Proposal CPRT Program Plan
? Cooperative Participation by Parties V.
and Boards a) Board approval of CPRT. Partial b) Continuous documentation oversight by 3rd party. No c) Monthly public meetings. No d) Mandatory compliance with approved No methodology.
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